80_FR_29199 80 FR 29102 - Dominion Nuclear Connecticut, Inc., Millstone Power Station, Unit 2

80 FR 29102 - Dominion Nuclear Connecticut, Inc., Millstone Power Station, Unit 2

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 80, Issue 97 (May 20, 2015)

Page Range29102-29105
FR Document2015-12264

The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to an April 11, 2014, request from Dominion Nuclear Connecticut, Inc., requesting an exemption to use a different fuel rod cladding material (M5<SUP>TM</SUP>, hereafter referred as M5).

Federal Register, Volume 80 Issue 97 (Wednesday, May 20, 2015)
[Federal Register Volume 80, Number 97 (Wednesday, May 20, 2015)]
[Notices]
[Pages 29102-29105]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2015-12264]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-336; NRC-2015-0125]


Dominion Nuclear Connecticut, Inc., Millstone Power Station, Unit 
2

AGENCY: Nuclear Regulatory Commission.

ACTION: Exemption; issuance.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an 
exemption in response to an April 11, 2014, request from Dominion 
Nuclear Connecticut, Inc., requesting an exemption to use a different 
fuel rod cladding material (M5TM, hereafter referred as M5).

DATES: May 20, 2015.

ADDRESSES: Please refer to Docket ID NRC-2015-0125 when contacting the 
NRC about the availability of information regarding this document. You 
may obtain publicly-available information related to this document 
using any of the following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0125. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. For technical questions, contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS

[[Page 29103]]

Search.'' For problems with ADAMS, please contact the NRC's Public 
Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or 
by email to [email protected]. The ADAMS accession number for each 
document referenced (if it available in ADAMS) is provided the first 
time that a document is referenced.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT: Richard V. Guzman, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 
20555-0001; telephone: 301-415-1030, email: [email protected].

I. Background

    Dominion Nuclear Connecticut, Inc. (the licensee) is the holder of 
Renewed Facility Operating License No. DPR-65, which authorizes 
operation of Millstone Power Station, Unit 2 (MPS2), a pressurized 
water reactor. The license provides, among other things, that the 
facility is subject to all rules, regulations, and orders of the NRC 
now or hereafter in effect.
    The MPS2 shares the site with Millstone Power Station, Unit 1, a 
permanently defueled boiling water reactor nuclear unit, and Millstone 
Power Station, Unit 3, a pressurized water reactor. The facility is 
located in Waterford, Connecticut, approximately 3.2 miles west 
southwest of New London, Connecticut. This exemption applies to MPS2 
only. The other units, Units 1 and 3, are not covered by this 
exemption.

II. Request/Action

    Pursuant to section 50.12 of Title 10 of the Code of Federal 
Regulations (10 CFR), ``Specific exemptions,'' the licensee has, by 
letter dated April 11, 2014 (ADAMS Accession No. ML14112A072), 
requested an exemption from 10 CFR 50.46, ``Acceptance criteria for 
emergency core cooling systems [ECCS] for light-water nuclear power 
reactors,'' and 10 CFR part 50, appendix K, ``ECCS Evaluation Models,'' 
to allow the use of fuel rod cladding with M5 alloy for future reload 
applications. The regulations in 10 CFR 50.46 contain acceptance 
criteria for the ECCS for reactors fueled with Zircaloy or 
ZIRLO[supreg] fuel rod cladding material. In addition, paragraph I.A.5 
of appendix K to 10 CFR part 50 requires that the Baker-Just equation 
be used to predict the rates of energy release, hydrogen concentration, 
and cladding oxidation from the metal/water reaction. The Baker-Just 
equation assumes the use of a zirconium alloy, which is a material 
different from M5. Thus, the strict application of these regulations 
does not permit the use of fuel rod cladding material other than 
Zircaloy or ZIRLO[supreg]. Because the material specifications of M5 
differ from the specifications for Zircaloy or ZIRLO[supreg], and the 
regulations specify a cladding material other than M5, a plant-specific 
exemption is required to allow the use of, and application of these 
regulations to, M5 at MPS2.
    The exemption request relates solely to the cladding material 
specified in these regulations (i.e., fuel rods with Zircaloy or 
ZIRLO[supreg] cladding material). This exemption would allow 
application of the acceptance criteria of 10 CFR 50.46 and appendix K 
to 10 CFR part 50, to fuel assembly designs using M5 fuel rod cladding 
material. The licensee is not seeking an exemption from the acceptance 
and analytical criteria of these regulations. The intent of the request 
is to allow the use of the criteria set forth in these regulations for 
the use of M5 fuel rod cladding material at MPS2. The detailed 
technical basis of the licensee's proposed use of M5 cladding is being 
addressed by the Nuclear Regulatory Commission staff under a proposed 
amendment to the MPS2 operating license; the amendment is issued 
concurrently with the issuance of this exemption.

III. Discussion

    Pursuant to 10 CFR 50.12, the Commission may, upon application by 
any interested person or upon its own initiative, grant exemptions from 
the requirements of 10 CFR part 50 when: (1) The exemptions are 
authorized by law, will not present an undue risk to public health or 
safety, and are consistent with the common defense and security; and 
(2) when special circumstances are present. Under 10 CFR 
50.12(a)(2)(ii), special circumstances include, among other things, 
when application of the specific regulation in the particular 
circumstance would not serve, or is not necessary to achieve, the 
underlying purpose of the rule.

A. Special Circumstances

    Special circumstances, in accordance with 10 CFR 50.12(a)(2)(ii), 
are present whenever application of the regulation in the particular 
circumstances is not necessary to achieve the underlying purpose of the 
rule. The underlying purpose of 10 CFR 50.46 and appendix K to 10 CFR 
part 50 is to establish acceptance criteria for ECCS performance to 
provide reasonable assurance of safety in the event of a loss-of-
coolant accident (LOCA). Although the regulations in 10 CFR 50.46 and 
appendix K to 10 CFR part 50 are not expressly applicable to M5 alloy 
cladding, the evaluations described in the following sections of this 
exemption show that the purpose of the regulations are met by this 
exemption, in that the effectiveness of the ECCS will not be affected 
by a change from Zircaloy or ZIRLO[supreg] clad fuel rod to M5 clad 
fuel rod. Normal reload safety analyses will confirm that there is no 
adverse impact on ECCS performance. Thus, a strict application of the 
rule (which would preclude the applicability of ECCS performance 
acceptance criteria to, and the use of, M5 fuel cladding material) is 
not necessary to achieve the underlying purposes of 10 CFR 50.46 and 
appendix K to 10 CFR part 50. The purpose of these regulations is 
achieved through application of the requirements to the use of M5 fuel 
rod clad material. Therefore, the special circumstances required by 10 
CFR 50.12(a)(2)(ii) for the granting of an exemption exist.

B. Authorized by Law

    This exemption would allow the use of M5 fuel rod cladding material 
for future reload operations at MPS2. As stated above, 10 CFR 50.12 
allows the NRC to grant exemptions from the requirements of 10 CFR part 
50 provided that special circumstances are present. As described above, 
the NRC staff has determined that special circumstances exist to grant 
the requested exemption. In addition, granting the exemption will not 
result in a violation any part of the Atomic Energy Act of 1954, as 
amended, or the Commission's regulations. Therefore, the exemption is 
authorized by law.

C. No Undue Risk to Public Health and Safety

    Section 10 CFR 50.46 requires that each boiling or pressurized 
light-water nuclear power reactor fueled with uranium dioxide pellets 
within cylindrical Zircaloy or ZIRLO[supreg] cladding must be provided 
with an ECCS that must be designed so that its calculated cooling 
performance following a postulated LOCA conforms to the criteria set 
forth in paragraph (B) of this section. The underlying purpose of 10 
CFR 50.46 is to establish acceptance criteria for adequate ECCS 
performance.
    The NRC-approved topical report BAW-10227(P)-A, ``Evaluation of 
Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel'' 
(ADAMS Accession No. ML003686365) has demonstrated that predicted 
chemical, mechanical, and material performance characteristics of the 
M5

[[Page 29104]]

alloy cladding are bound for those approved for Zircaloy under 
anticipated operational occurrences and postulated accidents. The NRC 
staff's Safety Evaluation (ADAMS Accession No. ML003671021) evaluating 
this topical report concluded that the M5 properties and mechanical 
design methodology are acceptable for fuel reload licensing 
applications. Topical report BAW-10227(P)-A also confirms that no new 
or different type of accident will be initiated that could pose a risk 
to public health and safety.
    The NRC-approved topical Report BAW-10240(P)-A, Revision 0, 
``Incorporation of M5 Properties in Framatome-ANP Approved Methods'' 
(ADAMS Accession No. ML042800314) describes the incorporation of the 
NRC-approved M5 material properties in a set of mechanical analyses, 
small-break loss-of-coolant accident (SBLOCA) and non-LOCA 
methodologies. This topical report demonstrates that the effectiveness 
of the ECCS will not be affected by changing the cladding from Zircaloy 
to M5 alloy.
    The objective of 10 CFR 50.46(b)(2) and (b)(3), and appendix K to 
10 CFR part 50, paragraph I.A.5 is to ensure that cladding oxidation 
and hydrogen generation are appropriately limited during a LOCA and 
conservatively accounted for in a plant's ECCS evaluation model. 
Paragraph I.A.5 of appendix K requires that the Baker-Just equation be 
used in the ECCS evaluation model to determine the rate of energy 
release, cladding oxidation, and hydrogen generation. Based on the 
above, the NRC staff concludes that the intent of 10 CFR 50.46 and 
appendix K to 10 CFR part 50 will continue to be satisfied for the 
planned operation of MPS2 with M5 alloy fuel cladding and fuel assembly 
material.

D. Consistent With the Common Defense and Security

    The M5 cladding material is similar in design to Zircaloy, the 
current cladding material used at MPS2. Thus, the change in cladding 
material from Zircaloy to M5 will not require any change to the 
security and control of special nuclear material. The licensee will 
continue to be required to handle and control special nuclear material 
in these assemblies in accordance with its approved procedures. This 
change to reactor core internals is adequately controlled by NRC 
requirements and is not related to security issues. Therefore, the NRC 
staff determined that this exemption does not impact, and thus is 
consistent with, the common defense and security.

E. Environmental Considerations

    The NRC staff determined that the exemption discussed herein meets 
the eligibility criteria for the categorical exclusion set forth in 10 
CFR 51.22(c)(9) because it is related to a requirement concerning the 
installation or use of a facility component located within the 
restricted area, as defined in 10 CFR part 20, and issuance of this 
exemption involves: (i) no significant hazards consideration, (ii) no 
significant change in the types or a significant increase in the 
amounts of any effluents that may be released offsite, and (iii) no 
significant increase in individual or cumulative occupational radiation 
exposure. Therefore, in accordance with 10 CFR 51.22(b), no 
environmental impact statement or environmental assessment need be 
prepared in connection with the NRC's consideration of this exemption 
request. The basis for the NRC staff's determination is discussed as 
follows with an evaluation against each of the requirements in 10 CFR 
51.22(c)(9)(i)-(iii).
Requirements in 10 CFR 51.22(c)(9)(i)
    The NRC staff evaluated whether the exemption involves no 
significant hazards consideration using the standards described in 10 
CFR 50.92(c), as presented below:
    1. Does the proposed exemption involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed exemption would allow the use of M5 fuel rod cladding 
material in the MPS2 reactor. The NRC approved topical reports cited 
above demonstrate that M5 alloy has similar properties as the currently 
licensed Zircaloy. The fuel cladding itself is not a postulated 
initiator of previously evaluated accidents; thus, fuel cladding 
material does not affect the probability of occurrence of any accident. 
The consequences of none of the previously evaluated accidents were 
affected by fuel cladding material, and M5, likewise, is not expected 
to have any effect on the consequences of any previously evaluated 
accidents.
    Therefore, the proposed exemption does not involve a significant 
increase in the probability or consequences of an accident previously 
evaluated.
    2. Does the proposed exemption create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    The use of M5 fuel rod cladding material will not result in changes 
in the operation or configuration of the facility. The above cited 
topical reports demonstrated that the material properties of M5 are 
similar to those of standard Zircaloy. Therefore, M5 fuel rod cladding 
material will perform similarly to those fabricated from standard 
Zircaloy. The fuel cladding itself is not a postulated initiator of 
previously evaluated accidents and does not create the possibility of a 
new or different kind of accident.
    Therefore, the proposed exemption does not create the possibility 
of a new or different kind of accident from any previously evaluated.
    3. Does the proposed exemption involve a significant reduction in a 
margin of safety?
    Response: No.
    The proposed exemption will not involve a significant reduction in 
the margin of safety because it has been demonstrated that the material 
properties of the M5 alloy are not significantly different from those 
of standard Zircaloy. M5 alloy is expected to perform similarly to 
standard Zircaloy for all normal operating and accident scenarios. Use 
of M5 alloy does not require changing any of the current regulatory 
acceptance criteria, or relaxation of the methods of analysis.
    Therefore, the proposed exemption does not involve a significant 
reduction in a margin of safety.
    Based on the above evaluation of the standards set forth in 10 CFR 
50.92(c), the NRC staff concludes that the proposed exemption involves 
no significant hazards consideration. Accordingly, the requirements of 
10 CFR 51.22(c)(9)(i) are met.
Requirements in 10 CFR 51.22(c)(9)(ii)
    The proposed exemption would allow the use of M5 fuel rod cladding 
material in the MPS2 reactor. M5 alloy has similar material properties 
and performance characteristics as the currently licensed Zircaloy 
cladding. Thus, the use of M5 fuel rod cladding material will not 
significantly change the types of effluents that may be released 
offsite, or significantly increase the amount of effluents that may be 
released offsite. Therefore, the requirements of 10 CFR 51.22(c)(9)(ii) 
are met.
Requirements in 10 CFR 51.22(c)(9)(iii)
    The proposed exemption would allow the use of M5 fuel rod cladding 
material in the reactors. M5 alloy has similar material properties and 
performance characteristics as the currently licensed Zircaloy 
cladding. Thus, the use of M5 fuel rod cladding material will not 
significantly increase individual occupational radiation exposure, or

[[Page 29105]]

significantly increase cumulative occupational radiation exposure. 
Therefore, the requirements of 10 CFR 51.22(c)(9)(iii) are met.
Conclusion
    Based on the above, the NRC staff concludes that the proposed 
exemption meets the eligibility criteria for the categorical exclusion 
set forth in 10 CFR 51.22(c)(9). Therefore, in accordance with 10 CFR 
51.22(b), no environmental impact statement or environmental assessment 
need be prepared in connection with the NRC's proposed issuance of this 
exemption.

IV. Conclusions

    Accordingly, the Commission has determined that, pursuant to 10 CFR 
50.12, the exemption is authorized by law, will not present an undue 
risk to the public health and safety, and is consistent with the common 
defense and security. Also, special circumstances pursuant to 10 CFR 
50.12(a)(2)(ii) are present. Therefore, the Commission hereby grants 
Dominion Nuclear Connecticut, Inc., an exemption from the requirements 
of 10 CFR 50.46 and Appendix K to 10 CFR part 50, to allow the 
application of those criteria to, and the use of, M5 fuel rod cladding 
material at MPS2.
    This exemption is effective upon issuance.

    Dated at Rockville, Maryland, this 12th Day of May, 2015.

For the Nuclear Regulatory Commission
Louise Lund,
Acting Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. 2015-12264 Filed 5-19-15; 8:45 am]
BILLING CODE 7590-01-P



                                                  29102                        Federal Register / Vol. 80, No. 97 / Wednesday, May 20, 2015 / Notices

                                                     • NRC’s PDR: You may examine and                     Title 10 of the Code of Federal                       10 CFR 40.46(b)(1) and (2) as the request
                                                  purchase copies of public documents at                  Regulations (10 CFR), ‘‘Domestic                      includes the identity and technical and
                                                  the NRC’s PDR, Room O1–F21, One                         Licensing of Source Material.’’ The                   financial qualifications of the proposed
                                                  White Flint North, 11555 Rockville                      Commission is required by 10 CFR                      transferee, and WNI has committed to
                                                  Pike, Rockville, Maryland 20852.                        40.46 to determine if the change of                   provide revised financial assurance for
                                                  FOR FURTHER INFORMATION CONTACT:                        control is in accordance with the                     decommissioning, during the next
                                                  Dominick Orlando, Office of Nuclear                     provisions of the Atomic Energy Act of                parent company guarantee submittal,
                                                  Material Safety and Safeguards, U.S.                    1954, as amended and to give its                      naming Freeport as parent company
                                                  Nuclear Regulatory Commission,                          consent in writing.                                   guarantor for the reclamation costs at
                                                  Washington, DC 20555–0001; telephone:                      The NRC staff reviews requests for                 the Split Rock Site.
                                                  301–415–6749, email:                                    license transfers using the guidance in
                                                                                                                                                                  Dated at Rockville, Maryland, this 5th day
                                                  Dominick.orlando@nrc.gov.                               NUREG 1556, Volume 15,                                of May 2015.
                                                                                                          ‘‘Consolidated Guidance About                         For the Nuclear Regulatory Commission.
                                                  SUPPLEMENTARY INFORMATION: The WNI
                                                                                                          Materials Licenses-Guidance About
                                                  is the holder of NRC Materials License                                                                        Larry W. Camper,
                                                                                                          Changes of Control and About
                                                  No. SUA–56 for its former Split Rock                                                                          Director, Division of Decommissioning,
                                                                                                          Bankruptcy Involving Byproduct,
                                                  Conventional Uranium Mill Site near                     Source, or Special Nuclear Materials                  Uranium Recovery and Waste Programs,
                                                  Jeffrey City, Wyoming. The WNI has                      Licenses,’’ dated November 2000
                                                                                                                                                                Office of Nuclear Material Safety and
                                                  been an NRC licensee since 1958. The                                                                          Safeguards.
                                                                                                          (NUREG 1556, Vol. 15) (ADAMS
                                                  Split Rock Site ceased active uranium                   Accession No. ML003778305). The                       [FR Doc. 2015–12266 Filed 5–19–15; 8:45 am]
                                                  recovery operations in 1987 and has                     purpose of the review is to determine                 BILLING CODE 7590–01–P
                                                  been engaging in final site reclamation                 whether the licensee, under the
                                                  activities since then. In 1971, WNI                     transaction, would continue to meet the
                                                  became a wholly owned subsidiary of                                                                           NUCLEAR REGULATORY
                                                                                                          regulatory requirements necessary to
                                                  PDC.                                                                                                          COMMISSION
                                                                                                          establish adequate financial assurance
                                                     On March 12, 2007, WNI informed the                  for decommissioning as required by 10                 [Docket No. 50–336; NRC–2015–0125]
                                                  NRC that the PDC would be acquired by                   CFR part 40. As discussed in NUREG–
                                                  Freeport (ADAMS Accession No.                           1556, Volume 15, the NRC uses the term                Dominion Nuclear Connecticut, Inc.,
                                                  ML071080087). On September 5, 2007,                     ‘‘change of control’’ rather than the                 Millstone Power Station, Unit 2
                                                  WNI informed the NRC that the                           statutory term ‘‘transfer’’ to describe the
                                                  acquisition of WNI by Freeport had                                                                            AGENCY:  Nuclear Regulatory
                                                                                                          variety of events that could require prior            Commission.
                                                  occurred (ADAMS Accession No.                           notification and written consent of the
                                                  ML072710031). By letter dated July 22,                                                                        ACTION: Exemption; issuance.
                                                                                                          NRC. The central issue is whether the
                                                  2009, WNI submitted a request to the                    authority over the license has changed.
                                                  NRC for Consent to Indirect License                                                                           SUMMARY:   The U.S. Nuclear Regulatory
                                                                                                          The WNI’s request for consent to                      Commission (NRC) is issuing an
                                                  Transfer of NRC Materials License No.                   indirect change of control describes an
                                                  SUA–56 (ADAMS Accession No.                                                                                   exemption in response to an April 11,
                                                                                                          indirect change of control resulting from             2014, request from Dominion Nuclear
                                                  ML092100247). On October 13, 2009,                      a merger between PDC, WNI’s former
                                                  the NRC issued a notice of application                                                                        Connecticut, Inc., requesting an
                                                                                                          parent company, and Freeport.                         exemption to use a different fuel rod
                                                  for indirect change of control and                      Following the merger, WNI became a
                                                  provided interested individuals an                                                                            cladding material (M5TM, hereafter
                                                                                                          wholly owned subsidiary of Freeport                   referred as M5).
                                                  opportunity to request a hearing (74 FR                 and, as such, the transfer requires NRC
                                                  52510).                                                                                                       DATES: May 20, 2015.
                                                                                                          consent.
                                                     On December 30, 2009, the NRC                           The NRC staff reviewed WNI’s request               ADDRESSES: Please refer to Docket ID
                                                  requested additional information from                   for consent to an indirect change in                  NRC–2015–0125 when contacting the
                                                  WNI on the indirect change of control                   control of its 10 CFR part 40 license                 NRC about the availability of
                                                  (ADAMS Accession Nos. ML093480467                       using the guidance in NUREG 1556, Vol.                information regarding this document.
                                                  and ML093480453). The WNI                               15. The NRC staff finds that the                      You may obtain publicly-available
                                                  responded on May 7, 2010 (the NRC                       information submitted by WNI                          information related to this document
                                                  staff was unable to locate this response                sufficiently describes and documents                  using any of the following methods:
                                                  in ADAMS and a copy was provided by                     the commitments made by Freeport is                      • Federal Rulemaking Web site: Go to
                                                  WNI on January 13, 2015 (ADAMS                          consistent with the guidance in                       http://www.regulations.gov and search
                                                  Accession No. ML15036A423)). On July                    NUREG–1556, Vol. 15. An                               for Docket ID NRC–2015–0125. Address
                                                  27, 2010, the NRC requested additional                  environmental assessment for this                     questions about NRC dockets to Carol
                                                  information from WNI on the indirect                    action is not required because this                   Gallagher; telephone: 301–415–3463;
                                                  change of control (ADAMS Accession                      action is categorically excluded under                email: Carol.Gallagher@nrc.gov. For
                                                  No. ML102040700). On June 24, 2011,                     10 CFR 51.22(c)(21).                                  technical questions, contact the
                                                  WNI provided information in response                       Based on the review summarized                     individual listed in the FOR FURTHER
                                                  to the request for additional information               above, the NRC has approved the                       INFORMATION CONTACT section of this
                                                  (ADAMS Accession No. ML111860086).                      indirect change of control, although the              document.
                                                  On December 2, 2014, the NRC                            licensee was required to obtain NRC                      • NRC’s Agencywide Documents
mstockstill on DSK4VPTVN1PROD with NOTICES




                                                  requested additional information from                   consent prior to the indirect change of               Access and Management System
                                                  WNI on the indirect change of control                   control occurring. The licensee has                   (ADAMS): You may obtain publicly-
                                                  (ADAMS Accession No. ML14301A290).                      further committed in its next parent                  available documents online in the
                                                  The WNI responded to the NRC’s                          company guarantee submission to                       ADAMS Public Documents collection at
                                                  request on January 13, 2015 (ADAMS                      provide a parent company guarantee                    http://www.nrc.gov/reading-rm/
                                                  Package Accession No. ML15036A423).                     issued by Freeport to cover the                       adams.html. To begin the search, select
                                                     The WNI’s Materials License No.                      remaining site reclamation costs. The                 ‘‘ADAMS Public Documents’’ and then
                                                  SUA–56 was issued under part 40 of                      WNI’s request meets the requirements of               select ‘‘Begin Web-based ADAMS


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                                                                               Federal Register / Vol. 80, No. 97 / Wednesday, May 20, 2015 / Notices                                              29103

                                                  Search.’’ For problems with ADAMS,                      assumes the use of a zirconium alloy,                 of-coolant accident (LOCA). Although
                                                  please contact the NRC’s Public                         which is a material different from M5.                the regulations in 10 CFR 50.46 and
                                                  Document Room (PDR) reference staff at                  Thus, the strict application of these                 appendix K to 10 CFR part 50 are not
                                                  1–800–397–4209, 301–415–4737, or by                     regulations does not permit the use of                expressly applicable to M5 alloy
                                                  email to pdr.resource@nrc.gov. The                      fuel rod cladding material other than                 cladding, the evaluations described in
                                                  ADAMS accession number for each                         Zircaloy or ZIRLO®. Because the                       the following sections of this exemption
                                                  document referenced (if it available in                 material specifications of M5 differ from             show that the purpose of the regulations
                                                  ADAMS) is provided the first time that                  the specifications for Zircaloy or                    are met by this exemption, in that the
                                                  a document is referenced.                               ZIRLO®, and the regulations specify a                 effectiveness of the ECCS will not be
                                                    • NRC’s PDR: You may examine and                      cladding material other than M5, a                    affected by a change from Zircaloy or
                                                  purchase copies of public documents at                  plant-specific exemption is required to               ZIRLO® clad fuel rod to M5 clad fuel
                                                  the NRC’s PDR, Room O1–F21, One                         allow the use of, and application of                  rod. Normal reload safety analyses will
                                                  White Flint North, 11555 Rockville                      these regulations to, M5 at MPS2.                     confirm that there is no adverse impact
                                                  Pike, Rockville, Maryland 20852.                           The exemption request relates solely               on ECCS performance. Thus, a strict
                                                  FOR FURTHER INFORMATION CONTACT:                        to the cladding material specified in                 application of the rule (which would
                                                  Richard V. Guzman, Office of Nuclear                    these regulations (i.e., fuel rods with               preclude the applicability of ECCS
                                                  Reactor Regulation, U.S. Nuclear                        Zircaloy or ZIRLO® cladding material).                performance acceptance criteria to, and
                                                  Regulatory Commission, Washington DC                    This exemption would allow                            the use of, M5 fuel cladding material) is
                                                  20555–0001; telephone: 301–415–1030,                    application of the acceptance criteria of             not necessary to achieve the underlying
                                                  email: Richard.guzman@nrc.gov.                          10 CFR 50.46 and appendix K to 10 CFR                 purposes of 10 CFR 50.46 and appendix
                                                                                                          part 50, to fuel assembly designs using               K to 10 CFR part 50. The purpose of
                                                  I. Background                                           M5 fuel rod cladding material. The                    these regulations is achieved through
                                                     Dominion Nuclear Connecticut, Inc.                   licensee is not seeking an exemption                  application of the requirements to the
                                                  (the licensee) is the holder of Renewed                 from the acceptance and analytical                    use of M5 fuel rod clad material.
                                                  Facility Operating License No. DPR–65,                  criteria of these regulations. The intent             Therefore, the special circumstances
                                                  which authorizes operation of Millstone                 of the request is to allow the use of the             required by 10 CFR 50.12(a)(2)(ii) for the
                                                  Power Station, Unit 2 (MPS2), a                         criteria set forth in these regulations for           granting of an exemption exist.
                                                  pressurized water reactor. The license                  the use of M5 fuel rod cladding material
                                                  provides, among other things, that the                  at MPS2. The detailed technical basis of              B. Authorized by Law
                                                  facility is subject to all rules,                       the licensee’s proposed use of M5                       This exemption would allow the use
                                                  regulations, and orders of the NRC now                  cladding is being addressed by the                    of M5 fuel rod cladding material for
                                                  or hereafter in effect.                                 Nuclear Regulatory Commission staff                   future reload operations at MPS2. As
                                                     The MPS2 shares the site with                        under a proposed amendment to the                     stated above, 10 CFR 50.12 allows the
                                                  Millstone Power Station, Unit 1, a                      MPS2 operating license; the amendment                 NRC to grant exemptions from the
                                                  permanently defueled boiling water                      is issued concurrently with the issuance              requirements of 10 CFR part 50
                                                  reactor nuclear unit, and Millstone                     of this exemption.                                    provided that special circumstances are
                                                  Power Station, Unit 3, a pressurized                                                                          present. As described above, the NRC
                                                  water reactor. The facility is located in               III. Discussion                                       staff has determined that special
                                                  Waterford, Connecticut, approximately                      Pursuant to 10 CFR 50.12, the                      circumstances exist to grant the
                                                  3.2 miles west southwest of New                         Commission may, upon application by                   requested exemption. In addition,
                                                  London, Connecticut. This exemption                     any interested person or upon its own                 granting the exemption will not result in
                                                  applies to MPS2 only. The other units,                  initiative, grant exemptions from the                 a violation any part of the Atomic
                                                  Units 1 and 3, are not covered by this                  requirements of 10 CFR part 50 when:                  Energy Act of 1954, as amended, or the
                                                  exemption.                                              (1) The exemptions are authorized by                  Commission’s regulations. Therefore,
                                                                                                          law, will not present an undue risk to                the exemption is authorized by law.
                                                  II. Request/Action
                                                                                                          public health or safety, and are
                                                     Pursuant to section 50.12 of Title 10                consistent with the common defense                    C. No Undue Risk to Public Health and
                                                  of the Code of Federal Regulations (10                  and security; and (2) when special                    Safety
                                                  CFR), ‘‘Specific exemptions,’’ the                      circumstances are present. Under 10                     Section 10 CFR 50.46 requires that
                                                  licensee has, by letter dated April 11,                 CFR 50.12(a)(2)(ii), special                          each boiling or pressurized light-water
                                                  2014 (ADAMS Accession No.                               circumstances include, among other                    nuclear power reactor fueled with
                                                  ML14112A072), requested an exemption                    things, when application of the specific              uranium dioxide pellets within
                                                  from 10 CFR 50.46, ‘‘Acceptance criteria                regulation in the particular                          cylindrical Zircaloy or ZIRLO® cladding
                                                  for emergency core cooling systems                      circumstance would not serve, or is not               must be provided with an ECCS that
                                                  [ECCS] for light-water nuclear power                    necessary to achieve, the underlying                  must be designed so that its calculated
                                                  reactors,’’ and 10 CFR part 50, appendix                purpose of the rule.                                  cooling performance following a
                                                  K, ‘‘ECCS Evaluation Models,’’ to allow                                                                       postulated LOCA conforms to the
                                                  the use of fuel rod cladding with M5                    A. Special Circumstances                              criteria set forth in paragraph (B) of this
                                                  alloy for future reload applications. The                 Special circumstances, in accordance                section. The underlying purpose of 10
                                                  regulations in 10 CFR 50.46 contain                     with 10 CFR 50.12(a)(2)(ii), are present              CFR 50.46 is to establish acceptance
                                                  acceptance criteria for the ECCS for                    whenever application of the regulation                criteria for adequate ECCS performance.
                                                  reactors fueled with Zircaloy or ZIRLO®
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                                                                                                          in the particular circumstances is not                  The NRC-approved topical report
                                                  fuel rod cladding material. In addition,                necessary to achieve the underlying                   BAW–10227(P)–A, ‘‘Evaluation of
                                                  paragraph I.A.5 of appendix K to 10 CFR                 purpose of the rule. The underlying                   Advanced Cladding and Structural
                                                  part 50 requires that the Baker-Just                    purpose of 10 CFR 50.46 and appendix                  Material (M5) in PWR Reactor Fuel’’
                                                  equation be used to predict the rates of                K to 10 CFR part 50 is to establish                   (ADAMS Accession No. ML003686365)
                                                  energy release, hydrogen concentration,                 acceptance criteria for ECCS                          has demonstrated that predicted
                                                  and cladding oxidation from the metal/                  performance to provide reasonable                     chemical, mechanical, and material
                                                  water reaction. The Baker-Just equation                 assurance of safety in the event of a loss-           performance characteristics of the M5


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                                                  29104                        Federal Register / Vol. 80, No. 97 / Wednesday, May 20, 2015 / Notices

                                                  alloy cladding are bound for those                      E. Environmental Considerations                       facility. The above cited topical reports
                                                  approved for Zircaloy under anticipated                    The NRC staff determined that the                  demonstrated that the material
                                                  operational occurrences and postulated                  exemption discussed herein meets the                  properties of M5 are similar to those of
                                                  accidents. The NRC staff’s Safety                       eligibility criteria for the categorical              standard Zircaloy. Therefore, M5 fuel
                                                  Evaluation (ADAMS Accession No.                         exclusion set forth in 10 CFR 51.22(c)(9)             rod cladding material will perform
                                                  ML003671021) evaluating this topical                    because it is related to a requirement                similarly to those fabricated from
                                                  report concluded that the M5 properties                 concerning the installation or use of a               standard Zircaloy. The fuel cladding
                                                  and mechanical design methodology are                   facility component located within the                 itself is not a postulated initiator of
                                                  acceptable for fuel reload licensing                    restricted area, as defined in 10 CFR                 previously evaluated accidents and does
                                                  applications. Topical report BAW–                       part 20, and issuance of this exemption               not create the possibility of a new or
                                                  10227(P)-A also confirms that no new or                 involves: (i) no significant hazards                  different kind of accident.
                                                  different type of accident will be                                                                               Therefore, the proposed exemption
                                                                                                          consideration, (ii) no significant change
                                                  initiated that could pose a risk to public                                                                    does not create the possibility of a new
                                                                                                          in the types or a significant increase in
                                                  health and safety.                                                                                            or different kind of accident from any
                                                                                                          the amounts of any effluents that may be
                                                     The NRC-approved topical Report                                                                            previously evaluated.
                                                                                                          released offsite, and (iii) no significant
                                                  BAW–10240(P)–A, Revision 0,                                                                                      3. Does the proposed exemption
                                                                                                          increase in individual or cumulative
                                                  ‘‘Incorporation of M5 Properties in                                                                           involve a significant reduction in a
                                                                                                          occupational radiation exposure.
                                                  Framatome-ANP Approved Methods’’                                                                              margin of safety?
                                                                                                          Therefore, in accordance with 10 CFR                     Response: No.
                                                  (ADAMS Accession No. ML042800314)                       51.22(b), no environmental impact
                                                  describes the incorporation of the NRC-                                                                          The proposed exemption will not
                                                                                                          statement or environmental assessment                 involve a significant reduction in the
                                                  approved M5 material properties in a set                need be prepared in connection with the
                                                  of mechanical analyses, small-break                                                                           margin of safety because it has been
                                                                                                          NRC’s consideration of this exemption                 demonstrated that the material
                                                  loss-of-coolant accident (SBLOCA) and                   request. The basis for the NRC staff’s
                                                  non-LOCA methodologies. This topical                                                                          properties of the M5 alloy are not
                                                                                                          determination is discussed as follows                 significantly different from those of
                                                  report demonstrates that the                            with an evaluation against each of the
                                                  effectiveness of the ECCS will not be                                                                         standard Zircaloy. M5 alloy is expected
                                                                                                          requirements in 10 CFR 51.22(c)(9)(i)–                to perform similarly to standard
                                                  affected by changing the cladding from                  (iii).
                                                  Zircaloy to M5 alloy.                                                                                         Zircaloy for all normal operating and
                                                                                                          Requirements in 10 CFR 51.22(c)(9)(i)                 accident scenarios. Use of M5 alloy does
                                                     The objective of 10 CFR 50.46(b)(2)
                                                                                                                                                                not require changing any of the current
                                                  and (b)(3), and appendix K to 10 CFR                       The NRC staff evaluated whether the                regulatory acceptance criteria, or
                                                  part 50, paragraph I.A.5 is to ensure that              exemption involves no significant                     relaxation of the methods of analysis.
                                                  cladding oxidation and hydrogen                         hazards consideration using the                          Therefore, the proposed exemption
                                                  generation are appropriately limited                    standards described in 10 CFR 50.92(c),               does not involve a significant reduction
                                                  during a LOCA and conservatively                        as presented below:                                   in a margin of safety.
                                                  accounted for in a plant’s ECCS                            1. Does the proposed exemption                        Based on the above evaluation of the
                                                  evaluation model. Paragraph I.A.5 of                    involve a significant increase in the                 standards set forth in 10 CFR 50.92(c),
                                                  appendix K requires that the Baker-Just                 probability or consequences of an                     the NRC staff concludes that the
                                                  equation be used in the ECCS evaluation                 accident previously evaluated?                        proposed exemption involves no
                                                  model to determine the rate of energy                      Response: No.                                      significant hazards consideration.
                                                  release, cladding oxidation, and                           The proposed exemption would allow                 Accordingly, the requirements of 10
                                                  hydrogen generation. Based on the                       the use of M5 fuel rod cladding material              CFR 51.22(c)(9)(i) are met.
                                                  above, the NRC staff concludes that the                 in the MPS2 reactor. The NRC approved
                                                  intent of 10 CFR 50.46 and appendix K                   topical reports cited above demonstrate               Requirements in 10 CFR 51.22(c)(9)(ii)
                                                  to 10 CFR part 50 will continue to be                   that M5 alloy has similar properties as                 The proposed exemption would allow
                                                  satisfied for the planned operation of                  the currently licensed Zircaloy. The fuel             the use of M5 fuel rod cladding material
                                                  MPS2 with M5 alloy fuel cladding and                    cladding itself is not a postulated                   in the MPS2 reactor. M5 alloy has
                                                  fuel assembly material.                                 initiator of previously evaluated                     similar material properties and
                                                                                                          accidents; thus, fuel cladding material               performance characteristics as the
                                                  D. Consistent With the Common Defense
                                                                                                          does not affect the probability of                    currently licensed Zircaloy cladding.
                                                  and Security
                                                                                                          occurrence of any accident. The                       Thus, the use of M5 fuel rod cladding
                                                    The M5 cladding material is similar in                consequences of none of the previously                material will not significantly change
                                                  design to Zircaloy, the current cladding                evaluated accidents were affected by                  the types of effluents that may be
                                                  material used at MPS2. Thus, the                        fuel cladding material, and M5,                       released offsite, or significantly increase
                                                  change in cladding material from                        likewise, is not expected to have any                 the amount of effluents that may be
                                                  Zircaloy to M5 will not require any                     effect on the consequences of any                     released offsite. Therefore, the
                                                  change to the security and control of                   previously evaluated accidents.                       requirements of 10 CFR 51.22(c)(9)(ii)
                                                  special nuclear material. The licensee                     Therefore, the proposed exemption                  are met.
                                                  will continue to be required to handle                  does not involve a significant increase
                                                  and control special nuclear material in                 in the probability or consequences of an              Requirements in 10 CFR 51.22(c)(9)(iii)
                                                  these assemblies in accordance with its                 accident previously evaluated.                          The proposed exemption would allow
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                                                  approved procedures. This change to                        2. Does the proposed exemption                     the use of M5 fuel rod cladding material
                                                  reactor core internals is adequately                    create the possibility of a new or                    in the reactors. M5 alloy has similar
                                                  controlled by NRC requirements and is                   different kind of accident from any                   material properties and performance
                                                  not related to security issues. Therefore,              accident previously evaluated?                        characteristics as the currently licensed
                                                  the NRC staff determined that this                         Response: No.                                      Zircaloy cladding. Thus, the use of M5
                                                  exemption does not impact, and thus is                     The use of M5 fuel rod cladding                    fuel rod cladding material will not
                                                  consistent with, the common defense                     material will not result in changes in the            significantly increase individual
                                                  and security.                                           operation or configuration of the                     occupational radiation exposure, or


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                                                                               Federal Register / Vol. 80, No. 97 / Wednesday, May 20, 2015 / Notices                                                   29105

                                                  significantly increase cumulative                       www.prc.gov. Those who cannot submit                  interests of the general public (Public
                                                  occupational radiation exposure.                        comments electronically should contact                Representative) in this docket.
                                                  Therefore, the requirements of 10 CFR                   the person identified in the FOR FURTHER
                                                                                                                                                                III. Ordering Paragraphs
                                                  51.22(c)(9)(iii) are met.                               INFORMATION CONTACT section by
                                                                                                          telephone for advice on filing                           It is ordered:
                                                  Conclusion                                                                                                       1. The Commission reopens Docket
                                                                                                          alternatives.
                                                     Based on the above, the NRC staff                                                                          No. CP2015–9 for consideration of
                                                                                                          FOR FURTHER INFORMATION CONTACT:                      matters raised by the Postal Service’s
                                                  concludes that the proposed exemption
                                                                                                          David A. Trissell, General Counsel, at                Notice.
                                                  meets the eligibility criteria for the
                                                                                                          202–789–6820.                                            2. Pursuant to 39 U.S.C. 505, the
                                                  categorical exclusion set forth in 10 CFR
                                                  51.22(c)(9). Therefore, in accordance                   SUPPLEMENTARY INFORMATION:                            Commission appoints Lyudmila Y.
                                                  with 10 CFR 51.22(b), no environmental                  Table of Contents                                     Bzhilyanskaya to serve as an officer of
                                                  impact statement or environmental                                                                             the Commission (Public Representative)
                                                                                                          I. Introduction                                       to represent the interests of the general
                                                  assessment need be prepared in
                                                                                                          II. Notice of Filing                                  public in this proceeding.
                                                  connection with the NRC’s proposed                      III. Ordering Paragraphs
                                                  issuance of this exemption.                                                                                      3. Comments are due no later than
                                                                                                          I. Introduction                                       May 21, 2015.
                                                  IV. Conclusions                                                                                                  4. The Secretary shall arrange for
                                                                                                             On May 13, 2015, the Postal Service                publication of this order in the Federal
                                                     Accordingly, the Commission has                      filed notice that it has agreed to a
                                                  determined that, pursuant to 10 CFR                                                                           Register.
                                                                                                          Modification to the existing Global
                                                  50.12, the exemption is authorized by                                                                           By the Commission.
                                                                                                          Expedited Package Services 3 negotiated
                                                  law, will not present an undue risk to                  service agreement approved in this                    Shoshana M. Grove,
                                                  the public health and safety, and is                    docket.1 In support of its Notice, the                Secretary.
                                                  consistent with the common defense                      Postal Service includes a redacted copy               [FR Doc. 2015–12119 Filed 5–19–15; 8:45 am]
                                                  and security. Also, special                             of the Modification and a certification of            BILLING CODE 7710–FW–P
                                                  circumstances pursuant to 10 CFR                        compliance with 39 U.S.C. 3633(a), as
                                                  50.12(a)(2)(ii) are present. Therefore, the             required by 39 CFR 3015.5. Notice,
                                                  Commission hereby grants Dominion                       Attachments 1 and 2.                                  OFFICE OF SCIENCE AND
                                                  Nuclear Connecticut, Inc., an exemption                    The Postal Service also filed the                  TECHNOLOGY POLICY
                                                  from the requirements of 10 CFR 50.46                   unredacted Modification and supporting
                                                  and Appendix K to 10 CFR part 50, to                    financial information under seal. Notice              Microbiome Research
                                                  allow the application of those criteria to,             at 1. The Postal Service seeks to
                                                  and the use of, M5 fuel rod cladding                                                                          ACTION:Notice of Request for
                                                                                                          incorporate by reference the Application
                                                  material at MPS2.                                                                                             Information
                                                                                                          for Non-Public Treatment originally
                                                     This exemption is effective upon                     filed in this docket for the protection of            SUMMARY:   Advanced sequencing
                                                  issuance.                                               information that it has filed under seal.             technologies have illuminated vast
                                                    Dated at Rockville, Maryland, this 12th               Id. at 1–2.                                           networks of microorganisms that drive
                                                  Day of May, 2015.                                          The Modification adds a new                        essential functions in all environments
                                                  For the Nuclear Regulatory Commission                   paragraph to Article 5 addressing the                 on Earth. The study of these
                                                  Louise Lund,                                            use of permit imprints, adds a new                    communities of microorganisms, or
                                                  Acting Director, Division of Operating Reactor          paragraph to Article 5 (text under seal),             microbiomes, is nascent, and the
                                                  Licensing, Office of Nuclear Reactor                    revises the minimum commitment in                     potential of microbiome research has
                                                  Regulation.                                             Article 11, and replaces Annex 2 (price               only begun to be tapped. Primary to
                                                  [FR Doc. 2015–12264 Filed 5–19–15; 8:45 am]             charts). Id. at 1. The Postal Service                 achieving this potential is a functional
                                                  BILLING CODE 7590–01–P                                  intends the rates in the Modification to              understanding of microbiomes, which
                                                                                                          take effect June 1, 2015. Id. at 1. The               would be greatly advanced by
                                                                                                          Postal Service asserts that the                       addressing fundamental questions
                                                  POSTAL REGULATORY COMMISSION                            Modification will not impair the ability              common to all fields of microbiome
                                                  [Docket No. CP2015–9; Order No. 2483]
                                                                                                          of the contract to comply with 39 U.S.C.              research; developing platform
                                                                                                          3633. Id. Attachment 2.                               technologies useful to all fields; and
                                                  New Postal Product                                                                                            identifying gaps in training or fields of
                                                                                                          II. Notice of Filing
                                                                                                                                                                research that should be addressed. The
                                                  AGENCY: Postal Regulatory Commission.                     The Commission invites comments on                  Office of Science and Technology Policy
                                                  ACTION: Notice.                                         whether the changes presented in the                  (OSTP) is interested in developing an
                                                                                                          Postal Service’s Notice are consistent                effort to unify and focus microbiome
                                                  SUMMARY:   The Commission is noticing a                 with the policies of 39 U.S.C. 3632,                  research across sectors. The views of
                                                  recent Postal Service filing concerning a               3633, or 3642, 39 CFR 3015.5, and 39                  stakeholders—academic and industry
                                                  modification to a Global Expedited                      CFR part 3020, subpart B. Comments are                researchers, private companies, and
                                                  Package Services 3 negotiated service                   due no later than May 21, 2015. The                   charitable foundations—are important
                                                  agreement. This notice informs the                      public portions of these filings can be               to inform an understanding of current
                                                  public of the filing, invites public                    accessed via the Commission’s Web site                and future needs in diverse fields.
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                                                  comment, and takes other                                (http://www.prc.gov).                                 DATES: Responses must be received by
                                                  administrative steps.                                     The Commission appoints Lyudmila                    June 15, 2015, to be considered.
                                                  DATES: Comments are due: May 21,                        Y. Bzhilyanskaya to represent the                     ADDRESSES: You may submit comments
                                                  2015.
                                                                                                            1 Notice of the United States Postal Service of
                                                                                                                                                                by any of the following methods:
                                                  ADDRESSES:   Submit comments                            Filing Modification to Global Expedited Package
                                                                                                                                                                   • Email: MicrobiomeRFI@
                                                  electronically via the Commission’s                     Services 3 Negotiated Service Agreement, May 13,      ostp.eop.gov. Include [Microbiome RFI]
                                                  Filing Online system at http://                         2015 (Notice).                                        in the subject line of the message.


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Document Created: 2018-02-21 10:29:59
Document Modified: 2018-02-21 10:29:59
CategoryRegulatory Information
CollectionFederal Register
sudoc ClassAE 2.7:
GS 4.107:
AE 2.106:
PublisherOffice of the Federal Register, National Archives and Records Administration
SectionNotices
ActionExemption; issuance.
DatesMay 20, 2015.
ContactRichard V. Guzman, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-1030, email: [email protected]
FR Citation80 FR 29102 

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