81 FR 51218 - Virginia Electric Power Company; Surry Power Station, Unit Nos. 1 and 2; Use of AREVA's M5® Alloy Fuel Rod Cladding Material
NUCLEAR REGULATORY COMMISSION Federal Register Volume 81, Issue 149 (August 3, 2016)
Federal Register Volume 81, Issue 149 (August 3, 2016)
| Page Range | 51218-51220 | |
| FR Document | 2016-18375 |
[Federal Register Volume 81, Number 149 (Wednesday, August 3, 2016)] [Notices] [Pages 51218-51220] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2016-18375] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-280 and 50-281 NRC-2016-0105] Virginia Electric Power Company; Surry Power Station, Unit Nos. 1 and 2; Use of AREVA's M5[supreg] Alloy Fuel Rod Cladding Material AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a September 30, 2016, request from Virginia Electric Power Company (Dominion or the licensee) in order to use AREVA's M5[supreg] alloy fuel rod cladding material at Surry Power Station, Unit Nos. 1 and 2 (SPS). DATES: The exemption was issued on July 27, 2016. ADDRESSES: Please refer to Docket ID NRC-2016-0105 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-2016-0105. 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 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 in this document (if that document is 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: Karen R. Cotton, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-1438, email: [email protected]. SUPPLEMENTARY INFORMATION: I. Background Dominion is the holder of Facility Operating License Nos. DPR-32 and DPR-37, which authorize operation of SPS. The licenses provide, among other things, that the facility is subject to all rules, regulations, and orders of the NRC now or hereafter in effect. The facility consists of two pressurized-water reactors (PWR) located in Surry County, Virginia. II. Request/Action Pursuant to Sec. 50.12 of title 10 of the Code of Federal Regulations (10 CFR), ``Specific exemptions,'' the licensee has requested, by letter dated September 30, 2015 (ADAMS Accession No. ML15282A036), 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 rods clad with AREVA's M5[supreg] alloy. The regulations in 10 CFR 50.46 require that the calculated cooling performance following postulated loss-of-coolant accidents (LOCAs) at reactors fueled with zircaloy or ZIRLOTM cladding conforms to the criteria set forth in 10 CFR 50.46(b). In addition, 10 CFR part [[Page 51219]] 50, appendix K, requires, in part, 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 zircaloy or ZIRLOTM materials that have different chemical compositions from AREVA's M5[supreg] alloy. As written, these regulations presume only the use of zircaloy or ZIRLOTM fuel rod cladding and do not contain provisions for use of fuel rods with other cladding materials. Therefore, an exemption from the requirements of 10 CFR 50.46 and 10 CFR part 50, appendix K, is needed to support the use of a different fuel cladding material. Accordingly, the licensee requested an exemption that would allow the use of fuel rods clad with AREVA's M5[supreg] alloy to be loaded into the SPS reactor cores as non-limiting lead test assemblies (LTAs) in up to eight locations. 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 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. However, 10 CFR 50.12(a)(2) states that the Commission will not consider granting an exemption unless special circumstances are present as set forth in 10 CFR 50.12(a)(2). Under 10 CFR 50.12(a)(2)(ii), special circumstances are present when application of the regulation in the particular circumstances 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 10 CFR part 50, appendix K, is to establish acceptance criteria for ECCS performance to provide reasonable assurance of safety in the event of a LOCA. The special circumstance that necessitates the request for exemption to 10 CFR 50.46 and 10 CFR 50, appendix K, is that neither of these regulations explicitly allows the use of AREVA's M5[supreg] alloy fuel rod cladding material. The ultimate objective of 10 CFR 50.46 is to ensure that nuclear power reactors fueled with uranium oxide pellets within zircaloy or ZIRLOTM cladding must be provided with an ECCS that is designed to provide core cooling following a postulated LOCA. AREVA NP, in its NRC-approved Topical Report BAW-10227-A, ``Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel,'' February 2000 (ADAMS Accession No. ML003686365), has demonstrated that the effectiveness of the ECCS will not be affected by a change from zircaloy or ZIRLOTM clad fuel to fuel rods clad with AREVA's M5[supreg] alloy. Normal reload safety analyses will confirm that there is no adverse impact on ECCS performance. The objective of 10 CFR 50.46(b)(2) and (b)(3), and 10 CFR part 50, appendix K I.A.5, is to ensure that cladding oxidation and hydrogen generation are appropriately limited during a LOCA and conservatively accounted for in the ECCS evaluation model. Appendix K of 10 CFR part 50 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. AREVA NP has shown in an appendix of Topical Report BAW-10227-A that the Baker-Just model is conservative in all post-LOCA scenarios with respect to the use of AREVA's M5[supreg] alloy fuel rod cladding material. Based on the regulatory review of the exemption request, the NRC staff concludes that the intent of 10 CFR 50.46 and 10 CFR part 50, appendix K, will continue to be satisfied for the planned operation of SPS with AREVA's M5[supreg] alloy fuel rod cladding material used for non-limiting LTAs and the special circumstance required by 10 CFR 50.12(a)(2)(ii) for granting of an exemption exists. B. Authorized by Law This exemption would allow the use of fuel rods clad with AREVA's M5[supreg] alloy in up to eight fuel assemblies at SPS. The regulations in 10 CFR 50.12 allow the NRC to grant exemptions from the requirements of 10 CFR part 50 provided that the exemptions are authorized by law. The NRC staff determined that special circumstances exist to grant the proposed exemption and that granting the exemption would not result in a violation of the Atomic Energy Act of 1954, as amended. Therefore, the exemption is authorized by law. C. No Undue Risk to Public Health and Safety The provisions of 10 CFR 50.46 establish acceptance criteria for ECCS performance. Topical Report BAW-10227-A contains the justification to use AREVA's M5[supreg] alloy fuel rod cladding material, a proprietary variant of Zr1Nb, to replace Zircaloy-4 in the construction of fuel assembly components such as fuel rod cladding, guide tubes, and spacer grids. This justification is required to support the request by Dominion for an exemption to 10 CFR 50.46 to permit the use of AREVA's M5[supreg] alloy fuel rod cladding material, in addition to Zircaloy-4 and ZIRLOTM. AREVA's M5[supreg] alloy is an AREVA NP proprietary material composed of 1.0 percent niobium, 0.125 percent oxygen, and the balance zirconium. AREVA's M5[supreg] alloy fuel rod cladding provides improved performance in fuel cladding corrosion and hydrogen pickup. An AREVA NP LOCA evaluation showed compliance with 10 CFR 50.46. Topical Report BAW-10227-A has addressed all of the important aspects of AREVA's M5[supreg] alloy fuel rod cladding material with respect to ECCS performance requirements, as follows: Since the material properties of AREVA's M5[supreg] alloy are similar to those of zirconium-based materials, the NRC staff found it appropriately conservative to apply the criteria in 10 CFR 50.46 and 10 CFR part 50, appendix K. Material properties of AREVA's M5[supreg] alloy, including cladding thermal conductivity, cladding creep, clad swelling, rupture deformation, and temperature, were found to be very similar to those of Zircaloy-4. The retention of the Baker-Just equation for the calculation of metal-water reaction rate specified in 10 CFR part 50, appendix K, is justified to be suitably conservative. Based on the NRC staff's evaluation of the exemption request, the staff concludes that the intent of 10 CFR 50.46 and 10 CFR part 50, appendix K, will continue to be satisfied for the planned operation of SPS, with AREVA's M5[supreg] alloy fuel rod cladding material used in up to eight non-limiting LTAs. The probability of postulated accidents is not increased. Also, based on the NRC staff's evaluation of the exemption request, the consequences of postulated accidents are not increased. Therefore, there is no undue risk to public health and safety due to using M5[supreg] alloy fuel cladding and fuel assembly material in up to eight non-limiting LTAs. D. Consistent With the Common Defense and Security The proposed exemption would allow the use of AREVA's M5[supreg] alloy fuel rod cladding material at SPS. This change to the plant configuration is adequately controlled by technical specification [[Page 51220]] requirements and is not related to security issues. Because the common defense and security is not impacted by this exemption, the exemption is consistent with the common defense and security. IV. Conclusions Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12(a), the exemption is authorized by law, will not present an undue risk to the public health and safety, is consistent with the common defense and security, and that special circumstances are present to warrant issuance of the exemption. Therefore, the Commission hereby grants SPS an exemption from the requirements of 10 CFR 50.46 and 10 CFR part 50, appendix K, paragraph I.A.5, to allow the use of AREVA's M5[supreg] alloy fuel rod cladding material in up to eight non-limiting LTAs at SPS. Pursuant to 10 CFR 51.32, an environmental assessment and finding of no significant impact related to this exemption was published in the Federal Register on May 31, 2016 (81 FR 34382). Based upon the environmental assessment, the Commission has determined that issuance of this exemption will not have a significant effect on the quality of the human environment. This exemption is effective upon issuance. Dated at Rockville, Maryland, this 27th day of July 2016. For the Nuclear Regulatory Commission. Anne T. Boland, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2016-18375 Filed 8-2-16; 8:45 am] BILLING CODE 7590-01-P
![51218 Federal Register / Vol. 81, No. 149 / Wednesday, August 3, 2016 / Notices
otherwise be inconsistent with the issue a manner that is inconsistent with any technical questions, contact the
finality provisions in 10 CFR part 52. issue finality provisions. If, in the individual listed in the FOR FURTHER
The NRC’s position is based upon the future, the NRC staff seeks to impose a INFORMATION CONTACT section of this
following considerations: position in the SRP in a manner which document.
1. The SRP positions do not constitute does not provide issue finality as • NRC’s Agencywide Documents
backfitting, inasmuch as the SRP is described in the applicable issue finality Access and Management System
internal guidance directed at the NRC provision, then the NRC staff must (ADAMS): You may obtain publicly-
staff with respect to their regulatory address the criteria for avoiding issue available documents online in the
responsibilities. finality as described in the applicable ADAMS Public Documents collection at
The SRP provides guidance to the issue finality provision. http://www.nrc.gov/reading-rm/
NRC staff on how to review an adams.html. To begin the search, select
application for the NRC’s regulatory III. Congressional Review Act
‘‘ADAMS Public Documents’’ and then
approval in the form of licensing. This SRP section revision is a rule as select ‘‘Begin Web-based ADAMS
Changes in internal NRC staff guidance defined in the Congressional Review Search.’’ For problems with ADAMS,
are not matters for which either nuclear Act (5 U.S.C. 801–808). However, the please contact the NRC’s Public
power plant applicants or licensees are Office of Management and Budget has Document Room (PDR) reference staff at
protected under either the Backfit Rule not found it to be a major rule as 1–800–397–4209, 301–415–4737, or by
or the issue finality provisions of 10 defined in the Congressional Review email to pdr.resource@nrc.gov. The
CFR part 52. Act. ADAMS accession number for each
2. The NRC staff has no intention to document referenced in this document
impose the SRP positions on current Dated at Rockville, Maryland, this 29th day
of July 2016. (if that document is available in
licensees and regulatory approvals ADAMS) is provided the first time that
either now or in the future. For the Nuclear Regulatory Commission.
Joseph Colaccino, a document is referenced.
The NRC staff does not intend to
Chief, New Reactor Rulemaking and
• NRC’s PDR: You may examine and
impose or apply the positions described
Guidance Branch, Division of Engineering, purchase copies of public documents at
in the SRP to existing (already issued)
Infrastructure, and Advanced Reactors, Office the NRC’s PDR, Room O1–F21, One
licenses and regulatory approvals.
of New Reactors. White Flint North, 11555 Rockville
Therefore, the issuance of a final SRP—
even if considered guidance that is [FR Doc. 2016–18390 Filed 8–2–16; 8:45 am] Pike, Rockville, Maryland 20852.
within the purview of the issue finality BILLING CODE 7590–01–P FOR FURTHER INFORMATION CONTACT:
provisions in 10 CFR part 52—need not Karen R. Cotton, Office of Nuclear
be evaluated as if it were a backfit or as Reactor Regulation, U.S. Nuclear
being inconsistent with issue finality NUCLEAR REGULATORY Regulatory Commission, Washington,
provisions. If, in the future, the NRC COMMISSION DC 20555–0001; telephone: 301–415–
staff seeks to impose a position in the [Docket Nos. 50–280 and 50–281 NRC– 1438, email: Karen.Cotton@nrc.gov.
SRP on holders of already issued 2016–0105] SUPPLEMENTARY INFORMATION:
licenses in a manner which does not
Virginia Electric Power Company; I. Background
provide issue finality as described in the
applicable issue finality provision, then Surry Power Station, Unit Nos. 1 and Dominion is the holder of Facility
the NRC staff must make the showing as 2; Use of AREVA’s M5® Alloy Fuel Rod Operating License Nos. DPR–32 and
set forth in the Backfit Rule or address Cladding Material DPR–37, which authorize operation of
the criteria for avoiding issue finality as SPS. The licenses provide, among other
AGENCY: Nuclear Regulatory things, that the facility is subject to all
described in the applicable issue finality Commission.
provision. rules, regulations, and orders of the NRC
3. Backfitting and issue finality do ACTION: Exemption; issuance. now or hereafter in effect.
not—with limited exceptions not The facility consists of two
SUMMARY: The U.S. Nuclear Regulatory
applicable here—protect current or pressurized-water reactors (PWR)
Commission (NRC) is issuing an
future applicants. located in Surry County, Virginia.
exemption in response to a September
Applicants and potential applicants
30, 2016, request from Virginia Electric II. Request/Action
are not, with certain exceptions,
Power Company (Dominion or the Pursuant to § 50.12 of title 10 of the
protected by either the Backfit Rule or
licensee) in order to use AREVA’s M5® Code of Federal Regulations (10 CFR),
any issue finality provisions under 10
alloy fuel rod cladding material at Surry ‘‘Specific exemptions,’’ the licensee has
CFR part 52. This is because neither the
Power Station, Unit Nos. 1 and 2 (SPS). requested, by letter dated September 30,
Backfit Rule nor the issue finality
provisions under 10 CFR part 52—with DATES: The exemption was issued on 2015 (ADAMS Accession No.
certain exclusions discussed in the next July 27, 2016. ML15282A036), an exemption from 10
paragraph—were intended to apply to ADDRESSES: Please refer to Docket ID CFR 50.46, ‘‘Acceptance criteria for
every NRC action which substantially NRC–2016–0105 when contacting the emergency core cooling systems [ECCS]
changes the expectations of current and NRC about the availability of for light-water nuclear power reactors,’’
future applicants. information regarding this document. and 10 CFR part 50, appendix K, ‘‘ECCS
The exceptions to the general You may obtain publicly-available Evaluation Models,’’ to allow the use of
asabaliauskas on DSK3SPTVN1PROD with NOTICES
principle are applicable whenever an information related to this document fuel rods clad with AREVA’s M5® alloy.
applicant references a 10 CFR part 52 using any of the following methods: The regulations in 10 CFR 50.46 require
license (e.g., an early site permit) and/ • Federal Rulemaking Web site: Go to that the calculated cooling performance
or NRC regulatory approval (e.g., a http://www.regulations.gov and search following postulated loss-of-coolant
design certification rule) with specified for Docket ID: NRC–2016–0105. Address accidents (LOCAs) at reactors fueled
issue finality provisions. The NRC staff questions about NRC dockets to Carol with zircaloy or ZIRLOTM cladding
does not, at this time, intend to impose Gallagher; telephone: 301–415–3463; conforms to the criteria set forth in 10
the positions represented in the SRP in email: Carol.Gallagher@nrc.gov. For CFR 50.46(b). In addition, 10 CFR part
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![51220 Federal Register / Vol. 81, No. 149 / Wednesday, August 3, 2016 / Notices
requirements and is not related to www.prc.gov. Those who cannot submit interests of the general public in this
security issues. Because the common comments electronically should contact proceeding.
defense and security is not impacted by the person identified in the FOR FURTHER 3. Comments by interested persons
this exemption, the exemption is INFORMATION CONTACT section by are due by August 4, 2016.
consistent with the common defense telephone for advice on filing 4. The Secretary shall arrange for
and security. alternatives. publication of this order in the Federal
Register.
IV. Conclusions FOR FURTHER INFORMATION CONTACT:
David A. Trissell, General Counsel, at By the Commission.
Accordingly, the Commission has Stacy L. Ruble,
determined that, pursuant to 10 CFR 202–789–6820.
Secretary.
50.12(a), the exemption is authorized by SUPPLEMENTARY INFORMATION:
[FR Doc. 2016–18310 Filed 8–2–16; 8:45 am]
law, will not present an undue risk to Table of Contents BILLING CODE 7710–FW–P
the public health and safety, is
consistent with the common defense I. Introduction
and security, and that special II. Notice of Commission Action
III. Ordering Paragraphs SECURITIES AND EXCHANGE
circumstances are present to warrant
issuance of the exemption. Therefore, I. Introduction COMMISSION
the Commission hereby grants SPS an [Release No. 34–78438; File No. SR–OCC–
On July 27, 2016, the Postal Service
exemption from the requirements of 10 2016–002]
filed a notice of a minor classification
CFR 50.46 and 10 CFR part 50,
change regarding the Country Price Lists Self-Regulatory Organizations; The
appendix K, paragraph I.A.5, to allow
for International Mail in Part D of the Options Clearing Corporation; Notice
the use of AREVA’s M5® alloy fuel rod
Mail Classification Schedule (MCS), of Filing of Proposed Rule Change
cladding material in up to eight non-
under Commission rules 39 CFR Concerning Enhancements to The
limiting LTAs at SPS.
Pursuant to 10 CFR 51.32, an 3020.90 and 3020.91.1 The Postal Options Clearing Corporation’s
environmental assessment and finding Service also presents proposed changes Governance Arrangements
of no significant impact related to this to the MCS. Notice at 2; Attachment 1.
The Postal Service states that the July 28, 2016.
exemption was published in the Federal Pursuant to Section 19(b)(1) of the
Register on May 31, 2016 (81 FR 34382). proposed changes are minor in nature
and are not inconsistent with 39 U.S.C. Securities Exchange Act of 1934
Based upon the environmental (‘‘Act’’) 1 and Rule 19b–4 thereunder,2
assessment, the Commission has 3642. Notice at 3.
MCS change. The Postal Service plans notice is hereby given that on July 15,
determined that issuance of this 2016, The Options Clearing Corporation
exemption will not have a significant to provide outbound Priority Mail
Express International (PMEI) service to (‘‘OCC’’) filed with the Securities and
effect on the quality of the human Exchange Commission (‘‘Commission’’)
environment. Cuba. Id. at 1. Accordingly, the Postal
Service seeks to assign Country Group 9 the proposed rule change as described
This exemption is effective upon in Items I, II and III below, which Items
issuance. to Cuba for variable weight PMEI and
Country Group 8 to Cuba for PMEI Flat have been prepared by OCC. The
Dated at Rockville, Maryland, this 27th day Commission is publishing this notice to
Rate Envelope. Id. at 2.
of July 2016. solicit comments on the proposed rule
For the Nuclear Regulatory Commission. II. Notice of Commission Action change from interested persons.
Anne T. Boland, Pursuant to 39 CFR 3020.92, the I. Clearing Agency’s Statement of the
Director, Division of Operating Reactor Commission has posted the Notice on Terms of Substance of the Proposed
Licensing, Office of Nuclear Reactor its Web site and invites comments on
Regulation.
Rule Change
whether the Postal Service’s filings in
[FR Doc. 2016–18375 Filed 8–2–16; 8:45 am] Docket No. MC2016–172 are consistent This proposed rule change by The
BILLING CODE 7590–01–P with the policies of 39 U.S.C. 3642 and Options Clearing Corporation (‘‘OCC’’)
39 CFR 3020 subpart E. Comments are concerns modifications and
due no later than August 4, 2016. The enhancements to OCC’s governance
POSTAL REGULATORY COMMISSION public portions of these filings can be arrangements. OCC is proposing to
accessed via the Commission’s Web site amend its Certificate of Incorporation,
[Docket No. MC2016–172; Order No. 3451] By-Laws, and Board of Directors
(http://www.prc.gov).
(‘‘Board’’) Charter to require that only
New Postal Product The Commission appoints Katrina R.
one Management Director serve on
Martinez to represent the interests of the
AGENCY: Postal Regulatory Commission. OCC’s Board (as opposed to the current
general public (Public Representative)
ACTION: Notice. requirement of two Management
in this docket.
Directors). Moreover, OCC is proposing
SUMMARY: The Commission is noticing a III. Ordering Paragraphs to amend its By-Laws and Rules to
recent Postal Service filing concerning delete all references to the title and
IT IS ORDERED:
minor classification changes to the responsibilities of the Management Vice
1. The Commission establishes Docket
Country Price Lists for International Chairman. In addition, OCC is
No. MC2016–172 to consider matters
asabaliauskas on DSK3SPTVN1PROD with NOTICES
Mail. This notice informs the public of proposing to amend its By-Laws to: (i)
raised by the Notice.
the filing, invites public comment, and Provide that the Compensation and
2. Pursuant to 39 U.S.C. 505, Katrina
takes other administrative steps. Performance Committee (‘‘CPC’’) 3 and
R. Martinez is appointed to serve as an
DATES: Comments are due: August 4,
officer of the Commission (Public
2016. Representative) to represent the
1 15 U.S.C. 78s(b)(1).
2 17 CFR 240.19b–4.
ADDRESSES: Submit comments 3 As described below, the Performance Committee
electronically via the Commission’s 1 Notice of United States Postal Service of Minor would be renamed as the Compensation and
Filing Online system at http:// Classification Change, July 27, 2016 (Notice). Performance Committee.
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Document Created: 2016-08-02 23:44:02
Document Modified: 2016-08-02 23:44:02
| Category | Regulatory Information | |
| Collection | Federal Register | |
| sudoc Class | AE 2.7: GS 4.107: AE 2.106: | |
| Publisher | Office of the Federal Register, National Archives and Records Administration | |
| Section | Notices | |
| Action | Exemption; issuance. | |
| Dates | The exemption was issued on July 27, 2016. | |
| Contact | Karen R. Cotton, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-1438, email: [email protected] | |
| FR Citation | 81 FR 51218 |
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