81 FR 8750 - Independent Spent Fuel Storage Installation, Yankee Atomic Electric Company
NUCLEAR REGULATORY COMMISSION Federal Register Volume 81, Issue 34 (February 22, 2016)
Federal Register Volume 81, Issue 34 (February 22, 2016)
| Page Range | 8750-8752 | |
| FR Document | 2016-03591 |
[Federal Register Volume 81, Number 34 (Monday, February 22, 2016)] [Notices] [Pages 8750-8752] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2016-03591] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-029, and 72-1025; NRC 2016-0029] Independent Spent Fuel Storage Installation, Yankee Atomic Electric Company AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a September 1, 2015, request from Yankee Atomic Electric Company, (YAEC or licensee) from the requirement to comply with the terms, conditions, and specifications regarding the method of compliance defined in Amendment No. 5 of the NAC International, Inc. (NAC),--MPC Certificate of Compliance (CoC) No. 1025, Appendix A ``Technical Specifications for NAC-MPC System,'' Technical Specifications (TS) A.5.3 ``Surveillance After an Off-Normal, Accident, or Natural Phenomena Event'' at the Yankee Nuclear Power Station (YNPS) Independent Spent Fuel Storage Installation (ISFSI). The exemption request seeks a modification of TS A 5.3 inspection requirements for the inlet and outlet vents following off-normal, accident and natural phenomena events. ADDRESSES: Please refer to Docket ID NRC-2016-0029 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-2016-0029. 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: John Goshen, Office of Nuclear Material Safety and Safeguards, telephone: 301-415-6933, email: [email protected]; U.S. Nuclear Regulatory Commission, Washington, DC 20555. SUPPLEMENTARY INFORMATION: I. Background The licensee is the holder of Facility Operating License No. DPR-3 which authorizes operation of the YNPS located near Rowe, Massachusetts, pursuant to part 50 of title 10 of the Code of Federal Regulations (10 CFR). The facility is in decommissioned status. 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. Under subpart K of 10 CFR part 72, a general license has been issued for the storage of spent fuel in an ISFSI at power reactor sites to persons authorized to possess or operate nuclear power reactors under 10 CFR part 50. The licensee is licensed to operate a nuclear power reactor under 10 CFR part 50, and authorized under the 10 CFR part 72 general license to store spent fuel at the YNPS ISFSI. Under the terms of the general license, YNPS stores spent fuel using Amendment No. 5 of the NAC-MPC CoC No. 1025. II. Request/Action YAEC requests an exemption from 10 CFR 72.212(b)(3), 10 CFR 72.212(b)(5)(i), and 10 CFR 72.214 for the YNPS ISFSI. Section 72.212(b)(3) requires that a general licensee use casks that conform to the terms, conditions, and specifications of a CoC or amended CoC listed in Sec. 72.214. The NAC-MPC CoC No. 1025 is listed in 10 CFR 72.214. Section 72.212(b)(5)(i) requires, in relevant part, that a general licensee demonstrate a loaded cask will conform to the terms, conditions, and specifications of a CoC for a cask listed in Sec. 72.214. Section 72.214 lists casks which are approved for storage of spent fuel under conditions specified in their CoCs, including CoC 1025 and Amendment No. 5. The licensee, as a 10 CFR 72 general licensee, is required to use the NAC-MPC System according to the technical specifications of the NAC-MPC System CoC No. 1025. Amendment No. 5 of the NAC-MPC CoC No. 1025, Appendix A, ``Technical Specifications for the NAC-MPC System,'' TS A 5.3, ``Surveillance After an Off-Normal, Accident, or Natural Phenomena Event,'' requires that a general licensee undertake a visual surveillance of the NAC-MPC casks within 4 hours after the occurrence of an off-normal, accident or natural phenomena event in the area of the ISFSI. This NAC-MPC cask inspection is part of the general licensee's surveillance response to verify that all the CONCRETE CASK inlets and outlets are not blocked or obstructed. The NAC-MPC TS A 5.3 also requires that at least one-half of the inlets and outlets on each CONCRETE CASK be cleared of blockage or debris within 24 hours to restore air circulation. [[Page 8751]] The licensee seeks the NRC's authorization to use NAC-MPC TS A 3.1.6 as an alternative to the visual surveillance method specified in NAC-MPC TS A 5.3. technical Specification A 3.1.6 permits (either) visual surveillance of the inlets and outlets screens or temperature monitoring of each cask to establish the operability of the Concrete Cask Heat Removal System for each NAC-MPC cask and to show that the limiting conditions for operation under 3.1.6 are met. Technical Specification A 3.1.6 establishes ongoing requirements that YNPS must comply with during all phases of the cask storage operations, not only after an unusual event in the area of the ISFSI. In effect, TS A 3.1.6 provides continuous temperature monitoring or visual verification to establish operability of the Concrete Cask Heat Removal System for all NAC-MPC CoC No. 1025 casks. The proposed alternative for implementing TS A 5.3 provides that Surveillance Requirement (SR) 3.1.6.1 is required following off-normal, accident or natural phenomena events. The NAC-MPC Systems in use at an ISFSI shall be inspected in accordance with SR 3.1.6.1 within 4 hours after the occurrence of an off-normal, accident or natural phenomena event in the area of the ISFSI to confirm operability of the CONCRETE CASK Heat Removal System for each NAC-MPC System. Additionally, if a CONCRETE CASK Heat Removal System(s) for one or more NAC-MPC Systems is determined to be inoperable, Required Action A.1 of TS A 3.1.6 requires the licensee to restore the affected Concrete Cask Heat Removal System(s) to an operable condition within 8 hours. The NAC-MPC Final Safety Analysis Report (FSAR) supports the use of either method defined in SR 3.1.6.1 to establish operability to comply with NAC-MPC TS A 3.1.6 or NAC-MPC TS A 5.3. Section 11.1.1 of the FSAR states, ``Blockage of Half of the Air Inlets would be detected by the daily concrete cask operability inspection, which is performed either by the outlet air temperature measurements or by visual inspection of the inlet and outlet screens for blockage and integrity.'' III. Discussion Under 10 CFR 72.7, the Commission may, upon application by any interested person or upon its own initiative, grant an exemption from the requirements of 10 CFR part 72 if the exemption is authorized by law, will not endanger life or property or the common defense and security and is otherwise in the public interest. As explained below, the proposed exemption is lawful, will not endanger life or property, or the common defense and security, and is otherwise in the public interest. The ADAMS accession numbers for the applicable documents are: ------------------------------------------------------------------------ ADAMS accession Document Date No. ------------------------------------------------------------------------ Exemption Request............ September 1, 2015.... ML15254A050 Letter of transmittal........ NA................... ML16033A150 ------------------------------------------------------------------------ The Exemption Is Authorized by Law The exemption would permit the licensee to use either of the inspection methods permitted by NAC-MPC TS A 3.1.6 as an alternative to the single surveillance method in NAC-MPC TS A 5.3. The licensee would conduct a surveillance response within 4 hours after the occurrence of an off-normal, accident, or natural phenomena event, as required by NAC-MPC TS A 5.3, but would be permitted to use either temperature monitoring or visual inspection to ensure the Concrete Cask Heat Removal Systems are within the limiting conditions for operation. The exemption is limited to off-normal, accident, or natural phenomena events, specifically major snow or icing events (snow/ice events that have the potential to or that exceed blockage of greater than one-half of the inlet or outlet vents). The licensee requested an exemption from the provisions in 10 CFR part 72 that require the licensee to comply with the terms, conditions, and specifications of the CoC for the approved cask model that it uses. Section 72.7 of 10 CFR allows the NRC to grant exemptions from the requirements of 10 CFR part 72. Issuance of this exemption is consistent with the Atomic Energy Act of 1954, as amended, and is not inconsistent with NRC regulations or other applicable laws. As explained below, the proposed exemption will not endanger life or property, or the common defense and security, and is otherwise in the public interest. Therefore, the exemption is authorized by law. The Exemption Is Consistent With the Common Defense and Security The requested exemption would allow the licensee to use the SR, conditions, required actions, and completion times defined in NAC-MPC TS A 3.1.6 as an alternative to the single-method surveillance response in NAC-MPC TS A 5.3. Technical Specification A 3.1.6 permits (either) visual inspection of the inlet and outlet screens or temperature monitoring to establish the operability of the Concrete Cask Heat Removal System for each NAC-MPC System and to comply with the limiting conditions for operation for TS A 3.1.6. SR 3.1.6.1 permits temperature monitoring or visual inspection of the inlet and outlet screens to be utilized to establish the operability of the Concrete Cask Heat Removal System for each NAC-MPS System to meet Limiting Condition for Operation 3.1.6. In the event the applicable acceptance criterion of SR 3.1.6.1 is not met, Required Action A.1 requires the licensee to restore the affected Concrete Cask Heat Removal System(s) to an operable condition within 8 hours. The NRC staff reviewed the licensee's request and finds allowing the use of either visual surveillance of the inlet and outlet screens or temperature monitoring of the inlets and outlets within 4 hours of the occurrence of off-normal, accident, or natural phenomena events, when limited to major snow and icing events, does not compromise safety. The exemption still requires the licensee to perform SR 3.1.6.1 to establish the operability of the Concrete Cask Heat Removal Systems event 24 hours via temperature monitoring or visual inspection of the inlet and outlet screens. In addition, the exemption provides no additional time to complete the required surveillance of the inlets and outlets screens in accordance with TS A 5.3. The use of either method will ensure that adequate air flows past the storage canister and that heat transfer occurs. For these reasons, the NRC staff found the same level of safety is obtained by using either of the TS A 3.1.6 methods to comply with NAC-MPC TS A 5.3 during limited types off-normal, accident, or natural phenomena. The NRC staff has determined that the thermal, structural, criticality, [[Page 8752]] retrievability, and radiation protection requirements of 10 CFR part 72 and the offsite dose limits of 10 CFR part 20 will be maintained. For these reasons, the staff finds the same level of safety is obtained by using either of the TS A 3.1.6 methods to comply with NAC-MPC TS A 5.3. Therefore, the NRC concludes that the exemption will not endanger life or property or the common defense and security. The Exemption Presents No Undue Risk to Public Health and Safety As described in the application, exempting the licensee from visual surveillance of cask inlet and outlet vents within 4-hours of a major snowstorm would allow the licensee to more effectively prioritize important storm-related activities at the YNPS site. Snow and ice blockage of the inlet and outlet vents is unusual. Moreover, snow and ice blockages are identified reliably by temperature monitoring of individual casks. The NRC staff recognizes there is a risk to the safety of workers responsible for clearing snow and ice from cask pads during extreme winter conditions when visual surveillance of casks must be undertaken within 4 hours. The NRC staff finds this risk to workers can be reduced by using SR 3.1.6.1 to establish the operability of the Concrete Cask Heat Removal Systems via temperature monitoring or visual inspection of the inlet and outlet screens. In addition, the limiting conditions for operation of the NAC-MPC System require the Concrete Cask Heat Removal System for each cask to be operable during storage operations thus ensuring public health and safety are not reduced. Therefore the NRC staff finds that allowing the licensee to use the SR, conditions, required actions, and completion times defined in NAC- MPC TS A 3.1.6 as an alternative to the single-method surveillance response in NAC-MPC TS A 5.3 would reduce worker safety risks to plant workers involved in snow removal. Therefore, granting the exemption is otherwise in the public interest. Environmental Considerations The staff evaluated whether there would be significant environmental impacts associated with the issuance of the requested exemption. The staff determined the proposed action fits a category of actions that do not require an environmental assessment or environmental impact statement. The exemption meets the categorical exclusion requirements of 10 CFR 51.22(c)(25)(i)-(vi). Granting an exemption from the requirements of 10 CFR 72.212(b)(3), 10 CFR 72.212(b)(5)(i), and 10 CFR 72.214 for the YNPS ISFSI involves the visual surveillance requirement associated with TS A 5.3A. A categorical exclusion for inspection and SRs is provided under 10 CFR 51.22(c)(25)(vi)(C), if the criteria in 10 CFR 51.22(c)(25)(i)-(v) are also satisfied. The granting of the exemption: (i) Would not involve a significant hazards consideration because it does not reduce a margin of safety, create a new or different kind of accident not previously evaluated, or significantly increase the probability or consequences of an unevaluated accident; (ii) would not create a significant change in the types or significant increase in the amounts of any effluents that may be released offsite because the exemption does not change or produce additional avenues of effluent release; (iii) would not significantly increase individual or cumulative public or occupational radiation exposure because the exemption does not introduce new or increased radiological hazards; (iv) would not result in significant construction impacts because the exemption would not involve construction or other ground disturbing activities, nor change the footprint of the existing ISFSI; v) would not significantly increase the potential for, or consequences from, radiological accidents because the exemption requires a surveillance method that ensures the heat removal system of casks is maintained within the limiting conditions for operation; and (vi) the request seeks exemption from inspection or surveillance requirements, specifically, the single-method surveillance requirement in NAC-MPC TS A 5.3, may be substituted with the SR, conditions, required actions, and completion times defined in NAC-MPC TS 3.1.6. In its review of the exemption request, the NRC staff determined the proposed exemption meets the eligibility criterion for categorical exclusion in 10 CFR 51.22(c)(25). Therefore, there are no significant radiological environmental impacts associated with the proposed action. IV. Conclusion The NRC has determined that, under 10 CFR 72.7, the exemption is authorized by law, will not endanger life or property or the common defense and security, and is otherwise in the public interest. Therefore, the NRC grants YAEC an exemption from the requirements in10 CFR 72.212(b)(3), 10 CFR 72.212(b)(5)(i), 10 CFR 72.214, and to TS A.5.3 for the NAC-MPC System CoC No. 1025 storage casks at the YNPS ISFSI. The exemption authorizes the licensee to use the SR, conditions, required actions, and completion times defined in NAC-MPC TS A 3.1.6 to comply with NAC-MPC TS A 5.3 after off-normal, accident, or natural phenomena events, but is specifically limited to major snow or icing events (events that have the potential to or that exceed blockage of greater than one-half of the inlet or outlet vents). This exemption is effective upon issuance. Dated at Rockville, Maryland, this 4th day of February, 2016. For the Nuclear Regulatory Commission. Steve Ruffin, Acting Chief, Spent Fuel Licensing Branch, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2016-03591 Filed 2-19-16; 8:45 am] BILLING CODE 7590-01-P
![8750 Federal Register / Vol. 81, No. 34 / Monday, February 22, 2016 / Notices
The schedule for Commission Certificate of Compliance (CoC) No. Code of Federal Regulations (10 CFR).
meetings is subject to change on short 1025, Appendix A ‘‘Technical The facility is in decommissioned
notice. For more information or to verify Specifications for NAC–MPC System,’’ status. The license provides, among
the status of meetings, contact Denise Technical Specifications (TS) A.5.3 other things, that the facility is subject
McGovern at 301–415–0681 or via email ‘‘Surveillance After an Off-Normal, to all rules, regulations, and orders of
at Denise.McGovern@nrc.gov. Accident, or Natural Phenomena Event’’ the NRC now or hereafter in effect.
* * * * * at the Yankee Nuclear Power Station Under subpart K of 10 CFR part 72,
The NRC Commission Meeting (YNPS) Independent Spent Fuel Storage a general license has been issued for the
Schedule can be found on the Internet Installation (ISFSI). The exemption storage of spent fuel in an ISFSI at
at: http://www.nrc.gov/public-involve/ request seeks a modification of TS A 5.3 power reactor sites to persons
public-meetings/schedule.html. inspection requirements for the inlet authorized to possess or operate nuclear
* * * * * and outlet vents following off-normal, power reactors under 10 CFR part 50.
The NRC provides reasonable accident and natural phenomena events. The licensee is licensed to operate a
accommodation to individuals with ADDRESSES: Please refer to Docket ID nuclear power reactor under 10 CFR
disabilities where appropriate. If you NRC–2016–0029 when contacting the part 50, and authorized under the 10
need a reasonable accommodation to NRC about the availability of CFR part 72 general license to store
participate in these public meetings, or information regarding this document. spent fuel at the YNPS ISFSI. Under the
need this meeting notice or the You may obtain publicly-available terms of the general license, YNPS
transcript or other information from the information related to this document stores spent fuel using Amendment No.
public meetings in another format (e.g. using any of the following methods: 5 of the NAC–MPC CoC No. 1025.
braille, large print), please notify • Federal Rulemaking Web site: Go to II. Request/Action
Kimberly Meyer, NRC Disability http://www.regulations.gov and search
Program Manager, at 301–287–0739, by for Docket ID NRC–2016–0029. Address YAEC requests an exemption from 10
videophone at 240–428–3217, or by questions about NRC dockets to Carol CFR 72.212(b)(3), 10 CFR 72.212(b)(5)(i),
email at Kimberly.Meyer-Chambers@ Gallagher; telephone: 301–415–3463; and 10 CFR 72.214 for the YNPS ISFSI.
nrc.gov. Determinations on requests for email: Carol.Gallagher@nrc.gov. For • Section 72.212(b)(3) requires that a
reasonable accommodation will be technical questions, contact the general licensee use casks that conform
made on a case-by-case basis. individual listed in the FOR FURTHER to the terms, conditions, and
* * * * * INFORMATION CONTACT section of this specifications of a CoC or amended CoC
Members of the public may request to document. listed in § 72.214. The NAC–MPC CoC
receive this information electronically. • NRC’s Agencywide Documents No. 1025 is listed in 10 CFR 72.214.
If you would like to be added to the Access and Management System • Section 72.212(b)(5)(i) requires, in
distribution, please contact the Nuclear (ADAMS): You may obtain publicly relevant part, that a general licensee
Regulatory Commission, Office of the available documents online in the demonstrate a loaded cask will conform
Secretary, Washington, DC 20555 (301– ADAMS Public Documents collection at to the terms, conditions, and
415–1969), or email http://www.nrc.gov/reading-rm/ specifications of a CoC for a cask listed
Brenda.Akstulewicz@nrc.gov or adams.html. To begin the search, select in § 72.214.
Patricia.Jimenez@nrc.gov. ‘‘ADAMS Public Documents’’ and then • Section 72.214 lists casks which are
select ‘‘Begin Web-based ADAMS approved for storage of spent fuel under
Dated: February 18, 2016.
Search.’’ For problems with ADAMS, conditions specified in their CoCs,
Denise McGovern, please contact the NRC’s Public including CoC 1025 and Amendment
Policy Coordinator, Office of the Secretary. Document Room (PDR) reference staff at No. 5.
[FR Doc. 2016–03752 Filed 2–18–16; 4:15 pm] 1–800–397–4209, 301–415–4737, or by The licensee, as a 10 CFR 72 general
BILLING CODE 7590–01–P email to pdr.resource@nrc.gov. The licensee, is required to use the NAC–
ADAMS accession number for each MPC System according to the technical
document referenced in this document specifications of the NAC–MPC System
NUCLEAR REGULATORY (if that document is available in CoC No. 1025. Amendment No. 5 of the
COMMISSION ADAMS) is provided the first time that NAC–MPC CoC No. 1025, Appendix A,
[Docket Nos. 50–029, and 72–1025; a document is referenced. ‘‘Technical Specifications for the NAC–
NRC 2016–0029] • NRC’s PDR: You may examine and MPC System,’’ TS A 5.3, ‘‘Surveillance
purchase copies of public documents at After an Off-Normal, Accident, or
Independent Spent Fuel Storage the NRC’s PDR, Room O1–F21, One Natural Phenomena Event,’’ requires
Installation, Yankee Atomic Electric White Flint North, 11555 Rockville that a general licensee undertake a
Company Pike, Rockville, Maryland 20852. visual surveillance of the NAC–MPC
AGENCY: Nuclear Regulatory FOR FURTHER INFORMATION CONTACT: John casks within 4 hours after the
Commission. Goshen, Office of Nuclear Material occurrence of an off-normal, accident or
ACTION: Exemption; issuance.
Safety and Safeguards, telephone: 301– natural phenomena event in the area of
415–6933, email: John.Goshen@nrc.gov; the ISFSI. This NAC–MPC cask
SUMMARY: The U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission, inspection is part of the general
Commission (NRC) is issuing an Washington, DC 20555. licensee’s surveillance response to
mstockstill on DSK4VPTVN1PROD with NOTICES
exemption in response to a September 1, SUPPLEMENTARY INFORMATION: verify that all the CONCRETE CASK
2015, request from Yankee Atomic inlets and outlets are not blocked or
Electric Company, (YAEC or licensee) I. Background obstructed. The NAC–MPC TS A 5.3
from the requirement to comply with The licensee is the holder of Facility also requires that at least one-half of the
the terms, conditions, and specifications Operating License No. DPR–3 which inlets and outlets on each CONCRETE
regarding the method of compliance authorizes operation of the YNPS CASK be cleared of blockage or debris
defined in Amendment No. 5 of the located near Rowe, Massachusetts, within 24 hours to restore air
NAC International, Inc. (NAC),—MPC pursuant to part 50 of title 10 of the circulation.
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![8752 Federal Register / Vol. 81, No. 34 / Monday, February 22, 2016 / Notices
retrievability, and radiation protection Granting an exemption from the to TS A.5.3 for the NAC–MPC System
requirements of 10 CFR part 72 and the requirements of 10 CFR 72.212(b)(3), 10 CoC No. 1025 storage casks at the YNPS
offsite dose limits of 10 CFR part 20 will CFR 72.212(b)(5)(i), and 10 CFR 72.214 ISFSI. The exemption authorizes the
be maintained. For these reasons, the for the YNPS ISFSI involves the visual licensee to use the SR, conditions,
staff finds the same level of safety is surveillance requirement associated required actions, and completion times
obtained by using either of the TS A with TS A 5.3A. A categorical exclusion defined in NAC–MPC TS A 3.1.6 to
3.1.6 methods to comply with NAC– for inspection and SRs is provided comply with NAC–MPC TS A 5.3 after
MPC TS A 5.3. Therefore, the NRC under 10 CFR 51.22(c)(25)(vi)(C), if the off-normal, accident, or natural
concludes that the exemption will not criteria in 10 CFR 51.22(c)(25)(i)–(v) are phenomena events, but is specifically
endanger life or property or the common also satisfied. limited to major snow or icing events
defense and security. The granting of the exemption: (i) (events that have the potential to or that
Would not involve a significant hazards exceed blockage of greater than one-half
The Exemption Presents No Undue Risk consideration because it does not reduce of the inlet or outlet vents).
to Public Health and Safety a margin of safety, create a new or This exemption is effective upon
As described in the application, different kind of accident not previously issuance.
exempting the licensee from visual evaluated, or significantly increase the
Dated at Rockville, Maryland, this 4th day
surveillance of cask inlet and outlet probability or consequences of an of February, 2016.
vents within 4-hours of a major unevaluated accident; (ii) would not
For the Nuclear Regulatory Commission.
snowstorm would allow the licensee to create a significant change in the types
or significant increase in the amounts of Steve Ruffin,
more effectively prioritize important Acting Chief, Spent Fuel Licensing Branch,
storm-related activities at the YNPS site. any effluents that may be released
offsite because the exemption does not Division of Spent Fuel Management, Office
Snow and ice blockage of the inlet and of Nuclear Material Safety and Safeguards.
outlet vents is unusual. Moreover, snow change or produce additional avenues of
effluent release; (iii) would not [FR Doc. 2016–03591 Filed 2–19–16; 8:45 am]
and ice blockages are identified reliably
by temperature monitoring of individual significantly increase individual or BILLING CODE 7590–01–P
casks. The NRC staff recognizes there is cumulative public or occupational
a risk to the safety of workers radiation exposure because the
exemption does not introduce new or NUCLEAR REGULATORY
responsible for clearing snow and ice COMMISSION
from cask pads during extreme winter increased radiological hazards; (iv)
conditions when visual surveillance of would not result in significant [Docket No. 50–336; NRC–2016–0034]
casks must be undertaken within 4 construction impacts because the
exemption would not involve Dominion Nuclear Connecticut, Inc., et
hours. The NRC staff finds this risk to
construction or other ground disturbing al.; Millstone Power Station, Unit No. 2
workers can be reduced by using SR
3.1.6.1 to establish the operability of the activities, nor change the footprint of
AGENCY: Nuclear Regulatory
the existing ISFSI; v) would not
Concrete Cask Heat Removal Systems Commission.
significantly increase the potential for,
via temperature monitoring or visual ACTION: License amendment application;
or consequences from, radiological
inspection of the inlet and outlet opportunity to comment, request a
accidents because the exemption
screens. In addition, the limiting hearing, and petition for leave to
requires a surveillance method that
conditions for operation of the NAC– intervene.
ensures the heat removal system of
MPC System require the Concrete Cask
casks is maintained within the limiting SUMMARY: The U.S. Nuclear Regulatory
Heat Removal System for each cask to
conditions for operation; and (vi) the Commission (NRC) is considering
be operable during storage operations
request seeks exemption from issuance of an amendment to Facility
thus ensuring public health and safety
inspection or surveillance requirements, Operating License No. DPR–65, issued
are not reduced.
specifically, the single-method to Dominion Nuclear Connecticut, Inc.,
Therefore the NRC staff finds that surveillance requirement in NAC–MPC
allowing the licensee to use the SR, et al. (the licensee), for operation of the
TS A 5.3, may be substituted with the Millstone Power Station, Unit No. 2
conditions, required actions, and SR, conditions, required actions, and
completion times defined in NAC–MPC (MPS2). The proposed amendment
completion times defined in NAC–MPC would modify the MPS2 Technical
TS A 3.1.6 as an alternative to the TS 3.1.6.
single-method surveillance response in Specifications (TSs) to revise the peak
In its review of the exemption request, calculated primary containment internal
NAC–MPC TS A 5.3 would reduce the NRC staff determined the proposed
worker safety risks to plant workers pressure (Pa) for the design-basis loss-of-
exemption meets the eligibility criterion coolant accident in TS 6.19, TS
involved in snow removal. Therefore, for categorical exclusion in 10 CFR
granting the exemption is otherwise in 3.6.1.2.a, and TS 3.6.1.3.b to be
51.22(c)(25). consistent with the definition of Pa in
the public interest. Therefore, there are no significant
the NRC’s regulations. The proposed
Environmental Considerations radiological environmental impacts
amendment would also revise the
associated with the proposed action.
The staff evaluated whether there acceptance criteria for leakage rate
would be significant environmental IV. Conclusion testing of containment air lock door
impacts associated with the issuance of The NRC has determined that, under seals to substitute the use of the makeup
flow method in lieu of the pressure
mstockstill on DSK4VPTVN1PROD with NOTICES
the requested exemption. The staff 10 CFR 72.7, the exemption is
determined the proposed action fits a authorized by law, will not endanger decay method currently used at MPS2.
category of actions that do not require life or property or the common defense DATES: Submit comments by March 23,
an environmental assessment or and security, and is otherwise in the 2016. A request for a hearing or petition
environmental impact statement. The public interest. Therefore, the NRC for leave to intervene must be filed by
exemption meets the categorical grants YAEC an exemption from the April 22, 2016.
exclusion requirements of 10 CFR requirements in10 CFR 72.212(b)(3), 10 ADDRESSES: You may submit comments
51.22(c)(25)(i)–(vi). CFR 72.212(b)(5)(i), 10 CFR 72.214, and by any of the following methods (unless
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Document Created: 2016-02-19 23:56:43
Document Modified: 2016-02-19 23:56:43
| 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. | |
| Contact | John Goshen, Office of Nuclear Material Safety and Safeguards, telephone: 301-415-6933, email: [email protected]; U.S. Nuclear Regulatory Commission, Washington, DC 20555. | |
| FR Citation | 81 FR 8750 |
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