Independent Spent Fuel Storage Installation, Yankee Atomic Electric Company, 8750-8752 [2016-03591]

Download as PDF 8750 Federal Register / Vol. 81, No. 34 / Monday, February 22, 2016 / Notices The schedule for Commission meetings is subject to change on short notice. For more information or to verify the status of meetings, contact Denise McGovern at 301–415–0681 or via email at Denise.McGovern@nrc.gov. * * * * * The NRC Commission Meeting Schedule can be found on the Internet at: https://www.nrc.gov/public-involve/ public-meetings/schedule.html. * * * * * The NRC provides reasonable accommodation to individuals with disabilities where appropriate. If you need a reasonable accommodation to participate in these public meetings, or need this meeting notice or the transcript or other information from the public meetings in another format (e.g. braille, large print), please notify Kimberly Meyer, NRC Disability Program Manager, at 301–287–0739, by videophone at 240–428–3217, or by email at Kimberly.Meyer-Chambers@ nrc.gov. Determinations on requests for reasonable accommodation will be made on a case-by-case basis. * * * * * Members of the public may request to receive this information electronically. If you would like to be added to the distribution, please contact the Nuclear Regulatory Commission, Office of the Secretary, Washington, DC 20555 (301– 415–1969), or email Brenda.Akstulewicz@nrc.gov or Patricia.Jimenez@nrc.gov. Dated: February 18, 2016. Denise McGovern, Policy Coordinator, Office of the Secretary. [FR Doc. 2016–03752 Filed 2–18–16; 4:15 pm] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–029, and 72–1025; NRC 2016–0029] Independent Spent Fuel Storage Installation, Yankee Atomic Electric Company Nuclear Regulatory Commission. ACTION: Exemption; issuance. AGENCY: 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 mstockstill on DSK4VPTVN1PROD with NOTICES SUMMARY: VerDate Sep<11>2014 19:03 Feb 19, 2016 Jkt 238001 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 https://www.regulations.gov and search for Docket ID NRC–2016–0029. Address questions about NRC dockets to Carol Gallagher; telephone: 301–415–3463; email: Carol.Gallagher@nrc.gov. 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 https://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 pdr.resource@nrc.gov. 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: John.Goshen@nrc.gov; 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 PO 00000 Frm 00070 Fmt 4703 Sfmt 4703 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 § 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 § 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. E:\FR\FM\22FEN1.SGM 22FEN1 Federal Register / Vol. 81, No. 34 / Monday, February 22, 2016 / Notices 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 8751 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: Document Date ADAMS accession No. Exemption Request .................................................................... Letter of transmittal ..................................................................... September 1, 2015 .................................................................... NA .............................................................................................. ML15254A050 ML16033A150 mstockstill on DSK4VPTVN1PROD with NOTICES 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 VerDate Sep<11>2014 19:03 Feb 19, 2016 Jkt 238001 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 PO 00000 Frm 00071 Fmt 4703 Sfmt 4703 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 offnormal, 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 offnormal, accident, or natural phenomena. The NRC staff has determined that the thermal, structural, criticality, E:\FR\FM\22FEN1.SGM 22FEN1 8752 Federal Register / Vol. 81, No. 34 / Monday, February 22, 2016 / Notices 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. mstockstill on DSK4VPTVN1PROD with NOTICES 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). VerDate Sep<11>2014 19:03 Feb 19, 2016 Jkt 238001 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 PO 00000 Frm 00072 Fmt 4703 Sfmt 4703 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 NUCLEAR REGULATORY COMMISSION [Docket No. 50–336; NRC–2016–0034] Dominion Nuclear Connecticut, Inc., et al.; Millstone Power Station, Unit No. 2 Nuclear Regulatory Commission. ACTION: License amendment application; opportunity to comment, request a hearing, and petition for leave to intervene. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Facility Operating License No. DPR–65, issued to Dominion Nuclear Connecticut, Inc., et al. (the licensee), for operation of the Millstone Power Station, Unit No. 2 (MPS2). The proposed amendment would modify the MPS2 Technical Specifications (TSs) to revise the peak calculated primary containment internal pressure (Pa) for the design-basis loss-ofcoolant accident in TS 6.19, TS 3.6.1.2.a, and TS 3.6.1.3.b to be consistent with the definition of Pa in the NRC’s regulations. The proposed amendment would also revise the acceptance criteria for leakage rate testing of containment air lock door seals to substitute the use of the makeup flow method in lieu of the pressure decay method currently used at MPS2. DATES: Submit comments by March 23, 2016. A request for a hearing or petition for leave to intervene must be filed by April 22, 2016. ADDRESSES: You may submit comments by any of the following methods (unless SUMMARY: E:\FR\FM\22FEN1.SGM 22FEN1

Agencies

[Federal Register Volume 81, Number 34 (Monday, February 22, 2016)]
[Notices]
[Pages 8750-8752]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-03591]


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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 https://www.regulations.gov and search for Docket ID NRC-2016-0029. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. 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 https://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 pdr.resource@nrc.gov. 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: 
John.Goshen@nrc.gov; 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
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