81 FR 8756 - Independent Spent Fuel Storage Installation, Connecticut Yankee Atomic Power Company
NUCLEAR REGULATORY COMMISSION Federal Register Volume 81, Issue 34 (February 22, 2016)
Federal Register Volume 81, Issue 34 (February 22, 2016)
| Page Range | 8756-8758 | |
| FR Document | 2016-03590 |
[Federal Register Volume 81, Number 34 (Monday, February 22, 2016)] [Notices] [Pages 8756-8758] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2016-03590] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-213, and 72-1025; NRC-2016-0031] Independent Spent Fuel Storage Installation, Connecticut Yankee Atomic Power Company AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to an August 31, 2015, request from Connecticut Yankee Atomic Power Company, (CYAPC or licensee) from NRC's requirement to comply with the terms, conditions, and specifications in Amendment 5 of the NAC International, (NAC),--Multi-Purpose Canister (MPC) System 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 Haddam Neck Plant (HNP) 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-2016-0031 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-2016-0031. 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, the holder of Facility Operating License No. DPR-61, is CYAPC, which authorizes operation of the HNP in Haddam, Connecticut, 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, CYAPC, 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 HNP ISFSI. Under the terms of the general license, CYAPC stores spent fuel using Amendment 5 of the NAC-MPC CoC No. 1025. II. Request/Action The licensee requests an exemption from 10 CFR 72.212(b)(3), 10 CFR 72.212(b)(5)(i), and 10 CFR 72.214 for the HNP 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 [[Page 8757]] 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 5 of the NAC-MPC CoC No. 1025, Appendix A, ``Technical Specifications for the NAC-MPC System,'' Technical Specification (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. 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 HNP 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 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, provided 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 in following paragraphs, 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............ August 31, 2015...... ML15254A051 Letter of transmittal........ NA................... ML16042A395 ------------------------------------------------------------------------ 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 requires the licensee to comply with the terms, conditions, and specifications of the CoC for the approved cask model that it uses. Section 72.7 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. 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 Specifications 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. Surveillance Requirement 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. [[Page 8758]] 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 every 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 canisters and that heat transfer occurs. For these reasons, NRC the 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, 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 NRC 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 prioritize more effectively important storm-related activities at the HNP 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 operation, therefore 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 NRC staff evaluated whether there would be significant environmental impacts associated with the issuance of the requested exemption. The NRC 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 CYAPC ISFSI involves the visual surveillance requirement associated with TS A 5.3. 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 SR in NAC-MPC TS A 5.3, may be substituted with the SR, conditions, required actions, and completion times defined in NAC-MPC TS A 3.1.6. In its review of the exemption request, the 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 CYAPC an exemption from the requirements in 10 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 HNP 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 (snow/ice 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 10th day of February, 2016. For the Nuclear Regulatory Commission. Bernard H. White IV, Acting Chief, Spent Fuel Licensing Branch, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2016-03590 Filed 2-19-16; 8:45 am] BILLING CODE 7590-01-P
![8756 Federal Register / Vol. 81, No. 34 / Monday, February 22, 2016 / Notices
Maryland, 20852, Attention: For the Nuclear Regulatory Commission. http://www.nrc.gov/reading-rm/
Rulemaking and Adjudications Staff. Richard V. Guzman, adams.html. To begin the search, select
Participants filing a document in this Senior Project Manager, Plant Licensing ‘‘ADAMS Public Documents’’ and then
manner are responsible for serving the Branch I–1, Division of Operating Reactor select ‘‘Begin Web-based ADAMS
document on all other participants. Licensing, Office of Nuclear Reactor Search.’’ For problems with ADAMS,
Filing is considered complete by first- Regulation. please contact the NRC’s Public
class mail as of the time of deposit in [FR Doc. 2016–03592 Filed 2–19–16; 8:45 am] Document Room (PDR) reference staff at
the mail, or by courier, express mail, or BILLING CODE 7590–01–P 1–800–397–4209, 301–415–4737, or by
expedited delivery service upon email to pdr.resource@nrc.gov. The
depositing the document with the ADAMS accession number for each
provider of the service. A presiding NUCLEAR REGULATORY document referenced in this document
officer, having granted an exemption COMMISSION (if that document is available in
request from using E-Filing, may require [Docket Nos. 50–213, and 72–1025; NRC– ADAMS) is provided the first time that
a participant or party to use E-Filing if 2016–0031] a document is referenced.
the presiding officer subsequently • NRC’s PDR: You may examine and
determines that the reason for granting Independent Spent Fuel Storage purchase copies of public documents at
the exemption from use of E-Filing no Installation, Connecticut Yankee the NRC’s PDR, Room O1–F21, One
longer exists. Atomic Power Company White Flint North, 11555 Rockville
Documents submitted in adjudicatory AGENCY: Nuclear Regulatory Pike, Rockville, Maryland 20852.
proceedings will appear in NRC’s Commission. FOR FURTHER INFORMATION CONTACT: John
electronic hearing docket which is ACTION: Exemption; issuance. Goshen, Office of Nuclear Material
available to the public at http://ehd1. Safety and Safeguards, telephone: 301–
nrc.gov/ehd/, unless excluded pursuant SUMMARY: The U.S. Nuclear Regulatory 415–6933, email: John.Goshen@nrc.gov;
to an order of the Commission, or the Commission (NRC) is issuing an U.S. Nuclear Regulatory Commission,
presiding officer. Participants are exemption in response to an August 31, Washington, DC 20555.
requested not to include personal 2015, request from Connecticut Yankee SUPPLEMENTARY INFORMATION:
privacy information, such as social Atomic Power Company, (CYAPC or
security numbers, home addresses, or licensee) from NRC’s requirement to I. Background
home phone numbers in their filings, comply with the terms, conditions, and The licensee, the holder of Facility
unless an NRC regulation or other law specifications in Amendment 5 of the Operating License No. DPR–61, is
requires submission of such NAC International, (NAC),—Multi- CYAPC, which authorizes operation of
information. However, in some Purpose Canister (MPC) System the HNP in Haddam, Connecticut,
instances, a request to intervene will Certificate of Compliance (CoC) No. pursuant to part 50 of title 10 of the
require including information on local 1025, Appendix A ‘‘Technical Code of Federal Regulations (10 CFR).
residence in order to demonstrate a Specifications for NAC–MPC System,’’ The facility is in decommissioned
proximity assertion of interest in the Technical Specifications (TS) A.5.3 status. The license provides, among
proceeding. With respect to copyrighted ‘‘Surveillance After an Off-Normal, other things, that the facility is subject
works, except for limited excerpts that Accident, or Natural Phenomena Event’’ to all rules, regulations, and orders of
serve the purpose of the adjudicatory at the Haddam Neck Plant (HNP) the NRC now or hereafter in effect.
filings and would constitute a Fair Use independent spent fuel storage Under subpart K of 10 CFR part 72,
application, participants are requested installation (ISFSI). The exemption a general license has been issued for the
not to include copyrighted materials in request seeks a modification of TS A.5.3 storage of spent fuel in an ISFSI at
their submission. inspection requirements for the inlet power reactor sites to persons
Petitions for leave to intervene must and outlet vents following off-normal, authorized to possess or operate nuclear
be filed no later than 60 days from the accident, and natural phenomena power reactors under 10 CFR part 50.
date of publication of this notice. events. The licensee, CYAPC, is licensed to
Requests for hearing, petitions for leave ADDRESSES: Please refer to Docket ID operate a nuclear power reactor under
to intervene, and motions for leave to NRC–2016–0031 when contacting the 10 CFR part 50 and authorized under
file new or amended contentions that NRC about the availability of the 10 CFR part 72 general license to
are filed after the 60-day deadline will information regarding this document. store spent fuel at the HNP ISFSI. Under
not be entertained absent a You may obtain publicly-available the terms of the general license, CYAPC
determination by the presiding officer information related to this document stores spent fuel using Amendment 5 of
that the filing demonstrates good cause using any of the following methods: the NAC–MPC CoC No. 1025.
by satisfying the three factors in 10 CFR • Federal Rulemaking Web site: Go to
II. Request/Action
2.309(c)(1)(i)–(iii). http://www.regulations.gov and search
For further details with respect to this for Docket ID NRC–2016–0031. Address The licensee requests an exemption
action, see the application for questions about NRC dockets to Carol from 10 CFR 72.212(b)(3), 10 CFR
amendment, dated March 2, 2015, as Gallagher; telephone: 301–415–3463; 72.212(b)(5)(i), and 10 CFR 72.214 for
supplemented by letter dated August 31, email: Carol.Gallagher@nrc.gov. For the HNP ISFSI.
2015, in ADAMS. technical questions, contact the • Section 72.212(b)(3) requires that a
mstockstill on DSK4VPTVN1PROD with NOTICES
individual listed in the FOR FURTHER general licensee use casks that conform
Attorney for licensee: Lillian M. to the terms, conditions, and
INFORMATION CONTACT section of this
Cuoco, Senior Counsel, Dominion specifications of a CoC or amended CoC
document.
Resources Services, Inc., 120 Tredegar • NRC’s Agencywide Documents listed in § 72.214. The NAC–MPC CoC
Street, RS–2, Richmond, VA 23219. Access and Management System No. 1025 is listed in 10 CFR 72.214.
NRC Branch Chief: Travis L. Tate. (ADAMS): You may obtain publicly • Section 72.212(b)(5)(i) requires, in
Dated at Rockville, Maryland, this 12th day available documents online in the relevant part, that a general licensee
of February 2016. ADAMS Public Documents collection at demonstrate a loaded cask will conform
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The NRC staff reviewed the licensee’s conditions for operation of the NAC– requires a surveillance method that
request and finds allowing the use of MPC System require the Concrete Cask ensures the heat removal system of
either visual surveillance of the inlet Heat Removal System for each cask to casks is maintained within the limiting
and outlet screens or temperature be operable during storage operation, conditions for operation; and (vi) the
monitoring of the inlets and outlets therefore ensuring public health and request seeks exemption from
within 4 hours of the occurrence of off- safety are not reduced. inspection or surveillance requirements,
normal, accident, or natural phenomena Therefore, the NRC staff finds that specifically, the single-method SR in
events, when limited to major snow and allowing the licensee to use the SR, NAC–MPC TS A 5.3, may be substituted
icing events, does not compromise conditions, required actions, and with the SR, conditions, required
safety. The exemption still requires the completion times defined in NAC–MPC actions, and completion times defined
licensee to perform SR 3.1.6.1 to TS A 3.1.6 as an alternative to the in NAC–MPC TS A 3.1.6.
establish the operability of the Concrete single-method surveillance response in In its review of the exemption request,
Cask Heat Removal Systems every 24 NAC–MPC TS A 5.3, would reduce the staff determined the proposed
hours via temperature monitoring or worker safety risks to plant workers exemption meets the eligibility criterion
visual inspection of the inlet and outlet involved in snow removal. Therefore, for categorical exclusion in 10 CFR
screens. In addition, the exemption granting the exemption is otherwise in 51.22(c)(25). Therefore, there are no
provides no additional time to complete the public interest. significant radiological environmental
the required surveillance of the inlets Environmental Considerations impacts associated with the proposed
and outlets screens in accordance with action.
TS A 5.3. The use of either method will The NRC staff evaluated whether
ensure that adequate air flows past the there would be significant IV. Conclusion
storage canisters and that heat transfer environmental impacts associated with
The NRC has determined that, under
occurs. For these reasons, NRC the staff the issuance of the requested
10 CFR 72.7, the exemption is
found the same level of safety is exemption. The NRC staff determined
authorized by law, will not endanger
obtained by using either of the TS A the proposed action fits a category of
life or property or the common defense
3.1.6 methods to comply with NAC– actions that do not require an
and security, and is otherwise in the
MPC TS A 5.3 during limited types off- environmental assessment or
public interest. Therefore, the NRC
normal, accident, or natural environmental impact statement. The
grants CYAPC an exemption from the
phenomena. exemption meets the categorical
exclusion requirements of 10 CFR requirements in 10 CFR 72.212(b)(3), 10
The NRC staff has determined that the CFR 72.212(b)(5)(i), 10 CFR 72.214, and
thermal, structural, criticality, 51.22(c)(25)(i)–(vi).
Granting an exemption from the to TS A.5.3 for the NAC–MPC System
retrievability, and radiation protection CoC No. 1025 storage casks at the HNP
requirements of 10 CFR part 72 and the requirements of 10 CFR 72.212(b)(3), 10
CFR 72.212(b)(5)(i), and 10 CFR 72.214 ISFSI. The exemption authorizes the
offsite dose limits of 10 CFR part 20 will licensee to use the SR, conditions,
be maintained For these reasons, the for the CYAPC ISFSI involves the visual
surveillance requirement associated required actions, and completion times
NRC staff finds the same level of safety defined in NAC–MPC TS A 3.1.6 to
is obtained by using either of the TS A with TS A 5.3. A categorical exclusion
for inspection and SRs is provided comply with NAC–MPC TS A 5.3 after
3.1.6 methods to comply with NAC–
under 10 CFR 51.22(c)(25)(vi)(C), if the off-normal, accident, or natural
MPC TS A 5.3. Therefore, the NRC
criteria in 10 CFR 51.22(c)(25)(i)–(v) are phenomena events, but is specifically
concludes that the exemption will not
also satisfied. limited to major snow or icing events
endanger life or property or the common
The granting of the exemption: (i) (snow/ice events that have the potential
defense and security.
Would not involve a significant hazards to or that exceed blockage of greater
The Exemption Presents No Undue Risk consideration because it does not reduce than one-half of the inlet or outlet
to Public Health and Safety a margin of safety, create a new or vents).
As described in the application, different kind of accident not previously This exemption is effective upon
exempting the licensee from visual evaluated, or significantly increase the issuance.
surveillance of cask inlet and outlet probability or consequences of an Dated at Rockville, Maryland, this 10th day
vents within 4 hours of a major unevaluated accident; (ii) would not of February, 2016.
snowstorm would allow the licensee to create a significant change in the types For the Nuclear Regulatory Commission.
prioritize more effectively important or significant increase in the amounts of Bernard H. White IV,
storm-related activities at the HNP site. any effluents that may be released Acting Chief, Spent Fuel Licensing Branch,
Snow and ice blockage of the inlet and offsite because the exemption does not Division of Spent Fuel Management, Office
outlet vents is unusual. Moreover, snow change or produce additional avenues of of Nuclear Material Safety and Safeguards.
and ice blockages are identified reliably effluent release; (iii) would not [FR Doc. 2016–03590 Filed 2–19–16; 8:45 am]
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
responsible for clearing snow and ice exemption does not introduce new or
from cask pads during extreme winter increased radiological hazards; (iv) OFFICE OF PERSONNEL
conditions when visual surveillance of would not result in significant MANAGEMENT
mstockstill on DSK4VPTVN1PROD with NOTICES
casks must be undertaken within 4 construction impacts because the
hours. The NRC staff finds this risk to exemption would not involve Privacy Act of 1974; Computer
workers can be reduced by using SR construction or other ground disturbing Matching Program
3.1.6.1 to establish the operability of the activities, nor change the footprint of
Concrete Cask Heat Removal Systems the existing ISFSI; (v) would not AGENCY: Office of Personnel
via temperature monitoring or visual significantly increase the potential for or Management.
inspection of the inlet and outlet consequences from radiological ACTION: Notice—computer matching
screens. In addition, the limiting accidents because the exemption between the Office of Personnel
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Document Created: 2016-02-19 23:56:51
Document Modified: 2016-02-19 23:56:51
| 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 8756 |
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