Virginia Electric and Power Company, North Anna Power Station Units 1 and 2, Independent Spent Fuel Storage Installation; Exemption, 24541-24543 [2012-9803]

Download as PDF Federal Register / Vol. 77, No. 79 / Tuesday, April 24, 2012 / Notices the proposed action. In addition the proposed action only affects the requirements associated with the fuel assemblies already loaded into the casks and does not affect non-radiological plant effluents, or any other aspects of the environment. The Environmental Assessment and the Finding of No Significant Impact are documented in the Federal Register (77 FR 20440, dated April 4, 2012). 4.0 Conclusion Based on the foregoing considerations, the NRC has determined pursuant to 10 CFR 72.7, that 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 Dominion a one-time exemption from the requirements in 10 CFR 72.212(b)(3) and from the portion of 10 CFR 72.212(b)(11) that states the licensee shall comply with the terms, conditions, and specifications of the CoC for the TN NUHOMS® HD dry cask storage system with DSCs serial numbers DOM–32PTH–001–C, –002–C, –003–C, and –009–C, at the Surry Power Station ISFSI. This exemption is effective upon issuance. For the Nuclear Regulatory Commission. Dated: Dated at Rockville, Maryland, this 12th day of April 2012. Doug Weaver, Deputy Director, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2012–9802 Filed 4–23–12; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–338, 50–339, 72–56, and 72–1030; NRC–2012–0084] Virginia Electric and Power Company, North Anna Power Station Units 1 and 2, Independent Spent Fuel Storage Installation; Exemption mstockstill on DSK4VPTVN1PROD with NOTICES 1.0 Background Virginia Electric and Power Company (Dominion, the licensee) is the holder of Facility Operating License Nos. NPF–4 and NPF–7, which authorize operation of the North Anna Power Station Units 1 and 2 in Louisa County, Virginia, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), part 50. The licenses provide, among other things, that the facility is subject to all rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC VerDate Mar<15>2010 17:40 Apr 23, 2012 Jkt 226001 or the Commission) now or hereafter in effect. Pursuant to 10 CFR part 72, Subpart K, a general license is issued for the storage of spent fuel in an independent spent fuel storage installation (ISFSI) at power reactor sites to persons authorized to possess or operate nuclear power reactors under 10 CFR part 50. Dominion is authorized to operate a nuclear power reactor under 10 CFR part 50, and holds a 10 CFR part 72 general license for storage of spent fuel at the North Anna Power Station ISFSI. Under the terms of its general license, Dominion loaded spent fuel using the Transnuclear, Inc., (TN) NUHOMS® HD Storage System (HD–32PTH) dry cask storage system (Certificate of Compliance (CoC) No. 1030, Amendment No. 0) at the North Anna Power Station ISFSI. 2.0 Request/Action The TN NUHOMS® HD dry cask storage system is designed for zone loading based on decay heat. CoC 1030 specifies requirements, conditions, and operating limits of the dry shielded canisters (DSCs) in Appendix A of the Technical Specifications (TS). The TS restrict the decay heat in lower Zone 1a locations to <1.05 kW and the upper Zone 1b locations to ≤0.8 kW. The licensee inadvertently reversed the upper and lower zones while preparing the DSC loading maps. This resulted in twelve fuel assemblies being loaded into seven DSCs with decay heat greater than the limits specified in the CoC. The seven DSCs are designated with serial numbers DOM–32PTH–004–C, –005–C, –007–C, –010–C, –013–C, –019–C and GBC–32PTH–011–C. In a letter dated July 21, 2011, as supplemented September 28, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML11208C453 and ML11286A143, respectively), Dominion requested a one-time exemption from the following requirements to allow storage of the seven DSCs, with serial numbers DOM–32PTH–004–C, –005–C, –007–C, –010–C, –013–C, –019–C and GBC–32PTH–011–C, in their current, asloaded, condition at the North Anna Power Station ISFSI: • 10 CFR 72.212(b)(3), which states the general licensee must ‘‘[e]nsure that each cask used by the general licensee conforms to the terms, conditions, and specifications of a CoC or an amended CoC listed in § 72.214.’’ • The portion of 10 CFR 72.212(b)(11), which states that ‘‘[t]he licensee shall comply with the terms, conditions, and specifications of the CoC * * *’’ PO 00000 Frm 00087 Fmt 4703 Sfmt 4703 3.0 24541 Discussion Pursuant to 10 CFR 72.7, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of the regulations of 10 CFR part 72 as it determines are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest. Authorized by Law This exemption would allow the licensee to continue to store seven DSCs (loaded with spent nuclear fuel assemblies having decay heat exceeding the limits required by CoC No. 1030, Amendment No. 0, at the time of loading) in their as-loaded configuration at the North Anna Power Station ISFSI. The provisions in 10 CFR Part 72 from which Dominion is requesting an exemption, require the licensee to comply with the terms, conditions, and specifications of the CoC for the approved cask model that it uses. The Commission issued 10 CFR 72.7 under the authority granted to it under Section 133 of the Nuclear Waste Policy Act of 1982, as amended, 42 U.S.C. 10153. Section 72.7 allows the NRC to grant exemptions from the requirements of 10 CFR part 72. Granting the licensee’s proposed exemption provides adequate protection to public health and safety, and the environment. 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. Will Not Endanger Life or Property or the Common Defense and Security The provisions in 10 CFR 72.212(a) specifically state that the general licensee is limited to spent fuel that the general licensee is authorized to possess at the site under the specific license for the site. Sections 72.212(b)(3) and 72.212(b)(11) require the general licensee to store spent fuel in cask models approved under the provisions of 10 CFR part 72 (which are listed in 10 CFR 72.214) and require general licensees to comply with the terms and conditions of the CoC for the approved cask model that is used. The requested exemption would allow the licensee to continue to store seven DSCs (loaded with spent nuclear fuel assemblies having decay heat exceeding the limits required by CoC No. 1030, Amendment No. 0 at the time of loading) in their asloaded configuration at the North Anna Power Station ISFSI. E:\FR\FM\24APN1.SGM 24APN1 mstockstill on DSK4VPTVN1PROD with NOTICES 24542 Federal Register / Vol. 77, No. 79 / Tuesday, April 24, 2012 / Notices Currently, the twelve affected fuel assemblies have been in storage for a minimum of 1.3 years and have decayed to meet the required decay heat limits of the CoC. The licensee submitted TN Calculation No. 10494–174, which performed a bounding thermal analysis using ANSYS finite element software to evaluate the misloading events. The ANSYS analysis consists of a halfsymmetric, three-dimensional model of a 32PTH DSC with a number of conservative assumptions. First, the modeled fuel assembly loading pattern is based on the configuration that resulted in the maximum fuel cladding temperature presented in the UFSAR analysis dated October 2, 2009, with the exception that the two fuel assemblies in Zone 1b were set to 860 W. The licensee states this configuration bounds the design zone limits as listed in TS, Section 2.1, which are based on each Zone 1b fuel assemblies being 800 W. It also bounds the as-loaded configurations, where one or both fuel assemblies in Zone 1b exceeded a decay heat of 800 W, up to a value of 859 W. The remaining DSC fuel assembly decay heats were within the design basis. Therefore, since the as-loaded configuration had a total DSC decay heat of 31.167 kW, the licensee states the model conservatively assumes a total DSC decay heat of 34.92 kW. Secondly, the licensee applies a storage condition ambient temperature of 115 °F, which is above the maximum normal storage ambient temperature of 100 °F. The NRC staff finds the assumed 115 °F boundary condition provides a reasonably conservative ambient temperature choice, considering that summer temperatures often are greater than 90 °F and can reach 100 °F (per weather almanac, www.NOAA.gov). The NRC staff further finds that applying a higher ambient temperature boundary condition also mitigates the thermal effects of other ambient weather conditions, such as wind direction relative to the DSC’s inlet and outlet openings. Using the conservative assumptions stated above, the TN Calculation No. 10494–174 analysis presented by the licensee indicates a maximum cladding temperature of 689 °F for the as loaded DSC with the reversed heat load zoning for storage conditions. This is 5 °F higher than the previously calculated cladding temperature found in Table 4– 2 of the UFSAR. The temperatures of other DSC components increased by less than 5 °F. The temperature increases due to the misloaded fuel assemblies are essentially unchanged for transfer conditions. By applying an additional 5 VerDate Mar<15>2010 17:40 Apr 23, 2012 Jkt 226001 °F to the previously calculated temperature for transfer conditions listed in Table 4–1 of the UFSAR, the licensee estimates that the maximum fuel cladding temperature for the asloaded DSC with the reversed heat load zoning for transfer conditions to be 724 °F. As a result, the licensee concluded that the maximum cladding temperatures for both normal storage and transfer conditions were below the 752 °F maximum allowable cladding temperature limit noted in the UFSAR analysis. The NRC staff has reviewed the analysis presented by Dominion and finds the thermal effect of the misloaded fuel assemblies to be minimal, and that the thermal margins were sufficient to mitigate the effects of the misloaded fuel assemblies so as to provide adequate heat removal capabilities when the DSC fuel assembly arrangement was not within the design basis. This thermal evaluation provides reasonable assurance that the TN NUHOMS® HD Storage System (HD–32PTH) loaded with fuel assemblies exceeding the decay heat limits allowed by the CoC will allow for continued safe storage of the spent fuel. The licensee also discusses structural and pressure considerations due to the increased decay heat of the Zone 1b fuel assemblies. The licensee concludes that the increased decay heat did not have an effect on the structural evaluation since the DSC fuel compartment and basket rails are at temperatures below those considered in the design basis analysis. The submitted analysis finds that the 5 °F higher temperature, due to the larger as-loaded decay heat, would result in a DSC pressure increase of 0.1 psig. The resulting 6 psig and 6.5 psig DSC pressures for the normal storage and transfer conditions were less than the 15 psig design basis pressure. The NRC staff has reviewed the analysis submitted in the exemption request and finds that there were no structural implications on the cask system resulting from the misloaded fuel assemblies. The licensee verified the design basis shielding analysis remained bounding for the as-loaded DSCs. The licensee concluded the design basis shielding analysis assumes a DSC loading of 32 assemblies all having source terms applicable to assemblies generating 1.5 kW of decay heat and, therefore, bounds the as-loaded DSCs. The NRC staff has reviewed the design basis shielding analysis and concludes that the design remains bounding for the as-loaded DSCs and the radiation protection system of the NUHOMS® HD–32PTH dry cask storage system remains in compliance with 10 CFR part 72. PO 00000 Frm 00088 Fmt 4703 Sfmt 4703 The NRC staff has reviewed Dominion’s exemption request and finds that the twelve fuel assemblies loaded into seven DSCs with decay heat greater than specified in the CoC do not affect the heat removal capabilities, the structural integrity, or the radiation protection system of the cask systems. Therefore, the NRC staff concludes that the exemption to allow the licensee to store the seven DSCs in their as-loaded configuration does not pose an increased risk to public health and safety or the common defense or security. Otherwise in the Public Interest The information Dominion submitted with its exemption request and the TN analysis documented in TN Calculation No. 10494–174 demonstrate that the asloaded DSCs are not compromised due to the misloaded fuel assemblies. Dominion has also considered alternative action to correct the condition by reloading the affected DSCs to be in compliance with CoC No. 1030. This would involve retrieving each of the DSCs from their Horizontal Storage Modules (HSM), unloading the spent fuel assemblies from the DSC, performing inspections of various DSC components, reloading the spent fuel assemblies into the used DSC or a new DSC (if there was damage noted on the used DSC) in accordance with CoC No. 1030, performing the DSC closing procedures, and transferring the DSC back to the ISFSI for re-insertion into the HSM. The licensee estimates this alternative action of loading and unloading operations would increase personnel exposures by 250 mRem per affected DSC. In addition, the licensee also states the alternative to the proposed action would generate radioactive contaminated material and waste during loading and unloading operations and disposal of the used DSCs (if the DSCs were damaged during the unloading process). The licensee estimates the alternative to the proposed action would cost an estimated $300,000 for unloading and reloading operations of each affected DSC and also necessitate additional fuel handling operations. If the DSC was damaged during unloading, the licensee estimates an additional $1,000,000 for purchase of a new DSC and $200,000 for disposal of the used DSC. The exemption, by allowing the seven affected DSCs to remain in their asloaded condition, is consistent with NRC’s mission to protect public health and safety. Approving the DSCs to remain in their as-loaded condition results in less of an opportunity for a E:\FR\FM\24APN1.SGM 24APN1 Federal Register / Vol. 77, No. 79 / Tuesday, April 24, 2012 / Notices release of radioactive material than the alternative to the proposed action. Therefore, the exemption is in the public interest. mstockstill on DSK4VPTVN1PROD with NOTICES Environmental Consideration The NRC staff also considered in the review of this exemption request whether there would be any significant environmental impacts associated with the exemption. For this proposed action, the NRC staff performed an environmental assessment pursuant to 10 CFR 51.30. The proposed action is the approval of a request for a one-time exemption from the requirements of 10 CFR 72.212(b)(3) and the portion of 72.212(b)(11), which requires compliance with the terms, conditions, and specifications of a CoC, but only to the extent necessary to allow Dominion to store the seven DSCs in the current as-loaded configuration at the North Anna Power Station ISFSI. The NRC staff determined that the proposed action will not significantly impact the quality of the human environment. The NRC staff concludes that there are no changes being made in the types or amounts of any radiological effluents that may be released offsite, and there is no significant increase in occupational or public radiation exposure as a result of the proposed action. In addition the proposed action only affects the requirements associated with the fuel assemblies already loaded into the casks and does not affect nonradiological plant effluents, or any other aspects of the environment. The Environmental Assessment and the Finding of No Significant Impact are documented in the Federal Register (77 FR 20438, dated April 4, 2012). 4.0 Conclusion Based on the foregoing considerations, the NRC has determined, pursuant to 10 CFR 72.7, that 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 Dominion a one-time exemption from the requirements in 10 CFR 72.212(b)(3) and from the portion of 10 CFR 72.212(b)(11) that states the licensee shall comply with the terms, conditions, and specifications of the CoC for TN NUHOMS® HD dry cask storage system with DSCs serial numbers DOM– 32PTH–004–C, -005–C,t -007–C, -010–C, -013–C, -019–C and GBC–32PTH–011–C at the North Anna Power Station ISFSI. This exemption is effective upon issuance. Dated at Rockville, Maryland, this 12th day of April 2012. VerDate Mar<15>2010 17:40 Apr 23, 2012 Jkt 226001 For the Nuclear Regulatory Commission. Douglas Weaver, Deputy Director, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2012–9803 Filed 4–23–12; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2012–0002] Sunshine Act Meeting Noice AGENCY HOLDING THE MEETINGS: Nuclear Regulatory Commission. DATE: Weeks of April 23, 30, May 7, 14, 21, 28, 2012. PLACE: Commissioners’ Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of April 23, 2012 Tuesday, April 24, 2012 9 a.m. Briefing on Part 35 Medical Events Definitions—Permanent Implant Brachytherapy (Public Meeting) (Contact: Michael Fuller, 301–415– 0520). This meeting will be webcast live at the Web address—www.nrc.gov. Week of April 30, 2012—Tentative Monday, April 30, 2012 9:30 a.m. Briefing on Human Capital and Equal Employment Opportunity (EEO) (Public Meeting) (Contact: Kristin Davis, 301–492–2208). This meeting will be webcast live at the Web address—www.nrc.gov. Week of May 7, 2012—Tentative 24543 This meeting will be webcast live at the Web address—www.nrc.gov. The schedule for Commission meetings is subject to change on short notice. To verify the status of meetings, call (recording)—301–415–1292. Contact person for more information: Rochelle Bavol, 301–415–1651. * * * * * 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 Bill Dosch, Chief, Work Life and Benefits Branch, at 301–415–6200, TDD: 301– 415–2100, or by email at william.dosch@nrc.gov. Determinations on requests for reasonable accommodation will be made on a caseby-case basis. * * * * * This notice is distributed electronically to subscribers. If you no longer wish to receive it, or would like to be added to the distribution, please contact the Office of the Secretary, Washington, DC 20555 (301–415–1969), or send an email to darlene.wright@nrc.gov. Dated: April 19, 2012. Rochelle C. Bavol, Policy Coordinator, Office of the Secretary. [FR Doc. 2012–9970 Filed 4–20–12; 4:15 pm] BILLING CODE 7590–01–P Friday, May 11, 2012 9 a.m. Briefing on Potential Medical Isotope Production Licensing Actions (Public Meeting) (Contact: Jessie Quichocho, 301–415–0209). This meeting will be webcast live at the Web address—www.nrc.gov. SECURITIES AND EXCHANGE COMMISSION [Investment Company Act Release No. 30036; 812–13767] Week of May 14, 2012—Tentative Beverly Hills Bancorp Inc.; Notice of Application There are no meetings scheduled for the week of May 14, 2012. April 18, 2012. Week of May 21, 2012—Tentative There are no meetings scheduled for the week of May 21, 2012. Week of May 28, 2012—Tentative Friday, June 1, 2012 9 a.m. Briefing on Results of the Agency Action Review Meeting (AARM) (Public Meeting) (Contact: Rani Franovich, 301–415–1868). PO 00000 Frm 00089 Fmt 4703 Sfmt 4703 Securities and Exchange Commission (the ‘‘Commission’’). ACTION: Notice of application for an order under sections 6(c) and 6(e) of the Investment Company Act of 1940 (‘‘Act’’) for an exemption from all provisions of the Act, except sections 9, 17(a), 17(d), 17(e), 17(f), 36 through 45, and 47 through 51 of the Act and the rules thereunder, modified as discussed in the application. AGENCY: E:\FR\FM\24APN1.SGM 24APN1

Agencies

[Federal Register Volume 77, Number 79 (Tuesday, April 24, 2012)]
[Notices]
[Pages 24541-24543]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2012-9803]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-338, 50-339, 72-56, and 72-1030; NRC-2012-0084]


Virginia Electric and Power Company, North Anna Power Station 
Units 1 and 2, Independent Spent Fuel Storage Installation; Exemption

1.0 Background

    Virginia Electric and Power Company (Dominion, the licensee) is the 
holder of Facility Operating License Nos. NPF-4 and NPF-7, which 
authorize operation of the North Anna Power Station Units 1 and 2 in 
Louisa County, Virginia, pursuant to Title 10 of the Code of Federal 
Regulations (10 CFR), part 50. The licenses provide, among other 
things, that the facility is subject to all rules, regulations, and 
orders of the U.S. Nuclear Regulatory Commission (NRC or the 
Commission) now or hereafter in effect.
    Pursuant to 10 CFR part 72, Subpart K, a general license is issued 
for the storage of spent fuel in an independent spent fuel storage 
installation (ISFSI) at power reactor sites to persons authorized to 
possess or operate nuclear power reactors under 10 CFR part 50. 
Dominion is authorized to operate a nuclear power reactor under 10 CFR 
part 50, and holds a 10 CFR part 72 general license for storage of 
spent fuel at the North Anna Power Station ISFSI. Under the terms of 
its general license, Dominion loaded spent fuel using the Transnuclear, 
Inc., (TN) NUHOMS[supreg] HD Storage System (HD-32PTH) dry cask storage 
system (Certificate of Compliance (CoC) No. 1030, Amendment No. 0) at 
the North Anna Power Station ISFSI.

2.0 Request/Action

    The TN NUHOMS[supreg] HD dry cask storage system is designed for 
zone loading based on decay heat. CoC 1030 specifies requirements, 
conditions, and operating limits of the dry shielded canisters (DSCs) 
in Appendix A of the Technical Specifications (TS). The TS restrict the 
decay heat in lower Zone 1a locations to <1.05 kW and the upper Zone 1b 
locations to <=0.8 kW. The licensee inadvertently reversed the upper 
and lower zones while preparing the DSC loading maps. This resulted in 
twelve fuel assemblies being loaded into seven DSCs with decay heat 
greater than the limits specified in the CoC. The seven DSCs are 
designated with serial numbers DOM-32PTH-004-C, -005-C, -007-C, -010-C, 
-013-C, -019-C and GBC-32PTH-011-C.
    In a letter dated July 21, 2011, as supplemented September 28, 2011 
(Agencywide Documents Access and Management System (ADAMS) Accession 
Nos. ML11208C453 and ML11286A143, respectively), Dominion requested a 
one-time exemption from the following requirements to allow storage of 
the seven DSCs, with serial numbers DOM-32PTH-004-C, -005-C, -007-C, -
010-C, -013-C, -019-C and GBC-32PTH-011-C, in their current, as-loaded, 
condition at the North Anna Power Station ISFSI:
     10 CFR 72.212(b)(3), which states the general licensee 
must ``[e]nsure that each cask used by the general licensee conforms to 
the terms, conditions, and specifications of a CoC or an amended CoC 
listed in Sec.  72.214.''
     The portion of 10 CFR 72.212(b)(11), which states that 
``[t]he licensee shall comply with the terms, conditions, and 
specifications of the CoC * * *''

3.0 Discussion

    Pursuant to 10 CFR 72.7, the Commission may, upon application by 
any interested person or upon its own initiative, grant exemptions from 
the requirements of the regulations of 10 CFR part 72 as it determines 
are authorized by law and will not endanger life or property or the 
common defense and security and are otherwise in the public interest.

Authorized by Law

    This exemption would allow the licensee to continue to store seven 
DSCs (loaded with spent nuclear fuel assemblies having decay heat 
exceeding the limits required by CoC No. 1030, Amendment No. 0, at the 
time of loading) in their as-loaded configuration at the North Anna 
Power Station ISFSI. The provisions in 10 CFR Part 72 from which 
Dominion is requesting an exemption, require the licensee to comply 
with the terms, conditions, and specifications of the CoC for the 
approved cask model that it uses.
    The Commission issued 10 CFR 72.7 under the authority granted to it 
under Section 133 of the Nuclear Waste Policy Act of 1982, as amended, 
42 U.S.C. 10153. Section 72.7 allows the NRC to grant exemptions from 
the requirements of 10 CFR part 72. Granting the licensee's proposed 
exemption provides adequate protection to public health and safety, and 
the environment. 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.

Will Not Endanger Life or Property or the Common Defense and Security

    The provisions in 10 CFR 72.212(a) specifically state that the 
general licensee is limited to spent fuel that the general licensee is 
authorized to possess at the site under the specific license for the 
site. Sections 72.212(b)(3) and 72.212(b)(11) require the general 
licensee to store spent fuel in cask models approved under the 
provisions of 10 CFR part 72 (which are listed in 10 CFR 72.214) and 
require general licensees to comply with the terms and conditions of 
the CoC for the approved cask model that is used. The requested 
exemption would allow the licensee to continue to store seven DSCs 
(loaded with spent nuclear fuel assemblies having decay heat exceeding 
the limits required by CoC No. 1030, Amendment No. 0 at the time of 
loading) in their as-loaded configuration at the North Anna Power 
Station ISFSI.

[[Page 24542]]

    Currently, the twelve affected fuel assemblies have been in storage 
for a minimum of 1.3 years and have decayed to meet the required decay 
heat limits of the CoC. The licensee submitted TN Calculation No. 
10494-174, which performed a bounding thermal analysis using ANSYS 
finite element software to evaluate the misloading events. The ANSYS 
analysis consists of a half-symmetric, three-dimensional model of a 
32PTH DSC with a number of conservative assumptions. First, the modeled 
fuel assembly loading pattern is based on the configuration that 
resulted in the maximum fuel cladding temperature presented in the 
UFSAR analysis dated October 2, 2009, with the exception that the two 
fuel assemblies in Zone 1b were set to 860 W. The licensee states this 
configuration bounds the design zone limits as listed in TS, Section 
2.1, which are based on each Zone 1b fuel assemblies being 800 W. It 
also bounds the as-loaded configurations, where one or both fuel 
assemblies in Zone 1b exceeded a decay heat of 800 W, up to a value of 
859 W. The remaining DSC fuel assembly decay heats were within the 
design basis. Therefore, since the as-loaded configuration had a total 
DSC decay heat of 31.167 kW, the licensee states the model 
conservatively assumes a total DSC decay heat of 34.92 kW. Secondly, 
the licensee applies a storage condition ambient temperature of 115 
[deg]F, which is above the maximum normal storage ambient temperature 
of 100 [deg]F. The NRC staff finds the assumed 115 [deg]F boundary 
condition provides a reasonably conservative ambient temperature 
choice, considering that summer temperatures often are greater than 90 
[deg]F and can reach 100 [deg]F (per weather almanac, www.NOAA.gov). 
The NRC staff further finds that applying a higher ambient temperature 
boundary condition also mitigates the thermal effects of other ambient 
weather conditions, such as wind direction relative to the DSC's inlet 
and outlet openings.
    Using the conservative assumptions stated above, the TN Calculation 
No. 10494-174 analysis presented by the licensee indicates a maximum 
cladding temperature of 689 [deg]F for the as loaded DSC with the 
reversed heat load zoning for storage conditions. This is 5 [deg]F 
higher than the previously calculated cladding temperature found in 
Table 4-2 of the UFSAR. The temperatures of other DSC components 
increased by less than 5 [deg]F. The temperature increases due to the 
misloaded fuel assemblies are essentially unchanged for transfer 
conditions. By applying an additional 5 [deg]F to the previously 
calculated temperature for transfer conditions listed in Table 4-1 of 
the UFSAR, the licensee estimates that the maximum fuel cladding 
temperature for the as-loaded DSC with the reversed heat load zoning 
for transfer conditions to be 724 [deg]F. As a result, the licensee 
concluded that the maximum cladding temperatures for both normal 
storage and transfer conditions were below the 752 [deg]F maximum 
allowable cladding temperature limit noted in the UFSAR analysis. The 
NRC staff has reviewed the analysis presented by Dominion and finds the 
thermal effect of the misloaded fuel assemblies to be minimal, and that 
the thermal margins were sufficient to mitigate the effects of the 
misloaded fuel assemblies so as to provide adequate heat removal 
capabilities when the DSC fuel assembly arrangement was not within the 
design basis. This thermal evaluation provides reasonable assurance 
that the TN NUHOMS[supreg] HD Storage System (HD-32PTH) loaded with 
fuel assemblies exceeding the decay heat limits allowed by the CoC will 
allow for continued safe storage of the spent fuel.
    The licensee also discusses structural and pressure considerations 
due to the increased decay heat of the Zone 1b fuel assemblies. The 
licensee concludes that the increased decay heat did not have an effect 
on the structural evaluation since the DSC fuel compartment and basket 
rails are at temperatures below those considered in the design basis 
analysis. The submitted analysis finds that the 5 [deg]F higher 
temperature, due to the larger as-loaded decay heat, would result in a 
DSC pressure increase of 0.1 psig. The resulting 6 psig and 6.5 psig 
DSC pressures for the normal storage and transfer conditions were less 
than the 15 psig design basis pressure. The NRC staff has reviewed the 
analysis submitted in the exemption request and finds that there were 
no structural implications on the cask system resulting from the 
misloaded fuel assemblies.
    The licensee verified the design basis shielding analysis remained 
bounding for the as-loaded DSCs. The licensee concluded the design 
basis shielding analysis assumes a DSC loading of 32 assemblies all 
having source terms applicable to assemblies generating 1.5 kW of decay 
heat and, therefore, bounds the as-loaded DSCs. The NRC staff has 
reviewed the design basis shielding analysis and concludes that the 
design remains bounding for the as-loaded DSCs and the radiation 
protection system of the NUHOMS[supreg] HD-32PTH dry cask storage 
system remains in compliance with 10 CFR part 72.
    The NRC staff has reviewed Dominion's exemption request and finds 
that the twelve fuel assemblies loaded into seven DSCs with decay heat 
greater than specified in the CoC do not affect the heat removal 
capabilities, the structural integrity, or the radiation protection 
system of the cask systems. Therefore, the NRC staff concludes that the 
exemption to allow the licensee to store the seven DSCs in their as-
loaded configuration does not pose an increased risk to public health 
and safety or the common defense or security.

Otherwise in the Public Interest

    The information Dominion submitted with its exemption request and 
the TN analysis documented in TN Calculation No. 10494-174 demonstrate 
that the as-loaded DSCs are not compromised due to the misloaded fuel 
assemblies. Dominion has also considered alternative action to correct 
the condition by reloading the affected DSCs to be in compliance with 
CoC No. 1030. This would involve retrieving each of the DSCs from their 
Horizontal Storage Modules (HSM), unloading the spent fuel assemblies 
from the DSC, performing inspections of various DSC components, 
reloading the spent fuel assemblies into the used DSC or a new DSC (if 
there was damage noted on the used DSC) in accordance with CoC No. 
1030, performing the DSC closing procedures, and transferring the DSC 
back to the ISFSI for re-insertion into the HSM.
    The licensee estimates this alternative action of loading and 
unloading operations would increase personnel exposures by 250 mRem per 
affected DSC. In addition, the licensee also states the alternative to 
the proposed action would generate radioactive contaminated material 
and waste during loading and unloading operations and disposal of the 
used DSCs (if the DSCs were damaged during the unloading process). The 
licensee estimates the alternative to the proposed action would cost an 
estimated $300,000 for unloading and reloading operations of each 
affected DSC and also necessitate additional fuel handling operations. 
If the DSC was damaged during unloading, the licensee estimates an 
additional $1,000,000 for purchase of a new DSC and $200,000 for 
disposal of the used DSC.
    The exemption, by allowing the seven affected DSCs to remain in 
their as-loaded condition, is consistent with NRC's mission to protect 
public health and safety. Approving the DSCs to remain in their as-
loaded condition results in less of an opportunity for a

[[Page 24543]]

release of radioactive material than the alternative to the proposed 
action. Therefore, the exemption is in the public interest.

Environmental Consideration

    The NRC staff also considered in the review of this exemption 
request whether there would be any significant environmental impacts 
associated with the exemption. For this proposed action, the NRC staff 
performed an environmental assessment pursuant to 10 CFR 51.30. The 
proposed action is the approval of a request for a one-time exemption 
from the requirements of 10 CFR 72.212(b)(3) and the portion of 
72.212(b)(11), which requires compliance with the terms, conditions, 
and specifications of a CoC, but only to the extent necessary to allow 
Dominion to store the seven DSCs in the current as-loaded configuration 
at the North Anna Power Station ISFSI.
    The NRC staff determined that the proposed action will not 
significantly impact the quality of the human environment. The NRC 
staff concludes that there are no changes being made in the types or 
amounts of any radiological effluents that may be released offsite, and 
there is no significant increase in occupational or public radiation 
exposure as a result of the proposed action. In addition the proposed 
action only affects the requirements associated with the fuel 
assemblies already loaded into the casks and does not affect non-
radiological plant effluents, or any other aspects of the environment. 
The Environmental Assessment and the Finding of No Significant Impact 
are documented in the Federal Register (77 FR 20438, dated April 4, 
2012).

4.0 Conclusion

    Based on the foregoing considerations, the NRC has determined, 
pursuant to 10 CFR 72.7, that 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 Dominion 
a one-time exemption from the requirements in 10 CFR 72.212(b)(3) and 
from the portion of 10 CFR 72.212(b)(11) that states the licensee shall 
comply with the terms, conditions, and specifications of the CoC for TN 
NUHOMS[supreg] HD dry cask storage system with DSCs serial numbers DOM-
32PTH-004-C, -005-C,t -007-C, -010-C, -013-C, -019-C and GBC-32PTH-011-
C at the North Anna Power Station ISFSI.
    This exemption is effective upon issuance.

    Dated at Rockville, Maryland, this 12th day of April 2012.

    For the Nuclear Regulatory Commission.
Douglas Weaver,
Deputy Director, Division of Spent Fuel Storage and Transportation, 
Office of Nuclear Material Safety and Safeguards.
[FR Doc. 2012-9803 Filed 4-23-12; 8:45 am]
BILLING CODE 7590-01-P
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