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| | issue date = 12/07/2017 | | | issue date = 12/07/2017 |
| | title = Supplement to Exemption Request from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 to Support the Dry Fuel Loading Campaign | | | title = Supplement to Exemption Request from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 to Support the Dry Fuel Loading Campaign |
| | author name = Chappell C C | | | author name = Chappell C |
| | author affiliation = Entergy Nuclear Operations, Inc | | | author affiliation = Entergy Nuclear Operations, Inc |
| | addressee name = | | | addressee name = |
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| ==REFERENCES:== | | ==REFERENCES:== |
| : 1. Letter, Entergy Nuclear Operations, Inc. to USNRC, "Exemption Request from Certain Requirements of 1 o CFR 72.212 and 1 o CFR 72.214 to Support the Dry Fuel Loading Campaign," BVY 17-006, dated May 16, 2017 (ML 17142A358} | | : 1. Letter, Entergy Nuclear Operations, Inc. to USNRC, "Exemption Request from Certain Requirements of 1 o CFR 72.212 and 1 o CFR 72.214 to Support the Dry Fuel Loading Campaign," BVY 17-006, dated May 16, 2017 (ML17142A358} |
| : 2. Letter, USNRC to Holtec International, "Certificate of Compliance No. 1014, Amendment No. 1 O for the HI-STORM 100 Cask System (CAC No. L24979)," dated May 25, 2016 (ML 16144A 177) 3. Letter, Entergy Nuclear Operations, Inc. to USNRC, "Response to Request for Additional Information Related to Exemption Request from Certain Requirements of 1 O CFR 72.212 and 1 O CFR 72.214 to Support the Dry Fuel Loading Campaign (CAC No. L25219}," BVY 17-031, dated September 7, 2017 (ML17255A236) | | : 2. Letter, USNRC to Holtec International, "Certificate of Compliance No. 1014, Amendment No. 1 O for the HI-STORM 100 Cask System (CAC No. L24979)," dated May 25, 2016 (ML16144A177) 3. Letter, Entergy Nuclear Operations, Inc. to USNRC, "Response to Request for Additional Information Related to Exemption Request from Certain Requirements of 1 O CFR 72.212 and 1 O CFR 72.214 to Support the Dry Fuel Loading Campaign (CAC No. L25219}," BVY 17-031, dated September 7, 2017 (ML17255A236) |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
Revision as of 11:01, 18 June 2019
Letter Sequence Supplement |
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MONTHYEARBVY 16-030, Exemption Request from Certain Requirements of 1 O CFR 72.212 and 10 CFR 72.2142016-11-0909 November 2016 Exemption Request from Certain Requirements of 1 O CFR 72.212 and 10 CFR 72.214 Project stage: Other BVY 17-041, Supplement to Exemption Request from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 to Support the Dry Fuel Loading Campaign2017-12-0707 December 2017 Supplement to Exemption Request from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 to Support the Dry Fuel Loading Campaign Project stage: Supplement ML17249A1572018-01-11011 January 2018, 16 January 2018 Package: Vermont Yankee Nuclear Power Station ISFSI Environmental Assessment and Finding of No Significant Impact Related to Issuance of Exemption to Allow a New Loading Pattern and Loading Fuel Cooled for at Least 2 Years Project stage: Request ML17249A1592018-01-16016 January 2018 Letter to C. C. Chappell Vermont Yankee Nuclear Power Station ISFSI Environmental Assessment and Finding of No Significant Impact Related to Issuance of Exemption to Allow a New Loading Pattern and Loading Fuel Cooled for at Least 2 Years Project stage: Approval ML17298A1352018-02-0202 February 2018 Safety Evaluation Report (Letter to C. C. Chappell Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation, Issuance of Exemption (CAC No.: 001028, Docket Nos. 50-271, 72-59, and 72-1014; EPID L-2017-LLE-0005) Project stage: Approval ML17298A1332018-02-0202 February 2018 Package: Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation, Issuance of Exemption (CAC No.: 001028, Docket Nos. 50-271, 72-59, and 72-1014; EPID L-2017-LLE-0005) Project stage: Request ML17298A1342018-02-0202 February 2018 Letter to C. C. Chappell Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation, Issuance of Exemption (CAC No.: 001028, Docket Nos. 50-271, 72-59, and 72-1014; EPID L-2017-LLE-0005) Project stage: Approval 2018-01-11
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Category:Letter type:BVY
MONTHYEARBVY 24-005, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-01-30030 January 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-004, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-01-23023 January 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-003, Nuclear Onsite Property Damage Insurance2024-01-0404 January 2024 Nuclear Onsite Property Damage Insurance BVY 24-001, Pre-Notice of Disbursement from Decommissioning Trust2024-01-0202 January 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-030, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-12-20020 December 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-029, Proof of Financial Protection2023-12-12012 December 2023 Proof of Financial Protection BVY 23-028, Pre-Notice of Disbursement from Decommissioning Trust2023-11-28028 November 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-027, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-11-21021 November 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-026, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-11-13013 November 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-025, Pre-Notice of Disbursement from Decommissioning Trust2023-11-0202 November 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-023, License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 3172023-10-10010 October 2023 License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 317 BVY 23-022, Pre-Notice of Disbursement from Decommissioning Trust2023-08-23023 August 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-020, Pre-Notice of Disbursement from Decommissioning Trust2023-08-0202 August 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-08-0202 August 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-019, Update to 2022 Radiological Effluent Release Report2023-07-24024 July 2023 Update to 2022 Radiological Effluent Release Report BVY 23-018, Update to Nuclear Onsite Property Damage Insurance2023-07-12012 July 2023 Update to Nuclear Onsite Property Damage Insurance BVY 23-017, Pre-Notice of Disbursement from Decommissioning Trust2023-06-29029 June 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-016, 10 CFR 72.48 Report2023-06-0505 June 2023 10 CFR 72.48 Report BVY 23-015, Report of Investigation Pursuant to 1O CFR 20, Appendix G2023-06-0505 June 2023 Report of Investigation Pursuant to 1O CFR 20, Appendix G BVY 23-014, Pre-Notice of Disbursement from Decommissioning Trust2023-05-31031 May 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-013, 2022 Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Radiological Environmental Operating Report BVY 23-011, 2022 Radiological Effluent Release Report2023-05-10010 May 2023 2022 Radiological Effluent Release Report BVY 23-012, Pre-Notice of Disbursement from Decommissioning Trust2023-05-0202 May 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-009, 2022 Individual Monitoring NRC Form 5 Report2023-04-24024 April 2023 2022 Individual Monitoring NRC Form 5 Report BVY 23-008, Pre-Notice of Disbursement from Decommissioning Trust2023-04-0606 April 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-006, Status of Decommissioning and Spent Fuel Management Fund for Year Ending 20222023-03-29029 March 2023 Status of Decommissioning and Spent Fuel Management Fund for Year Ending 2022 BVY 23-007, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-03-29029 March 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-005, Nuclear Onsite Property Damage Insurance2023-03-13013 March 2023 Nuclear Onsite Property Damage Insurance BVY 23-004, Pre-Notice of Disbursement from Decommissioning Trust2023-03-0202 March 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-003, Pre-Notice of Disbursement from Decommissioning Trust2023-01-31031 January 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-030, Documentary Evidence of Performance Bond2022-12-30030 December 2022 Documentary Evidence of Performance Bond BVY 22-028, Re Proof of Financial Protection2022-11-28028 November 2022 Re Proof of Financial Protection BVY 22-027, Bvy 22-027; Pre-Notice of Disbursement from Decommissioning Trust for Vermont Yankee Nuclear Power Station2022-11-11011 November 2022 Bvy 22-027; Pre-Notice of Disbursement from Decommissioning Trust for Vermont Yankee Nuclear Power Station BVY 22-026, Pre-Notice of Disbursement from Decommissioning Trust2022-10-31031 October 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-025, Pre-Notice of Disbursement from Decommissioning Trust2022-10-0404 October 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-023, Pre-Notice of Disbursement from Decommissioning Trust2022-09-0101 September 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-022, Report of Investigation Pursuant to 10 CFR 20, Appendix G2022-08-22022 August 2022 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 22-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G2022-08-16016 August 2022 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 22-020, Pre-Notice of Disbursement from Decommissioning Trust2022-08-0101 August 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-019, Pre-Notice of Disbursement from Decommissioning Trust2022-07-0606 July 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-013, Notification of Revised Decommissioning Cost Estimate2022-06-17017 June 2022 Notification of Revised Decommissioning Cost Estimate BVY 22-018, Pre-Notice of Disbursement from Decommissioning Trust2022-06-0808 June 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-015, 2021 Radiological Environmental Operating Report2022-05-0505 May 2022 2021 Radiological Environmental Operating Report BVY 22-017, Pre-Notice of Disbursement from Decommissioning Trust2022-05-0505 May 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-014, 2021 Radiological Effluent Release Report2022-04-28028 April 2022 2021 Radiological Effluent Release Report BVY 22-012, Biennial Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d)2022-04-12012 April 2022 Biennial Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d) BVY 22-011, Pre-Notice of Disbursement from Decommissioning Trust2022-04-0404 April 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-009, Status of Decommissioning and Spent Fuel Management Fund for the Year Ending 20212022-03-23023 March 2022 Status of Decommissioning and Spent Fuel Management Fund for the Year Ending 2021 BVY 22-008, Pre-Notice of Disbursement from Decommissioning Trust2022-02-24024 February 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-005, ISFSI Decommissioning Funding Plan2022-02-24024 February 2022 ISFSI Decommissioning Funding Plan 2024-01-04
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- ~Entergy Entergy Nuclear Operations, Inc. Vermont Yankee 320 Governor Hunt Rd. Vernon, VT 05354 802-257-7711 Coley C. Chappell Manager, Design and Programs 10 CFR 72.7 BVY 17-041 December 7, 2017 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Supplement to Exemption Request from Certain Requirements of 1 O CFR 72.212 and 1 O CFR 72.214 to Support the Dry Fuel Loading Campaign (EPID No. L-2017-LLE-0005)
Vermont Yankee Nuclear Power Station License No. DPR-28 Docket Nos. 50-271, 72-59 and 72-1014
REFERENCES:
- 1. Letter, Entergy Nuclear Operations, Inc. to USNRC, "Exemption Request from Certain Requirements of 1 o CFR 72.212 and 1 o CFR 72.214 to Support the Dry Fuel Loading Campaign," BVY 17-006, dated May 16, 2017 (ML17142A358}
- 2. Letter, USNRC to Holtec International, "Certificate of Compliance No. 1014, Amendment No. 1 O for the HI-STORM 100 Cask System (CAC No. L24979)," dated May 25, 2016 (ML16144A177) 3. Letter, Entergy Nuclear Operations, Inc. to USNRC, "Response to Request for Additional Information Related to Exemption Request from Certain Requirements of 1 O CFR 72.212 and 1 O CFR 72.214 to Support the Dry Fuel Loading Campaign (CAC No. L25219}," BVY 17-031, dated September 7, 2017 (ML17255A236)
Dear Sir or Madam:
By letter dated May 16, 2017 (Reference 1 ), Entergy Nuclear Operations, Inc. (ENO) submitted a request for exemption from certain requirements of 10 CFR 72.212 and 72.214 for Vermont Yankee Nuclear Power Station (VY). These regulations require, in part, compliance with the terms and conditions of the Holtec International (Holtec) Cask System Certificate of Compliance (CoC) for spent fuel storage at the VY's independent spent fuel storage installation.
Specifically, the requested exemption would allow the loading of selected fuel assemblies with shorter cooling times and higher heat *loads than those specified in CoC Amendment 1 o (Reference
- 2) into MPC-68M multi-purpose canisters (MPCs), as well as an optional loading pattern for the MPC-68M.
BVY 17-041 / Page 2 of 3 In Reference 3 , VY provided a response to a Request for Additional Information (RAI) from the U.S. Nuclear Regulatory Commission (NRC), supplementing the information in Reference
- 1. Subsequently , it has been identified that an additional supplement to Reference 1 is warranted. Specifically , ENO has determined that the proposed peak " Fuel Cladding" temperature (PCT) in the revised Table 4.111.7 , as prov i ded in Attachment 2 of Reference 1 , shou l d be revised based upon the following: The analysis of record in CoC Amendment 1 O is based on a total can i ster heat load of 36.9 kW and a maximum per storage location decay heat of 71 O watts (reference Table 2.1.30 of the Cask Final Safety Analysis Report). In comparison , for VY's site specific cask loading plan , the highest heat load cask planned for loading is approximately 24.5 kW and the highest decay heat in any cell location is 912 watts. Although the planned per assembly decay heat is slightly higher than that in the approved Amendment 10 pattern , the total canister heat l oad , wh i ch has a first orde r effect on the PCT rise during a postulated duct blockage event , is substantially lower. Based on this comparison , i t is concluded that the PCT for canisters with VY's site specific heat loads will be lower than the temperature of 722°F in Amendment 10 , providing reasonable assu r ance that the PCT will r emain less than 752°F. Accordingly , the p r oposed changes to Table 4.111.7 as provided in VY's exemption request (Reference
- 1) is revised as shown below , reverting the Fuel Cladding temperature to the 722°F value reported in CoC Amendment 1 O and adding a new Note 2 (all other previously proposed changes to this table are not affected by this supplement):
Table 4.111.7: Maximum Temperatures and Pressures Under 32-Hour 100% Air Inlets Blockage Accident Component Temperature
(°F) Fuel Cladding 722 Note.! Fuel Basket 818700 Basket Shims 702e2e MPC Shell 639&74 MPC Lid Noce l 599Ma Overpack Inner Shell 531~ Body Concrete (Local Temperature) 5254ae Lid Concrete (Local Temperature) 447~ Pressure (osig) MPC +44-:e116.3 Note 1: Maximum thru thickness section average temperature reported.
Note 2: The fuel cladding maximum temperature reported in this table is from calculations based on a canister heat load limit of 36.9 kW and a maximum per storage decay heat of 710 watts. Figure 2.111.1 optional loading pattern for the MPC-68M allows for higher canister and per cell allowable heat loads , which could result in a higher maximum cladding temperature. However , for any cask planned for loading at VY , the highest heat load is approximately 24.5 kW and the highest decay heat in an y cell location is 912 watts. Although this highest per assembly decay heat is higher than the maximum used in the prev i ous calculation , the total canister heat load, which has a first order effect on the cladding temperature rise during this accident , is substantially lowe r. B ased upon this comparison , it is concluded that the maximum fuel cladding temperature for any cask planned for loading at VY is lower than 722°F.
BVY 17-041 / Page 3 of 3 This letter contains no new regulatory commitments.
Should you have any questions concerning this letter, please contact me at (802) 451-3374.
Sincerely, cc: Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Mr. Jack D. Parrott, Sr. Project Manager Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Mail Stop T-8F5
- Washington, DC 20555 Ms. Yen-Ju Chen, Sr. Project Manager Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Mail Stop T-4B-34 Washington, DC 20555 Ms. June Tierney, Commissioner Vermont Department of Public Service 112 State Street -Drawer 20 Montpelier, Vermont 05602-2601