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| | number = ML17197A000 | | | number = ML17197A000 |
| | issue date = 07/17/2017 | | | issue date = 07/17/2017 |
| | title = Indian Point Nuclear Generating, Unit Nos. 2 and 3 - Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel (CAC Nos. MF8991 and MF8992) | | | title = Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel |
| | author name = Guzman R V | | | author name = Guzman R |
| | author affiliation = NRC/NRR/DORL/LPLI | | | author affiliation = NRC/NRR/DORL/LPLI |
| | addressee name = | | | addressee name = |
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| | docket = 05000247, 05000286 | | | docket = 05000247, 05000286 |
| | license number = DPR-026, DPR-064 | | | license number = DPR-026, DPR-064 |
| | contact person = Guzman R V | | | contact person = Guzman R |
| | case reference number = CAC MF8991, CAC MF8992 | | | case reference number = CAC MF8991, CAC MF8992 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION Vice President, Operations Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 WASHINGTON, D.C. 20555-0001 July 17, 2017 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 17, 2017 Vice President, Operations Entergy Nuclear Operations, Inc. |
| | Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| INDIAN POINT NUCLEAR GENERATING, UNIT NOS. 2 AND 3 -REQUEST FOR ADDITIONAL INFORMATION REGARDING INTER-UNIT TRANSFER OF SPENT FUEL (CAC NOS. MF8991 AND MF8992) | | INDIAN POINT NUCLEAR GENERATING, UNIT NOS. 2 AND 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING INTER-UNIT TRANSFER OF SPENT FUEL (CAC NOS. MF8991 AND MF8992) |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| By letter dated December 14, 2016, as supplemented on April 19, 2017, Entergy Nuclear Operations, Inc., submitted a license amendment request to revise the Appendix C Technical Specifications (TSs) Limiting Condition for Operation (LCO) 3.1.2 for Indian Point, Units 2 and 3 (IP2 and IP3) and Appendix A TS LCO 3.7.13 for IP2 in order to increase the population of IP3 fuel eligible for transfer to the IP2 spent fuel pit and maintain full core offload capability for IP3. The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). Based on our discussions we understand that a response to the RAI will be provided within 30 days of the date of this letter. Please contact me at (301) 415-1030 if you have any questions on this issue. Docket Nos. 50-24 7 and 50-286 | | |
| | By letter dated December 14, 2016, as supplemented on April 19, 2017, Entergy Nuclear Operations, Inc., submitted a license amendment request to revise the Appendix C Technical Specifications (TSs) Limiting Condition for Operation (LCO) 3.1.2 for Indian Point, Units 2 and 3 (IP2 and IP3) and Appendix A TS LCO 3.7.13 for IP2 in order to increase the population of IP3 fuel eligible for transfer to the IP2 spent fuel pit and maintain full core offload capability for IP3. |
| | The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). Based on our discussions we understand that a response to the RAI will be provided within 30 days of the date of this letter. |
| | Please contact me at (301) 415-1030 if you have any questions on this issue. |
| | Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-24 7 and 50-286 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION ENTERGY NUCLEAR OPERATIONS, INC. INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 DOCKET NOS. 50-247 AND 50-286 By letter dated December 14, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16355A066), as supplemented by letter dated April 19, 2017 (ADAMS Accession No. ML 17114A467), Entergy Nuclear Operations, Inc. (the licensee), submitted a license amendment request (LAR) to revise the Appendix C Technical Specifications (TSs) Limiting Condition for Operation (LCO) 3.1.2 for Indian Point Units 2 and 3 (IP2 and IP3) and Appendix A TS LCO 3.7.13 for IP2 in order to increase the population of IP3 fuel eligible for transfer to the IP2 spent fuel pit and maintain full core offload capability for IP3. Title 10 of the Code of Federal Regulations (10 CFR) Section 50.68, "Criticality accident requirements," and General Design Criterion (GDC)-62, provide requirements for licensees with regards to maintaining sub-criticality in the spent fuel pool (SFP). For licensees that utilize neutron absorbing materials (NAM) in the SFP, the condition of the NAM (including Boron-10 areal density) must be verified so that the assumptions related to the NAM in the SFP criticality analysis are supported. In order for the Nuclear Regulatory Commission (NRC) staff to verify the requirements of 10 CFR 50.68 and GDC-62 are met, the staff requests additional information regarding the condition of the NAM, and the programs in place to ensure the condition of the NAM. Request for Additional Information (RAl)-1 (RCCB) In the supplement dated April 19, 2017, the licensee stated that the preliminary results from the 2017 BADGER campaign demonstrate that the Boraflex degradation in Region 1-2 is still bounded by the current IP2 SFP criticality analysis of record (CAOR). In order to verify that the Boraflex degradation is bounded, the NRC staff requests that the licensee provide: a. A comparison of the maximum local degradation recorded during the 2017 BADGER campaign to the IP2 SFP CAOR. b. A comparison of the average panel degradation recorded during the 2017 BADGER campaign to the IP2 SFP CAOR. c. A comparison of the maximum and average gap size recorded during the 2017 BADGER campaign to the IP2 SFP CAOR. d. Any additional relevant information that demonstrates the Boraflex degradation is bounded by the current IP2 SFP CAOR. Enclosure RAl-2 (RCCB) In order for the staff to have reasonable assurance that the Boraflex will continue to perform its safety function, provide a comparison between the test results from the 2017 BADGER campaign and the RACKLIFE predicted degradation (e.g. was the RACKLIFE escape coefficient adjusted, continuing and future monitoring plans, etc.). RAl-3 (SNPB) The current IP2 and IP3 TSs limit the IP3 fuel that can be moved over to the IP2 SFP to fuel that has a maximum 4.4 weight percent (w/%) enrichment of uranium-235 (U235), minimum 3.2 w/% enrichment of U235, and from operations earlier than I P3 Cycle 12. The restriction on I P3 fuel discharged prior to Cycle 12 carries with it an implicit minimum burn up of the fuel and minimum cooling time. These TS restrictions provided margin that the NRC staff relied upon in the initial licensing of the shield transfer canister. As initially proposed the LAR of December 14, 2016, would have revised the IP2 and IP3 TSs in a way that would have permitted the transfer of fresh unpoisoned fuel with a maximum 5.0 w/% enrichment of U235 from IP3 to IP2 SFP. This would have removed margin without providing sufficient justification for doing so. In response to the NRC staff's request for supplemental information, Entergy submitted the April 19, 2017, supplemental letter, which revised the LAR in that only the lower enrichment limit in the current TSs would be removed. Additionally, the supplemental letter provided information on the remaining limited population of fuel assemblies still residing in the IP3 SFP that would meet the stipulation that they be from operations earlier than IP3 Cycle 12. However, the supplemental letter did not revise the proposed TSs from the initial LAR letter submitted on December 14, 2016. Therefore, the NRC staff requests that the licensee, submit a revision to its proposed IP2 and IP3 TSs and/or proposed license conditions (consistent with the revision in the April 10, 2017, supplemental letter) that will control the transfer of IP3 fuel to the IP2 SFP. RAl-4 (SNPB) The NRC staff has determined that the vast majority of the proprietary markings in Hl-2094289 Appendix 4.A are inappropriate as they do not meet the requirements in 1 O CFR, Section 2.390(b)(iv). The analysis follows NUREG/CR-6698, "Guide for Validation of Nuclear Criticality Safety Calculational Methodology" (ADAMS Accession No. ML012000481), which is publicly available. The licensee's April 19, 2017, supplemental letter did not rectify this discrepancy. Therefore, the NRC staff also requests that the licensee provide a revision to Hl-2094289 Appendix 4.A with proprietary markings that are consistent with 10 CFR 2.390(b).
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| ML17197AOOO *Concurrence via e-mail or memo OFFICE DORL/LPL 1 /PM DORL/LPL 1/LA DSS/SNPB/BC* DLR/RASB/BC* DORL/LPL 1/BC* NAME RGuzman LRonewicz RLukes SB loom JDanna (BClayton for) DATE 7/17/2017 7/17/2017 6/19/2017 6/13/2017 7/17/2017}} | | Request for Additional Information cc w/encl: Distribution via Listserv |
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| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION ENTERGY NUCLEAR OPERATIONS, INC. |
| | INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 DOCKET NOS. 50-247 AND 50-286 By letter dated December 14, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16355A066), as supplemented by letter dated April 19, 2017 (ADAMS Accession No. ML17114A467), Entergy Nuclear Operations, Inc. (the licensee), |
| | submitted a license amendment request (LAR) to revise the Appendix C Technical Specifications (TSs) Limiting Condition for Operation (LCO) 3.1.2 for Indian Point Units 2 and 3 (IP2 and IP3) and Appendix A TS LCO 3.7.13 for IP2 in order to increase the population of IP3 fuel eligible for transfer to the IP2 spent fuel pit and maintain full core offload capability for IP3. |
| | Title 10 of the Code of Federal Regulations (10 CFR) Section 50.68, "Criticality accident requirements," and General Design Criterion (GDC)-62, provide requirements for licensees with regards to maintaining sub-criticality in the spent fuel pool (SFP). For licensees that utilize neutron absorbing materials (NAM) in the SFP, the condition of the NAM (including Boron-10 areal density) must be verified so that the assumptions related to the NAM in the SFP criticality analysis are supported. In order for the Nuclear Regulatory Commission (NRC) staff to verify the requirements of 10 CFR 50.68 and GDC-62 are met, the staff requests additional information regarding the condition of the NAM, and the programs in place to ensure the condition of the NAM. |
| | Request for Additional Information (RAl)-1 (RCCB) |
| | In the supplement dated April 19, 2017, the licensee stated that the preliminary results from the 2017 BADGER campaign demonstrate that the Boraflex degradation in Region 1-2 is still bounded by the current IP2 SFP criticality analysis of record (CAOR). In order to verify that the Boraflex degradation is bounded, the NRC staff requests that the licensee provide: |
| | : a. A comparison of the maximum local degradation recorded during the 2017 BADGER campaign to the IP2 SFP CAOR. |
| | : b. A comparison of the average panel degradation recorded during the 2017 BADGER campaign to the IP2 SFP CAOR. |
| | : c. A comparison of the maximum and average gap size recorded during the 2017 BADGER campaign to the IP2 SFP CAOR. |
| | : d. Any additional relevant information that demonstrates the Boraflex degradation is bounded by the current IP2 SFP CAOR. |
| | Enclosure |
| | |
| | RAl-2 (RCCB) |
| | In order for the staff to have reasonable assurance that the Boraflex will continue to perform its safety function, provide a comparison between the test results from the 2017 BADGER campaign and the RACKLIFE predicted degradation (e.g. was the RACKLIFE escape coefficient adjusted, continuing and future monitoring plans, etc.). |
| | RAl-3 (SNPB) |
| | The current IP2 and IP3 TSs limit the IP3 fuel that can be moved over to the IP2 SFP to fuel that has a maximum 4.4 weight percent (w/%) enrichment of uranium-235 (U235), minimum 3.2 w/% |
| | enrichment of U235, and from operations earlier than IP3 Cycle 12. The restriction on IP3 fuel discharged prior to Cycle 12 carries with it an implicit minimum burn up of the fuel and minimum cooling time. These TS restrictions provided margin that the NRC staff relied upon in the initial licensing of the shield transfer canister. As initially proposed the LAR of December 14, 2016, would have revised the IP2 and IP3 TSs in a way that would have permitted the transfer of fresh unpoisoned fuel with a maximum 5.0 w/% enrichment of U235 from IP3 to IP2 SFP. This would have removed margin without providing sufficient justification for doing so. In response to the NRC staff's request for supplemental information, Entergy submitted the April 19, 2017, supplemental letter, which revised the LAR in that only the lower enrichment limit in the current TSs would be removed. Additionally, the supplemental letter provided information on the remaining limited population of fuel assemblies still residing in the IP3 SFP that would meet the stipulation that they be from operations earlier than IP3 Cycle 12. However, the supplemental letter did not revise the proposed TSs from the initial LAR letter submitted on December 14, 2016. Therefore, the NRC staff requests that the licensee, submit a revision to its proposed IP2 and IP3 TSs and/or proposed license conditions (consistent with the revision in the April 10, 2017, supplemental letter) that will control the transfer of IP3 fuel to the IP2 SFP. |
| | RAl-4 (SNPB) |
| | The NRC staff has determined that the vast majority of the proprietary markings in Hl-2094289 Appendix 4.A are inappropriate as they do not meet the requirements in 10 CFR, Section 2.390(b)(iv). The analysis follows NUREG/CR-6698, "Guide for Validation of Nuclear Criticality Safety Calculational Methodology" (ADAMS Accession No. ML012000481), which is publicly available. The licensee's April 19, 2017, supplemental letter did not rectify this discrepancy. |
| | Therefore, the NRC staff also requests that the licensee provide a revision to Hl-2094289 Appendix 4.A with proprietary markings that are consistent with 10 CFR 2.390(b). |
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| | ML17197AOOO *Concurrence via e-mail or memo OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DSS/SNPB/BC* DLR/RASB/BC* DORL/LPL 1/BC* |
| | NAME RGuzman LRonewicz RLukes SB loom JDanna (BClayton for) |
| | DATE 7/17/2017 7/17/2017 6/19/2017 6/13/2017 7/17/2017}} |
Letter Sequence RAI |
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MONTHYEARNL-16-118, Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel2016-12-14014 December 2016 Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel Project stage: Other ML17100A1282017-04-11011 April 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment of Inter Unit Transfer of Spent Fuel Project stage: Acceptance Review NL-17-044, Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Amendment of Inter-Unit Transfer of Spent Fuel2017-04-19019 April 2017 Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Amendment of Inter-Unit Transfer of Spent Fuel Project stage: Request ML17115A0482017-04-26026 April 2017 Acceptance of Requested Licensing Action Amendment of Inter-Unit Transfer of Spent Fuel Project stage: Acceptance Review ML17197A0002017-07-17017 July 2017 Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel Project stage: RAI ML17219A1062017-08-10010 August 2017 Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel - Shielded Transfer Canister Requests for Additional Information Project stage: RAI NL-17-102, Response to Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel2017-08-16016 August 2017 Response to Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel Project stage: Response to RAI ML17261B1902017-09-18018 September 2017 Request for RAI Response Due Date Extension License Amendment Request for Inter-Unit Transfer of Spent Fuel (CAC Nos. MF8991 and MF8992) Project stage: RAI ML17267A0002017-09-22022 September 2017 E-mail from R.Guzman to R.Walpole Indian Point Unit Nos. 2 and 3 - Request for RAI Response Due Date Extension License Amendment Request for Inter-Unit Transfer of Spent Fuel Project stage: RAI NL-17-115, Response to Request for Additional Information Re Inter-Unit Transfer of Spent Fuel, Attachments 1, 2, 3 (non-proprietary Version of Report HI-2094289, Rev. 9) and 7 Enclosed2017-10-0202 October 2017 Response to Request for Additional Information Re Inter-Unit Transfer of Spent Fuel, Attachments 1, 2, 3 (non-proprietary Version of Report HI-2094289, Rev. 9) and 7 Enclosed Project stage: Response to RAI ML17289A6552017-10-0202 October 2017 Attachment 6 to NL-17-115, Revised HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Energy Center, Revision 9 Project stage: Other ML17298B6472017-10-25025 October 2017 10/25/17 E-mail from M. Mirzai to R. Guzman Inter-Unit Transfer of Spent Fuel LAR - Clarification Response Following Teleconference on October 19, 2017 Project stage: Meeting ML17300A1742017-10-27027 October 2017 10/27/17 E-mail from M. Mirzai to R. Guzman Inter-Unit Transfer of Spent Fuel LAR - Updated Clarification Response Following Teleconference on October 19, 2017 Project stage: Meeting ML17316A0022017-11-27027 November 2017 Request for Withholding Information from Public Disclosure (CAC Nos. MF8991 and MF8992; EPID: L-2016-LLA-0039) Project stage: Withholding Request Acceptance ML17316A0012017-11-27027 November 2017 Request for Withholding Information from Public Disclosure (CAC Nos. MF8991 and MF8992; EPID: L-2016-LLA-0039) Project stage: Withholding Request Acceptance ML17316A0002017-11-27027 November 2017 Request for Withholding Information from Public Disclosure (CAC Nos. MF8991 and MF8992; EPID: L-2016-LLA-0039) Project stage: Withholding Request Acceptance ML17320A3542017-12-22022 December 2017 Issuance of Amendments Amendment of Inter-Unit Transfer of Spent Fuel (CAC Nos. MF8991 and MF8992; EPID L-2016-LLA-0039) Project stage: Approval 2017-04-11
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Category:Letter
MONTHYEARML24011A1982024-01-12012 January 2024 ISFSI, Notice of Organization Change for Site Vice President ML23342A1082024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23353A1742023-12-19019 December 2023 ISFSI, Emergency Plan, Revision 23-04 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23338A2262023-12-0404 December 2023 Signed Amendment No. 27 to Indemnity Agreement No. B-19 ML23356A0212023-12-0101 December 2023 American Nuclear Insurers, Secondary Financial Protection (SFP) Program ML23242A2772023-11-30030 November 2023 NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 ML22339A1572023-11-27027 November 2023 Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E IR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage ML23100A1252023-11-17017 November 2023 Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23100A1432023-11-16016 November 2023 Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23237A5712023-09-22022 September 2023 09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23242A2182023-09-12012 September 2023 IPEC NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286) ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23255A0142023-08-31031 August 2023 LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 ML23227A1852023-08-15015 August 2023 Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML23222A1442023-08-10010 August 2023 Registration of Spent Fuel Casks ML23208A1642023-07-26026 July 2023 Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater ML23200A0422023-07-19019 July 2023 Registration of Spent Fuel Casks ML23235A0602023-07-17017 July 2023 LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23194A0442023-07-11011 July 2023 Clarification for Indian Point Energy Center License Amendment Request, Independent Spent Fuel Storage Installation Physical Security Plan ML23192A1002023-07-11011 July 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme ML23171B0432023-06-23023 June 2023 Letter - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment ML23118A0972023-06-0606 June 2023 06-06-23 Letter to the Honorable Michael V. Lawler, Et Al., from Chair Hanson Regarding Holtec'S Announcement to Expedite Plans to Release Over 500,000 Gallons of Radioactive Wastewater from Indian Point Energy Center Into the Hudson River ML23144A3512023-05-25025 May 2023 Clementina Bartolotta of Pearl River, New York Email Against Treated Water Release from Indian Point Site ML23144A3522023-05-25025 May 2023 Loredana Bidmead of New York E-Mail Against Treated Water Release from Indian Point Site ML23144A3412023-05-25025 May 2023 Dianne Schirripa of Rockland County, New York Email Against Treated Water Release from Indian Point Site ML23144A3472023-05-25025 May 2023 David Mart of Blauvelt, New York Email Against Treated Water Release from Indian Point Site ML23144A3402023-05-25025 May 2023 Melvin Israel of New York Email Against Treated Water Release from Indian Point Site ML23144A3542023-05-25025 May 2023 Terri Thal of New City, New York Email Against Treated Water Release from Indian Point Site ML23144A3532023-05-25025 May 2023 John Shaw of New York Email Against Treated Water Release from Indian Point Site 2024-01-09
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23171B0442023-06-23023 June 2023 Enclosure - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment ML22292A2402022-10-21021 October 2022 RAIs for Master Dtf Agreement on IP1 IP2 10 18 2022 ML22103A2442022-04-13013 April 2022 Attachment - Request for Additional Information - License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme for Permanently Defueled Condition for Indian Point Energy Center ML22104A0352022-04-13013 April 2022 Request for Additional Information Related to Exemption Request from Emergency Planning Holtec Decommissioning International, LLC Indian Point Energy Center ML22006A0452022-01-0505 January 2022 PSDAR RAIs Final ML21337A2952021-12-0303 December 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (E-mail Dated 12/3/2021) ML21183A1602021-06-30030 June 2021 Update Request for Additional Information - Indian Point Energy Center Quality Assurance Program Manual (06/30/2021 E-mail) ML21138A9412021-05-18018 May 2021 Request for Additional Information - Indian Point Energy Center Quality Assurance Program Manual (05/18/2021 E-mail) ML21112A2672021-04-22022 April 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (Public Redacted Version) ML21019A5672021-01-19019 January 2021 Second Round Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML21013A0152021-01-12012 January 2021 Draft Request for Additional Information (E-mail Dated 1/12/2021) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML20268C2352020-09-24024 September 2020 Request for Additional Information (E-mail Dated 9/24/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML20233B0152020-08-20020 August 2020 Request for Additional Information (E-mail Dated 8/20/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML20190A2342020-07-0808 July 2020 Request for Additional Information - Application for Order Consenting to Transfers of Control of Licenses (07/08/2020 E-mail) ML20190A1502020-06-25025 June 2020 (06/25/2020 E-mail) Draft Request for Additional Information Application for Order Consenting to Transfers of Control of Licenses ML20106F2492020-04-15015 April 2020 E-mail (04/15/2020) Request for Additional Information Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic ML20070J7902020-03-10010 March 2020 Request for Information to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000286/2020012 ML19045A6252019-02-14014 February 2019 Request for Additional Information - Proposed License Amendment Request Regarding Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool - 2/14/19 E-mail from R.Guzman to M.Mirzai NL-18-053, Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension2018-07-18018 July 2018 Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension ML18155A4842018-06-0404 June 2018 Request for Additional Information Regarding Relief Request IP3-ISI-RR-11, E-mail from R.Guzman to C.Mackaman ML18143B6792018-05-23023 May 2018 Request for Additional Information Regarding LAR for One-Time Extension of the Containment Leakage Rate Test - Email from R.Guzman to M.Mirzai ML18094B0922018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to B. S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59) ML17296A2352017-10-23023 October 2017 Request for Additional Information -10/23/17 E-mail from R.Guzman to R.Louie Cyber Security Plan Milestone 8 Implementation Schedule (CAC Nos. MF9656, MF9657, MF9658; EPID: L-2017-LLA-0217) ML17277B5482017-10-0303 October 2017 Request for Additional Information - Relief Request IP2-ISI-RR-20 Regarding Weld Examination ML17219A1062017-08-10010 August 2017 Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel - Shielded Transfer Canister Requests for Additional Information ML17200A0852017-07-19019 July 2017 Request for Additional Information Regarding the Connection of Non-Seismic Boric Acid Recovery System to RWST Seismic Piping ML17197A0002017-07-17017 July 2017 Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel ML17170A2862017-06-27027 June 2017 RAI Set 2017-06 ML17103A4182017-04-25025 April 2017 Baffle Bolt Rais. Requests for Additional Information for the Review of the Indian Point License Renewal Application (TAC Nos. MD5407 and MD5408) ML17088A4052017-04-20020 April 2017 Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-3 (CAC Nos. MD5407 and MD5408) ML17088A3272017-04-19019 April 2017 Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408) ML17100A1282017-04-11011 April 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment of Inter Unit Transfer of Spent Fuel ML17046A2312017-03-0808 March 2017 Request for Additional Information for the Review of the Indian Point License Renewal - Set 2017-01 ML16232A1192016-09-12012 September 2016 Request for Additional Information for the Review of the Indian Point Nuclear Generating Units Nos. 2 and 3, License Renewal Application Environmental Review - Severe Accident Mitigation Alternatives (CAC Nos. MD5411 and MD5412) ML16138A1942016-07-25025 July 2016 Request for Additional Information for the Review of License Renewal Application, Set 2016-01 ML16139A0302016-06-10010 June 2016 Request for Additional Information Regarding Conditional Exemption from End-of-Line Moderator Temperature Coefficient Measurement ML16112A2262016-04-26026 April 2016 Request for Additional Information Regarding Relief Request IP2-ISI-RR-02 Alternative Examination Volume Required by Code Case N-729-1 ML16041A5782016-02-18018 February 2016 Request for Additional Information Related to License Amendment Request Regarding Moderator Temperature Coefficient Measurement Change ML16005A6292016-01-14014 January 2016 Request for Additional Information Regarding Relief Request IP2-RR-19 ML16013A0642016-01-13013 January 2016 NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097) ML15341A1662015-12-0707 December 2015 NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349) ML15148A4032015-06-29029 June 2015 Request for Additional Information Regarding the Spent Fuel Pool Criticality Analysis ML15156B2742015-06-16016 June 2015 Request for Additional Information Regarding Request to Permanently Extend the Frequency of the Containment Integrated Leak Rate Test ML15125A0972015-05-0606 May 2015 Request for Additional Information Regarding License Amendment to Permanently Extend the Frequency of the Containment Integrated Leak Rate Test ML15071A1012015-05-0404 May 2015 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-01 (TAC Nos. MD5407 and MD5408) ML15103A2592015-04-28028 April 2015 Request for Additional Information Regarding the Proposed License Amendment to Extend the Containment Type a Leak Rate Testing Frequency to 15 Years ML15104A5412015-04-22022 April 2015 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application Environmental Review (TAC Nos. MD5411 and MD5412) ML15072A4172015-03-17017 March 2015 Request for Additional Information Regarding Extension of the Containment Type a Leak Rate Testing Frequency to 15 Years ML14329B2452015-02-18018 February 2015 Request for Additional Information for the Review of the Indian Point Nuclear Generating Units 2 and 3, License Renewal Application Environmental Review (TAC Nos. MD5411 and MD5412) CNRO-2015-00008, Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company2015-02-18018 February 2015 Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company 2023-06-23
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 17, 2017 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
SUBJECT:
INDIAN POINT NUCLEAR GENERATING, UNIT NOS. 2 AND 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING INTER-UNIT TRANSFER OF SPENT FUEL (CAC NOS. MF8991 AND MF8992)
Dear Sir or Madam:
By letter dated December 14, 2016, as supplemented on April 19, 2017, Entergy Nuclear Operations, Inc., submitted a license amendment request to revise the Appendix C Technical Specifications (TSs) Limiting Condition for Operation (LCO) 3.1.2 for Indian Point, Units 2 and 3 (IP2 and IP3) and Appendix A TS LCO 3.7.13 for IP2 in order to increase the population of IP3 fuel eligible for transfer to the IP2 spent fuel pit and maintain full core offload capability for IP3.
The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). Based on our discussions we understand that a response to the RAI will be provided within 30 days of the date of this letter.
Please contact me at (301) 415-1030 if you have any questions on this issue.
Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-24 7 and 50-286
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 DOCKET NOS. 50-247 AND 50-286 By letter dated December 14, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16355A066), as supplemented by letter dated April 19, 2017 (ADAMS Accession No. ML17114A467), Entergy Nuclear Operations, Inc. (the licensee),
submitted a license amendment request (LAR) to revise the Appendix C Technical Specifications (TSs) Limiting Condition for Operation (LCO) 3.1.2 for Indian Point Units 2 and 3 (IP2 and IP3) and Appendix A TS LCO 3.7.13 for IP2 in order to increase the population of IP3 fuel eligible for transfer to the IP2 spent fuel pit and maintain full core offload capability for IP3.
Title 10 of the Code of Federal Regulations (10 CFR) Section 50.68, "Criticality accident requirements," and General Design Criterion (GDC)-62, provide requirements for licensees with regards to maintaining sub-criticality in the spent fuel pool (SFP). For licensees that utilize neutron absorbing materials (NAM) in the SFP, the condition of the NAM (including Boron-10 areal density) must be verified so that the assumptions related to the NAM in the SFP criticality analysis are supported. In order for the Nuclear Regulatory Commission (NRC) staff to verify the requirements of 10 CFR 50.68 and GDC-62 are met, the staff requests additional information regarding the condition of the NAM, and the programs in place to ensure the condition of the NAM.
Request for Additional Information (RAl)-1 (RCCB)
In the supplement dated April 19, 2017, the licensee stated that the preliminary results from the 2017 BADGER campaign demonstrate that the Boraflex degradation in Region 1-2 is still bounded by the current IP2 SFP criticality analysis of record (CAOR). In order to verify that the Boraflex degradation is bounded, the NRC staff requests that the licensee provide:
- a. A comparison of the maximum local degradation recorded during the 2017 BADGER campaign to the IP2 SFP CAOR.
- b. A comparison of the average panel degradation recorded during the 2017 BADGER campaign to the IP2 SFP CAOR.
- c. A comparison of the maximum and average gap size recorded during the 2017 BADGER campaign to the IP2 SFP CAOR.
- d. Any additional relevant information that demonstrates the Boraflex degradation is bounded by the current IP2 SFP CAOR.
Enclosure
RAl-2 (RCCB)
In order for the staff to have reasonable assurance that the Boraflex will continue to perform its safety function, provide a comparison between the test results from the 2017 BADGER campaign and the RACKLIFE predicted degradation (e.g. was the RACKLIFE escape coefficient adjusted, continuing and future monitoring plans, etc.).
RAl-3 (SNPB)
The current IP2 and IP3 TSs limit the IP3 fuel that can be moved over to the IP2 SFP to fuel that has a maximum 4.4 weight percent (w/%) enrichment of uranium-235 (U235), minimum 3.2 w/%
enrichment of U235, and from operations earlier than IP3 Cycle 12. The restriction on IP3 fuel discharged prior to Cycle 12 carries with it an implicit minimum burn up of the fuel and minimum cooling time. These TS restrictions provided margin that the NRC staff relied upon in the initial licensing of the shield transfer canister. As initially proposed the LAR of December 14, 2016, would have revised the IP2 and IP3 TSs in a way that would have permitted the transfer of fresh unpoisoned fuel with a maximum 5.0 w/% enrichment of U235 from IP3 to IP2 SFP. This would have removed margin without providing sufficient justification for doing so. In response to the NRC staff's request for supplemental information, Entergy submitted the April 19, 2017, supplemental letter, which revised the LAR in that only the lower enrichment limit in the current TSs would be removed. Additionally, the supplemental letter provided information on the remaining limited population of fuel assemblies still residing in the IP3 SFP that would meet the stipulation that they be from operations earlier than IP3 Cycle 12. However, the supplemental letter did not revise the proposed TSs from the initial LAR letter submitted on December 14, 2016. Therefore, the NRC staff requests that the licensee, submit a revision to its proposed IP2 and IP3 TSs and/or proposed license conditions (consistent with the revision in the April 10, 2017, supplemental letter) that will control the transfer of IP3 fuel to the IP2 SFP.
RAl-4 (SNPB)
The NRC staff has determined that the vast majority of the proprietary markings in Hl-2094289 Appendix 4.A are inappropriate as they do not meet the requirements in 10 CFR, Section 2.390(b)(iv). The analysis follows NUREG/CR-6698, "Guide for Validation of Nuclear Criticality Safety Calculational Methodology" (ADAMS Accession No. ML012000481), which is publicly available. The licensee's April 19, 2017, supplemental letter did not rectify this discrepancy.
Therefore, the NRC staff also requests that the licensee provide a revision to Hl-2094289 Appendix 4.A with proprietary markings that are consistent with 10 CFR 2.390(b).
ML17197AOOO *Concurrence via e-mail or memo OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DSS/SNPB/BC* DLR/RASB/BC* DORL/LPL 1/BC*
NAME RGuzman LRonewicz RLukes SB loom JDanna (BClayton for)
DATE 7/17/2017 7/17/2017 6/19/2017 6/13/2017 7/17/2017