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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) |
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| 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:== |
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| ==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. |
| 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 | | 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:== |
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| 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), | | Request for Additional Information cc w/encl: Distribution via Listserv |
| 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.
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| 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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|
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| ==SUBJECT:==
| | 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 |
|
| |
|
| 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) DATED JULY 17, 2017 DISTRIBUTION:
| | RAl-2 (RCCB) |
| PUBLIC LPL 1-1 Reading File AChereskin, RASB RidsNrrDssSnpb RidsNrrDorlLpl1-1 RidsNrrLALRonewicz
| | 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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| RidsRgn1 MailCenter RidsNrrDlrRasb RidsNrrPMlndianPoint RidsAcrsAcnw_MailCTR
| | 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* |
| : JGreives, R1 KWood, SNPB ADAMS Accession No.: ML17197AOOO
| | NAME RGuzman LRonewicz RLukes SB loom JDanna (BClayton for) |
| *Concurrence via e-mail or memo OFFICE DORL/LPL 1 /PM DORL/LPL 1/LA DSS/SNPB/BC* | | DATE 7/17/2017 7/17/2017 6/19/2017 6/13/2017 7/17/2017}} |
| 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 OFFICIAL RECORD COPY}} | |
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
[Table View] |
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|---|
Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
IR 05000003/20240022024-08-0606 August 2024
NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002
PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024
Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0
ML24171A0122024-06-18018 June 2024
Reply to a Notice of Violation EA-24-037
ML24156A1162024-06-0404 June 2024
Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
IR 05000003/20240052024-05-21021 May 2024
and 3 - NRC Inspection Report Nos. 05000003/2024005, 05000247/2024005, 05000286/2024005, 07200051/2024001, and Notice of Violation
ML24128A0632024-05-0707 May 2024
Submittal of 2023 Annual Radiological Environmental Operating Report
L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024
HDI Annual Occupational Radiation Exposure Data Reports - 2023
ML24116A2412024-04-25025 April 2024
Annual Environmental Protection Plan Report
ML24114A2282024-04-23023 April 2024
Annual Radioactive Effluent Release Report
L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024
Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)
ML24080A1722024-03-20020 March 2024
Reply to a Notice of Violation EA-2024-010
IR 05000003/20240012024-03-20020 March 2024
NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only)
ML24045A0882024-02-22022 February 2024
Correction to the Technical Specifications to Reflect Appropriate Pages Removed and Retained by Previous License Amendments
ML24053A0642024-02-22022 February 2024
2023 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report
IR 05000003/20230042024-02-22022 February 2024
NRC Inspection Report Nos. 05000003/2023004, 05000247/2023004, 05000286/2023004, and 07200051/2023004 and Notice of Violation
ML24011A1982024-01-12012 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
ML23326A1322023-12-0505 December 2023
Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan
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
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
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
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
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)
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
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
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
2024-09-18
[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
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Second Round Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device
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2023-06-23
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Text
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
