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| {{#Wiki_filter:4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office RS-18-067 10 CFR 50.54(f) May 29, 2018 | | {{#Wiki_filter:4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office RS-18-067 10 CFR 50.54(f) |
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| ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | | ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 |
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| Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333 | | Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 |
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| | James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333 |
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| ==Subject:== | | ==Subject:== |
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| ==References:== | | ==References:== |
| : 1. NRC Generic Letter 2016-01, "Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools," dated April 7, 2016 (ADAMS Accession No. | | : 1. NRC Generic Letter 2016-01, "Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools," dated April 7, 2016 (ADAMS Accession No. |
| ML16097A169) 2. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "Response to Generic Letter 2016-01," dated November 3, 2016 (ADAMS Accession No. ML16308A470) 3. Letter from B. R. Sullivan (Entergy Nuclear Operations, Inc.) to U.S. NRC, "Response to Generic Letter 2016 Monitoring of Neutron Absorbing Materials in Spent Fuel Pools," dated November 3, 2016 (ADAMS Accession No. ML16308A461) 4. Letter from B. Purnell (U.S. NRC) to B. C. Hanson (Exelon Generation Company, LLC), "Calvert Cliffs Nuclear Power Plant, Unit 1; Clinton Power Station, Unit No. 1; James A. FitzPatrick Nuclear Power Plant; Nine Mile Point Nuclear Station, Units 1 and 2; and Three Mile Island Nuclear Station, Unit 1 - Request for Additional Information Regarding Generic Letter 2016-01, 'Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools' (CAC Nos. MF9450, MF9448, MF9440, MF9429, MF9428, and MF9414, EPID L-2016-LRC-0001)," dated October 27, 2017 (ADAMS Accession No. | | ML16097A169) |
| | : 2. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "Response to Generic Letter 2016-01," dated November 3, 2016 (ADAMS Accession No. ML16308A470) |
| | : 3. Letter from B. R. Sullivan (Entergy Nuclear Operations, Inc.) to U.S. NRC, "Response to Generic Letter 2016 Monitoring of Neutron Absorbing Materials in Spent Fuel Pools," dated November 3, 2016 (ADAMS Accession No. ML16308A461) |
| | : 4. Letter from B. Purnell (U.S. NRC) to B. C. Hanson (Exelon Generation Company, LLC), "Calvert Cliffs Nuclear Power Plant, Unit 1; Clinton Power Station, Unit No. 1; James A. FitzPatrick Nuclear Power Plant; Nine Mile Point Nuclear Station, Units 1 and 2; and Three Mile Island Nuclear Station, Unit 1 - Request for Additional Information Regarding Generic Letter 2016-01, 'Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools' (CAC Nos. MF9450, MF9448, MF9440, MF9429, MF9428, and MF9414, EPID L-2016-LRC-0001)," dated October 27, 2017 (ADAMS Accession No. |
| ML17285B196) | | ML17285B196) |
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| ATTACHMENT Response to Request for Additional Information Page 1 Clinton Power Station, Unit No. 1 CPS-RAl-1 (Generic RAI) The licensee's November 3, 2016, letter states that CPS does not have a site-specific monitoring program. Instead, the licensee is relying on general industry operating experience as a surrogate for the condition of the Boral installed in the CPS spent fuel pool. a. Describe how industry operating experience bounds the condition of the Boral at CPS, thereby providing assurance that any degradation or deformation that may affect the Boral at CPS is identified. b. Discuss the criticality impact due to relevant material deformation identified in general industry operating experience, and how it can be accommodated by the nuclear criticality safety analysis of record for CPS without exceeding subcriticality requirements. Response Through its Nuclear Safety Culture, procedures, and processes, Exelon Generation Company, LLC (EGC) systematically and effectively collects, evaluates, and implements relevant internal and external operating experience (OE) in a timely manner. Issues emerging from the use of Boral in the spent fuel racks are monitored through the EGC OE Program and Corrective Action Program. As indicated in the original Generic Letter response for Clinton Power Station (CPS), the site will continue to monitor industry OE related to Boral, which includes ongoing participation in the EPRI Neutron Absorber Users Group (NAUG) and its related programs (e.g., industry-wide learning aging management for neutron-absorbing material). Industry-wide, to date there have been no indications of a loss of Boral material of a nature that diminished the neutron-absorbing capability of the Boral (Reference 1). CPS follows the EPRI Water Chemistry Control Program and there have been no indications of a loss of Boral neutron-absorbing capabilities at a plant following the guidelines. In addition, to date there are no plant-specific operating conditions or rack attributes that would merit concern that the CPS spent fuel racks or SFP environment are not bounded by the industry-wide OE. Finally, Reference 2 documents that observed or foreseen degradation or deformation of the Boral has an insignificant impact on SFP criticality. | | ATTACHMENT Response to Request for Additional Information Page 1 Clinton Power Station, Unit No. 1 CPS-RAl-1 (Generic RAI) The licensee's November 3, 2016, letter states that CPS does not have a site-specific monitoring program. Instead, the licensee is relying on general industry operating experience as a surrogate for the condition of the Boral installed in the CPS spent fuel pool. a. Describe how industry operating experience bounds the condition of the Boral at CPS, thereby providing assurance that any degradation or deformation that may affect the Boral at CPS is identified. b. Discuss the criticality impact due to relevant material deformation identified in general industry operating experience, and how it can be accommodated by the nuclear criticality safety analysis of record for CPS without exceeding subcriticality requirements. |
| | Response Through its Nuclear Safety Culture, procedures, and processes, Exelon Generation Company, LLC (EGC) systematically and effectively collect s, evaluates, and implements relevant internal and external operating experience (OE) in a timely manner. Issues emerging from the use of Boral in the spent fuel racks are monitored through the EGC OE Program and Corrective Action Program. As indicated in the original Generic Letter response for Clinton Power Station (CPS), the site will continue to monitor industry OE related to Boral, which includes ongoing participation in the EPRI Neutron Absorber Users Group (NAUG) and its related programs (e.g., industry-wide learning aging management for neutron-absorbing material). Industry-wide, to date there have been no indications of a loss of Boral material of a nature that diminished the neutron-absorbing capability of the Boral (Reference 1). CPS follows the EPRI Water Chemistry Control Program and there have been no indications of a loss of Boral neutron-absorbing capabilities at a plant following the guidelines. In addition, to date there are no plant-specific operating conditions or rack attributes that would merit concern that the CPS spent fuel racks or SFP environment are not bounded by the industry-wide OE. Finally, Reference 2 documents that observed or foreseen degradation or deformation of the Boral has an insignificant impact on SFP criticality. |
| The industry OE aligns with the CPS licensing basis. The NAUG, through EPRI, is currently developing an industry-wide program/database to aid in monitoring indications of potential Boral degradation and deformation. Over 70,000 water chemistry data points have been collected to date, from over 30 SFPs, for this program. | | The industry OE aligns with the CPS licensing basis. The NAUG, through EPRI, is currently developing an industry-wide program/database to aid in monitoring indications of potential Boral degradation and deformation. Over 70,000 water chemistry data points have been collected to date, from over 30 SFPs, for this program. |
| Surveillance data from 50 coupons across 25 SFPs has also been collected to date. The program, supported by EPRI NAUG and industry participants, is described in Reference 3 and includes insights and feedback received from numerous communications with the NRC. Relevant issues emerging from this industry effort will be monitored through the EGC OE Program and Corrective Action Program. To date, the industry OE has revealed no instances of an impact on SFP criticality due to observed Boral deformation (e.g., blistering) or degradation (e.g., pitting). The NAUG, through ATTACHMENT Response to Request for Additional Information Page 2 EPRI, has recently completed a study (Reference 2) which analyzes the criticality impact of blisters and pits on Boral. Simulations were performed at unborated conditions (i.e., 0 ppm) to ensure applicability to BWRs such as CPS. The study results demonstrate that pitting and blistering, on a scale much larger than any that has been observed in the industry OE, has an insignificant impact on SFP criticality. Therefore, the SFP criticality safety analysis of record remains applicable. James A. FitzPatrick Nuclear Power Plant JAF-RAl-1 (Generic RAI) Discuss the criticality impact due to the material deformation identified at JAF, and how it can be accommodated by the nuclear criticality safety analysis of record without exceeding subcriticality requirements. Response To date, the industry OE has revealed no instances of an impact on SFP criticality due to observed Boral deformation (e.g., blistering) or degradation (e.g., pitting). The NAUG, through EPRI, has recently completed a study (Reference 2) which analyzes the criticality impact of blisters and pits on Boral. Simulations were performed at unborated conditions (i.e., 0 ppm) to ensure applicability to BWRs such as James A. FitzPatrick. The study results demonstrate that pitting and blistering, on a scale much larger than any that has been observed in the industry OE, has an insignificant impact on SFP criticality. Therefore, the SFP criticality safety analysis of record remains applicable. References 1. EPRI Report 1021052, "Overview of BORAL Performance Based Upon Surveillance Coupon Measurements," dated December 2010 2. EPRI Report 3002013119, "Evaluation of the Impact of Neutron Absorber Material Blistering and Pitting on Spent Fuel Pool Reactivity," dated May 2018 3. EPRI Document 3002013122, "Roadmap for the Industrywide Learning Aging Management Program (i-LAMP) for Neutron Absorber Materials in Spent Fuel Pools," dated May 2018}} | | Surveillance data from 50 coupons across 25 SFPs has also been collected to date. The program, supported by EPRI NAUG and industry participants, is described in Reference 3 and includes insights and feedback received from numerous communications with the NRC. Relevant issues emerging from this industry effort will be monitored through the EGC OE Program and Corrective Action Program. To date, the industry OE has revealed no instances of an impact on SFP criticality due to observed Boral deformation (e.g., blistering) or degradation (e.g., pitting). The NAUG, through ATTACHMENT Response to Request for Additional Information Page 2 EPRI, has recently completed a study (Reference 2) which analyzes the criticality impact of blisters and pits on Boral. Simulations were performed at unborated conditions (i.e., 0 ppm) to ensure applicability to BWRs such as CPS. The study results demonstrate that pitting and blistering, on a scale much larger than any that has been observed in the industry OE, has an insignificant impact on SFP criticality. Therefore, the SFP criticality safety analysis of record remains applicable. |
| | James A. FitzPatrick Nuclear Power Plant JAF-RAl-1 (Generic RAI) Discuss the criticality impact due to the material deformation identified at JAF, and how it can be accommodated by the nuclear criticality safety analysis of record without exceeding subcriticality requirements. |
| | Response To date, the industry OE has revealed no instances of an impact on SFP criticality due to observed Boral deformation (e.g., blistering) or degradation (e.g., pitting). The NAUG, through EPRI, has recently completed a study (Reference 2) which analyzes the criticality impact of blisters and pits on Boral. Simulations were performed at unborated conditions (i.e., 0 ppm) to ensure applicability to BWRs such as James A. FitzPatrick. The study results demonstrate that pitting and blistering, on a scale much larger than any that has been observed in the industry OE, has an insignificant impact on SFP criticality. Therefore, the SFP criticality safety analysis of record remains applicable. References 1. EPRI Report 1021052, "Overview of BORAL Performance Based Upon Surveillance Coupon Measurements," dated December 2010 2. EPRI Report 3002013119, "Evaluation of the Impact of Neutron Absorber Material Blistering and Pitting on Spent Fuel Pool Reactivity," dated May 2018 3. EPRI Document 3002013122, "Roadmap for the Industrywide Learning Aging Management Program (i-LAMP) for Neutron Absorber Materials in Spent Fuel Pools," dated May 2018}} |
Letter Sequence Response to RAI |
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EPID:L-2016-LRC-0001, Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station (Open) CAC:MF9409, (Open) |
Results
Other: ML17297A847, ML17303B158, ML17307A330, ML18030B178, ML18030B238, ML18030B361, ML18031A995, ML18249A049, ML18249A061, ML18249A075, ML18249A080, ML18249A091, ML18249A162, ML18249A178, ML18249A180, ML18249A231, ML18249A242, ML18249A334, ML18249A365, ML18249A380, ML18249A383, ML18249A386, ML18249A392, ML18249A407, ML18253A099, ML18253A130, ML18269A351
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MONTHYEARRS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017 Response to Request for Additional Information Regarding Generic Letter 2016-01 Project stage: Response to RAI ML17297A8472017-10-27027 October 2017 Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools (CAC No. MF9430; EPID L-2016-LRC-0001) Project stage: Other ML17285B1962017-10-27027 October 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. Project stage: RAI ML17304A0102017-11-0101 November 2017 Unit Nos.1 and 2 - Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9444 and MF9445; EPID L-2016-LRC-0001) Project stage: RAI ML17303B1582017-11-0707 November 2017 FENOC-Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, Perry Nuclear Power Plant Unit 1 - Generic Letter 2016-01, Request for Supplemental Information Project stage: Other ML17307A3302017-11-20020 November 2017 Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools(Cac Nos. MF9920, MF9452, MF9437, MF9919, and MF9432; EPID L-2016-LRC-0001) Project stage: Other ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 Project stage: Response to RAI NL-18-0085, Response to NRC RAIs Regarding Generic Letter 2016-012018-02-0505 February 2018 Response to NRC RAIs Regarding Generic Letter 2016-01 Project stage: Request ML18030B2382018-04-13013 April 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools Project stage: Other L-16-001, Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2018-05-24024 May 2018 Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. Project stage: Request PLA-7704, Response to Generic Letter 2016-01, Request for Supplemental Information2018-05-24024 May 2018 Response to Generic Letter 2016-01, Request for Supplemental Information Project stage: Request AEP-NRC-2018-01, Response to Request for Additional Information Regarding Generic Letter 2016-012018-05-25025 May 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 Project stage: Response to RAI L-18-121, Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2018-05-25025 May 2018 Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. Project stage: Request RS-18-067, Response to Request for Additional Information Regarding Generic Letter 2016-012018-05-29029 May 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 Project stage: Response to RAI ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information2018-05-29029 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information Project stage: Request RA-18-0011, Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools Project stage: Request CNRO-2018-00021, Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station Project stage: Request CNL-18-061, Response to NRC Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-31031 May 2018 Response to NRC Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools Project stage: Supplement ULNRC-06440, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools - Request for Supplemental Information2018-05-31031 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools - Request for Supplemental Information Project stage: Request ML18031A9952018-08-27027 August 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9423; EPID L-2016-LRC-0001) Project stage: Other ML18030B1782018-08-27027 August 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9441; EPID L-2016-LRC-0001) Project stage: Other ML18030B3612018-08-30030 August 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9427; EPID L-2016-LRC-0001) Project stage: Other ML18249A2312018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9448; EPID L-2016-LRC-0001) Project stage: Other ML18249A0802018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9431 and MF9430; EPID L-2016-LRC-0001) Project stage: Other ML18249A4072018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC MF9920, MF9452, MF9451, MF9425, MF9406-MF9408; EPID L-2016-LRC-0001) Project stage: Other ML18249A0492018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9449 and MF9450; EPID L-2016-LRC-0001) Project stage: Other ML18249A0612018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9428 and MF9429; EPID L-2016-LRC-0001) Project stage: Other ML18249A0752018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9410 and MF9411; EPID L-2016-LRC-0001) Project stage: Other ML18249A0912018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9421 and MF9422; EPID L-2016-LRC-0001) Project stage: Other ML18249A1622018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9424; EPID L-2016-LRC-0001) Project stage: Other ML18249A1782018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9438; EPID L-2016-LRC-0001) Project stage: Other ML18249A1802018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9456 and MF9457; EPID L-2016-LRC-0001) Project stage: Other ML18249A2422018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9415 and MF9416; EPID L-2016-LRC-0001) Project stage: Other ML18249A3342018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9435 and MF9436; EPID L-2016-LRC-0001) Project stage: Other ML18249A3652018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9437; EPID L-2016-LRC-0001) Project stage: Other ML18249A3802018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9412 and MF9413; EPID L-2016-LRC-0001) Project stage: Other ML18249A3832018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9418 and MF9419; EPID L-2016-LRC-0001) Project stage: Other ML18249A3862018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9433 and MF9434; EPID L-2016-LRC-0001) Project stage: Other ML18249A3922018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC MF9444, MF9445, MF9443, MF9440, MF9409; EPID L-2016-LRC-0001) Project stage: Other ML18253A0992018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9414; EPID L-2016-LRC-0001) Project stage: Other ML18253A1302018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9920 and MF9432; EPID L-2016-LRC-0001) Project stage: Other ML18269A3512018-09-26026 September 2018 Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools Project stage: Other 2018-04-13
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Category:Letter
MONTHYEARML24270A0742024-09-30030 September 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0134) - LTR ML24270A1452024-09-26026 September 2024 Notice of Enforcement Discretion for James A. Fitzpatrick Nuclear Power Plant JAFP-24-0047, License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software2024-09-25025 September 2024 License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software JAFP-24-0045, Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2024-09-20020 September 2024 Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20240112024-09-19019 September 2024 Follow-up to Inspection Procedure 71153 Report 05000333/2024011 and Preliminary White Finding and Apparent Violation JAFP-24-0044, Core Operating Limits Report Cycle 272024-09-16016 September 2024 Core Operating Limits Report Cycle 27 JAFP-24-0043, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2024-09-12012 September 2024 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues ML24211A2302024-09-11011 September 2024 – Request for Partial Site Release for Facility Operating License No. NPF-62 RS-24-087, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2024-09-0909 September 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station IR 05000461/20240112024-09-0909 September 2024 Commercial Grade Dedication Inspection Report 05000461/2024011 05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-0404 September 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation ML24165A0382024-09-0404 September 2024 Issuance of Amendment No. 356 Update Fuel Handling Accident Analysis IR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) IR 05000461/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Clinton Power Station (Report 05000461/2024005) ML24222A3952024-08-23023 August 2024 Regulatory Audit Report to Support the Review of the Amendments to Revise Reactor Water Cleanup Valve Isolation Timing 05000333/LER-2024-001, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-08-21021 August 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000461/20240022024-08-0909 August 2024 Integrated Inspection Report 05000461/2024002 ML24220A2772024-08-0707 August 2024 Request for Information for the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000461/2025010 IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 ML24212A2212024-08-0202 August 2024 License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-LNE-0000) (Docket Number: 50-461) JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report ML24208A0492024-07-30030 July 2024 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Proposed No Significant Hazards Consideration Determination (Letter) JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20244032024-07-18018 July 2024 Biennial Problem Identification and Resolution Inspection Report 05000333/2024403 (Cover Letter Only) IR 05000333/20244012024-07-15015 July 2024 Security Baseline Inspection 05000333/2024401 RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions ML24157A3242024-07-11011 July 2024 Issuance of Amendment No. 254 Revision of Reactor Water Cleanup Isolation Valve Timing ML24190A1932024-07-0909 July 2024 Correction Letter of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 ML24184A1662024-07-0303 July 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24158A0772024-07-0303 July 2024 Notice of Consideration of Approval of Partial Site Release, Public Meeting, and Request for Comments (EPID L-2023-LLA-0088) - Letter ML24163A3242024-06-28028 June 2024 LRA - Portal Letter ML24163A3252024-06-28028 June 2024 Aging Management Regulatory Audit Plan ML24179A3112024-06-27027 June 2024 05000461; Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24136A1162024-06-26026 June 2024 Issuance of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance ML24176A0272024-06-25025 June 2024 Confirmation of Initial License Examination, July 2025 JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24176A2412024-06-24024 June 2024 Licensed Operator Positive Fitness-for-Duty Test RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations JAFP-24-0026, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance2024-06-12012 June 2024 Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes IR 05000461/20240122024-05-20020 May 2024 Biennial Problem Identification and Resolution Inspection Report Report 05000461/2024012 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-050, Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2024-05-0909 May 2024 Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation JAFP-24-0023, 2023 Annual Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000333/20240012024-05-0909 May 2024 Integrated Inspection Report 05000333/2024001 IR 05000461/20240012024-05-0707 May 2024 Integrated Inspection Report 05000461/2024001 2024-09-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-050, Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2024-05-0909 May 2024 Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation ML24085A2362024-03-25025 March 2024 Response to Request for Additional Information JAFP-24-0010, Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2024-02-29029 February 2024 Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-24-0009, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-02-28028 February 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis RS-24-005, Additional Information Supporting Request for Partial Site Release2024-02-0808 February 2024 Additional Information Supporting Request for Partial Site Release RS-22-089, Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-07-25025 July 2022 Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..2022-06-16016 June 2022 Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.. CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-22-0008, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary2022-01-14014 January 2022 Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments RS-21-087, Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-08-31031 August 2021 Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.2021-08-0909 August 2021 Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance. NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments ML21138A0132021-05-18018 May 2021 NRC Response to Request for Additional Time to Respond to James A. Fitzpatrick Nuclear Power Plant: Final Significance Determination of a White Finding with Assessment Follow Up and Notice of Violation-Inspection No. 05000333/2021090 JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting ML21111A0042021-04-20020 April 2021 Response to Request to Request Clinton, Unit 1, COVID-19 Related Request for Exemption from Part 26 Work Hours Requirements RS-21-037, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 22021-03-23023 March 2021 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 2 JAFP-21-0008, Supplement to Application to Revise Surveillance Requirement (SR) 3.5.1.62021-02-18018 February 2021 Supplement to Application to Revise Surveillance Requirement (SR) 3.5.1.6 JAFP-21-0005, Response to Request for Additional Information to Support Review of License Amendment Request - Application to Modify Technical Specifications 3.6.1.3 Primary Containment Isolation Valves2021-01-26026 January 2021 Response to Request for Additional Information to Support Review of License Amendment Request - Application to Modify Technical Specifications 3.6.1.3 Primary Containment Isolation Valves RS-20-139, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.692020-11-24024 November 2020 Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 ML20315A2452020-11-10010 November 2020 Response to Request for Additional Information to Support Review of License Amendment Request - Application to Modify Technical Specifications 3.6.1.3 Primary Containment Isolation Valves RS-20-095, Response to Request for Additional Information Related to Relief Request I4R-06 for the Fourth Inservice Inspection Interval2020-08-13013 August 2020 Response to Request for Additional Information Related to Relief Request I4R-06 for the Fourth Inservice Inspection Interval RS-20-096, Response to Request for Additional Information Related to Relief Request I4R-07 for the Fourth Inservice Inspection Interval2020-08-13013 August 2020 Response to Request for Additional Information Related to Relief Request I4R-07 for the Fourth Inservice Inspection Interval ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information RS-20-069, Additional Information Supporting Request for License Amendment Regarding Automatic Operation of Transformer Load Tap Changer2020-06-29029 June 2020 Additional Information Supporting Request for License Amendment Regarding Automatic Operation of Transformer Load Tap Changer RS-20-067, Response to Request for Additional Information Related to Relief Request I4R-01 for the Fourth Inservice Inspection Interval2020-05-13013 May 2020 Response to Request for Additional Information Related to Relief Request I4R-01 for the Fourth Inservice Inspection Interval JAFP-20-0030, Response to Request for Additional Information in Support of License Amendment Request - Proposed Changes to the Technical Specifications to Primary Containment Hydrodynamic Loads2020-04-0606 April 2020 Response to Request for Additional Information in Support of License Amendment Request - Proposed Changes to the Technical Specifications to Primary Containment Hydrodynamic Loads RS-20-045, Response to Request for Additional Information Related to Relief Request 14R.05 for the Fourth Inservice Inspection Interval2020-04-0101 April 2020 Response to Request for Additional Information Related to Relief Request 14R.05 for the Fourth Inservice Inspection Interval JAFP-20-0026, Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation2020-03-31031 March 2020 Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation JAFP-20-0020, Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation2020-02-21021 February 2020 Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation JAFP-20-0008, Response to Request for Additional Information Associated with the License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences2020-01-16016 January 2020 Response to Request for Additional Information Associated with the License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences RS-19-112, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control2019-12-0505 December 2019 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control JAFP-19-0105, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (Rwcu)...2019-11-0606 November 2019 Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (Rwcu)... NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 ML19279A0012019-10-0606 October 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to the TS 3.8.1 Action ... JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants JAFP-19-0009, End of Interval Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval2019-01-15015 January 2019 End of Interval Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 RS-18-150, Transmittal of Supplemental Information for Exelon Evaluation of Preliminary White Finding2018-12-20020 December 2018 Transmittal of Supplemental Information for Exelon Evaluation of Preliminary White Finding RS-18-143, Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements2018-11-29029 November 2018 Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements RS-18-103, Response to Request for Additional Information Concerning License Amendment Request to Revise Alternate Source Term Dose Calculation2018-08-29029 August 2018 Response to Request for Additional Information Concerning License Amendment Request to Revise Alternate Source Term Dose Calculation RS-18-097, Response to Request for Additional Information and Supplemental Information-License Amendment.2018-07-27027 July 2018 Response to Request for Additional Information and Supplemental Information-License Amendment. JAFP-18-0068, Response to Request for Additional Information: License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2018-07-12012 July 2018 Response to Request for Additional Information: License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors RS-18-067, Response to Request for Additional Information Regarding Generic Letter 2016-012018-05-29029 May 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 2024-08-09
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Text
4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office RS-18-067 10 CFR 50.54(f)
May 29, 2018
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461
James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333
Subject:
Response to Request for Additional Information Regarding Generic Letter 2016-01
References:
- 1. NRC Generic Letter 2016-01, "Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools," dated April 7, 2016 (ADAMS Accession No.
ML16097A169)
- 2. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "Response to Generic Letter 2016-01," dated November 3, 2016 (ADAMS Accession No. ML16308A470)
- 3. Letter from B. R. Sullivan (Entergy Nuclear Operations, Inc.) to U.S. NRC, "Response to Generic Letter 2016 Monitoring of Neutron Absorbing Materials in Spent Fuel Pools," dated November 3, 2016 (ADAMS Accession No. ML16308A461)
- 4. Letter from B. Purnell (U.S. NRC) to B. C. Hanson (Exelon Generation Company, LLC), "Calvert Cliffs Nuclear Power Plant, Unit 1; Clinton Power Station, Unit No. 1; James A. FitzPatrick Nuclear Power Plant; Nine Mile Point Nuclear Station, Units 1 and 2; and Three Mile Island Nuclear Station, Unit 1 - Request for Additional Information Regarding Generic Letter 2016-01, 'Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools' (CAC Nos. MF9450, MF9448, MF9440, MF9429, MF9428, and MF9414, EPID L-2016-LRC-0001)," dated October 27, 2017 (ADAMS Accession No.
ML17285B196)
ATTACHMENT Response to Request for Additional Information Page 1 Clinton Power Station, Unit No. 1 CPS-RAl-1 (Generic RAI) The licensee's November 3, 2016, letter states that CPS does not have a site-specific monitoring program. Instead, the licensee is relying on general industry operating experience as a surrogate for the condition of the Boral installed in the CPS spent fuel pool. a. Describe how industry operating experience bounds the condition of the Boral at CPS, thereby providing assurance that any degradation or deformation that may affect the Boral at CPS is identified. b. Discuss the criticality impact due to relevant material deformation identified in general industry operating experience, and how it can be accommodated by the nuclear criticality safety analysis of record for CPS without exceeding subcriticality requirements.
Response Through its Nuclear Safety Culture, procedures, and processes, Exelon Generation Company, LLC (EGC) systematically and effectively collect s, evaluates, and implements relevant internal and external operating experience (OE) in a timely manner. Issues emerging from the use of Boral in the spent fuel racks are monitored through the EGC OE Program and Corrective Action Program. As indicated in the original Generic Letter response for Clinton Power Station (CPS), the site will continue to monitor industry OE related to Boral, which includes ongoing participation in the EPRI Neutron Absorber Users Group (NAUG) and its related programs (e.g., industry-wide learning aging management for neutron-absorbing material). Industry-wide, to date there have been no indications of a loss of Boral material of a nature that diminished the neutron-absorbing capability of the Boral (Reference 1). CPS follows the EPRI Water Chemistry Control Program and there have been no indications of a loss of Boral neutron-absorbing capabilities at a plant following the guidelines. In addition, to date there are no plant-specific operating conditions or rack attributes that would merit concern that the CPS spent fuel racks or SFP environment are not bounded by the industry-wide OE. Finally, Reference 2 documents that observed or foreseen degradation or deformation of the Boral has an insignificant impact on SFP criticality.
The industry OE aligns with the CPS licensing basis. The NAUG, through EPRI, is currently developing an industry-wide program/database to aid in monitoring indications of potential Boral degradation and deformation. Over 70,000 water chemistry data points have been collected to date, from over 30 SFPs, for this program.
Surveillance data from 50 coupons across 25 SFPs has also been collected to date. The program, supported by EPRI NAUG and industry participants, is described in Reference 3 and includes insights and feedback received from numerous communications with the NRC. Relevant issues emerging from this industry effort will be monitored through the EGC OE Program and Corrective Action Program. To date, the industry OE has revealed no instances of an impact on SFP criticality due to observed Boral deformation (e.g., blistering) or degradation (e.g., pitting). The NAUG, through ATTACHMENT Response to Request for Additional Information Page 2 EPRI, has recently completed a study (Reference 2) which analyzes the criticality impact of blisters and pits on Boral. Simulations were performed at unborated conditions (i.e., 0 ppm) to ensure applicability to BWRs such as CPS. The study results demonstrate that pitting and blistering, on a scale much larger than any that has been observed in the industry OE, has an insignificant impact on SFP criticality. Therefore, the SFP criticality safety analysis of record remains applicable.
James A. FitzPatrick Nuclear Power Plant JAF-RAl-1 (Generic RAI) Discuss the criticality impact due to the material deformation identified at JAF, and how it can be accommodated by the nuclear criticality safety analysis of record without exceeding subcriticality requirements.
Response To date, the industry OE has revealed no instances of an impact on SFP criticality due to observed Boral deformation (e.g., blistering) or degradation (e.g., pitting). The NAUG, through EPRI, has recently completed a study (Reference 2) which analyzes the criticality impact of blisters and pits on Boral. Simulations were performed at unborated conditions (i.e., 0 ppm) to ensure applicability to BWRs such as James A. FitzPatrick. The study results demonstrate that pitting and blistering, on a scale much larger than any that has been observed in the industry OE, has an insignificant impact on SFP criticality. Therefore, the SFP criticality safety analysis of record remains applicable. References 1. EPRI Report 1021052, "Overview of BORAL Performance Based Upon Surveillance Coupon Measurements," dated December 2010 2. EPRI Report 3002013119, "Evaluation of the Impact of Neutron Absorber Material Blistering and Pitting on Spent Fuel Pool Reactivity," dated May 2018 3. EPRI Document 3002013122, "Roadmap for the Industrywide Learning Aging Management Program (i-LAMP) for Neutron Absorber Materials in Spent Fuel Pools," dated May 2018