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| ==Subject:== | | ==Subject:== |
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| Reactor Vessel Surveillance Capsule to Remain in Spent Fuel Pool | | Reactor Vessel Surveillance Capsule to Remain in Spent Fuel Pool |
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| ==Reference:== | | ==Reference:== |
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| Letter from J. Barstow (Exelon) to NRC, "Reactor Vessel Surveillance Capsule," | | Letter from J. Barstow (Exelon) to NRC, "Reactor Vessel Surveillance Capsule," dated July 10, 2015 This letter is to inform the Nuclear Regulatory Commission (NRC) that the 30 degree reactor vessel surveillance capsule which was removed from the Nine Mile Point Nuclear Station, Unit 1 (NMP1) reactor vessel during the 2015 refueling outage will remain in the spent fuel pool (SFP) and will not be re-installed into the reactor vessel. By the referenced letter dated July 10, 2015, the NRC was notified that the NMP1 30 degree reactor vessel surveillance capsule was found dislodged from the vessel pad and was removed from the reactor vessel. The referenced letter states: "The capsule will remain in the spent fuel pool at least until the next planned refueling outage in 2017. NMP1 will retain the capsule in the spent fuel pool and ensure the capsule is maintained in a condition to allow re-installation at the next refueling outage. This meets the requirements of the NMP1 Renewed Facility Operating License, Item 2.H, and the BWRVIP [Integrated Surveillance Program] ISP implementation plan." The 30 degree capsule is identified in the NMP1 Updated Final Safety Analysis Report as Capsule A' and was one of the two remaining reactor vessel surveillance capsules in the reactor vessel. Both NMP1 capsules are not identified as ISP test capsules and are defined as "deferred" in the BWRVIP-86A, Rev. 1-A, Table 4-8, ISP Test Matrix Results. The ISP intention is that plants leave the capsules defined as "deferred" in the reactor design locations such that they continue to receive exposure to preserve ISP contingency planning. |
| dated July 10, 2015 This letter is to inform the Nuclear Regulatory Commission (NRC) that the 30 degree reactor vessel surveillance capsule which was removed from the Nine Mile Point Nuclear Station, Unit 1 (NMP1) reactor vessel during the 2015 refueling outage will remain in the spent fuel pool (SFP) and will not be re-installed into the reactor vessel. By the referenced letter dated July 10, 2015, the NRC was notified that the NMP1 30 degree reactor vessel surveillance capsule was found dislodged from the vessel pad and was removed from the reactor vessel. The referenced letter states: "The capsule will remain in the spent fuel pool at least until the next planned refueling outage in 2017. NMP1 will retain the capsule in the spent fuel pool and ensure the capsule is maintained in a condition to allow re-installation at the next refueling outage. This meets the requirements of the NMP1 Renewed Facility Operating | | NMP1 has consulted with the EPRI I BWRVIP ISP program manager and they concur that reinstallation of the NMP1 Capsule A' is not required to support the ISP in either the initial 40 year term or in the ISP 60 year license renewal term. The NMP1 Capsule A' is not the original NMP1 reactor vessel surveillance capsule and is not required to support the NMP1 specific reactor vessel embrittlement program. This capsule does not provide the industry with data required by NMP1 or any other BWR. Testing of the NMP1 Capsule A' is not required to Reactor Vessel Surveillance Capsule September 29, 2016 Page 2 support the ISP. NMP1 plans to maintain the capsule in the NMP1 SFP consistent with the NMP1 Renewed Facility Operating License, Item 2.H, and the BWRVIP program implementation protocol as noted in the referenced letter. There are no regulatory commitments contained in this letter. Should you have any questions, please contact Ron Reynolds at (610) 765-5247. |
| : License, Item 2.H, and the BWRVIP [Integrated Surveillance Program]
| |
| ISP implementation plan." The 30 degree capsule is identified in the NMP1 Updated Final Safety Analysis Report as Capsule A' and was one of the two remaining reactor vessel surveillance capsules in the reactor vessel. Both NMP1 capsules are not identified as ISP test capsules and are defined as "deferred" in the BWRVIP-86A, Rev. 1-A, Table 4-8, ISP Test Matrix Results. | |
| The ISP intention is that plants leave the capsules defined as "deferred" in the reactor design locations such that they continue to receive exposure to preserve ISP contingency planning. | |
| NMP1 has consulted with the EPRI I BWRVIP ISP program manager and they concur that reinstallation of the NMP1 Capsule A' is not required to support the ISP in either the initial 40 year term or in the ISP 60 year license renewal term. The NMP1 Capsule A' is not the original NMP1 reactor vessel surveillance capsule and is not required to support the NMP1 specific reactor vessel embrittlement program. | |
| This capsule does not provide the industry with data required by NMP1 or any other BWR. Testing of the NMP1 Capsule A' is not required to Reactor Vessel Surveillance Capsule September 29, 2016 Page 2 support the ISP. NMP1 plans to maintain the capsule in the NMP1 SFP consistent with the NMP1 Renewed Facility Operating | |
| : License, Item 2.H, and the BWRVIP program implementation protocol as noted in the referenced letter. There are no regulatory commitments contained in this letter. Should you have any questions, please contact Ron Reynolds at (610) 765-5247.
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| Sincerely, David T. Gudger Manager -Licensing | | Sincerely, David T. Gudger Manager -Licensing |
| & Regulatory Affairs Exelon Generation | | & Regulatory Affairs Exelon Generation Company, LLC cc: USNRC Regional Administrator, Region I USNRC Project Manager, NMP USNRC Senior Resident Inspector, NMP}} |
| : Company, LLC cc: USNRC Regional Administrator, Region I USNRC Project Manager, NMP USNRC Senior Resident Inspector, NMP}}
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan 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 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations 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 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 NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, 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-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station 2024-09-04
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Exelon NMP1L3101 September 29, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-63 NRC Docket No. 50-220 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com
Subject:
Reactor Vessel Surveillance Capsule to Remain in Spent Fuel Pool
Reference:
Letter from J. Barstow (Exelon) to NRC, "Reactor Vessel Surveillance Capsule," dated July 10, 2015 This letter is to inform the Nuclear Regulatory Commission (NRC) that the 30 degree reactor vessel surveillance capsule which was removed from the Nine Mile Point Nuclear Station, Unit 1 (NMP1) reactor vessel during the 2015 refueling outage will remain in the spent fuel pool (SFP) and will not be re-installed into the reactor vessel. By the referenced letter dated July 10, 2015, the NRC was notified that the NMP1 30 degree reactor vessel surveillance capsule was found dislodged from the vessel pad and was removed from the reactor vessel. The referenced letter states: "The capsule will remain in the spent fuel pool at least until the next planned refueling outage in 2017. NMP1 will retain the capsule in the spent fuel pool and ensure the capsule is maintained in a condition to allow re-installation at the next refueling outage. This meets the requirements of the NMP1 Renewed Facility Operating License, Item 2.H, and the BWRVIP [Integrated Surveillance Program] ISP implementation plan." The 30 degree capsule is identified in the NMP1 Updated Final Safety Analysis Report as Capsule A' and was one of the two remaining reactor vessel surveillance capsules in the reactor vessel. Both NMP1 capsules are not identified as ISP test capsules and are defined as "deferred" in the BWRVIP-86A, Rev. 1-A, Table 4-8, ISP Test Matrix Results. The ISP intention is that plants leave the capsules defined as "deferred" in the reactor design locations such that they continue to receive exposure to preserve ISP contingency planning.
NMP1 has consulted with the EPRI I BWRVIP ISP program manager and they concur that reinstallation of the NMP1 Capsule A' is not required to support the ISP in either the initial 40 year term or in the ISP 60 year license renewal term. The NMP1 Capsule A' is not the original NMP1 reactor vessel surveillance capsule and is not required to support the NMP1 specific reactor vessel embrittlement program. This capsule does not provide the industry with data required by NMP1 or any other BWR. Testing of the NMP1 Capsule A' is not required to Reactor Vessel Surveillance Capsule September 29, 2016 Page 2 support the ISP. NMP1 plans to maintain the capsule in the NMP1 SFP consistent with the NMP1 Renewed Facility Operating License, Item 2.H, and the BWRVIP program implementation protocol as noted in the referenced letter. There are no regulatory commitments contained in this letter. Should you have any questions, please contact Ron Reynolds at (610) 765-5247.
Sincerely, David T. Gudger Manager -Licensing
& Regulatory Affairs Exelon Generation Company, LLC cc: USNRC Regional Administrator, Region I USNRC Project Manager, NMP USNRC Senior Resident Inspector, NMP