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| | number = ML17065A162 | | | number = ML17065A162 |
| | issue date = 03/14/2017 | | | issue date = 03/14/2017 |
| | title = Nine Mile Point Nuclear Station, Units 1 and 2 - Request for Additional Information Regarding Proposed Alternative to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR Part 50, Appendix J (CAC Nos. MF907 | | | title = Request for Additional Information Regarding Proposed Alternative to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR Part 50, Appendix J |
| | author name = Marshall M L | | | author name = Marshall M |
| | author affiliation = NRC/NRR/DORL/LPLI | | | author affiliation = NRC/NRR/DORL/LPLI |
| | addressee name = Hanson B C | | | addressee name = Hanson B |
| | addressee affiliation = Exelon Nuclear | | | addressee affiliation = Exelon Nuclear |
| | docket = 05000220, 05000410 | | | docket = 05000220, 05000410 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 March 14, 2017 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 14, 2017 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED ALTERNATIVE REQUEST NUMBER GVRR-3 TO PERFORM PRESSURE ISOLATION VALVE LEAKAGE TESTING AT FREQUENCIES CONSISTENT WITH TITLE 10 OF THE CODE OF FEDERAL REGULATIONS, PART 50, APPENDIX J (CAC NOS. MF9073 AND MF9074) | | NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED ALTERNATIVE REQUEST NUMBER GVRR-3 TO PERFORM PRESSURE ISOLATION VALVE LEAKAGE TESTING AT FREQUENCIES CONSISTENT WITH TITLE 10 OF THE CODE OF FEDERAL REGULATIONS, PART 50, APPENDIX J (CAC NOS. |
| | MF9073 AND MF9074) |
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| ==Dear Mr. Hanson:== | | ==Dear Mr. Hanson:== |
| By letter dated December 27, 2017 (Agencywide Documents Access and Management System Accession No. ML 17003A096), Exelon Generation Company, LLC (the licensee) submitted a request in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1) for a proposed alternative to the requirements of 10 CFR 50.55a and the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Nine Mile Point Nuclear Station, Units 1 and 2. The proposed alternative would allow the licensee to perform pressure isolation valve leakage testing at frequencies consistent with 10 CFR Part 50, Appendix J, primary reactor containment leakage testing performance-based requirements. | | |
| The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that additional information is needed to complete its review. Enclosed is our Request for Additional Information (RAI). The RAI was discussed with your staff on March 13, 2017, and it was agreed that your response would be provided within 30 days from the date of this letter. Docket Nos. 50-220 and 50-410 | | By letter dated December 27, 2017 (Agencywide Documents Access and Management System Accession No. ML17003A096), Exelon Generation Company, LLC (the licensee) submitted a request in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1) for a proposed alternative to the requirements of 10 CFR 50.55a and the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Nine Mile Point Nuclear Station, Units 1 and 2. The proposed alternative would allow the licensee to perform pressure isolation valve leakage testing at frequencies consistent with 10 CFR Part 50, Appendix J, primary reactor containment leakage testing performance-based requirements. |
| | The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that additional information is needed to complete its review. |
| | Enclosed is our Request for Additional Information (RAI). The RAI was discussed with your staff on March 13, 2017, and it was agreed that your response would be provided within 30 days from the date of this letter. |
| | Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information cc: Distribution via Listserv Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION PROPOSED ALTERNATIVE REQUEST NUMBER GVRR-3 FOR THE INSERVICE TESTING PROGRAM FOURTH AND THIRD 10-YEAR INTERVALS NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-220 AND 50-410 By letter dated December 27, 2017 (Agencywide Documents Access and Management System Accession No. ML 17003A096), Exelon Generation Company, LLC (Exelon, the licensee) submitted a request in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1) for a proposed alternative to the requirements of 10 CFR 50.55a and the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code for Nine Mile Point Nuclear Station, Units 1 and 2 (NMP1 and NMP2). The Proposed Alternative Request Number GVRR-3 would allow the licensee to perform pressure isolation valve (PIV) leakage testing at frequencies consistent with the 10 CFR Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors,'' | | Request for Additional Information cc: Distribution via Listserv |
| reactor containment leakage testing performance-based requirements. | | |
| The licensee has proposed an alternative test in lieu of the requirements found in the 2004 Edition of the ASME Operation and Maintenance (OM) Code Section ISTC-3630(a) for 35 PIVs. The licensee proposes to functionally test and verify the leakage rate of these PIVs using 10 CFR Part 50, Appendix J, Option B, performance-based schedule. | | REQUEST FOR ADDITIONAL INFORMATION PROPOSED ALTERNATIVE REQUEST NUMBER GVRR-3 FOR THE INSERVICE TESTING PROGRAM FOURTH AND THIRD 10-YEAR INTERVALS NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-220 AND 50-410 By letter dated December 27, 2017 (Agencywide Documents Access and Management System Accession No. ML17003A096), Exelon Generation Company, LLC (Exelon, the licensee) submitted a request in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1) for a proposed alternative to the requirements of 10 CFR 50.55a and the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code for Nine Mile Point Nuclear Station, Units 1 and 2 (NMP1 and NMP2). The Proposed Alternative Request Number GVRR-3 would allow the licensee to perform pressure isolation valve (PIV) leakage testing at frequencies consistent with the 10 CFR Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors,'' reactor containment leakage testing performance-based requirements. The licensee has proposed an alternative test in lieu of the requirements found in the 2004 Edition of the ASME Operation and Maintenance (OM) Code Section ISTC-3630(a) for 35 PIVs. |
| Valves would initially be tested at the required interval schedule, which is currently every refueling outage (RFO), or 2 years, as specified by ASME OM Code, Section ISTC-3630(a). | | The licensee proposes to functionally test and verify the leakage rate of these PIVs using 10 CFR Part 50, Appendix J, Option B, performance-based schedule. Valves would initially be tested at the required interval schedule, which is currently every refueling outage (RFO), or 2 years, as specified by ASME OM Code, Section ISTC-3630(a). Valves that have demonstrated good performance for two consecutive cycles may have their test interval extended. Any PIV leakage test failure would require the component to return to the initial interval of every RFO, or 2 years, until good performance can again be established. |
| Valves that have demonstrated good performance for two consecutive cycles may have their test interval extended. | | In its proposed alternative, Exelon states that the extension of test frequencies will be consistent with the guidance provided for Appendix J, Type C, leak rate tests as detailed in NEI 94-01, Revision 2-A, "Industry Guidelines for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J,'' paragraph 10.2.3.2, "Extended Test Interval" (ADAMS Accession No. ML100620847), which states that, "Intervals for Type C testing may be increased to a specific value in a range of frequencies from 30 months up to a maximum of 60 months" (see page 10 of proposed alternative). |
| Any PIV leakage test failure would require the component to return to the initial interval of every RFO, or 2 years, until good performance can again be established. | | Also, the licensee states that it proposes to perform PIV testing at intervals ranging from every refueling outage to every third refueling outage (see page 3 of proposed alternative). The U.S. Nuclear Regulatory Commission (NRC) staff understands that NMP1 and NMP2 have a refueling cycle of 24 months. The proposed testing interval from every refueling outage to every Enclosure |
| In its proposed alternative, Exelon states that the extension of test frequencies will be consistent with the guidance provided for Appendix J, Type C, leak rate tests as detailed in NEI 94-01, Revision 2-A, "Industry Guidelines for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J,'' paragraph 10.2.3.2, "Extended Test Interval" (ADAMS Accession No. ML 100620847), which states that, "Intervals for Type C testing may be increased to a specific value in a range of frequencies from 30 months up to a maximum of 60 months" (see page 10 of proposed alternative). | | |
| Also, the licensee states that it proposes to perform PIV testing at intervals ranging from every refueling outage to every third refueling outage (see page 3 of proposed alternative). | | third refueling outage would exceed the maximum 60-month test interval described in NEI 94-01, Revision 2-A. |
| The U.S. Nuclear Regulatory Commission (NRC) staff understands that NMP1 and NMP2 have a refueling cycle of 24 months. The proposed testing interval from every refueling outage to every Enclosure third refueling outage would exceed the maximum 60-month test interval described in NEI 94-01, Revision 2-A. NEI 94-01 has been updated and is currently on its third version that has been accepted by the NRC staff. For NMP1, the Type C test interval is in accordance with NEI 94-01, Revision 0 (ADAMS Accession No. ML 11327 A025), which is endorsed by Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program" (ADAMS Accession No. ML003740058). | | NEI 94-01 has been updated and is currently on its third version that has been accepted by the NRC staff. For NMP1, the Type C test interval is in accordance with NEI 94-01, Revision 0 (ADAMS Accession No. ML11327A025), which is endorsed by Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program" (ADAMS Accession No. ML003740058). |
| Type C tests intervals are set to 60 months. For NMP2, the Type C test interval is in accordance with NEI 94-01, Revision 2-A which has been accepted with limitations by letter dated June 25, 2008 (ADAMS Accession No. ML081140105). | | Type C tests intervals are set to 60 months. For NMP2, the Type C test interval is in accordance with NEI 94-01, Revision 2-A which has been accepted with limitations by letter dated June 25, 2008 (ADAMS Accession No. ML081140105). Type C test intervals are set to 60 months with a 9-month grace period. The third version of NEI 94-01, Revision 3-A (ADAMS Accession No. ML12221A202), has been approved with conditions by NRC staff. Type C test intervals can be extended to 75 months with a 9-month grace period with conditions. |
| Type C test intervals are set to 60 months with a 9-month grace period. The third version of NEI 94-01, Revision 3-A (ADAMS Accession No. ML 12221A202), has been approved with conditions by NRC staff. Type C test intervals can be extended to 75 months with a 9-month grace period with conditions. | | The NRC staff has determined that the following additional information is required to complete its review: |
| The NRC staff has determined that the following additional information is required to complete its review: (1) Explain which version of NEI 94-01 NMP1 and NMP2 wants to apply to the extension of PIV test frequencies. | | (1) Explain which version of NEI 94-01 NMP1 and NMP2 wants to apply to the extension of PIV test frequencies. |
| (2) Clarify whether the extension of the PIV test frequencies will be consistent with NEI 94-01, paragraph 10.2.3.2, or up to every third refueling outage. | | (2) Clarify whether the extension of the PIV test frequencies will be consistent with NEI 94-01, paragraph 10.2.3.2, or up to every third refueling outage. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED ALTERNATIVE TO PERFORM PRESSURE ISOLATION VALVE LEAKAGE TESTING AT FREQUENCIES CONSISTENT WITH TITLE 10 OF THE CODE OF FEDERAL REGULATIONS, PART 50, APPENDIX J (CAC NOS. MF9073 AND MF9074) DATED MARCH 14, 2017 DISTRIBUTION: | | NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED ALTERNATIVE TO PERFORM PRESSURE ISOLATION VALVE LEAKAGE TESTING AT FREQUENCIES CONSISTENT WITH TITLE 10 OF THE CODE OF FEDERAL REGULATIONS, PART 50, APPENDIX J (CAC NOS. MF9073 AND MF9074) |
| Public LPL 1 R/F RidsNrrDorlLpl1 RidsACRS _MailCTR RidsRgn1 MailCente RidsNrrPMNineMilePoint | | DATED MARCH 14, 2017 DISTRIBUTION: |
| | | Public LPL 1 R/F RidsNrrDorlLpl1 RidsACRS _MailCTR RidsRgn1 MailCente RidsNrrPMNineMilePoint RidsNrrLALRonewicz RidsNrrDeEpnb MFarnan, NRR ADAMS Accession Number: ML17065A162 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DORL/LPL 1/BC DORL/LPL 1/PM NAME MMarshall LRonewicz JDanna MMarshall DATE 03/14/2017 03/13/2017 03/14/2017 03/14/2017 OFFICIAL RECORD COPY}} |
| RidsNrrLALRonewicz RidsNrrDeEpnb MFarnan, NRR ADAMS Accession Number: ML 17065A162 OFFICE DORL/LPL 1 /PM DORL/LPL 1 /LA DORL/LPL 1/BC NAME MMarshall LRonewicz JDanna DATE 03/14/2017 03/13/2017 03/14/2017 OFFICIAL RECORD COPY DORL/LPL 1 /PM MMarshall 03/14/2017}} | |
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Category:Letter
MONTHYEARNMP1L3570, 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 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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23205A2432023-07-19019 July 2023 NRC Staff Follow-up Question on Audit Question 18 TSTF-505 and 50.69 Regulatory Audit (E-mail Dated 7/19/2023) (EPIDs L-2022-LLA-0185 and L-2022-LLA-0186) ML23087A2912023-03-28028 March 2023 Request for Additional Information (3/28/2023 E-mail) - Proposed Emergent I5R-11 Alternative Associated with a Weld Overlay on RPV Recirculation Nozzle N2E DM Weld ML23061A0522023-03-0202 March 2023 Request for Additional Information (3/2/2023 E-mail) - Proposed Alternative Associated with a Weld Overlay Repair to the Torus ML23012A2002023-01-13013 January 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000220/2023401 and 05000410/2023401 ML22207A2162022-07-26026 July 2022 Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000220/2022010 and 05000410/2022010 ML22194A9412022-07-13013 July 2022 Request for Additional Information Relief Request CS-PR-02 (7/13/2022 e-mail) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21320A3472021-11-16016 November 2021 Request for Additional Information LAR to Revise TSs to Adopt TSTF-582, Revision 0 ML21306A3312021-11-0202 November 2021 Request for Additional Information Alternative Request GV-RR-10 (11/2/2021 e-mail) ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21125A1282021-05-0404 May 2021 OPC Document Request - Feb 2021 ML21110A5112021-04-20020 April 2021 Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt TSTF-582 ML21088A2682021-03-30030 March 2021 Notification of Conduct of a Fire Protection Team Inspection ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML20365A0092020-12-30030 December 2020 Request for Additional Information Concerning Review of License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency (EPIDs L-2020-LLA-0188 and L-2020-LLR-0114) ML20358A2602020-12-28028 December 2020 Changes to Draft Request for Additional Information Regarding License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency ML20272A2802020-09-28028 September 2020 Withdrawal and Replacement of Request for Additional Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20248H5192020-09-28028 September 2020 Changes to Draft Request for Additional Information Regarding Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20246G6362020-09-0202 September 2020 Request for Additonal Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times NMP2L2739, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-08-28028 August 2020 Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20212L8702020-07-30030 July 2020 Request for Additonal Information Review of License Amendment Requests Regarding Riskinformed Categorization and Treatment of Structures, Systems and Components (L-2019-LLA-0290) ML20213A9352020-07-30030 July 2020 Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20135H1972020-05-14014 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval ML20045E3582020-02-14014 February 2020 Draft Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates ML19296A1862019-10-23023 October 2019 Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates (L-2019-LLA-0115) ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19151A8132019-05-31031 May 2019 Licensed Operator Positive Fitness-For-Duty Test ML19025A1572019-01-25025 January 2019 Request for Additional Information Regarding Primary Containment Oxygen Concentration License Amendment Request ML19025A1202019-01-24024 January 2019 NRR E-mail Capture - Calvert Cliffs, Fitzpatrick, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Response Organization Staffing ML18341A2212018-12-0707 December 2018 Request for Additional Information Regarding Emergency Tech Spec Change Re HPCS Completion Time (EPID -L-2018-LLA-0491) ML18228A6932018-08-15015 August 2018 Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426) ML18205A3922018-07-24024 July 2018 Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426) ML18184A2882018-07-0303 July 2018 Request for Additional Information Regarding Removal of Boraflex Credit from Spent Fuel Pool License Amendment Request(L-2018-LLA-0039) ML18102A2372018-04-12012 April 2018 NRR E-mail Capture - Calvert Cliffs, Ginna, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Schemes (EPID-L-2017-LLA-0237) ML17331B1342017-12-12012 December 2017 2, and R.E. Ginna Nuclear Power Plant - Request for Additional Information - Regarding ML17285B1962017-10-27027 October 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. ML17272A0112017-10-10010 October 2017 Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control ML17234A3592017-08-30030 August 2017 Request for Additional Information Regarding Relief Request NMP-RR-001 to Utilize Code Case N-702 ML17241A2752017-08-29029 August 2017 Request for Additional Information Response MSA (MF7946,7) and FE (MG0087,8) E-mail Attachment ML17240A3102017-08-15015 August 2017 NRR E-mail Capture - Nine Mile Point MSA and FE RAI ML17172A0842017-06-27027 June 2017 Request for Additional Information Regarding Relief Request to Utilize ASME Code Case N-702 ML17065A1622017-03-14014 March 2017 Request for Additional Information Regarding Proposed Alternative to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR Part 50, Appendix J 2023-09-21
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 14, 2017 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED ALTERNATIVE REQUEST NUMBER GVRR-3 TO PERFORM PRESSURE ISOLATION VALVE LEAKAGE TESTING AT FREQUENCIES CONSISTENT WITH TITLE 10 OF THE CODE OF FEDERAL REGULATIONS, PART 50, APPENDIX J (CAC NOS.
MF9073 AND MF9074)
Dear Mr. Hanson:
By letter dated December 27, 2017 (Agencywide Documents Access and Management System Accession No. ML17003A096), Exelon Generation Company, LLC (the licensee) submitted a request in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1) for a proposed alternative to the requirements of 10 CFR 50.55a and the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Nine Mile Point Nuclear Station, Units 1 and 2. The proposed alternative would allow the licensee to perform pressure isolation valve leakage testing at frequencies consistent with 10 CFR Part 50, Appendix J, primary reactor containment leakage testing performance-based requirements.
The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that additional information is needed to complete its review.
Enclosed is our Request for Additional Information (RAI). The RAI was discussed with your staff on March 13, 2017, and it was agreed that your response would be provided within 30 days from the date of this letter.
Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410
Enclosure:
Request for Additional Information cc: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION PROPOSED ALTERNATIVE REQUEST NUMBER GVRR-3 FOR THE INSERVICE TESTING PROGRAM FOURTH AND THIRD 10-YEAR INTERVALS NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-220 AND 50-410 By letter dated December 27, 2017 (Agencywide Documents Access and Management System Accession No. ML17003A096), Exelon Generation Company, LLC (Exelon, the licensee) submitted a request in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1) for a proposed alternative to the requirements of 10 CFR 50.55a and the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code for Nine Mile Point Nuclear Station, Units 1 and 2 (NMP1 and NMP2). The Proposed Alternative Request Number GVRR-3 would allow the licensee to perform pressure isolation valve (PIV) leakage testing at frequencies consistent with the 10 CFR Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, reactor containment leakage testing performance-based requirements. The licensee has proposed an alternative test in lieu of the requirements found in the 2004 Edition of the ASME Operation and Maintenance (OM) Code Section ISTC-3630(a) for 35 PIVs.
The licensee proposes to functionally test and verify the leakage rate of these PIVs using 10 CFR Part 50, Appendix J, Option B, performance-based schedule. Valves would initially be tested at the required interval schedule, which is currently every refueling outage (RFO), or 2 years, as specified by ASME OM Code, Section ISTC-3630(a). Valves that have demonstrated good performance for two consecutive cycles may have their test interval extended. Any PIV leakage test failure would require the component to return to the initial interval of every RFO, or 2 years, until good performance can again be established.
In its proposed alternative, Exelon states that the extension of test frequencies will be consistent with the guidance provided for Appendix J, Type C, leak rate tests as detailed in NEI 94-01, Revision 2-A, "Industry Guidelines for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J, paragraph 10.2.3.2, "Extended Test Interval" (ADAMS Accession No. ML100620847), which states that, "Intervals for Type C testing may be increased to a specific value in a range of frequencies from 30 months up to a maximum of 60 months" (see page 10 of proposed alternative).
Also, the licensee states that it proposes to perform PIV testing at intervals ranging from every refueling outage to every third refueling outage (see page 3 of proposed alternative). The U.S. Nuclear Regulatory Commission (NRC) staff understands that NMP1 and NMP2 have a refueling cycle of 24 months. The proposed testing interval from every refueling outage to every Enclosure
third refueling outage would exceed the maximum 60-month test interval described in NEI 94-01, Revision 2-A.
NEI 94-01 has been updated and is currently on its third version that has been accepted by the NRC staff. For NMP1, the Type C test interval is in accordance with NEI 94-01, Revision 0 (ADAMS Accession No. ML11327A025), which is endorsed by Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program" (ADAMS Accession No. ML003740058).
Type C tests intervals are set to 60 months. For NMP2, the Type C test interval is in accordance with NEI 94-01, Revision 2-A which has been accepted with limitations by letter dated June 25, 2008 (ADAMS Accession No. ML081140105). Type C test intervals are set to 60 months with a 9-month grace period. The third version of NEI 94-01, Revision 3-A (ADAMS Accession No. ML12221A202), has been approved with conditions by NRC staff. Type C test intervals can be extended to 75 months with a 9-month grace period with conditions.
The NRC staff has determined that the following additional information is required to complete its review:
(1) Explain which version of NEI 94-01 NMP1 and NMP2 wants to apply to the extension of PIV test frequencies.
(2) Clarify whether the extension of the PIV test frequencies will be consistent with NEI 94-01, paragraph 10.2.3.2, or up to every third refueling outage.
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED ALTERNATIVE TO PERFORM PRESSURE ISOLATION VALVE LEAKAGE TESTING AT FREQUENCIES CONSISTENT WITH TITLE 10 OF THE CODE OF FEDERAL REGULATIONS, PART 50, APPENDIX J (CAC NOS. MF9073 AND MF9074)
DATED MARCH 14, 2017 DISTRIBUTION:
Public LPL 1 R/F RidsNrrDorlLpl1 RidsACRS _MailCTR RidsRgn1 MailCente RidsNrrPMNineMilePoint RidsNrrLALRonewicz RidsNrrDeEpnb MFarnan, NRR ADAMS Accession Number: ML17065A162 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DORL/LPL 1/BC DORL/LPL 1/PM NAME MMarshall LRonewicz JDanna MMarshall DATE 03/14/2017 03/13/2017 03/14/2017 03/14/2017 OFFICIAL RECORD COPY