Similar Documents at Ginna |
|---|
Category:Letter
MONTHYEARIR 05000244/20230042024-02-0505 February 2024
LLC - Integrated Inspection Report 05000244/2023004
ML24026A0112024-01-26026 January 2024
R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump
IR 05000244/20230102023-12-19019 December 2023
LLC - Age-Related Degradation Inspection Report 05000244/2023010
ML23348A0992023-12-15015 December 2023
R. E. Ginna Nuclear Power Plant Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23347A0092023-12-13013 December 2023
Annual Commitment Change Notification
ML23346A0142023-12-12012 December 2023
LLC - Senior Reactor and Reactor Operator Initial License Examinations
ML23341A1252023-12-0707 December 2023
Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements
ML23321A1392023-11-17017 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information
ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
IR 05000244/20230032023-10-25025 October 2023
LLC - Integrated Inspection Report 05000244/2023003
ML23292A0282023-10-19019 October 2023
LLC - Notification of Conduct of a Fire Protection Team Inspection
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
RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023
Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles
RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023
Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
ML23258A1382023-09-18018 September 2023
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000244/2023010
IR 05000244/20230052023-08-31031 August 2023
Updated Inspection Plan for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2023005)
ML23158A1952023-08-30030 August 2023
R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications
ML23235A1722023-08-23023 August 2023
Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report
IR 05000244/20234012023-08-15015 August 2023
LLC - Material Control and Accounting Program Inspection Report 05000244/2023401 (Cover Letter Only)
IR 05000244/20230022023-08-0303 August 2023
LLC - Integrated Inspection Report 05000244/2023002
ML23191A0592023-07-21021 July 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1
IR 05000244/20234022023-07-19019 July 2023
R. E. Ginna Nuclear Power Plant - Security Baseline Inspection Report 05000244/2023402 (Cover Letter Only)
RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023
Withdrawal - Proposed Alternatives Related to the Steam Generators
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
RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023
Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.
ML23135A0412023-05-15015 May 2023
2022 Annual Radioactive Effluent Release Report and 2022 Annual Radiological Environmental Operating Report
ML23121A0482023-05-0101 May 2023
R. E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 44, Revision 0
ML23114A2522023-04-28028 April 2023
Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI
IR 05000244/20230012023-04-26026 April 2023
LLC - Integrated Inspection Report 05000244/2023001
ML23100A0302023-04-10010 April 2023
2023 10 CFR 50.46 Annual Report
ML23114A1152023-03-29029 March 2023
Electronic Reporting of Exposure Data for 2022
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
ML23075A0872023-03-15015 March 2023
R. E. Ginna Nuclear Power Plant - Project Manager Assignment
ML23061A1632023-03-0303 March 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3
IR 05000244/20220062023-03-0101 March 2023
Annual Assessment Letter for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2022006)
ML22364A0242023-03-0101 March 2023
R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246
ML23060A1622023-03-0101 March 2023
R. E. Ginna Nuclear Power Plant, Supplemental Information - Proposed Alternatives Related to the Steam Generators
RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023
Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
ML23005A1762023-02-23023 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes
ML23005A1222023-02-22022 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2
RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023
Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators
ML22287A0692023-02-0808 February 2023
R. E. Ginna Station - Forward Fit Analysis (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094)
ML23031A2992023-02-0707 February 2023
R. E. Ginna Nuclear Power Plant - Withdrawal of an Amendment Request
ML23010A0112023-02-0101 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Inservice Testing of Refueling Water Storage Tank Outlet Value
RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023
Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
IR 05000244/20223012023-01-20020 January 2023
Initial Operator Licensing Examination Report 05000244/2022301
IR 05000244/20220122023-01-12012 January 2023
LLC - Design Basis Assurance Inspection (Teams) Inspection Report 05000244/2022012
ML22362A0382022-12-28028 December 2022
R. E. Ginna Nuclear Power Plant - Letter to Withdraw Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
ML22348A2062022-12-14014 December 2022
Re. Ginna Nuclear Power Plant - Annual Commitment Change Notification
RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022
Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator
2024-02-05
[Table view]
Category:Report
MONTHYEARML23235A1722023-08-23023 August 2023
Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report
NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022
Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits
ML21350A1142021-12-16016 December 2021
Annual Commitment Change Notification
ML21316A0512021-11-12012 November 2021
Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections
RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021
R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021
Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping
ML20303A1752020-10-23023 October 2020
Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting
ML20265A1982020-09-21021 September 2020
R. E. Ginna Nuclear Power Plant, Application to Revise Technical Specifications for Steam Generator Tube Inspection Frequency
ML17345A9902017-12-21021 December 2017
R. E. Ginna Nuclear Power Plant Flood Hazard Mitigation Strategies Assessment
ML17214A1182017-07-27027 July 2017
Transmittal of 2017 Owner'S Activity Report for the Plant
ML15167A5052015-06-11011 June 2015
(Redacted Version) Response to Request for Additional Information Regarding the License Amendment Request (LAR) to Adopt NFPA 805, Attachment 3
ML15153A0262015-06-11011 June 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insight
RS-15-069, Enclosure 2: Areva, Inc., Rev. 1 to 51-9205719-001, R.E. Ginna Nuclear Power Plant Flood Hazard Reevaluation Report, Part 2 of 22015-03-11011 March 2015
Enclosure 2: Areva, Inc., Rev. 1 to 51-9205719-001, R.E. Ginna Nuclear Power Plant Flood Hazard Reevaluation Report, Part 2 of 2
ML15072A0112015-03-11011 March 2015
Enclosure 2: Areva, Inc., Rev. 1 to 51-9205719-001, R.E. Ginna Nuclear Power Plant Flood Hazard Reevaluation Report, Part 1 of 2
RS-15-069, Enclosure 2: Areva, Inc., Rev. 1 to 51-9205719-001, R.E. Ginna Nuclear Power Plant Flood Hazard Reevaluation Report, Part 1 of 22015-03-11011 March 2015
Enclosure 2: Areva, Inc., Rev. 1 to 51-9205719-001, R.E. Ginna Nuclear Power Plant Flood Hazard Reevaluation Report, Part 1 of 2
RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014
Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1
ML14170B0222014-06-26026 June 2014
Staff Assessment of Flooding Walkdown Reports Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Accident
ML14099A1962014-03-31031 March 2014
Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.
ML14071A4782014-02-21021 February 2014
Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments
ML14007A7042014-02-19019 February 2014
R. E. Ginna Nuclear Power Plant - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14037A2772014-02-0909 February 2014
Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for R.E. Ginna Nuclear Power Plant, TAC No.: MF1152
ML13294A0232013-10-16016 October 2013
Snubber Program Plan
ML13210A0342013-07-25025 July 2013
Supplemental Response to 10 CFR 50.54(f) Request for Recommendation 2.3, Seismic Information
ML13093A0652013-03-29029 March 2013
Transition Report to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition - Transition Report, Redacted Version. Enclosure 2
ML13066A1712013-02-28028 February 2013
R.E. Gina, Overall Integrated Plan for Mitigation Strategies for Beyond-Design-Basis External Events
ML12362A4512012-12-21021 December 2012
Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3. Seismic, Attachment (1) Supplemental Seismic Walkdown Report, Table of Contents Through Attachment (2) Seismic Walkdown Checklists, Page B-90
ML12362A4522012-12-21021 December 2012
Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3. Seismic, Attachment (3) Area Walk-By Checklists Through End
ML12277A0902012-10-12012 October 2012
Technical Letter Report on Aging Management Program Audits at Ginna and Nine Mile Point 1
ML12277A1742012-09-28028 September 2012
R. E. Ginna - License Renewal Aging Management, Submit Revised Reactor Vessel Internals Program Document in Accordance with RIS 2011-07
ML12080A1422012-03-16016 March 2012
Attachments 1 & 2, Structural Integrity Evaluation of Circumferential Indication in Ginna Bmi Nozzle No. A86, and Location of Indications in A86 Bmi Penetration
ML11343A6792011-12-0606 December 2011
Report of Facility Changes. Tests, and Experiments Conducted Without Prior Commission Approval
ML11363A0752011-10-0505 October 2011
Reactor Vessel Bottom Mounted Instrumentation Paint Cracking Analysis
ML11363A0762011-08-31031 August 2011
Evaluation of Leakage and Deposit Formation in Painted Full-Scale Bmi Mockups, Final Report, Revision 2, Swri Project No. 18.16196, Ceng Purchase Order No. 6610691
ML1027306232010-09-22022 September 2010
R. E. Ginna - Transmittal of RCS Pressure and Temperature Limits Report (PTLR)
ML1012704392010-05-0505 May 2010
Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants
ML1009200572010-03-29029 March 2010
Report of Facility Changes, Tests, and Experiments Conducted Without Prior Commission Approval
ML0915502712009-05-31031 May 2009
WCAP-17036-NP, Rev 0, Analysis of Capsule N from the R.E. Ginna Reactor Vessel Radiation Surveillance Program.
ML0914802612009-05-19019 May 2009
Transmittal of RCS Pressure and Temperature Limits Report (PTLR)
ML0906411032009-02-27027 February 2009
R. E. Ginna Nuclear Power Plant - License Renewal Aging Management Reactor Vessel Internals Program
ML12220A1012008-11-24024 November 2008
Constellation Energy Group, Inc. Definitive Proxy Statement Schedule 14A
ML0827402682008-09-23023 September 2008
Transmittal of Steam Generator Examination Report for the R.E. Ginna Nuclear Power Plant Conducted in 2008
ML0821900132008-08-0707 August 2008
Monthly Operating Reports Second Quarter 2008
ML0807100412008-02-29029 February 2008
R.E. Ginna, Supplement Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML0712703072007-05-0101 May 2007
Report of Facility Changes, Tests and Experiments Conducted Without Prior Commission Approval
ML0612101732006-01-12012 January 2006
FEMA Final Exercise Report - R. E. Ginna (Dated 1/12/06)
ML0536201882005-11-17017 November 2005
Meeting with R. E. Ginna Nuclear Power Plant, LLC, Regarding Extended Power Uprate Amendment Application
ML0529204182005-10-10010 October 2005
R. E. Ginna - Report of Facility Changes, Tests, and Experiments Conducted Without Prior Commission Approval
ML0519300192005-07-0101 July 2005
R. E. Ginna Nuclear Power Plant, Transmittal of RCS Pressure and Temperature Limits Report (PTLR)
ML0727008492005-01-31031 January 2005
Caldon Experience in Nuclear Feedwater Flow Measurement
ML0414802942004-05-21021 May 2004
Appendix R Summary for the Proposed Control Room Emergency Air Treatment System (Creats) Modification
2023-08-23
[Table view]
Category:Miscellaneous
MONTHYEARML23235A1722023-08-23023 August 2023
Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report
ML21350A1142021-12-16016 December 2021
Annual Commitment Change Notification
ML21316A0512021-11-12012 November 2021
Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections
ML20303A1752020-10-23023 October 2020
Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting
ML17345A9902017-12-21021 December 2017
R. E. Ginna Nuclear Power Plant Flood Hazard Mitigation Strategies Assessment
ML17214A1182017-07-27027 July 2017
Transmittal of 2017 Owner'S Activity Report for the Plant
ML15153A0262015-06-11011 June 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insight
ML15167A5052015-06-11011 June 2015
(Redacted Version) Response to Request for Additional Information Regarding the License Amendment Request (LAR) to Adopt NFPA 805, Attachment 3
ML14170B0222014-06-26026 June 2014
Staff Assessment of Flooding Walkdown Reports Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Accident
ML14099A1962014-03-31031 March 2014
Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.
ML13294A0232013-10-16016 October 2013
Snubber Program Plan
ML13066A1712013-02-28028 February 2013
R.E. Gina, Overall Integrated Plan for Mitigation Strategies for Beyond-Design-Basis External Events
ML12362A4522012-12-21021 December 2012
Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3. Seismic, Attachment (3) Area Walk-By Checklists Through End
ML12362A4512012-12-21021 December 2012
Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3. Seismic, Attachment (1) Supplemental Seismic Walkdown Report, Table of Contents Through Attachment (2) Seismic Walkdown Checklists, Page B-90
ML12277A1742012-09-28028 September 2012
R. E. Ginna - License Renewal Aging Management, Submit Revised Reactor Vessel Internals Program Document in Accordance with RIS 2011-07
ML11343A6792011-12-0606 December 2011
Report of Facility Changes. Tests, and Experiments Conducted Without Prior Commission Approval
ML1027306232010-09-22022 September 2010
R. E. Ginna - Transmittal of RCS Pressure and Temperature Limits Report (PTLR)
ML1012704392010-05-0505 May 2010
Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants
ML1009200572010-03-29029 March 2010
Report of Facility Changes, Tests, and Experiments Conducted Without Prior Commission Approval
ML0906411032009-02-27027 February 2009
R. E. Ginna Nuclear Power Plant - License Renewal Aging Management Reactor Vessel Internals Program
ML12220A1012008-11-24024 November 2008
Constellation Energy Group, Inc. Definitive Proxy Statement Schedule 14A
ML0827402682008-09-23023 September 2008
Transmittal of Steam Generator Examination Report for the R.E. Ginna Nuclear Power Plant Conducted in 2008
ML0807100412008-02-29029 February 2008
R.E. Ginna, Supplement Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML0529204182005-10-10010 October 2005
R. E. Ginna - Report of Facility Changes, Tests, and Experiments Conducted Without Prior Commission Approval
ML0727008492005-01-31031 January 2005
Caldon Experience in Nuclear Feedwater Flow Measurement
ML0414802942004-05-21021 May 2004
Appendix R Summary for the Proposed Control Room Emergency Air Treatment System (Creats) Modification
ML0405502702003-11-11011 November 2003
to PCR 2000-0024, Control Room Emergency Air Treatment System (Creats) and Control Room Emergency Heating/Cooling System.
ML0405502712003-07-30030 July 2003
to Specification ME-326, Control Room Emergency Air Treatment System (Creats) and Emergency Cooling System Design, Fabrication, & Installation Specification.
ML0318904622003-07-10010 July 2003
Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for R.E. Ginna
ML0316902302003-06-10010 June 2003
Supplemental Response to LRA Request for Additional Information
ML0232203122002-11-0404 November 2002
Attachment 3, Model 956-201 Failure History Summary
ML0232202732002-11-0101 November 2002
Attachment 1, Qualification Report 950.366, Rev. 2 for Ginna Project P. O. 450008671
ML0232203232002-10-28028 October 2002
Software Validation Test Procedure for Prom P/N 94095603 G-M Area Monitor
ML0224004182002-08-16016 August 2002
Rochester Gas & Electric Corp., FFD Performance Data Report for January-June 2002
ML0206702382002-02-22022 February 2002
Submittal of Fitness-For-Duty Performance Data Report for Six Months Ending 12/31/2001 for Ginna Station
ML18143A8311973-01-17017 January 1973
Monthly Report of Activity Measurements for November 26, 1972 Through December 31, 1972
ML18143A8341972-11-15015 November 1972
Monthly Report of Activity Measurements for September 26, 1972 Through October 25, 1972
ML18143A8351972-10-16016 October 1972
Monthly Report of Activity Measurements
ML18143A8381972-09-0606 September 1972
Monthly Report of Activity Measurements for July 26, 1972 Through August 25, 1972
2023-08-23
[Table view] |
Text
Paul M. Swift Site Vice President RE. Ginna Nuclear Power Plant Exelon Generation 1503 Lake Rd.
Ontario. NY 14519 315-791-5200 Office www.exeloncorp.com November 12, 2021 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 RE . Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244
Subject:
Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report WCAP-17451-P, Revision 1, "Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections" Exelon Generation Company, LLC (EGC) is providing notification that Ginna, Unit 1, has processed a deviation from a Nuclear Energy Institute (NEI) 03-08, "Guideline for the Management of Materials Issues," Revision 4, "Needed" work product element in PWROG report WCAP-17 451-P, Revision 1, with appropriate justification and documentation.
Control Rod Guide Tube (CRGT) Guide Card Wear Measurement (GCWM) is a "Needed" requirement specified in WCAP-17451-P, Revision 1, which the document listed in MRP-227, Revision 1-A containing the examination requirements for CRGT guide cards . Ginna Unit 1 has elected to defer wear measurements of its CRGT guide cards from G1 R43 refueling outage in Fall 2021 to G1R49 refueling outage in Fall 2030.
NEI 03-08 allows deviation from "Needed" elements with the appropriate justification and documentation . The deviation was approved with the appropriate levels of EGC management.
Attachment 1 provides the Ginna Unit 1 Control Rod Guide Tube (CRGT) Guide Card Wear Measurements Deviation - Technical Evaluation ECP-21-000368.
This notification is provided for information only. No approval or action is expected. If you have any questions, please contact Mr. Chris Bradshaw at (315) 791-3246.
There are no regulatory commitments contained in this letter.
Respectfully,
- ~Q ~~
Paul Swift Attachment 1: Ginna Unit 1 Control Rod Guide Tube (CRGT) Guide Card Wear Measurements Deviation -Technical Evaluation ECP-21-000368 cc: RC Regional Administrator, Region 1 NRC Project Manager, Ginna NRC Resident Inspector, Ginna (e-mail)
Attachment 1 Ginna Unit 1 Control Rod Guide Tube (CRGT) Guide Card Wear Measurements Deviation - Technical Evaluation ECP-21-000368
ER-AA-4003 Revision 5 ATTACHMENT 2 MDMP Deviation Form Page 1 of 1 Utility: Exelon Applicable Site(s) and Unit No. : R.E. Ginna Nuclear Power Plant Unit 1 Utility Contact(s): Diane Render - Fleet Reactor Internals Program Engineer, Peter Logar - Ginna Programs Engineering Manager, Kayla Iazzetta - Ginna Reactor Internals Program Engineer, Heather Malikowski - Fleet Asset Protection Programs Manager Issue Program (IP) activity or document: WCAP-17451, Revision l , "Reactor Internals Guide Tube Wear -
Westinghouse Domestic Fleet Operational Projections" Scope I Description of Deviation: Control Rod Guide Tube (CRGT) Guide Card wear measurements require reinspection no later than 10 years after baseline inspection per WCAP-17451, Revision 1. The deviation defers this reinspection to a maximum of20 EFPY after baseline inspection per WCAP-17451, Revision 2, the latest industry approved revision of the guidance. The justification is based on Ginna's technical evaluation of their baseline guide card wear measurements using the latest approved industry guidance.
Reason for Deviation: Technical evaluation ECP-21-000368 supports deviation from the WCAP-17451, Revision 1 requirement of Guide Card Wear Measurement reinspection 10 years after baseline inspection. The technical evaluation results align with WCAP-17451, Revision 2 requirements for reinspection 20 EFPY past baseline inspections. Revision 2 of this document has not yet been NRC approved by reference in WCAP-17096-NP, Revision 3, "Reactor Internals Acceptance Criteria Methodology and Data Requirements," but has been industry accepted.
IR Number:_0=-4.:....4.:....4'"'"7..;:.0...:..43"'-------------- EC Number: ECP-21-000368 Time Frame the Deviation will be in Effect: The deviation will be in effect until WCAP-17096-NP, Revision 3, which references WCAP-17451, Revision 2, has been approved for use by the NRC.
Deviation to this IP document is classified as MANDATOR~
_i(ri,L ~ ~ ~'.gitally signed by lazzetta, Kayla Prepared By: l "'(J~ Date 2021092309:0312-04*00* Date:
Digitally signed by Rice, Mathew Rice1 Mathew M. M.
Station Program Manager: Date: 2021.09.23 08:56:23 -05'00' Date:
Dlgltally signed by Everett. Richard Everett, Richard Site Engineering Director: Date: 2021.0927 09'.50:05 -04'00' Date:
Ren d er D.Ian e DN"n=Render, Digitally signed Render, Diane by Diane Corporate IP Owner:______' ____0 *_,._,20_21_"*_*2_71_0'1_*"_s--04_*00_*- - - - - - - - - - - Date:
Digitally signed by Cirilli, James J.
Corporate Asset Management Sr. Mgr: Cirilli, James J. DN: cn= Cirilli, Jam es J.
b'aie* i!Qi!1 Q9 i!7 14*1 Q*!i!I Q4'QQ' Date:
D*iRado, Mark o'*"'"""ed*yolRado,M"k ON: cn=DiRado, Mark Corporate Prag rams Director: ______________0'_'"_20_ 2 "_
0*_ 1 *_
~ '_"_' ,,._
_*0_0* _ _ __
Date:
Digitally signed by Swift, Paul Site Vice President:
Swift, Paul DN: cn=Swift, Paul Date: 2021.10.0612:57:37 --04'00' Date:
Digitally signed by Greenlee, Greenlee, Scot A. ~~~,~*=Greenlee, Scot A.
Senior VP of Eng& Tech Services: Date: 2021.1O.13 09:40:S8 -05'00' Date:
Concurrence Independent of Exelon NIA Date:
(for " Mandatory" IP work product elements only)
ECP-21-000368 RO TECHNICAL EVALUATION Page 2 of 4 ECP No.: ECP-21-000368 Rev. No.: 0000 Reason for Evaluation/Scope:
Ginna Unit 1 has elected to defer the wear measurement reinspection of the Control Rod Guide Tube (CRGT) guide cards from the 2021 refueling outage (G1R43) to the 2030 refueling outage (G1R49). This is a deviation from the NEI 03-08 [Ref l]
"Needed" requirement specified in WCAP-17451-P, Revision 1 [Ref2]. WCAP-17451-P, Revision 1, is listed in MRP-227, Revision 1-A [Ref3], and contains the examination requirements for CRGT guide cards.
In support of license extension activities there are nine Primary Components that must be inspected as a part of MRP-227 for a Westinghouse Pressurized Water Reactor. One of these components is the CRGT guide cards. As a part of the upper internals, CRGT's provide guidance of the Rod Cluster Control Assemblies (RCCAs) above the core fuel assemblies. Each CRGT houses one RCCA that is made up of long, slender rodlets attached to a drive rod by a coupling fixture called a spider. The drive rod steps the RCCA into and out of the fuel assemblies. If needed for core shutdown, the RCCAs can also be released to allow them to drop into the fuel assembly. The individual rodlets are guided inside the CRGTs by approximately one-inch-thick guide cards. The guide cards are located about one foot apart and are guided by a continuous guidance assembly located at the bottom of the lower CRGT assembly. Guide card wear is a primary concern due to the possibility of the loss of guidance of the control rodlets inside of a CRGT. The unsupported length of a rodlet will increase if a loss of guidance occurs.
The examination frequency and coverage for this component is detailed in WCAP-17451-P, Revision 1. Based on the guidance in Section 5.4 of WCAP-17451-P, Revision 1, an initial Guide Card Wear Measurement (GCWM) should take place between 38 and 42 EFPY at 14xl4 CRGT-designed plants such as Ginna. The goal of this recommendation is to ensure that baseline inspections are performed in the Green Zone (i.e. while the guide cards have no low/wear). Ginna's initial GCWM was performed during the 2011 refueling outage at 33.15 EFPY. Based on these initial results, a technical evaluation, ECP 000595 [Ref 4 ], was performed to identify the timeline of the next required inspection as recommended by WCAP-17451-P, Revision 2 [Ref 5]. The results of this technical evaluation show that several guide cards at Ginna have orientations that will exceed W3 and/or W4 wear requirements prior to 27 EFPY, but no CRGT reaches the Red Zone prior to 27 EFPY. Therefore, the maximum reinspection interval of20 EFPY allowed by WCAP-17451-P, Revision 2, can be applied to all CRGTs at Ginna.
Using this evaluation, the next inspection is required in the fall of 2030 (G 1R49). The fall of 2030 outage is 19 years from the last performed inspection in the fall of 2011 during GlR35 and beyond the current operating license for Ginna (ending on 9/18/2029 at approximately 50 EFPY).
Per WCAP-17451-P, Revision 1, the reinspection interval for GCWM is limited to 10 years. This reinspection interval commits Ginna to reinspect during the fall 2021 refueling outage (GlR43) as this is the revision referenced in MRP-227-lA.
As a part of the ongoing review for WCAP-17096-NP, Revision 3 [Ref 6], the U.S. Nuclear Regulatory Commission (NRC) is currently reviewing WCAP-17451-P, Revision 2, which allows for a reinspection interval of up to 20 EFPY. The original intent for the Ginna GCWM reinspection plan was to utilize the 20 EFPY reinspection interval allowed by WCAP-17451-P, Revision 2. The NRC acceptance of WCAP-17451-P, Revision 2, is currently delayed due to ongoing issue resolution with other acceptance criteria methodologies within WCAP-17096-NP, Revision 3. The NRC acceptance of WCAP-17451-P, Revision 2, guidance would allow Ginna to defer reinspection from the 2021 outage (10 years past baseline inspection) until the 2030 outage (20 EFPY past baseline inspection). If Ginna's current operating license is not extended, the site would not need to perform GCWM reinspection before decommissioning. Due to delay of the NRC's review of both WCAP-17096-NP, Revision 3, and WCAP-17451-P, Revision 2, Ginna now requires a deviation from the 10 year reinspection interval of WCAP-17451-P, Revision 1.
Per NEI 03-08, a "Needed" work product is "to be implemented wherever possible, but alternative approaches are acceptable".
When a utility determines that "Needed" work product elements will not be fully implemented or will not be implemented in a manner consistent with their intent, or when a work product will not be implemented within the timeframe specified, a technical justification shall be developed. This evaluation justifies delay of the Ginna Unit 1 CRGT GCWM reinspection.
Detailed Evaluation:
During the 2020 outage, Ginna performed a full core offload to complete VT-3 and EVT-1 examinations of the reactor vessel and internals and the UT examinations of the baffle-to-former bolts per the requirements of MRP-227, Revision 1-A. The CRGT GCWM was not completed during the 2020 outage due to the expectation that the guidance in WCAP-17451-P, Revision 2, would be NRC approved by reference in WCAP-17096-NP, Revision 3, before the 2021 refueling outage (G 1R43).
ECP-21-000368 RO TECHNICAL EVALUATION Page 3 of 4 ECP No.: ECP-21-000368 Rev. No.: 0000 The GCWM scope would have required an assumption of an additional level of risk in the 2020 outage associated with coordination and execution of the large scope of activities, and there was added cost without any technical benefit. The 2021 refueling outage (G 1R43) presents the same level of risk as the 2020 outage and the outage window is shorter. If the outage window is extended, it would be solely to accommodate this exam. Deferring the GCWM to 2030 refueling outage (G 1R49) facilitates a favorable outage work risk profile and cost with no compromise on safety.
There is a 20 EFPY maximum reinspection interval in WCAP-17451-P, Revision 2, which is the latest industry approved guidance per NEI 03-08, but it is not yet approved by NRC. This requirement is less conservative than the 10 year reinspection interval guidance in WCAP-17451 -P, Revision 1. After the NRC's acceptance of WCAP-17451-P, Revision 2, the next GWCM would not need to occur before the end of Ginna's current operating license. If Ginna were to pursue a license extension to operate 80-years, the GCWM would take place during the 2030 refueling outage (G 1R49). Performing the CRGT GCWM in 2030 would allow the site ample time to plan for the cost, labor, and time required to complete the examinations.
Per the guidance ofWCAP-17451-P, Revision 1, reinspection of the CRGT guide cards should occur during the Yellow Zone and before the start of the Red Zone. The technical evaluation contained in ECP-19-000595, Revision 0, shows that the CRGTs with the most wear found during the 2011 baseline GCWM inspection will not reach the Red zone prior to the maximum reinspection interval of 20 EFPY allowed by WCAP-17451-P, Revision 2. The results of this evaluation justify the deviation from the GCWM 10 year reinspection interval of WCAP-17451-P, Revision 1. In addition to the results from Ginna's baseline GCWM in 20 11 and the technical evaluation, the industry accepted guidance of WCAP-17451-P, Revision 2, provides technical support of deferring the reinspection to 2030.
Conclusion/Findings:
The proposed Ginn a Unit 1 CRGT GCWM deferral from G 1R43 to G 1R49 is supported through use of the baseline 2011 GCWM results, existing station risk mitigation processes, and bounded by the reinspection timeframe of 20 EFPY in the industry accepted WCAP-17451-P, Revision 2, to ensure safety. Deferral risks are abated through several avenues such as:
expansion of industry CRGT GCWM data during the deferral period and planning time for refueling outage G 1R49 to potentially perform unanticipated corrective maintenance.
References:
- 1. NEI 03-08, Revision 4, "Guideline for the Management of Materials Issues," October 2020.
- 2. WCAP-17451-P, Revision 1, "Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections," October 2013.
- 3. MRP-227, Revision 1-A, "Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines", Product ID 3002017 168, December 2019.
- 4. ECP-19-000595, Revision 0, "Reactor Vessel Guide Card Wear Evaluation, January 2020.
- 5. WCAP-17451-P, Revision 2, "Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections, November 2018.
- 6. WCAP-17096-NP, Revision 3, "Reactor Internals Acceptance Criteria Methodology and Data Requirements, July 2019
