Similar Documents at Ginna |
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Category:Letter
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R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump
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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))
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Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
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Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI
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Electronic Reporting of Exposure Data for 2022
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R. E. Ginna Nuclear Power Plant - Project Manager Assignment
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Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3
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R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246
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R. E. Ginna Nuclear Power Plant, Supplemental Information - Proposed Alternatives Related to the Steam Generators
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Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
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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
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Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators
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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
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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
WPLN RC-1003551 Paul M. Swift Site Vice President R.E. Ginna Nuclear Power Plant Exelon Generation,. 1503 Lake Rd.
Ontario. NY 14519 315-791-5200 Office www.exeloncorp.com December 16, 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 NRG Docket No. 50-244
Subject:
Annual Commitment Change Notification As required by NEI 99-04, "Guidelines for Managing NRC Commitments," as endorsed by SECY-00-0045, Acceptance of NEI 99-04, "Guidelines for Managing NRC Commitments,"
Ginna submits this notification of commitment changes.
No approval or action is expected. If you have any questions, please contact Mr. Chris Bradshaw at (315) 791-3246.
There are no new regulatory commitments contained in this letter.
Respectfully,
~-~~
Paul Swift Attachment 1: Report of Commitment Changes cc: NRC Regional Administrator, Region 1 NRC Project Manager, Ginna NRC Resident Inspector, Ginna (e-mail)
Attachment 1 Report of Commitment Changes from November 2020 through December 2021 Performed in Accordance with NEI 99-04
Report of Commitment Changes from November 2020 through December 2021 Performed IAW NEI 99-04 Commitment Change Evaluation No.: 2021-0002, Reduce overall impact on strainer head loss and in-vessel effects [01704323]
Source Document: ML13141A272, Resolution Path and Schedule for Generic Safety Issue (GSl)-191 Closure, dated 05/15/2013 [WPLNRC-1002705]
Original Commitment: COMMITMENT: Reduce the overall impact on strainer head loss and in-vessel effects o Identify insulation and aluminum that can be removed from containment.
o Revise 3-D CAD model, debris generation, transport, and chemical effects analyses, for revised insulation and aluminum loading.
o Perform Strainer Bypass Testing.
COMPLETION DATE: September 30, 2014 Revised Commitment: Commitment cancelled.
Justification Summary:
On 07/23/2019, the NRC closed Generic Issue GSl-191 [ML19203A303)].
WPLNRC-1003489, R.E. Ginna Nuclear Power Plant, Final Response and Close-Out to Generic Letter 2004-02, was sent to the NRC on 04/28/2021 [ML21118A007]. This commitment composed of three (3) elements is cancelled as described in Attachment 1, Page 1 of 3, item No. 1.
The NRC sent Ginna WPLNRC-1003538, Closeout of Generic Letter 2004-02, 11 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-11 Water Reactors (EPID-L-2017-LRC-OOOO), dated 10/8/2021 [ML21214A178] stating, "Based on its review, the NRC staff finds the licensee's responses to GL 2004-02 are adequate and considers GL 2004-02 closed for Ginna."
Report of Commitment Changes from November 2020 through December 2021 Performed IAW NEI 99-04 Commitment Change Evaluation No.: 2021-0003, If needed, discuss alternate resolution path consistent with risk-informed methods [01704326]
Source Document: ML13141A272, Resolution Path and Schedule for Generic Safety Issue (GSl)-191 Closure, dated 05/15/2013 [WPLNRC-1002705]
Original Commitment: COMMITMENT: If Ginna determines that the proposed testing and analysis resolution path alone will not lead to acceptable results, then an alternate resolution path will be discussed with the NRC to gain acceptance of the proposed path and to establish an acceptable completion schedule. This resolution path may be consistent with risk-informed methods developed for Option 3.
COMPLETION DATE: 60 days following PWROG testing results or completion of thermal hydraulic analysis of vessel internals, whichever is later.
Revised Commitment: Commitment cancelled.
Justification Summary:
On 07/23/2019, the NRC closed Generic Issue GSl-191 [ML19203A303)].
WPLNRC-1003489, R.E. Ginna Nuclear Power Plant, Final Response and Close-Out to Generic Letter 2004-02, was sent to the NRC on 04/28/2021 [ML21118A007]. This commitment composed of three (3) elements is cancelled as described in Attachment 1, Page 2 of 3, item No. 4.
The NRC sent Ginna WPLNRC-1003538, Closeout of Generic Letter 2004-02, 11 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors 11 (EPID-L-2017-LRC-OOOO), dated 10/8/2021 fML21214A178] stating, "Based on its review, the NRC staff finds the licensee's responses to GL 2004-02 are adequate and considers GL 2004-02 closed for Ginna."
Report of Commitment Changes from November 2020 through December 2021 Performed IAW NEI 99-04 Commitment Change Evaluation No.: 2021-0004, CRFC demister filter Inspection frequency change from 6 to 9 months [04402994-01]
Source Document: In WPLNRC-RG014022, Notice of Violation (NRC Inspection Report No. 50-244/93-06), dated 05/14/1993, RG&E was given a violation for a fire in containment in the CRFC roughing filters/demisters.
In WPLNRC-RG014071, Reply to a Notice of Violation, dated 07/14/1993, RG&E accepted the violation and made a commitment to the NRC to inspect CRFC filters.
Original Commitment: In WPLNRC-RG014071, Reply to a Notice of Violation, dated 07/14/1993, RG&E accepted the violation and committed to the NRC to inspect CRFC filters monthly.
"Existing plant procedures will be enhanced to provide inspection criteria for visual inspection of the demisters for combustibility. Visual inspections will be conducted and documented on a monthly basis, in accordance with these enhanced plant procedures. These procedures will contain inspection criteria which will consider the recommendations from the manufacturer of the demisters and from a consultant experienced in nuclear safety-related ventilation system testing. These criteria will also incorporate the applicable portions of ANSl-N510, 1989 edition (for consistency with industry standards). When the established criteria are not satisfied, corrective actions will be taken in accordance with the Maintenance Work Control System."
This commitment was later revised to quarterly (4.54-2005-001) and then to semi-annually (4.54-2011-002).
Revised Commitment: In 04402994-01 (02/17/2021 ), the CRFC demister filter Inspection frequency was revised from 6 to 9 months.
Justification Summary:
[Commitment Change Tracking #2020-0001] The frequency was optimized based on negative inspection results to date and to save dose as documented in the Engineering evaluation in 02665227-04 stating that one mid-cycle inspection and the refueling outage inspection were sufficient to monitor the condition of the filters. The inspection criterion to ensure the filters are free of combustible material was unchanged.
NOTE: During the review to extend the frequency from 6 to 9 months, it was discovered that the scheduling mechanism for the procedure containing the online inspections had been cancelled (PMs P203552 and P201703 under PMMR PMC-18-107793). This is documented in Issue Report 04425003, Missed Regulatory Commitment - CRFC Demister Inspections, and the associated Work Group Evaluation. Several actions were taken including the formal updating of 04402994-01.
Report of Commitment Changes from November 2020 through December 2021 Performed IAW NEI 99-04 Commitment Change Evaluation No.: 2021-0004, CRFC demister filter Inspection frequency change from 9 to 18 months [04402994-03]
Source Document: In WPLNRC-RG014022, Notice of Violation (NRC Inspection Report No. 50-244/93-06), dated 05/14/1993, RG&E was given a violation for a fire in containment in the CRFC roughing filters/demisters.
In WPLNRC-RG014071, Reply to a Notice of Violation, dated 07/14/1993, RG&E accepted the violation and made a commitment to the NRC to inspect CRFC filters.
Original Commitment: In WPLNRC-RG014071, Reply to a Notice of Violation, dated 07/14/1993, RG&E accepted the violation and committed to the NRC to inspect CRFC filters monthly.
"Existing plant procedures will be enhanced to provide inspection criteria for visual inspection of the demisters for combustibility. Visual inspections will be conducted and documented on a monthly basis, in accordance with these enhanced plant procedures. These procedures will contain inspection criteria which will consider the recommendations from the manufacturer of the demisters and from a consultant experienced in nuclear safety-related ventilation system testing. These criteria will also incorporate the applicable portions of ANSl-N510, 1989 edition (for consistency with industry standards). When the established criteria are not satisfied, corrective actions will be taken in accordance with the Maintenance Work Control System."
This commitment was later revised to quarterly (4.54-2005-001 ), then to semi-annually (4.54-2011-002), and then to every 9 months (04402994-01 ).
Revised Commitment: In 04402994-03 (09/29/2021 ), the CRFC demister filter Inspection frequency was revised from 9 to 18 months, eliminating the online inspection but continuing to perform the refueling outage inspection.
Justification Summary:
In ECP-21-000329, ESR-21-0151 - CRFC roughing filter inspection extension, dated 08/04/2021 (Current), Engineering concluded, "The periodic inspection of the CRFC roughing filters/demisters can be extended to 18 months, as there is no reasonable combustion sources to ignite the filters outside of refueling outages, and there is no history of there being any issues with combustible debris or contamination buildup on the filters other than the event in 1993 that initiated the commitment."
Report of Commitment Changes from November 2020 through December 2021 Performed IAW NEI 99-04 Commitments modified in 2021 with notification to the NRC via separate correspondence:
Subject Date Accession No.
Use of Stainless-Steel Filler Rods in Core 09/20/2021 ML21264A014 (not publicly available)
Notification of Deviation from Pressurized 11/12/2021 ML21316A051 Water Reactor Owners Group (PWROG)
Report WCAP-17451-P, Revision 1, "Reactor Internals Guide Tube Wear -
Westinghouse Domestic Fleet Operational Projections"
