Letter Sequence Other |
---|
|
|
MONTHYEARML0304202642003-02-10010 February 2003 R. E. Ginna Nuclear Power Plant, Relief, Inservice Testing Program Relief Request PR-2, MB7232 Project stage: Other 2003-02-10
[Table View] |
Similar Documents at Ginna |
---|
Category:Code Relief or Alternative
MONTHYEARML23073A3682023-03-16016 March 2023 Authorization and Safety Evaluation for Proposed Alternative I6R-10, Revision 0 Related to the Steam Generators, RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.2022-09-20020 September 2022 Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request. ML21250A3822021-09-29029 September 2021 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request I6R-06 Alternate Inspection for Reactor Vessel Internals ML21246A1062021-09-22022 September 2021 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Alternative Request GR-03, Valve Position Verification Testing Extension Sixth 10-Year Inservice Testing Program Interval ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21117A0312021-04-26026 April 2021 Verbal Authorization by the NRC NRR for 10 CFR 50.55a Alternative Request Position Verification Testing Extension - Exelon Generation, R. E. Ginna Nuclear Power Plant ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML20090D2912020-06-0202 June 2020 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternative I6R-02 for the Sixth 10-Year Inservice Inspection Interval (EPID L-2019-LLR-0071). Supersedes ML20056D559 ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20099D9552020-04-17017 April 2020 Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations ML20055F8862020-03-13013 March 2020 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternative I6R-01 for the Sixth 10-Year Inservice Inspection Interval RS-20-020, Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi)2020-02-28028 February 2020 Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19205A4532019-08-0505 August 2019 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternatives PR-01 and PR-02 for Sixth 10-Year Inservice Testing Program ML19205A3532019-08-0505 August 2019 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternatives GR-01, VR-01, and VR-02 for the Sixth 10-Year Inservice Testing Program (EPID L-2018-LLR-0382; EPID L-2018-LLR-0383) ML19177A2182019-06-26026 June 2019 R. E. Ginna Nuclear Power Plant - Relief Request Associated with Snubber Inservice Testing Program for the Sixth Ten-Year Interval ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19100A0042019-04-22022 April 2019 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request ISI-18 Regarding Fifth 10-Year Inservice Inspection Program Interval JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds2019-02-15015 February 2019 Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds ML18347B0362018-12-13013 December 2018 Relief Requests Associated with Sixth Ten-Year Lnservice Testing Interval JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-8802018-05-30030 May 2018 Proposed Alternative to Utilize Code Cases N-878 and N-880 JAFP-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 ML17297A5242017-11-0606 November 2017 R. E. Ginna - Request for Use of a Portion of a Later Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (CAC Nos. MG0079-MG0083; EPID L-2017-LLR-0061) ML17170A0132017-06-26026 June 2017 Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) ML16230A2372016-09-0606 September 2016 Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) ML16138A0212016-05-19019 May 2016 Proposed Alternative to Use Code Case N-789 (CAC Nos. MF7018-MF7022) ML12264A5912012-09-18018 September 2012 Supplemental Information for Relief Request Number ISI-09 R. E. Ginna Nuclear Power Plant - Fifth Interval Inservice Inspection Program Proposed Alternative in Accordance with 10 CFR 50.55a (a)(3)(ii) Component Cooling Water 1 Inch Half-Cou ML12254A3782012-09-0606 September 2012 Relief Request Number ISI-09 - Fifth Interval Inservice Inspection Program Proposed Alternative in Accordance with 10 CFR 50.55a (a)(3)(ii) Component Cooling Water 1 Inch Half-Coupling Weld Leak ML12158A1152012-06-22022 June 2012 Inservice Inspections Program Relief Request Nos. ISI-02 and ISI-03 ML0920802292009-07-31031 July 2009 R. E. Ginna, Safety Evaluation for Relief Request No. 18, Reactor Vessel Weld Examination Extension ML0909000452009-04-0505 April 2009 Relief Request No. 23 on End-of-Interval System Pressure Test for Class 1 Components-R.E. Ginna Nuclear Power Plant ML0903501872009-02-0404 February 2009 Acceptance Review for Ginna Relief Request No. 23 ML0828800322008-10-0303 October 2008 Fourth Ten-Year Interval Inservice Inspection Program, Re-submittal of Relief Request Number 18 ML0617401562006-07-19019 July 2006 Relief Request No. PR-3 Regarding Testing of Auxiliary Feedwater Pumps ML0612805002006-05-0101 May 2006 R. E. Ginna Response to Request for Additional Information Regarding Relief Request PR-3 ML0507300162005-04-12012 April 2005 R. E. Ginna, Relief, Request 17 for the Fourth 10-Year Interval of the Inservice Inspection Program, MC5406 ML0435601532004-12-15015 December 2004 Fourth Ten-Year Interval in Service Inspection Program Submittal of Relief Request Number 17 Related to Appendix Viii, Supplement 10, PDI Program Alternative Requirements R. E. Ginna Nuclear Power Plant ML0424507782004-10-19019 October 2004 R. E. Ginna Nuclear Power Plant Relief Requests VR-1, VR-2 and VR-13 for the Fourth 10-Year Interval of the Pump and Valve Inservice Testing Program ML0330401202003-11-21021 November 2003 R. E. Ginna Nuclear Power Plant, Relief Request Review, Inservice Testing Program Relief Requests VR-4 and VR-8 ML0329603222003-10-20020 October 2003 Submittal of Relief Request VR-4 Related to the Requirements of 10CFR50.55a(f), Inservice Testing Requirements. ML0304202642003-02-10010 February 2003 R. E. Ginna Nuclear Power Plant, Relief, Inservice Testing Program Relief Request PR-2, MB7232 ML0314205202003-01-0909 January 2003 Enclosure - R.E. Ginna, Inservice Testing Program Relief Request PR-2 2023-03-16
[Table view] 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] |
Text
February 10, 2003 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
R. E. GINNA NUCLEAR POWER PLANT - INSERVICE TESTING PROGRAM RELIEF REQUEST PR-2 (TAC NO. MB7232)
Dear Dr. Mecredy:
By letter dated January 9, 2003, Rochester Gas and Electric (RG&E) requested the Nuclear Regulatory Commissions (NRCs) approval to use a more recent edition and addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). The revised Code with addenda allows for pump analysis and the establishment of new reference values as a part of the corrective actions to be taken when pump test acceptance criteria are not met. The current Code of record for the Ginna Inservice Test (IST) program is the 1987 Edition and 1988 Addenda of the ASME OM Part 6 Standard (OM-6). RG&E requested approval to use paragraph ISTB 6200(c) of the 1998 Edition up to and including the 2000 Addenda of the ASME OM Code related to inservice testing of pumps for the remainder of its fourth ten-year IST interval. The analysis required by ISTB 6200(c) includes both pump and system level evaluations to determine operational readiness, the cause of the change in pump performance, and an evaluation of all trends indicated by available data. The results of the analysis are to be documented in the Record of Tests as specified in paragraph 7.3 of OMa-1988, Part 6.
Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(f)(4)(iv) states that inservice testing of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to NRC approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met. The 1998 Edition up to and including the 2000 Addenda of the ASME OM Code were incorporated by reference in 10 CFR 50.55a(b) on September 26, 2002 (67 FR 60520), with no modifications or limitations placed on ISTB requirements. Therefore, the request to use the portions of a later Code and Addenda associated with the inservice testing of pumps at Ginna submitted by RG&E in its letter dated January 9, 2003, is approved pursuant to 10 CFR 50.55a(f)(4)(iv).
Sincerely,
/RA/
Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244 cc: See next page
February 10, 2003 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
R. E. GINNA NUCLEAR POWER PLANT - INSERVICE TESTING PROGRAM RELIEF REQUEST PR-2 (TAC NO. MB7232)
Dear Dr. Mecredy:
By letter dated January 9, 2003, Rochester Gas and Electric (RG&E) requested the Nuclear Regulatory Commissions (NRCs) approval to use a more recent edition and addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). The revised Code with addenda allows for pump analysis and the establishment of new reference values as a part of the corrective actions to be taken when pump test acceptance criteria are not met. The current Code of record for the Ginna Inservice Test (IST) program is the 1987 Edition and 1988 Addenda of the ASME OM Part 6 Standard (OM-6). RG&E requested approval to use paragraph ISTB 6200(c) of the 1998 Edition up to and including the 2000 Addenda of the ASME OM Code related to inservice testing of pumps for the remainder of its fourth ten-year IST interval. The analysis required by ISTB 6200(c) includes both pump and system level evaluations to determine operational readiness, the cause of the change in pump performance, and an evaluation of all trends indicated by available data. The results of the analysis are to be documented in the Record of Tests as specified in paragraph 7.3 of OMa-1988, Part 6.
Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(f)(4)(iv) states that inservice testing of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to NRC approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met. The 1998 Edition up to and including the 2000 Addenda of the ASME OM Code were incorporated by reference in 10 CFR 50.55a(b) on September 26, 2002 (67 FR 60520), with no modifications or limitations placed on ISTB requirements. Therefore, the request to use the portions of a later Code and addenda associated with the inservice testing of pumps at Ginna submitted by RG&E in its letter dated January 9, 2003, is approved pursuant to 10 CFR 50.55a(f)(4)(iv).
Sincerely,
/RA/
Richard J. , Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244 cc: See next page DISTRIBUTION:
PUBLIC PDI-1 R/F SRichards RLaufer DTerao RClark GKlein SLittle GHill (2) OGC HNeih, EDO ACRS BPlatchek, R-I Accession Number: ML030420264 *See previous concurrence OFFICE PDI-1:PM PDI-1:LA EMEB:SC* OGC* PDI-1:SC NAME RClark SLittle DTerao DHoefling RLaufer DATE 2/6/03 2/6/03 01/31/03 02/05/03 2/7/03 OFFICIAL RECORD COPY
R.E. Ginna Nuclear Power Plant cc:
Kenneth Kolaczyk, Sr. Resident Inspector Mr. Paul Eddy R.E. Ginna Plant New York State Department of U.S. Nuclear Regulatory Commission Public Service 1503 Lake Road 3 Empire State Plaza, 10th Floor Ontario, NY 14519 Albany, NY 12223 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. William M. Flynn, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Daniel F. Stenger Ballard Spahr Andrews & Ingersoll, LLP 601 13th Street, N.W., Suite 1000 South Washington, DC 20005 Ms. Thelma Wideman, Director Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31 Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 1190 Scottsville Road, Suite 200 Rochester, NY 14624