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Category:Letter
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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:Request for Additional Information (RAI)
MONTHYEARML23312A1302023-11-0707 November 2023 Final Rci/Rai - Constellation R. E. Ginna Nuclear Power Plant - Exemption from Security Rule (EPID L-2023-LLE-0029) (Email) ML22160A3962022-06-0909 June 2022 R. E. Ginna Nuclear Power Plant, LLC - Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000244/2022010 ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 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 ML21308A5592021-11-0404 November 2021 NRR E-mail Capture - NRC Request for Additional Information for Ginna Biennial EP Exercise Exemption Request ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21189A1602021-07-0808 July 2021 NRR E-mail Capture - Request for Additional Information - Braidwood, Byron, and Ginna - Amendment to Address the Issues in Westinghouse NSALs ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21119A1082021-04-27027 April 2021 Ti 2515/194 Inspection Documentation Request ML21076A5152021-03-17017 March 2021 R. E. Ginna Nuclear Power Plant - RAI Steam Generator LAR to Revise Technical Specifications for Steam Generator Tube Inspection Frequency (EPID L-2020-LLA-0207) (e-mail) 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) ML21029A3302021-01-29029 January 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885 ML20357A2232020-12-17017 December 2020 Update on Ginna POV - 3504A and 4562 (Email Request for Inspection Information) ML20218A6422020-08-0505 August 2020 R. E. Ginna Nuclear Power Plant - Request for Additional Information (RAI) for LAR to Implement WCAP, TSTF-411, and TSTF-418 ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML19120A3862019-04-30030 April 2019 Request for Additional Information to Revise Emergency Plan Response Organization Staffing and Augmentation ML18228A5242018-08-15015 August 2018 R. E. Ginna Nuclear Power Plant - TSTF 547 Adoption, Request for Additional Information (RAI) EPID L-2018-LLA-0179 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) ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML17331B1342017-12-12012 December 2017 2, and R.E. Ginna Nuclear Power Plant - Request for Additional Information - Regarding ML17277A2052017-10-0202 October 2017 Email - Ginna: Request for Additional Information (RAI) for NFPA-805 LAR RS-17-026, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-03-10010 March 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal ML17062A4912017-03-0303 March 2017 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative to RPV Threads in Flange Examination (CAC Nos. MF8712-MF8729) ML16278A0772016-11-0707 November 2016 Request for Additional Information Regarding: Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specifications ML16075A1192016-03-17017 March 2016 Request for Additional Information Regarding: Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specifications ML16077A1082016-03-17017 March 2016 NRR E-mail Capture - (External_Sender) Email Clarification and Supplementation to AMP RAI ML15344A3532016-01-0707 January 2016 Request for Additional Information Regarding Risk-Informed Technical Specifications Initiative 5B CAC No. MF6358) ML15349B0252016-01-0707 January 2016 Request for Additional Information Regarding Reactor Vessels Internals Program ML15100A2112015-04-28028 April 2015 RAI Regarding License Amendment Request to Adopt Technical Specification Task Force Traveler-523 ML14093A6772014-05-0101 May 2014 SONGS - Request for Additional Information Concerning Pre-Emption Authority ML13337A6252013-12-0505 December 2013 Constellation Energy Nuclear Group, R.E. Ginna Nuclear Power Plant, Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instru ML13337A3902013-12-0505 December 2013 Request for Additional Information Regarding Order Approving Direct Transfer of Renewed Facility Operating License and Conforming Amendments ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13261A0612013-09-24024 September 2013 R. E. Ginna Nuclear Power Plant - Request for Additional Information Regarding Amendment to Revise Technical Specification 3.6.5. Containment Air Temperature. ML13261A1142013-09-12012 September 2013 R. E. Ginna Nuclear Power Plant, E-mail Re. NFPA 805 License Amendment Request, Audit RAIs ML13226A3822013-08-29029 August 2013 Request for Additional Information Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) ML13108A0682013-04-23023 April 2013 (Security Related) Request for Additional Information for Review of Security Plan Changes in Revision 5 ML12264A6192012-09-20020 September 2012 RAI for the CRDM Nozzle Examination Relief Request ML12234A5172012-08-21021 August 2012 Physical Security Plan Change Per 10 CFR 50.54(p)(2) ML12228A6182012-08-15015 August 2012 Re_ Ginna-BMI Flaw Evaluation(ME8247) ML12178A1922012-06-25025 June 2012 Gina_ TAC Nos. ME8000 and ME8001-Relief Ginna Relief Request ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic ML12056A0502012-03-12012 March 2012 Enclosure 4 - Recommendation 2.3: Flooding ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML1201201272012-01-23023 January 2012 Request for Additional Information the 2011 Steam Generator Tube Inspections - R.E. Ginna Nuclear Power Plant ML1128401992011-10-12012 October 2011 Transmittal Letter, Request for Additional Information (NON-PROPRIETARY) Proposed Merger Between Exelon Corporation and Constellation Energy Group, Inc. 2023-11-07
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555*0001 February 7, 2011 Mr. John T. Carlin Vice President RE. Ginna Nuclear Power Plant RE. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST ISI-04, ALTERNATE DEPTH SIZING QUALIFICATION - RE. GINNA NUCLEAR POWER PLANT (TAC NO. ME5120)
Dear Mr. Carlin:
By letter dated November 24,2010. RE. Ginna Nuclear Power Plant, LLC, the licensee, submitted Relief Request ISI-04 from selected requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) at the RE.Ginna Nuclear Power Plant. Specifically, the ASME Code specifies that the acceptance depth sizing criterion for performance demonstrations not exceed O. 125-inch root mean square error (RMSE) for personnel, equipment, and procedure qualifications. The licensee proposed to use an alternative RMSE depth sizing criterion for qualification purposes.
The Nuclear Regulatory Commission staff has reviewed the information provided and has determined that additional information is needed to complete its review. Enclosed is the staff's request for additional information (RAI). As discussed with your staff, we understand that you intend to respond to this RAI by February 28, 2011.
Please contact me at 301-415-1364 if you have any questions.
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION REQUEST ISI-04 RE. GINNA NUCLEAR POWER PLANT, LLC RE.GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 By letter dated November 24,2010, (Reference 1), RE. Ginna Nuclear Power Plant, LLC (the licensee) submitted Relief Request ISI-04 from selected requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) at the RE. Ginna Nuclear Power Plant (Ginna). Specifically, the ASME Code specifies that the acceptance depth sizing criterion for performance demonstrations not exceed 0.125-inch root mean square error (RMSE) for personnel, equipment. and procedure qualifications. The licensee proposed to use an alternative RMSE depth sizing criterion for qualification purposes. The Nuclear Regulatory Commission (NRC) staff has reviewed the information submitted along with information from a prior submittal, Relief Request 19 (Reference 2). From the available information, the NRC staff has determined that the following information is needed to complete the review and evaluation.
- 1. If cladding is on the inside diameter (10) scanning surface, provide a representative sketch showing the cross section of the weld, butter, cladding, and base metal.
- 2. The Electric Power Research Institute (EPRI) - Performance Demonstration Initiative (POI) program tests candidates on large diameter, thick wall representative mockups containing rough and wavy, 10 surfaces (Reference 3). Smaller diameter, thinner wall mockups are available for add-on performance demonstrations. Provide the nominal inside diameter and nominal wall thickness (the thickness used to determine inspection volume) for the components in Reference 1, Table A. For the three different weld configurations, discuss the 10 surface roughness/waviness and scanning restrictions, if any (counter bore, field weld bead, etc).
- 3. Starting in 2004 (Reference 4), EPRI has requested licensees to make surface profilometry measurements of dissimilar metal (OM) welds and adjacent similar metal welds to identify scanning gaps greater than 1/32-inch between the transducer and 10 surface. The last 10 examination of the subject welds occurred prior to OM weld performance-based qualification requirements. Discuss the transducer footprint on the inspection subject weld areas (Le., curvature gaps, contoured transducers, etc.).
Discuss Ginna's effort to identify and record surface roughness/waviness of the selected welds and to locate scanning gaps greater than 1/32-inch between the transducer and 10 surface.
- 4. Discuss the nondestructive examination (NDE) methods and techniques used for examining the subject welds during the 2011 refueling outage (RFO). Discuss the NDE improvements (over prior examinations) that will be used for the 2011 RFO examinations, such as, performance-based qualifications, video camera records, surface waviness records, supplemental eddy current examinations, visual examinations, etc.
Enclosure
-2
- 5. Some vendors have performed supplemental, configuration specific, non-blind depth sizing demonstrations on smooth 10 surfaces of reactor coolant mockups containing statistically significant number of flaws (Example, Reference 5). Excluding the ASME Code required blind performance demonstrations (administered by the EPRI-POJ),
discuss demonstrations that Ginna's vendor performed that supported depth sizing effectiveness on configurations similar to the subject weld configurations. Include in the discussion mockup dimension {IO diameter and wall-thickness}, materials, through-wall flaw distributions, flaw types and quantities, blind/non-blind demonstrations, and RMSE's.
- 6. The submittal was based on Title 10 of the Code of Federal Regulations (10 CFR) 50.55a{a}(3)(i}. However, the industry has been unable to achieve the ASME Code required depth sizing RMSE requirement which was imposed on OM welds on November 22, 2002. The RMSE performance demonstration acceptance requirement occurred after Ginna was constructed and after the last examinations of the subject welds. However, the blind OM weld performance demonstrations administered by the EPRI-POI program have not qualified any ultrasonic testing personnel, equipment, or procedures for 10 depth sizing. The NRC staff has determined that the appropriated 10 CFR Part 50 paragraph for this request (Reference 1) is 10 CFR 50.55a(g)(5}(iii}.
Provide a discussion on the difficulties Ginna would experience trying to meet the RMSE requirement.
- 7. The licensee's proposed alternative (Reference 1) is to use Code Case N-695 qualifications for Appendix VIII, Supplement 10 qualifications. The proposal also contains words in the "Reason for the Request" that reference Supplement 2. If Supplement 2 is part of this relief request, provide the information to support the proposed alternative RMSE; if not, provide clarification.
- 8. From prior Relief Request 19 (Reference 2), Ginna identified the likely failure mechanism for the subject welds as fatigue cracking. In a response (Reference 6) to an NRC request for additional information, Ginna provided a crack depth divided by crack length (aspect ratio) of 6 to support a discussion on crack growth. The ASME Code,Section XI, Table IW8-3514-2, "Allowable Planar Flaw," in austenitic material gives a range of aspect ratios for acceptable flaw depths. The most conservative aspect ratio in this range is 0.05. The fatigue crack length is measured by ultrasonic testing and/or eddy current testing which can be used to estimate fatigue crack depth.
The proposal is for a crack depth sizing criterion that is based on the vendor's RMSE from a non-qualified performance demonstration. The criterion is being applied as a tolerance for determining crack depth. Since fatigue is the likely failure mechanism, the crack depth sizing proposal should include a comparison between values based on a conservative aspect ratio (assuming measured crack length by one or more methods) with values derived by adding the vendor's RMSE tolerance adjustment to the fatigue crack depth. Provide a discussion on using an aspect ratio for fatigue crack depth determinations. Provide application criteria for aspect ratio and RMSE performance demonstration tolerance adjustment that result in selecting the more conservative fatigue crack depth for disposition.
- 3
References:
- 1. Letter from Paul Swift, Constellation Energy, to NRC dated November 24, 2010, "10 CFR 50.55a Request ISI-04: Request for use of an Alternate Depth Sizing Qualification," Agencywide Documents Access and Management System (ADAMS)
Accession No. ML103350217.
- 2. Letter from Mark G. Kowal, NRC, to John T. Carlin, RE. Ginna Nuclear Power Plant, LLC dated February 17, 2009, "Fourth Intervallnservice Inspection Program Relief Request No. 19 - Deferral of Reactor Pressure Vessel Category B-F Exams from 2009 to 2011 - RE. Ginna Nuclear Power Plant," ADAMS Accession No. ML090330300.
- 3. Letter from Ali Rezai, NRC, to Timothy R Lupoid, NRC dated July 30, 2010, "Summary of Meeting Held on June 17 and 18, 2010 with the Electric Power Research Institute Performance Demonstration Initiative Representatives," ADAMS Accession No. ML102110443.
- 4. Letter from Donald G. Naujock, NRC, to Terence L. Chan, NRC dated January 18, 2005, "Summary of Public Meeting Held October 19 & 20, 2004 with EPRI-PDI Representatives," ADAMS Accession No. ML050690198.
- 5. Letter from James R Becker, Pacific Gas and Electric Company, to NRC dated August 12, 2010, "ASME Section XI Inservice Inspection Program Relief Request NDE-RCS-SE-2R16 Use of Alternate Sizing Qualification Criteria through a Protective Clad Layer," ADAMS Accession No. ML102350295.
- 6. Letter from Joseph E. Pacher, Constellation Energy, to NRC dated October 31,2008, "Response to Request for Additional Information Pertaining to Fourth 10-Year Inservice Inspection Program Relief Request Number 19," ADAMS Accession No. ML083110415.
February 7, 2011 Mr. John T. Carlin Vice President RE. Ginna Nuclear Power Plant RE. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST ISI-04, ALTERNATE DEPTH SIZING QUALIFICATION - RE. GINNA NUCLEAR POWER PLANT (TAC NO. ME5120)
Dear Mr. Carlin:
By letter dated November 24,2010, RE. Ginna Nuclear Power Plant, LLC, the licensee, submitted Relief Request ISI-04 from selected requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) at the RE.Ginna Nuclear Power Plant. Specifically, the ASME Code specifies that the acceptance depth sizing criterion for performance demonstrations not exceed 0.125-inch root mean square error (RMSE) for personnel, equipment, and procedure qualifications. The licensee proposed to use an alternative RMSE depth sizing criterion for qualification purposes.
The Nuclear Regulatory Commission staff has reviewed the information provided and has determined that additional information is needed to complete its review. Enclosed is the staff's request for additional information (RAI). As discussed with your staff, we understand that you intend to respond to this RAI by February 28, 2011.
Please contact me at 301-415-1364 if you have any questions.
Sincerely, IRAJ Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
As stated cc w/encl: Distribution via Listserv Distribution:
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~FICE PM/LPL1-1 LA:LPL1-1 CPNBIBC LPL 1-1/BC NAME DPickett SLittie TLupold by email dated NSalgado
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DATE 02/7/11 02/7/11 01 127 111 02/7/11 OFFICIAL RECORD COpy