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Category:Letter
MONTHYEARCP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 IR 05000445/20230042024-01-29029 January 2024 Integrated Inspection Report 05000445/2023004 and 05000446/2023004 CP-202400034, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1)2024-01-29029 January 2024 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1) ML24024A2102024-01-29029 January 2024 Summary of Regulatory Audit Regarding a License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24025A0052024-01-25025 January 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24023A0242024-01-24024 January 2024 Correction to Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident Methodology ML24018A1072024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000445/2024012 and 05000446/2024012) and Request for Information ML23159A2082023-12-20020 December 2023 Request for Withholding Information from Public Disclosure ML23319A3872023-12-20020 December 2023 Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology ML23348A2392023-12-19019 December 2023 Nonacceptance of License Amendment Request to Relocate Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual CP-202300575, (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 22023-12-13013 December 2023 (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 2 ML23333A0872023-12-13013 December 2023 Transmittal of Dam Safety Inspection Report - Public CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300494, License Renewal Application Revision 0, Supplement 32023-12-0606 December 2023 License Renewal Application Revision 0, Supplement 3 ML23313A0732023-12-0606 December 2023 Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications ML23291A4382023-11-30030 November 2023 Notice of Availability of the Draft Plant-Specific Supplement 60, to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Comanche Peak Nuclear Power Plant, Unit Numbers 1 and 2, License Renewal Applica ML23325A0182023-11-30030 November 2023 Schedule Revision for the License Renewal Application Review IR 05000445/20234022023-11-30030 November 2023 NRC Security Inspection Report 05000445/2023402 and 05000446/2023402 CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation2023-11-20020 November 2023 License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation ML23308A0032023-11-17017 November 2023 Letter to R. Nelson, Executive Director; Achp; Re., Comanche Peak Draft Environmental Impact Statement ML23308A0022023-11-17017 November 2023 Letter to M. Wolfe, Executive Director; Shpo; Re., Comanche Peak Draft Environmental Impact Statement ML23317A3002023-11-13013 November 2023 Letter to R. Sylestine, Chairman, Alabama-Coushatta Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2972023-11-13013 November 2023 Letter to R. Martin, President, Tonkawa Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2872023-11-13013 November 2023 Letter to J. Garza, Chairman, Kickapoo Traditional Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2832023-11-13013 November 2023 Letter to D. Dotson, President, Delaware Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2852023-11-13013 November 2023 Letter to E. Martinez, President, Mescalero Apache Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23306A0302023-11-13013 November 2023 Letter to J. Cernek, Chairman; Coushatta Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2902023-11-13013 November 2023 Letter to M. Pierite, Chairman, Tunica Biloxi Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2982023-11-13013 November 2023 Letter to R. Morrow, Town King, Thlopthlocco Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2842023-11-13013 November 2023 Letter to D. Kaskaske, Chairman, Kickapoo Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2822023-11-13013 November 2023 Letter to D. Cooper, Chairman, Apache Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2962023-11-13013 November 2023 Letter to M. Woommavovah, Chairman, Comanche Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2812023-11-13013 November 2023 Letter to C. Hoskin, Principal Chief, Cherokee Nation; Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2862023-11-13013 November 2023 Letter to J. Bunch, Chief, United Keetoowah Band of Cherokee Indians Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3032023-11-13013 November 2023 Letter to W. Yargee, Chief, Alabama-Quassarte Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2882023-11-13013 November 2023 Letter to L. Johnson, Chief, Seminole Nation of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3012023-11-13013 November 2023 Letter to S. Yahola, Mekko, Kialegee Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2792023-11-13013 November 2023 Letter to B. Gonzalez, Chairman, Caddo Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3022023-11-13013 November 2023 Letter to T. Parton, President, Wichita and Affiliated Tribes Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2892023-11-13013 November 2023 Letter to L. Spottedbird, Chairman, Kiowa Indian Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23360A6312023-10-26026 October 2023 FEMA, Submittal of Radiological Emergency Preparedness Final Report for the Comanche Peak Nuclear Power Plant Medical Services Drill Evaluated on August 23, 2023 CP-202300416, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-10-12012 October 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300432, Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 42023-10-0404 October 2023 Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 4 ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23263A0242023-09-21021 September 2023 Revision of Schedule for the Environmental Review of the Comanche Peak Nuclear Power Plant Units 1 and 2 License Renewal Application 2024-01-31
[Table view] Category:Safety Evaluation
MONTHYEARML23319A3872023-12-20020 December 2023 Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology ML23313A0732023-12-0606 December 2023 Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23198A3212023-07-27027 July 2023 Authorization and Safety Evaluation for Proposed Alternative RV-1 ML22192A0072022-08-22022 August 2022 Issuance of Amendment Nos. 183 and 183 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 ML22194A0592022-07-14014 July 2022 Correction to Amendment Nos. 182 and 182 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22129A0722022-05-16016 May 2022 Review of Quality Assurance Program Changes ML22077A8412022-03-24024 March 2022 Proposed Alternative SNB-3 for the Snubber Inservice Program Third Interval Extension ML21321A3492022-02-24024 February 2022 Issuance of Amendment Nos. 182 and 182 to Revise Technical Specifications to Adopt TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspections ML21322A1032021-12-0707 December 2021 Proposed Alternative for the Continued Use of a Risk-Informed Process for the Selection of Class 1 and 2 Piping Welds for Inservice Inspection ML21132A0892021-06-0909 June 2021 Issuance of Amendment Nos. 181 and 181 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-567, Rev. 1, Add Containment Sump TS to Address GSI - 191 Issues ML21061A2172021-05-19019 May 2021 Issuance of Amendment Nos. 180 and 180 to Authorize Revision of Certain Emergency Action Levels of the Emergency Plan ML21103A0392021-04-23023 April 2021 Issuance of Amendment Nos. 179 and 179 the Adoption of Technical Specifications Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition (EPID L-2020-0147) ML21015A2122021-02-12012 February 2021 Issuance of Amendment Nos. 178 and 178 Regarding One-Time Revision to Technical Specifications 3.7.8 Station Service Water System (Ssws) and 3.8.1 AC Sources - Operating ML21022A1622021-02-0808 February 2021 Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Testing Program Interval for Certain Check and Relief Valves (EPID L-2020-LLR-0096 (COVID-19)) ML20346A0192021-02-0101 February 2021 Issuance of Amendment Nos. 177 and 177 Regarding Revision to Technical Specifications 3.8.1, AC Sources - Operating ML21021A1002021-02-0101 February 2021 Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Testing Program Interval for Certain Snubbers (EPID L-2020-LLR-0095 (Covid 19)) ML21013A1282021-01-28028 January 2021 Approval of Proposed Alternative to the Requirements of the ASME Code to Extend the Third Inservice Inspection Interval (EPID L-2020-LLR-0092 (COVID-19)) ML21021A0022021-01-28028 January 2021 Approval of Proposed Alternatives 1A4-1 and 1A4-2 from Certain Requirements of 10 CFR 50.55a for Inservice Inspection of Nuclear Power Plants ML20282A7092020-11-17017 November 2020 Proposed Alternative to the Requirements of the ASME Omcode to Extend the Inservice Testing Program Interval for Certain Snubbers (EPID L-2020-LLR-0060 (COVID-19)) ML20281A4722020-11-0404 November 2020 Use of Later Code Edition to the Requirements of the ASME OM Code ML20255A1002020-10-0707 October 2020 Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Test Program Interval for Certain Check and Relief Valves (EPID L-2020-LLR-0061 and EPID L-2020-LLR-0062 (COVID-19)) ML20223A3492020-08-31031 August 2020 Issuance of Amendment Nos. 175 and 175 Regarding One-Time Revision to Technical Specification 3.7.19, Safety Chilled Water ML20226A0132020-08-17017 August 2020 Use of Later Code Edition to the Requirements of the ASME Code ML20167A3182020-07-0606 July 2020 Issuance of Amendment Nos. 174 and 174 Regarding Revision to Technical Specifications to Adopt TSTF-563, Revision 0 ML20108E8782020-04-17017 April 2020 Issuance of Amendment Nos. 173 and 173 Revision to TS 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator (SG) Program (Exigent Circumstances) ML20054A2762020-02-27027 February 2020 Approval of Change to the Quality Assurance Program as Described in the Comanche Peak Nuclear Power Plant Final Safety Analysis Report ML19267A0182019-11-0404 November 2019 Issuance of Amendment Nos. 172 and 172 to Revise Augmentation Times and Emergency Response Organization Staffing for the Emergency Plan ML18304A4872018-11-30030 November 2018 Issuance of Amendments 171 and 171 Regarding Revision to Technical Specifications for Engineered Safety Feature Actuation System Instrumentation ML18267A3842018-10-25025 October 2018 Issuance of Amendment Nos. 170 and 170 Revision to Technical Specification 3.8.4, DC Sources - Operating, Condition B (Exigent Circumstances) ML18221A6322018-08-15015 August 2018 Eicb Safety Evaluation - Comanche Peak Nuclear Power Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.2 Engineered Safety Feature Actuation System Instrumentation Docket/Epid 000976/05000446/L-2018-LLA-0 ML17129A0242017-06-29029 June 2017 Comanche Peak Nuclear Power Plant, Units 1 and 2 - Issuance of Amendment Nos. 169 and 169 Re: Administrative Change to Licensee Name (CAC Nos. MF8933 and MF8934) ML17074A4942017-04-13013 April 2017 Issuance of Amendment Nos. 168 and 168 Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML17095A2512017-04-0707 April 2017 Request for Alternative 2B3-1 Re Examination of Reactor Vessel Closure Head Penetration Nozzles ML16334A1732016-12-14014 December 2016 Comanche Peak Nuclear Power Plant, Units 1 And 2; Safety Evaluation Regarding Implementation Of Mitigating Strategies And Reliable Spent Fuel Pool Instrumentation Related To Orders EA-12-049 And EA-12-051 ML16179A4052016-07-11011 July 2016 Relief Request Nos. B-9, B-3, B-10, and B-11 for Piping Welds, Second 10-year Inservice Inspection Interval ML16137A0562016-06-14014 June 2016 Issuance of Amendment Nos. 166 and 166, Request to Revise Emergency Action Levels Based on Nuclear Energy Institute (NEI) 99-01, Revision 6 ML16096A2662016-05-0606 May 2016 Redacted Letter, Order, Safety Evaluation, and Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments ML16096A2642016-05-0606 May 2016 Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments ML16074A0012016-03-14014 March 2016 Relief Request 1B3-3, Alternative for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency from Not to Exceed 7 Years to 9 Years for the Third 10-Year Inservice Inspection Interval ML16063A0012016-03-11011 March 2016 Relief Request No. B-15, C-2, and C-4 for Welds in the RPV and Containment Spray and Residual Heat Removal Heat Exchanger Shells, Second 10-year Inservice Inspection Interval ML16011A0732016-01-19019 January 2016 Relief Request T-1; Alternative to the ASME OM Code Frequency Specifications for Inservice Testing for the Third 10-Year IST Interval ML15309A0732015-12-30030 December 2015 Issuance of Amendment Nos. 165 and 165, Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, to Increase ILRT Test Interval from 10 to 15 Years and Type C Tests from 60 to 75 Mos ML15259A0042015-10-30030 October 2015 Relief Request 1B3-4, Alternative for Reactor Pressure Vessel Head Penetration Weld Inspection Frequency (from 10 to 15 Years), Third 10-Year Inservice Inspection Interval ML15257A2422015-09-18018 September 2015 Relief Request 2A3-1, from ASME Code Section XI Requirements, Risk-Informed Process for Selection of Class 1 and Class 2 Piping Weld Examinations, Third 10-Year Inservice Inspection Interval ML15257A2402015-09-15015 September 2015 Relief Request 2C3-1, from ASME Code, Section XI Requirements Reactor Pressure Vessel Leak-Off Flange for the Third 10-Year Inservice Inspection Interval ML15090A1042015-04-0303 April 2015 Relief Requests B-7, B-12, and B-13 - Steam Generator Head-to-Tube Sheet Welds for the Second 10-Year Inservice Inspection Interval ML15008A1332015-02-24024 February 2015 Issuance of Amendment Nos. 164 and 164, Revise Technical Specification 3.8.1 for a 14-Day Completion Time for Offsite Circuits ML14183A3422014-09-0808 September 2014 Issuance of Amendment Nos. 163 and 163 to Revise License Condition Related to Approval of Revised Cyber Security Plan Implementation Schedule 2023-09-28
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 23, 2011 Mr. Rafael Flores Senior Vice President and Chief Nuclear Officer Attention: Regulatory Affairs Luminant Generation Company LLC P.O. Box 1002 Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 - REQUEST FOR A CHANGE TO THE QUALITY ASSURANCE PROGRAM INVOLVING A REDUCTION IN COMMITMENT (TAC NOS. ME6226 AND ME6227)
Dear Mr. Flores:
By letter dated May 3, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11131A070), as supplemented by letter dated August 10,2011 (ADAMS Accession No. ML11229A808), Luminant Generation Company LLC (the licensee) submitted a request for a change to the quality assurance (QA) program for Comanche Peak Nuclear Power Plant, Units 1 and 2 (CPNPP), pursuant to paragraph 50.54(a) of Title 10 of the Code of Federal Regulations (10 CFR). The change involves a reduction in a commitment to the QA program (CPNPP's Final Safety Analysis Report (FSAR), Chapter 17) previously accepted by the U.S. Nuclear Regulatory Commission (NRC). This change would revise FSAR Section 17.2.15, "Nonconforming Materials, Parts, or Components," and an associated commitment to allow conditional releases of nonconforming items from the warehouse for installation, testing, and operation, pending disposition of the nonconformance. Further, for nonconformance items installed with a conditional release, and affecting the CPNPP Technical Specifications (TSs), credit may be taken for TS operability of the item, provided that:
- 1) resolution of the nonconforming condition is tracked in the Corrective Action Program, and
- 2) an operability evaluation is performed that meets requirements of NRC Inspection Manual Part 9900: Technical Guidance, "Operability Determination and Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety" (ADAMS Accession No. ML073531346).
The NRC staff has reviewed the subject request and concludes that the proposed change to FSAR Section 17.2.15 is consistent with Criterion 15, "Nonconforming Materials, Parts, or Components," of Appendix B to 10 CFR Part 50 and is, therefore, acceptable.
R. Flores - 2 If you have any questions, please contact Balwant K. Singal at 301-415-3016 or bye-mail at Balwant.Singal@nrc.gov.
Sincerely, b~~ t2~6j~r.
Balwant K. Singal, Senior Project Manager Plant licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-445
Enclosure:
As stated cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR CHANGE TO THE QUALITY ASSURANCE PROGRAM INVOLVING A REDUCTION IN COMMITMENT LUMINANT GENERATION COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446
1.0 INTRODUCTION
By letter dated May 3, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11131A070), as supplemented by letter dated August 10, 2011 (ADAMS Accession No. ML11229A808), Luminant Generation Company LLC (the licensee) submitted a request for a change to the quality assurance (QA) program for Comanche Peak Nuclear Power Plant, Units 1 and 2 (CPNPP), pursuant to paragraph 50.54(a) of Title 10 of the Code of Federal Regulations (10 CFR). The change involves a reduction in a commitment to the QA program (CPNPP's Final Safety Analysis Report (FSAR), Chapter 17) previously accepted by the U.S. Nuclear Regulatory Commission (NRC). This change would revise FSAR Section 17.2.15, "Nonconforming Materials, Parts, or Components," and an associated commitment to allow conditional releases of nonconforming items from the warehouse for installation, testing, and operation, pending disposition of the nonconformance. Further, for nonconformance items installed with a conditional release, and affecting CPNPP's Technical Specifications (TSs), credit may be taken for TS operability of the item, provided that:
- 1) resolution of the nonconforming condition is tracked in the Corrective Action Program, and
- 2) an operability evaluation is performed that meets requirements of NRC Inspection Manual Part 9900: Technical Guidance, "Operability Determination and Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety" (ADAMS Accession No. ML073531346).
2.0 REGULATORY EVALUATION
The NRC staff considered the following regulatory requirements and guidance in its review of the application:
The regulations in 10 CFR Part 50 establish the fundamental regulatory requirements with respect to the domestic licensing of nuclear production and utilization facilities. Specifically, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Enclosure
-2 Plants," to 10 CFR Part 50 establishes QA requirements for the design, manufacture, construction, and operation of structures, systems, and components (SSCs). The pertinent requirements of Appendix B to 10 CFR Part 50 apply to all safety-related functions of SSCs to include design, purchase, fabrication, handling, shipping, storing, cleaning, erection, installation, inspection, testing, operation, maintaining, repairing, refueling, and modification.
Criterion 15, "Nonconforming Materials, Parts, or Components," in Appendix B to 10 CFR Part 50 requires that measures be established to control materials, parts, or components which do not conform to requirements in order to prevent their inadvertent use or installation.
The regulations in 10 CFR 50.54(a)(4) state, in part, that Changes to the quality assurance program description that do reduce the commitments must be submitted to the NRC and receive NRC approval prior to implementation ...
3.0 TECHNICAL EVALUATION
3.1 Background By letter dated May 3, 2011, the licensee submitted a proposed change to the CPNPP FSAR Section 17.2.15, "Nonconforming Materials, Parts, or Components." The proposed change would revise the current conditional release provision and allow for conditional release of a nonconforming item from the warehouse for installation, testing, and operation. The licensee proposes to complete an operability evaluation prior to taking TS credit for a newly installed item. The current QA program requires tracking resolution of the nonconforming condition in the licensee's corrective action program.
In its letter dated August 10, 2011, the licensee stated that it would perform an evaluation that meets the requirements of NRC Inspection Manual Part 9900 Technical Guidance for assessing a degraded or nonconforming component.
3.2 NRC Staff Evaluation Revision to NRC Inspection Manual Part 9900: Technical Guidance, "Operability Determination
& Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety" (ADAMS Accession No. ML073531346), issued by Regulatory Information Summary (RIS) 2005-20, Revision 1, "Revision to NRC Inspection Manual Part 9900 Technical Guidance, 'Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety'," dated April 16, 2008 (ADAMS Accession No. ML073440103), states that an operability determination should include:
- 1) The SSCs which are affected by the degraded or nonconforming condition;
- 2) The extent of the condition for all similarly affected SSCs;
- 3) The current licensing basis requirements or commitments established for the affected SSCs;
-3
- 4) The specified safety functions performed by the affected SSCs;
- 5) The effect or potential effect of the degraded or nonconforming condition on the affected SSCs' ability to perform specified safety functions; and
- 6) Whether there is reasonable expectation of operability, including the basis for the determination and any compensatory measures put in place to establish or restore operability.
The guidance in NRC Inspection Manual Part 9900, provides reasonable assurance that Criterion 15, "Nonconforming Materials, Parts, or Components," in Appendix B to 10 CFR Part 50, which requires that measures be established to control materials, parts, or components which do not conform to requirements in order to prevent their inadvertent use or installation, is met. Hence, the FSAR change proposed by the licensee is acceptable.
4.0 CONCLUSION
Based on the above evaluation, the NRC staff concludes that the licensee's proposed change to CPNPP's FSAR Section 17.2.15, "Nonconforming Materials, Parts, or Components," is consistent with Criterion 15 of Appendix B to 10 CFR Part 50, and is, therefore, acceptable.
Principal Contributor: Kerby Scales Date: September 23, 2011
R. Flores - 2 If you have any questions, please contact Balwant K. Singal at 301-415-3016 or bye-mail at Balwant.Singal@nrc.gov.
Sincerely, IRAJ Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-445
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrLAJBurkhardt Resource LPLIV Reading RidsOgcRp Resource RidsAcrsAcnw_MailCTR Resource RidsRgn4MailCenter Resource, RidsNrrDeEqvb Resource KScales, NRR/DE/EQVB RidsNrrDorlLpl4 Resource JMcHale, EDO RIV RidsNrrPMComanchePeak Resource ADAMS A ccesslon No. ML112550147 *SE memo dae t t d Seplemb er 9 , 2011 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DElEQVB/BC NRR/LPL4/BC NRR/LPL4/PM NAME BSingal JBurkhardt MMurphy* MMarkley BSingal DATE 9/16/11 9/16/11 9/9111 111 9123/11 OFFICIAL AGENCY RECORD