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MONTHYEARML15189A4552015-07-0707 July 2015 NRR E-mail Capture - Acceptance Review: Grand Gulf Nuclear Station, Unit 1 License Amendment Request: Permanent Extension of Type C Leak Rate Testing Frequency, (MF6310) Project stage: Acceptance Review ML15261A5652015-09-24024 September 2015 Request for Additional Information Regarding Proposed Revision of Technical Specifications for Containment Leak Rate Testing Project stage: RAI 2015-07-07
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Category:Letter
MONTHYEARML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 IR 05000416/20243012024-01-16016 January 2024 NRC Initial Operator Licensing Examination Approval 05000416/2024301 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23348A3712023-12-14014 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report (05000416/2024011) and Request for Information ML23340A2222023-12-13013 December 2023 Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000416/20234032023-11-13013 November 2023 Security Baseline Inspection Report 05000416/2023403 Cover Letter 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 IR 05000416/20230032023-11-0808 November 2023 Integrated Inspection Report 05000416/2023003 ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23270B1892023-09-27027 September 2023 Evacuation Time Estimate Study ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23240A3952023-08-28028 August 2023 Reply to a Notice of Violation; EA-23-019 IR 05000416/20230052023-08-21021 August 2023 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2023005) ML23226A1002023-08-18018 August 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 IR 05000416/20234042023-08-0707 August 2023 Material Control and Accounting Program Inspection Report 05000416/2023404 IR 05000416/20230912023-07-28028 July 2023 Final Significance Determination of a Green Finding and Notice of Violation; NRC Inspection Report 05000416/2023091 ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23166B0712023-06-15015 June 2023 Reply to Notice of Violation EA-22-104 and EA-22-115 ML23166B0662023-06-15015 June 2023 Response to NRC Integrated Inspection Report 05000416/2023001 ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) GNRO-2023/00014, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0606 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23122A1632023-05-18018 May 2023 NRC Inspection Report 05000416/2023090 and Preliminary White Finding IR 05000416/20234022023-05-17017 May 2023 Security Baseline Inspection Report 05000416/2023402 ML23110A8002023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000416/20230012023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23117A0422023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23110A0552023-04-20020 April 2023 Annual Radiological Environmental Operating Report (AREOR) ML23103A1022023-04-13013 April 2023 Annual Report of Individual Monitoring - NRC Form 5 for 2022 Per 10 CFR 20.2206 ML23102A1482023-04-12012 April 2023 Notification of NRC Initial Operator Licensing Examination 05000416/2024301 ML23089A0602023-03-30030 March 2023 Entergy Operations, Inc. - Fleet Project Manager Assignment ML23088A3922023-03-29029 March 2023 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML23079A2772023-03-21021 March 2023 U.S. Nuclear Regulatory Commission Presentation at the May 1, 2023, Port Gibson City Council Meeting ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc IR 05000416/20230112023-03-0808 March 2023 Design Basis Assurance Inspection Report 05000416/2023011 2024-01-31
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23348A1222023-12-14014 December 2023 NRR E-mail Capture - Grand Gulf, River Bend, and Waterford, Unit 3 - 2nd Round of Official RAIs for RR EN-RR-22-001, Use ASME Code Case N-752, Risk Informed Categorization for Class 2 and 3 Systems ML23116A1462023-04-26026 April 2023 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Final RAI for Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) ML23059A0742023-02-27027 February 2023 Information Request, Security IR 2023402 ML22353A6122022-12-19019 December 2022 March 2023 Emergency Preparedness Exercise Inspection - Request for Information ML22271A8572022-10-0303 October 2022 Notification of Commercial Grade Dedication Inspection (05000416/2023011) and Request for Information ML22110A1172022-04-19019 April 2022 (GG) 2022 Emergency Preparedness (EP) Program Inspection RFI Sdh 041922 ML21179A1202021-06-28028 June 2021 Notification of NRC Supplemental Inspection of Action Matrix Column 3 (Degraded Performance) Inputs and Request for Information ML21074A0822021-03-15015 March 2021 Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000416/2021002) and Request for Information ML20363A1462020-12-22022 December 2020 Request for Information: Grand Gulf EP Exercise Inspection - March 2021 ML20258A0202020-09-0909 September 2020 EP Program Inspection RFI, Request for Information to Support and Prepare for Emergency Preparedness (EP) Program Inspection Scheduled to Occur the Week of November 16, 2020 ML20260H4422020-09-0808 September 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Official RAIs for RR Associated with Updating ASME Code RR SEs with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020 and RBS-ISI-019) ML20155K7172020-06-0303 June 2020 Notification of NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000416/2020013) and Request for Information ML20150A6012020-05-29029 May 2020 NRR E-mail Capture - Grand Gulf - Official RAI for LAR Associated with Containment ILRT Interval Change from 10 Years to 15 Years ML19302E1082019-10-29029 October 2019 Document Request - GG 95001 - August 2 2019 ML19078A3772019-03-19019 March 2019 NRR E-mail Capture - Grand Gulf - Official Rais for Relief Request GG-ISI-023, Inservice Inspection Impracticality, Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval ML19063B4882019-03-0404 March 2019 Notification of NRC Triennial Heat Sink Performance Inspection (05000416/2019002) and Request for Information ML18304A4602018-10-31031 October 2018 NRR E-mail Capture - Final Request for Additional Information - TSTF-425 (L-2018-LLA-0106) ML18250A3042018-08-30030 August 2018 NRR E-mail Capture - Final Request for Additional Information - Emergency Action Level Scheme Change (L-2018-LLA-0116) ML18250A3032018-08-0101 August 2018 NRR E-mail Capture - Correction: Draft RAI - EAL Scheme Change (L-2018-LLA-0116) ML18187A3292018-07-20020 July 2018 Request for Additional Information, Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML18138A4682018-05-23023 May 2018 Supplemental Information Needed for Acceptance of Request for Licensing Action Adoption of TSTF-425, Relocate Surveillance Frequencies to License Control ML18058A0572018-02-23023 February 2018 Enclosurequest for Additional Information (Letter to J. Giddens Request for Additional Information Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update) ML17257A1422017-09-14014 September 2017 NRR E-mail Capture - Grand Gulf - Official Requests for Additional Information (Rais) for RR GG-ISI-020 to Use BWRVIP Guidelines ML17235B1752017-08-23023 August 2017 NRR E-mail Capture - Grand Gulf - Official RAI for Relief Request GG-ISI-021 Associated with Fourth Interval Inservice Inspection Using Code Case N-702 ML17214A0992017-08-0202 August 2017 NRR E-mail Capture - Grand Gulf - Official RAIs for LAR Associated with One Cycle Extension of Appendix J Type a ILRT and Drywell Bypass Test Interval ML17142A2582017-05-19019 May 2017 Notification of NRC Design Bases Assurance Inspection (05000416/2017007) and Initial Request for Information ML16181A1122016-07-12012 July 2016 Request for Additional Information on Severe Accident Mitigation Alternatives for the Review of the Grand Gulf Nuclear Station, Unit 1, License Renewal Application Environmental Review ML16117A1862016-04-26026 April 2016 Entergy Fleet Relief Request EN-ISI-15-1 Request for Additional Information - 04/26/16 Email from R. Guzman to G. Davant (CAC Nos. MF7133-MF7136) ML16013A0642016-01-13013 January 2016 NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097) ML15341A1662015-12-0707 December 2015 NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349) ML15286A1082015-10-28028 October 2015 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application ML15261A5652015-09-24024 September 2015 Request for Additional Information Regarding Proposed Revision of Technical Specifications for Containment Leak Rate Testing ML15085A4932015-04-0606 April 2015 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application, Set 52 GNRO-2015/00002, Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5. Amendment Request Dated 12/9/20142015-03-27027 March 2015 Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5. Amendment Request Dated 12/9/2014 ML15036A5642015-02-18018 February 2015 Updated Fluence Methodology License Amendment Request Unacceptable with Opportunity to Supplement GNRO-2014/00079, Request for Additional Information Regarding Request for Adoption of TSTF-423, Revision 1, Change in Technical Specification End States (CE-NPSD-1186)2014-11-13013 November 2014 Request for Additional Information Regarding Request for Adoption of TSTF-423, Revision 1, Change in Technical Specification End States (CE-NPSD-1186) GNRO-2014/00076, Response to Request for Additional (RAI) Set 51 Dated September 11, 20142014-11-0606 November 2014 Response to Request for Additional (RAI) Set 51 Dated September 11, 2014 GNRO-2014/00031, Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/20142014-04-11011 April 2014 Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/2014 ML13318A8052014-01-0202 January 2014 Request for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application (TAC No. ME7493) - Set 50 ML13353A6572013-12-19019 December 2013 Licensed Operator Positive Fitness-For-Duty Test ML13345A1822013-12-19019 December 2013 Supplemental Information Needed for Acceptance of Licensing Action, Request to Revise Technical Specification to Allow Operation in Expanded Maximum Extended Load Line Limit Analysis Plus (Mellla+) Domain ML13316B9862013-11-25025 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML13263A2252013-11-21021 November 2013 LRA Draft RAI Set 48 ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13260A0062013-09-16016 September 2013 Email, Request for Additional Information, Round 3, Request to Revise Technical Specifications and Surveillance Requirements to Support Operation with a 24-Month Fuel Cycle in Accordance with Generic Letter 91-04 ML13238A2342013-09-12012 September 2013 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application (TAC No. ME7493) - Set 49 ML13227A3942013-08-28028 August 2013 Request for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application (TAC No. ME7493) - Set 47 ML13226A1902013-08-14014 August 2013 Request for Additional Information Email, Round 2, Request to Revise FOL to Delete 2.C(32), Partial Feedwater Heating, to Allow Plant to Operate with Final Feedwater Temperature Reduction at End of Fuel Cycle ML13207A1242013-07-30030 July 2013 Request for Additional Information, Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051) ML13149A3662013-05-29029 May 2013 Request for Additional Information Email Decommissioning Funding Status Report 2023-04-26
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 24, 2015 Vice President, Operations Entergy Operations, Inc.
Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150
SUBJECT:
GRAND GULF NUCLEAR STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS FOR CONTAINMENT LEAK RATE TESTING (TAC NO. MF6310)
Dear Sir or Madam:
The U.S. Nuclear Regulatory Commission staff has determined that additional information is needed to complete its review of the subject license amendment request for Grand Gulf Nuclear Station, Unit 1, submitted by Entergy Operations, Inc., dated May 27, 2015 (Agencywide Documents Access and Management System Accession No. ML15147A599). The enclosed questions constitute our request for additional information (RAI).
This RAI was discussed with Mr. Richard Scarbrough on September 17, 2015, and it was agreed that a response would be provided within 30 days of receipt of this letter. If circumstances result in the need to revise the requested response date, please contact Stephen Koenick at 301-415-6631 or Stephen.Koenick@nrc.gov.
Sincerely, W.::x; (,,
Alan B. Wang, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION GRAND GULF NUCLEAR STATION. UNIT 1.
LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS FOR CONTAINMENT LEAK RATE TESTING By application dated May 27, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15147A599), Entergy Operations, Inc. (Entergy or the licensee) requested changes to the technical specifications (TSs) for Grand Gulf Nuclear Station, Unit 1 (GGNS). The proposed changes would permit the existing Title 1O of the Code of Federal Regulations (10 CFR) Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," Type C Local Leak Rate Test (LLRT) frequency to be extended from 5 years up to 75 months on a permanent basis and a permanent reduction of 10 CFR 50, Appendix J, Type B and Type C test grace intervals.
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed to complete its review of the subject license amendment request (LAR).
The following questions constitute our request for additional information (RAI).
The regulation at 10 CFR Section 50.54(0) requires primary reactor containments for water-cooled power reactors to be subject to the requirements of Appendix J to 10 CFR Part 50, "Leakage Rate Testing of Containment of Water Cooled Nuclear Power Plants." Appendix J specifies containment leakage testing requirements, including the types of tests required to ensure the leak-tight integrity of the primary reactor containment, systems, and components that penetrate the containment. In addition, Appendix J discusses leakage rate acceptance criteria, test methodology, frequency of testing, and reporting requirements for each type of test.
Option B to 10 CFR Part 50, Appendix J, requires that test intervals for Type A, Type B, and Type C testing be determined by using a performance-based approach. Performance-based test intervals are based on consideration of operating history of the component and resulting risk from its failure. Performance-based for Appendix J refers to both the performance history necessary to extend test intervals and the criteria necessary to meet the requirements of Option B.
The NRC staff approved the Nuclear Energy Institute (NEI) 94-01, Revision 3, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J,"
(ADAMS Accession No. ML12221A202) by NRC final safety evaluation report dated June 8, 2012 (ADAMS Accession No. ML121030286). Accordingly, if a licensee considers an extended test interval of greater than 60 months, the review to establish the surveillance test intervals should include programmatic controls to provide additional assurance that the increased probability of component leakage is kept to a minimum.
In Attachment 1 of Entergy's application, "Evaluation of the Proposed Change," Section 3.4.2, "Use of Grace in the Deferral of Type Band Type C Testing," the licensee notes: "For routine scheduling of tests at intervals over 60 months, refer to the additional requirements of Section 11.3.2" (i.e., of NEI 94-01, Revision 3-A (ADAMS Accession No. ML12221A202)).
However, the evaluation does not address how the recommended "additional considerations" (i.e., "as-found tests," "schedule," and "review") of Section 11.3.2 were applied to the Type B and Type C LLRT data contained in LAR Attachment 1, Tables 3.3.1-1 and 3.3.1-2.
The staff requests that Entergy provide the information related to the programmatic controls to support extended Type C LLRT test intervals beyond 60 months.
The staff notes that on July 18, 2012, the NRC approved License Amendment No. 191 (ADAMS Accession No. ML121210020) for GGNS to increase the maximum steady state reactor core power level by approximately 15 percent from the original licensed thermal power level of 3,833 megawatt thermal (i.e., extended power uprate (EPU)). The license was also amended to include a new License Condition 2.C.(44), which states, in part, that leak rate tests associated with surveillance requirements required by TS 5.5.12 are not required to be performed until their next scheduled performance dates.
License Condition 2.C.(44) states that the leak rate tests required in refueling outage RF-18 (i.e., fall of 2012) were to be performed at the EPU calculated peak containment pressure or within the EPU drywell bypass leakage limits, as appropriate. License Amendment No. 191 changed the license basis "Pa" of 11.5 pounds per square inch gauge (psig) to the current license basis (CLB) "Pa" of 14.8 psig, as reflected in the current TS 5.5.12.
The staff requests additional information regarding the LLRT Pa values used to perform Type B and Type C tests contained in LAR Attachment 1, Table 3.3.1-1, "Types Band C LLRT Combined As-Found/As-Left Trend Summary."
- 1) How many of the 78 component Type B tests and 151 component Type C tests were performed at the CLB Pa value of 14.8 psig during 2012 (RF-18) and 2014 (RF-19)?
- 2) Were any of the Type B and Type C component tests performed at the CLB Pa value of 14.8 psig before RF-18 (2012)?
- 3) How many Type B penetration tests and Type C containment isolation valve tests have yet to be performed at the CLB Pa value of 14.8 psig?
- 4) When was the last 10 CFR 50, Appendix J, Type A, ILRT performed on the containment at GGNS? What was the ILRT leakage (i.e., total of Type A+B+C) rate for this ILRT?
What was the range of the containment internal test pressure, Pa. during this ILRT?
- 5) The last paragraph of LAR Section 3.3.1, Attachment 1 (page 11 of 26), reads:
Table 3.3.1-1 provides the LLRT data trend summaries for GGNS since 2005 and encompasses previous ILRTs." This would imply that more than one ILRT was performed between the years of 2005 and 2014. If more than one ILRT was performed
during this timeframe, please provide the ILRT leakage rate and the range of the containment internal test pressure, Pa, recorded during the ILRT(s) performed.
The staff notes that an e-mail from Entergy to the NRC dated August 24, 2011 (ADAMS Accession No. ML112370085), predicted an increase in the total Type B + Type C leakage rate of 13. 75 percent (i.e., 0.182 + 0.160), due to the change in the license basis "Pa" of 11.5 psig to the CLB "Pa" of 14.8 psig. Upon review and analysis of the data contained in LAR Attachment 1, Table 3.3.1-1, the staff notes that the aggregate "AF Min Path" Type B +Type C LLRT leakage has gone up by 65 percent since the NRC issued License Amendment No. 191.
{(5918 + 12885 + 18984 + 18057) + 4} + {(24453+21595) + 2} = 1.65 Performing a similar calculation, larger ratios of 2.57 for the "AL Max Path" and 2.43 for the "AL Min Path" are obtained from the data contained in Table 3.3.3-1 of the LAR.
The staff requests that Entergy provide an explanation of these ratios in light of the GGNS prediction.
LAR Attachment 1 (page 17 of 26), Section 3.4.1, "Limitations and Conditions Applicable to NEI 94-01, Revision 3-A," second paragraph of "Response to Condition 2, ISSUE 1," reads, in part:
When the potential leakage understatement adjusted leak rate total for those Type C components being tested on a 75-month extended interval is summed with the non-adjusted total of those Type C components being tested at less than the 75-month interval and the total of the Type B tested components, if the MNPLR is greaterthan the GGNS administrative leakage summation limit of 0.50 La, but less than the regulatory limit of 0.6 La, then an analysis and corrective action plan shall be prepared to restore the leakage summation value to less than the GGNS administrative leakage limit.
This paragraph could be interpreted to mean that a component tested at 70 months would not be adjusted for the understatement adjustment factor of 1.25, which would not be consistent with the intent of NEI 94-01, Revision 3-A. Please clarify the meaning of the cited paragraph.
NEI 94-01, Revision 3-A, Section 11.3.2, reads, in part:
If a licensee considers extended test intervals of greater than 60 months for a Type B or a Type C tested component, the review to establish surveillance test intervals should include the additional considerations:
- As-found Tests - In order to provide additional assurance that the increased probability of component leakage is kept to a minimum, and is reasonably within the envelope of industry data, a licensee should consider requiring three successive periodic as-found tests to determine adequate performance.
LAR Attachment 1 (page 15 of 26), Section 3.3.2, "Type B and Type C Tested Components on Extended Intervals," reads:
The percentage of the total number of GGNS Type B tested components (78) that are on 120 month extended performance-based test interval is 65%.
The percentage of the total number of GGNS Type C tested components (151) that are on 60 month extended performance-based test interval is 58%.
GGNS's May 27, 2015, proposed amendment will change the licensing basis for the plant by referencing NEI 94-01, Revision 3-A, in TS 5.5.12, "10 CFR 50, Appendix J, Testing Program."
Per the above, Section 11.3.2 of NEI 94-01, Revision 3-A, requires at least two successive tests to be successful at the CLB Pa value of 14.8 psig to extend Type Band Type C test intervals beyond 60 months.
- a. Does Entergy plan to re-baseline the subset (i.e., 65 percent of 78) of GGNS Containment Type B penetrations currently on 120-month extended performance-based test interval at the EPU peak containment pressure of 14.8 psig?
Will Entergy use the proposed licensing basis criteria of at least two successive, successful Type B penetration tests before increasing the test interval frequency beyond 60 months for this subset of individual containment penetrations?
- b. Does Entergy plan to re-baseline the subset (i.e., 58 percent of 121) of GGNS Containment Type C containment isolation valve penetrations currently on 60-month extended performance-based test interval at the EPU peak containment pressure of 14.8 psig?
Will Entergy use the proposed licensing basis criteria of at least two successive, successful Type C containment isolation valve penetration tests before increasing the test interval frequency beyond 60 months for this subset of individual containment penetrations?
LAR Table 3.3.1-2, "Types Band C LLRT Program Implementation Review," Attachment 1 (page 13 of 26), contains a listing of the respective containment isolation valve LLRT failures from the last two refueling outages (RF-18 in 2012 and RF-19 in 2014):
- 1) With respect to the "Administrative Limit SCCM" column of Table 3.3.1-2, the staff requests clarification for its safety evaluation as to whether the GGNS 10 CFR 50,
Appendix J, Testing Program, already contains individual component administrative limits that are constrained so as to achieve the GGNS administrative summation limit of 0.50 La.
- 2) LAR Section 3.3.2, "Type Band Type C Tested Components on Extended Intervals,"
reads: "The percentage of the total number of GGNS Type B tested components (78) that are on 120-month extended performance-based test interval is 65%." Based on this, one could conclude that 35 percent of the total population of Type B penetrations did not successfully pass two consecutive Type B tests without failure. However, Table 3.3.1-2 does not list any failures of Type B penetration tests for the two most recent GGNS refueling outages (RF-18 and RF-19). The staff requests that Entergy provide the implied additional historical information about the Type B test failures experienced at GGNS since 2005.
The staff notes that NEI 94-01, Revision 3-A, Section 11.3.1, "Performance Factors," indicates that prior to determining and implementing extended test intervals for Type B and Type C components, an assessment of the plant's containment penetration and valve performance should be performed and documented. Factors that should be considered during the assessment include, but are not limited to: "past component performance"; "service"; "design";
"safety impact"; and "cause determination". However, the technical evaluation section of the LAR does not address how these factors will be incorporated into the GGNS plant-specific 10 CFR 50, Appendix J, Testing Program. The staff requests that Entergy provide the details of how GGNS considered, or plans to consider, these factors in its 10 CFR 50, Appendix J, Testing Program.
ML15261A565 OFFICE DORL/LPLIV-2/PM DORL/LPLIV-2/LA DORL/LPLIV-2/BC DORL/LPLIV-2/PM NAME SKoenick (LRonewicz for) PBlechman MKhanna (SKoenick for) AWang DATE 9/21/2015 9/21/2015 9/23/2015 9/24/2015