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MONTHYEARML0633203662006-11-28028 November 2006 Revised Notice of Meeting with Entergy Operations, Inc./Grand Gulf Nuclear Station, Unit 1 to Present Methodology for Applying and Implementing Risk-Informed Inservice Inspection Program Via American Society of Mechanical Engineers Project stage: Meeting ML0634500682006-12-0505 December 2006 12/5/06 Public Meeting Handout from Entergy/Epri Re GGNS Application of N-716 Project stage: Meeting ML0634605652006-12-19019 December 2006 12/5/2006 Summary of Meeting W/Entergy Operations, Inc. & GGNS, Unit 1 Methodology for Applying & Implementing the Risk-informed Inservice Inspection Program Via ASME Code Case N-716 at GGNS Project stage: Meeting ML0703102402007-02-0707 February 2007 Acceptance Review Request for Alternative GG-ISI-002 (Pilot Request), Request to Use ASME Code Case N-716 Project stage: Acceptance Review ML0711702462007-04-12012 April 2007 E-Mail from G. Davant, Entergy Operations, Inc. to B. Vaidya, NRR/DORL/LPL4, Enclosing Two Sets of Responses to Request for Information Re GG-ISI-002 (TAC No. MD3044) - E-Mail Project stage: Response to RAI ML0711702542007-04-12012 April 2007 Set 1 of Response to Request for Information Re GG-ISI-002 Code Case N-716 - Enclosure to 4/12/07 to E-Mail from G. Davant, Entergy Operations, Inc. to B. Vaidya, NRR/DORL/LPL4 Project stage: Response to RAI ML0711702612007-04-12012 April 2007 Set 2 of Response to Request for Information Re GG-ISI-002 Code Case N-716 - Enclosure to 4/12/07 to E-Mail from G. Davant, Entergy Operations, Inc. to B. Vaidya, NRR/DORL/LPL4 Project stage: Response to RAI ML0709604412007-04-20020 April 2007 Notice of Meeting with Indiana Michigan Power Co & Entergy Operations, Inc. to Discuss Risk-Informed Inservice Inspection Program Via ASME Code Case N-716 Project stage: Meeting ML0711604152007-04-25025 April 2007 Additional Issues to Discuss in the 5/7/07 Meeting Project stage: Meeting ML0712902032007-05-17017 May 2007 Summary of Meeting with Entergy Operations, Inc. & Indiana Michigan Power Co. Risk-informed Inservice Inspection Program/Code Case N-716 at Grand Gulf Ns & Donald C. Cook Np, Units 1 & 2 (TAC MD3044, MD3137 & MD3138) Project stage: Meeting CNRO-2007-00022, Request for Alternative GG-ISI-002, Response to Requests for Additional Information2007-05-23023 May 2007 Request for Alternative GG-ISI-002, Response to Requests for Additional Information Project stage: Response to RAI ML0716504412007-06-14014 June 2007 6/14/2007 E-mail from W. Brice, Entergy Operations, Inc. to B. Vaidya, NRR/DORL/LPL4 - Draft Responses to Requests for Additional Information, Questions 2a and 2b, for Relief Request GG-ISI-002 Project stage: Draft Response to RAI ML0716504462007-06-14014 June 2007 6/14/2007 Draft Responses to Requests for Additional Information, Questions 2a and 2b, for Relief Request GG-ISI-002 from W. Brice, Entergy Operations, Inc. Project stage: Draft Response to RAI ML0717200182007-06-20020 June 2007 6/20/07 E-Mail from G. Davant, Entergy, to B. Vaidya, NRR/DORL/LPL4 - Enclosing Draft Response to NRC Request for Additional Information Re GG-ISI-002, Code Case N-716 Project stage: Draft Response to RAI ML0717200252007-06-20020 June 2007 Draft Response to NRC Request for Additional Information Re GG-ISI-002, Code Case N-716 Project stage: Draft Response to RAI CNRO-2007-00026, Request for Alternative GG-ISI-002, Response to Request for Additional Information2007-07-0202 July 2007 Request for Alternative GG-ISI-002, Response to Request for Additional Information Project stage: Response to RAI CNRO-2007-00034, Request for Alternative GG-ISI-002, Response to Request for Additional Information2007-08-27027 August 2007 Request for Alternative GG-ISI-002, Response to Request for Additional Information Project stage: Response to RAI ML0724300052007-09-21021 September 2007 Request for Alternative GG-ISI-002 - to Implement Risk-Informed Inservice Inspection Program Based on the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-716 Project stage: Other 2007-04-25
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MONTHYEARML24109A2722024-04-18018 April 2024 Information Request, Security IR 2024401 ML22034A3952022-02-16016 February 2022 Enclosure 3 - IP 96001 CY2021 - IR 8 Baseline Inspection Completion ML22034A3972022-02-16016 February 2022 Enclosure 2 - IP 92707 CY2021 - IR 8 Baseline Inspection Completion ML22034A3992022-02-16016 February 2022 Enclosure 1 - IP 71130.03 Cy 2021 - IR 8 Baseline Inspection Completion ML21354A7602021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 15 of 18 ML21354A7462021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 1 of 18 ML21354A7492021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 4 of 18 ML21354A7562021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 11 of 18 ML21354A7572021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 12 of 18 ML21354A7592021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 14 of 18 ML21354A7612021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 16 of 18 ML21354A7632021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 18 of 18 ML21021A2832021-01-21021 January 2021 FAQ 20-06: GGNS Turbine Controls Upgrade Scrams One-Time Exemption ML21028A3872020-12-22022 December 2020 FAQ 20-06 GGNS Scram - Tentatively Approved ML21012A3982020-12-10010 December 2020 Enc 1 - Grand Gulf Nuclear Station - Regulatory Conference (Participant List) Dec '20 - (1850183) ML20329A1452020-11-20020 November 2020 Terrapower'S QAPD Preliminary Questions ML17235B1482017-08-23023 August 2017 U.S. Nuclear Regulatory Commission - Tornado Missile Risk Evaluator (TMRE) Methodology Topics and Methodology Feedback ML17207A0962017-07-26026 July 2017 FAQ 17-01: Grand Gulf June 2016 Power Change (Final NRC Response) CNRO-2016-00024, Entergy - Form 10-K for Fiscal Year Ended December 31, 20152016-12-20020 December 2016 Entergy - Form 10-K for Fiscal Year Ended December 31, 2015 ML15344A4522015-12-14014 December 2015 50 54(p) Review for Grand Gulf ML15014A1602015-01-14014 January 2015 Attachment 2 - NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML15014A1532015-01-14014 January 2015 Attachment 1- NEI Comments on NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML13213A2352013-07-16016 July 2013 NRC Staff Understanding of Information to Be Provided (2) ML12157A1762012-05-23023 May 2012 GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton, - Attachment B Labeled Enercon Study Assessing Groundwater Drawdown and Related Impacts. ML12157A2582012-05-23023 May 2012 Attachment 14 to GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Hydrology Information Needs for the Grand Gulf Nuclear Station (GGNS) License Renewal Environmental Revie ML12157A2612012-05-23023 May 2012 Attachment 16 to GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Ford - Grand Gulf Nuclear Site Needs List for Hydrology ML12157A4922012-05-23023 May 2012 Attachment 40 to GNRO-2012/00039 - Federal Migratory Bird Depredation Permit (Provided as Attachment a on the Terrestrial Ecology Response Cd) ML12157A1772012-05-23023 May 2012 GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Attachment D Labeled Well Permits. ML12157A1782012-05-23023 May 2012 GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Attachment E Labeled 2005, 2008, 2009 and 2010 Annual Water Use Reports. ML12157A1752012-05-23023 May 2012 GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton, - Attachment a Labeled Radial Collector Well Data. ML1208001572012-03-15015 March 2012 NRC ATWS March 2012 4408 Turbine Trip ML1208001632012-03-15015 March 2012 Simulator Parameter Designations ML1207905672012-03-15015 March 2012 NRC ATWS (4408 Mwt Cycle 19 Turbine Trip) ML1208001552012-03-15015 March 2012 NRC ATWS Mar 2012 4408 MSIV Closure ML1208001582012-03-13013 March 2012 ATWS 4408 Turbine Trip Report ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML11356A1852012-01-19019 January 2012 Enclosure 3: Request for List of Federal Protected Species within the Area Under Evaluation for the Grand Gulf Nuclear Station Unit 1, LRA Review ML0930806782009-11-0404 November 2009 Entergy, Grand Gulf Nuclear Station, Supporting Affidavit from Edward D. Scroll for the Steam Dryer Presentation for 11/12/2009 Meeting - (ME2423) ML1002209462009-03-30030 March 2009 Data Sheet for Grand Gulf Station, Checklist for Step 1 Review ML0823900082008-09-0404 September 2008 Enclosure 4 - FAQ Log July 2008 ML0806704192008-03-0707 March 2008 CDBI Findings ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions CNRO-2007-00038, Entergy Operations, Inc. - Proof of Financial Protection (10 CFR 140.15)2007-09-24024 September 2007 Entergy Operations, Inc. - Proof of Financial Protection (10 CFR 140.15) ML0726303192007-09-14014 September 2007 P. Paquin Ltr Amendment to Certificate of Compliance No. 6574 for the Model No. 3-82B Package (TAC L24116)/ Register User List ML0726301142007-09-14014 September 2007 / P. Paquin Ltr Amendment to Certificate of Compliance No. 9208 for the Model No. 10-142B Package (TAC L24117)/S121170 GNRO-2007/00061, (Ggns), Supplement to Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints2007-09-0505 September 2007 (Ggns), Supplement to Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints ML0723203212007-08-20020 August 2007 GG-05-2007-DRAFT Outline; NUREG-1021, Revision 9 ML0716504462007-06-14014 June 2007 6/14/2007 Draft Responses to Requests for Additional Information, Questions 2a and 2b, for Relief Request GG-ISI-002 from W. Brice, Entergy Operations, Inc. ML0711702542007-04-12012 April 2007 Set 1 of Response to Request for Information Re GG-ISI-002 Code Case N-716 - Enclosure to 4/12/07 to E-Mail from G. Davant, Entergy Operations, Inc. to B. Vaidya, NRR/DORL/LPL4 ML0711702612007-04-12012 April 2007 Set 2 of Response to Request for Information Re GG-ISI-002 Code Case N-716 - Enclosure to 4/12/07 to E-Mail from G. Davant, Entergy Operations, Inc. to B. Vaidya, NRR/DORL/LPL4 2024-04-18
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DRAFT a) The N-716 code case Section 2(5) does not include a LERF guideline analogous to the CDF guideline, and Table 3-1 in your submittal includes a column for CDF but not for LERF. Please explain why a LERF guideline is not included as a guideline in parallel with CDF.
Response N-716 provides five criteria for determining the classification of welds. These criteria are specifically designed to address CDF considerations and LERF considerations [e.g., break exclusion region (BER)]. Additionally, Section 4 of the code case was also developed to specifically address CDF and LERF considerations. In particular, Section 4(d) (LOCA - outside containment) and Section 4(e) (BER) are important requirements of the Case, from a LERF perspective. As such, Sections 2 and 4 taken together are used to define the revised inspection program (i.e., the number and locations for inspection). The CDF guideline for PRA internal flood segments was added to provide additional margin, as applicable, to the initial scope of HSS welds (i.e., a "belts and suspenders" approach). As discussed in the code case whitepaper, N-716 is based upon lessons learned from a large number of risk-informed applications (e.g., RI-ISI, RI-BER). With respect to defining the scope (e.g., HSS vs. LSS), these insights include both the impact on CDF and LERF (e.g., RI-BER insights). In the whitepaper, eight plants (4 BWRs and 4 PWRs) were compared to the N-716 criteria; N-716 was shown to provide for more inspections than traditional RI-ISI approaches even when the criterion of Section 2(5) is not used. Additionally, as a final step, after Sections 2 and 4 have been completed, N-716 requires an assessment of the impact on plant risk, which includes both CDF and LERF. This change-in-risk assessment includes so-called "risk category 6 and 7" locations, which are not required to be included in the EPRI RI-ISI delta risk assessment. Risk acceptance criteria for these metrics are consistent with other RI-ISI applications and meet Regulatory Guide (RG) 1.174 criteria. Irrespective of the above, GGNS reviewed LSS Class 2 piping to confirm that, in addition to having a CDF contribution of less than 1E-06, it also has a LERF contribution of less than 1E-07.
b) Please provide a discussion justifying the guideline value for CDF selected in Section 2(5) in N-716 (i.e., 1E-6/year).
Response N-716 provides five criteria for determining the classification of welds. The CDF guideline was added to provide additional margin, as applicable, to the initial scope of HSS welds (i.e., a "belts and suspenders" approach). As discussed in the code case whitepaper, N-716 is based upon lessons learned from a large number of risk-informed applications (e.g., RI-ISI, RI-BER). In the whitepaper, eight plants (4 BWRs, 4 PWRs) were compared to the N-716 criteria and N-716 was shown to provide for more inspections than traditional RI-ISI approaches even when the criterion of Section 2(a)(5) is not used.
DRAFT The criterion of Section 2(a)(5) of N-716 provides an additional criterion that can only potentially increase the scope of HSS locations (i.e., will only increase the number of inspections). Although, the criteria of Section 2(a) were created based on the large number of risk-informed applications performed to date, Section 2(a)5 was added as a defense-in-depth measure to N-716 to provide a method of ensuring that any plant-specific locations that are important to safety are identified. Therefore, it is important to use a value that is low enough to capture any significant risk, but high enough so that valuable resources are not spent for minimal or no appreciable capture of risk. According to the guidelines in RG 1.174, plant changes (permitting the reallocation of resources) that increase risk less than 1E-6/year would normally be considered acceptable as long as the other principles are satisfied. This indicates resources directed toward risk represented by CDFs of 1E-6/year or less may be more effectively applied elsewhere.
Adopting RI-ISI programs permits a reduction in inspection by focusing inspections on the more important locations while, at the same time, maintaining or improving public health and safety. Use of a technically adequate, plant-specific flooding evaluation to identify relatively important locations provides confidence that the inspection will be focused on the more important locations. Selecting the guideline value of 1E-6/year is consistent with the premises that resources allocated toward risks less than 1E-6/year may be more effectively applied elsewhere.
From a practical perspective, the criterion used in Section 2(a)(5) has two potential impacts. 1. Class 2 Piping Any piping that has inspections removed per this criterion is required to be assessed as to its impact on risk. This risk impact analysis is conducted on an individual system basis, which includes the cumulative effect of piping currently being inspected. The risk acceptance criteria on a system basis are defined as 1E-07 (CDF) and 1E-08 (LERF). If the risk acceptance criteria are not met, additional inspections need to be defined until these criteria are met [N-716 Section 5(d)]. Therefore, regardless of the number of segments (or inspections) that fall below this criterion, unacceptable risk changes will not occur. Conceivably, the risk impact analysis could be conducted without the benefit of this criterion and shown to have acceptable changes in plant risk. However, apart from the acceptability of the risk impact analysis, if risk outliers exist in Class 2 piping [e.g., piping that exceeds Section 2(a)(5) criterion], N-716 would require that this piping be added to the scope of HSS piping and subjected to inspection.
DRAFT 2. Class 3 / NNS Piping Currently, there are no Section XI NDE requirements for this piping. As such, use of this criterion, regardless of its value, can only result in a reduction in plant risk. These additional inspections will be imposed on the piping identified by the criterion of Section 2(a)(5) and cannot be used to reduce inspections in other HSS piping [N-716 Section 4(b)]. Finally, RI-ISI can be applied on a partial scope basis. That is, many plants have applied RI-ISI to Class 1 piping only. Thus, these plants have not witnessed the additional safety benefit of identifying and inspecting Class 2, 3 or NNS piping per the criterion of Section 2(a)(5).