Letter Sequence Supplement |
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TAC:ME2531, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
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MONTHYEARML0931404632009-11-0303 November 2009 License Amendment Request Regarding Power Range Neutron Monitoring System Upgrade Project stage: Request ML0934100662009-12-10010 December 2009 Acceptance Review of License Amendment Request for Power Range Neutron Monitoring System - Includes Revised Schedule for Completion Based on Late Submittal Project stage: Acceptance Review ML1004308252010-02-0808 February 2010 Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI ML1010902452010-04-22022 April 2010 Request for Additional Information Power Range Neutron Monitoring System Project stage: RAI ML1014100942010-05-18018 May 2010 Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI ML1014704032010-05-25025 May 2010 Affidavit for 5/25/10 NRC Meeting to Discuss Response to Requests for Additional Information on License Amendment Request for Digital Power Range Neutron Monitoring System Project stage: Response to RAI GNRO-2010/00040, Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System2010-06-0303 June 2010 Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI ML1018001492010-06-18018 June 2010 Schedule for Responding to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Request ML1017904372010-06-30030 June 2010 0000-0102-0888-RI, Plant-Specific Responses Required by Numac Prnm Retrofit Plus Option III Stability Trip Function Topical Report, (NEDC-3241OP-A) Project stage: Other ML1021500292010-07-29029 July 2010 Responses to NRC Request for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI GNRO-2010/00064, Response to NRC Request for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System2010-09-29029 September 2010 Response to NRC Request for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI GNRO-2010/00075, Response to NRC Request for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System2010-12-13013 December 2010 Response to NRC Request for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI GNRO-2010/00070, Response to NRC Request for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System2010-12-14014 December 2010 Response to NRC Request for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI ML1111704322011-04-27027 April 2011 Request for Additional Information, Round 4, License Amendment Request for Power Range Neutron Monitoring System Project stage: RAI ML1111704242011-04-27027 April 2011 E-mail, Request for Additional Information, Round 4, License Amendment Request for Power Range Neutron Monitoring System Project stage: RAI GNRO-2011/00032, Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System2011-05-0303 May 2011 Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI ML1113204932011-05-12012 May 2011 E-mail, Request for Additional Information, Round 5, License Amendment Request for Power Range Neutron Monitoring System Project stage: RAI GNRO-2011/00038, Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System2011-05-16016 May 2011 Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI GNRO-2011/00039, Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System2011-05-26026 May 2011 Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI GNRO-2011/00042, Responses to NRC Requests for Additional Information Re License Amendment Request for Power Range Neutron Monitoring System2011-05-31031 May 2011 Responses to NRC Requests for Additional Information Re License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI ML1113906562011-06-0202 June 2011 Request for Withholding Information from Public Disclosure, 5/11/2011 Affidavit Executed by J. Harrison, GE-Hitachi Nuclear Energy Americas LLC, Attachment 1 to GNRO-2011/00038 Project stage: Withholding Request Acceptance ML1113905962011-06-0202 June 2011 Request for Withholding Information from Public Disclosure, 4/28/2011 Affidavit Executed by E. Schrull, GE-Hitachi Nuclear Energy Americas LLC, Attachment 1 to GNRO-2011/00032 Project stage: Withholding Request Acceptance GNRO-2011/00044, Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System2011-06-13013 June 2011 Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI ML1117402132011-06-23023 June 2011 Email, Request for Additional Information, Round 6, License Amendment Request for Power Range Neutron Monitoring System Project stage: RAI GNRO-2011/00045, Supplemental Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System2011-06-28028 June 2011 Supplemental Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Supplement GNRO-2011/00057, Response to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System2011-07-22022 July 2011 Response to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI GNRO-2011/00066, Response to NRC Request for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System2011-09-28028 September 2011 Response to NRC Request for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI GNRO-2011/00089, Response to NRC Request for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System2011-10-18018 October 2011 Response to NRC Request for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI GNRO-2011/00090, Supplemental Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System (TAC No. ME2531) - Software Evaluation Report2011-10-26026 October 2011 Supplemental Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System (TAC No. ME2531) - Software Evaluation Report Project stage: Supplement GNRO-2011/00091, Supplemental Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System (TAC No. ME2531) V&V Summary Test Report2011-11-0808 November 2011 Supplemental Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System (TAC No. ME2531) V&V Summary Test Report Project stage: Supplement GNRO-2011/00110, Supplemental Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System (TAC No. ME2531) V&V Summary Test Report2011-12-0101 December 2011 Supplemental Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System (TAC No. ME2531) V&V Summary Test Report Project stage: Supplement ML1204406602012-02-27027 February 2012 Request for Withholding Information from Public Disclosure, 11/29/2011 Affidavit Executed by J. Harrison, GE-Hitachi Nuclear Energy Americas LLC, Attachment 1 to GNRO-2011/00110 Project stage: Withholding Request Acceptance ML1204406382012-02-27027 February 2012 Request for Withholding Information from Public Disclosure, 9/22/2011 Affidavit Executed by J. Harrison, GE-Hitachi Nuclear Energy Americas LLC, Attachment 1 to GNRO-2011/00066 Project stage: Withholding Request Acceptance ML1204406532012-02-27027 February 2012 Request for Withholding Information from Public Disclosure, 11/3/2011 Affidavit Executed by E. Schrull, GE-Hitachi Nuclear Energy Americas LLC, Attachment 1 to GNRO-2011/00091 Project stage: Withholding Request Acceptance ML1204406022012-02-27027 February 2012 Request for Withholding Information from Public Disclosure, 5/19/2011 Affidavit Executed by J. Harrison, GE-Hitachi Nuclear Energy Americas LLC, Attachment 1 to GNRO-2011/00039 Project stage: Withholding Request Acceptance ML1204406162012-02-27027 February 2012 Request for Withholding Information from Public Disclosure, 5/25/2011 Affidavit Executed by E. Schrull, GE-Hitachi Nuclear Energy Americas LLC, Attachment 1 to GNRO-2011/00042 Project stage: Withholding Request Acceptance ML1204406232012-02-27027 February 2012 Request for Withholding Information from Public Disclosure, 6/23/2011 Affidavit Executed by E. Schrull, GE-Hitachi Nuclear Energy Americas LLC, Attachment 1 to GNRO-2011/00045 Project stage: Withholding Request Acceptance ML1204406272012-02-27027 February 2012 Request for Withholding Information from Public Disclosure, 7/21/2011 Affidavit Executed by E. Schrull, GE-Hitachi Nuclear Energy Americas LLC, Attachment 1 to GNRO-2011/00057 Project stage: Withholding Request Acceptance ML1204406462012-02-27027 February 2012 Request for Withholding Information from Public Disclosure, 10/20/2011 Affidavit Executed by E. Schrull, GE-Hitachi Nuclear Energy Americas LLC, Attachment 1 to GNRO-2011/00090 Project stage: Withholding Request Acceptance ML1210701392012-04-0202 April 2012 Email Correction to Technical Specification Table 3.3.1-1 Project stage: Other ML1209403902012-04-16016 April 2012 Correction to Technical Specification (TS) Page 3.3-6 for Amendment No. 188, Revise TSs to Reflect Installation of Digital GE-Hitachi Nuclear Measurement Analysis and Control Power Range Neutron Monitoring System Project stage: Other GNRO-2012/00031, Supplemental Information - License Conditions, Extended Power Uprate2012-04-26026 April 2012 Supplemental Information - License Conditions, Extended Power Uprate Project stage: Supplement GNRO-2013/00031, Corrected Response to NRC Request for Additional Information Regarding License Amendment Request for Power Range Neutron Monitoring System2013-05-22022 May 2013 Corrected Response to NRC Request for Additional Information Regarding License Amendment Request for Power Range Neutron Monitoring System Project stage: Response to RAI ML13149A2252013-06-24024 June 2013 Correction to Safety Evaluation Page 60 (Redacted) for Amendment No. 188, Revise TSs to Reflect Installation of Digital GE-Hitachi Nuclear Measurement Analysis and Control Power Range Neutron Monitoring System Project stage: Approval 2011-04-27
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Category:Letter type:GNRO
MONTHYEARGNRO-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 GNRO-2021/00037, 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 12021-11-30030 November 2021 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 1 GNRO-2021/00017, Notification of Readiness for Supplemental Inspection2021-06-22022 June 2021 Notification of Readiness for Supplemental Inspection GNRO-2021/00014, Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency2021-06-0101 June 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency GNRO-2021/00015, Annual Radioactive Effluent Release Report2021-04-28028 April 2021 Annual Radioactive Effluent Release Report GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021 Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020 GNRO-2021/00012, Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.22062021-04-13013 April 2021 Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.2206 GNRO-2020/00045, 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis2020-12-16016 December 2020 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2020/00034, Notification of Spent Fuel Cask Use2020-10-0808 October 2020 Notification of Spent Fuel Cask Use GNRO-2020/00033, Response to NRC Integrated Inspection Report 05000416/20200022020-09-10010 September 2020 Response to NRC Integrated Inspection Report 05000416/2020002 GNRO-2020/00029, Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 20202020-08-18018 August 2020 Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 2020 GNRO-2020/00022, Report of Technical Specification Bases Changes2020-07-21021 July 2020 Report of Technical Specification Bases Changes GNRO-2020/00027, Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-07-16016 July 2020 Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00023, Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-06-26026 June 2020 Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2020/00020, Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-05-0505 May 2020 Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00018, Annual Radiological Effluent Release Report2020-04-30030 April 2020 Annual Radiological Effluent Release Report GNRO-2020/00016, Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.22062020-04-16016 April 2020 Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.2206 GNRO-2020/00015, Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test2020-04-0707 April 2020 Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test GNRO-2020/00007, Spent Fuel Storage Radioactive Effluent Release Report for 20192020-02-20020 February 2020 Spent Fuel Storage Radioactive Effluent Release Report for 2019 GNRO-2020/00006, License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-02-19019 February 2020 License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2019/00052, Report of Changes and Errors to 10 CFR 50.46 Analysis2019-12-13013 December 2019 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2019/00051, Notification of Readiness of 92723 Inspection2019-12-11011 December 2019 Notification of Readiness of 92723 Inspection GNRO-2019/00045, Emergency Plan, Revision 792019-10-29029 October 2019 Emergency Plan, Revision 79 GNRO-2019/00037, Notification of Spent Fuel Cask Use2019-09-20020 September 2019 Notification of Spent Fuel Cask Use GNRO-2019/00036, Correction to Gnro 2019-00017 Emergency Plan Revision 782019-08-0808 August 2019 Correction to Gnro 2019-00017 Emergency Plan Revision 78 GNRO-2019/00027, Notification of Readiness of 95001 Supplemental Inspections2019-07-0303 July 2019 Notification of Readiness of 95001 Supplemental Inspections GNRO-2019/00031, Annual Report of Individual Monitoring - 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GNRO-2019/00026, Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval2019-05-0606 May 2019 Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval GNRO-2019/00024, Annual Radioactive Effluent Release Report2019-04-30030 April 2019 Annual Radioactive Effluent Release Report GNRO-2019/00020, Annual Radiological Operating Report (AREOR)2019-04-30030 April 2019 Annual Radiological Operating Report (AREOR) GNRO-2019/00022, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.22062019-04-22022 April 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 GNRO-2019/00017, Emergency Plan, Revision 782019-03-14014 March 2019 Emergency Plan, Revision 78 GNRO-2019/00014, Snubber Testing Program for Fourth Inspection Interval2019-03-13013 March 2019 Snubber Testing Program for Fourth Inspection Interval GNRO-2019/00012, Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2019-03-0606 March 2019 Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program GNRO-2019/00016, Spent Fuel Storage Radioactive Effluent Release Report for 20182019-02-21021 February 2019 Spent Fuel Storage Radioactive Effluent Release Report for 2018 GNRO-2019/00003, Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation2019-01-23023 January 2019 Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation GNRO-2018/00057, Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan2018-12-0404 December 2018 Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan GNRO-2018/00055, Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ...2018-11-30030 November 2018 Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ... GNRO-2018/00054, Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval2018-11-30030 November 2018 Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval GNRO-2018/00052, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information2018-10-24024 October 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information GNRO-2018/00051, Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-10-23023 October 2018 Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control GNRO-2018/00046, Submittal of 2018 Report of Changes and Errors to 10CFR50.462018-10-16016 October 2018 Submittal of 2018 Report of Changes and Errors to 10CFR50.46 GNRO-2018/00047, Submittal of 2018 Inservice Inspection Summary Report2018-10-16016 October 2018 Submittal of 2018 Inservice Inspection Summary Report GNRO-2018/00048, Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62018-10-10010 October 2018 Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 GNRO-2018/00042, Core Operating Limits Report Cycle 22, Revision 12018-09-18018 September 2018 Core Operating Limits Report Cycle 22, Revision 1 GNRO-2018/00043, Revised Offsite Dose Calculation Manual2018-09-18018 September 2018 Revised Offsite Dose Calculation Manual GNRO-2018/00039, Report of Technical Specification Bases Changes2018-08-20020 August 2018 Report of Technical Specification Bases Changes GNRO-2018/00040, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 20182018-08-20020 August 2018 Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 2018 2023-06-06
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Text
Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 Michael A. Krupa Director, Extended Power Uprate Grand Gulf Nuclear Station Tel. (601) 437-6684 GNRO-2012/00031 April 26, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Supplemental Information - License Conditions Extended Power Uprate Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCES:
- 1. Entergy Operations, Inc. letter to the NRC (GNRO-2010/00056),
License Amendment Request - Extended Power Uprate, September 8, 2010 (ADAMS Accession No. ML102660403)
- 2. NRC letter to Entergy Operations, Inc. dated March 28, 2012, Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment Re: Power Range Neutron Monitoring System Replacement (TAC NO. ME2531)
(Amendment 188)
Dear Sir or Madam:
Entergy submitted a license amendment request (LAR) for an extended power uprate (EPU) for Grand Gulf Nuclear Station, Unit 1 (GGNS) in Reference 1. The LAR included a proposed License Condition 45 to ensure that the EPU would not be implemented prior to NRC approval of the Power Range Neutron Monitoring System LAR, which had been submitted on November 3, 2009. The NRC has since approved this LAR with the issuance of Amendment 188 to the GGNS Operating License in Reference 2. Entergy requests that this proposed license condition be withdrawn as it is no longer required for the GGNS EPU.
With the withdrawal of the PRNMS license condition, the two of the other three proposed EPU license conditions (spent fuel storage configuration and steam dryer testing) may now be re-numbered. Proposed License Condition 44, dealing with leak rate testing, is not affected by the withdrawal of License Condition 45. A new mark-up of these license conditions reflecting the correct numbering is attached. In addition, the steam dryer license condition has been expanded based on subsequent feedback from the NRC. This is an administrative change.
GNRO-2012/00031 Page 2 of 2 No change is needed to the no significant hazards consideration included in the initial LAR (Reference 1) as a result of the administrative revision to certain pages of the TS mark-up.
There are no new commitments in this letter.
If you have any questions or require additional information, please contact Jerry Burford at 601-368-5755.
I declare under penalty of perjury that the foregoing is true and correct. Executed on April 26, 2012.
Sincerely, MAK/FGB Attachments:
- 1. Revised EPU License Conditions (Mark-up) cc: Mr. Elmo E. Collins, Jr. NRC Senior Resident Inspector Regional Administrator, Region IV Grand Gulf Nuclear Station U. S. Nuclear Regulatory Commission Port Gibson, MS 39150 612 East Lamar Blvd., Suite 400 Arlington, TX 76011-4125 U. S. Nuclear Regulatory Commission State Health Officer ATTN: Mr. A. B. Wang, NRR/DORL (w/2) Mississippi Department of Health ATTN: ADDRESSEE ONLY P. O. Box 1700 ATTN: Courier Delivery Only Jackson, MS 39215-1700 Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2378
Attachment 1 GNRO-2012/00031 Grand Gulf Nuclear Station Extended Power Uprate Revised EPU License Conditions (Mark-up) to GNRO-2012-00031 Page 1 of 5 Revised EPU License Conditions This letter provides a revised mark-up of the EPU license conditions to reflect an administrative change: that is, the renumbering of the subsequent proposed license conditions to reflect the withdrawal of the proposed EPU license condition requiring the implementation of the PRNMS.
With the approval of the PRNMS LAR, that license condition (proposed as 45) is no longer required. Two subsequent license conditions, one for spent fuel pool configuration and one for steam dryer testing, are to be renumbered 45 and 46. This change does not affect the proposed EPU License Condition 44 regarding leak rate testing. The revised mark-up is provided below. All three conditions have been included here for completeness; they are to be inserted into the GGNS OL immediately following License Condition 43 on page 16a.
(44) Leak rate tests associated with Surveillance Requirements (SR) 3.6.1.1.1, 3.6.1.3.5, and 3.6.1.3.9, as required by TS 5.5.12 and in accordance with 10 CFR 50, Appendix J, Option B, and SRs 3.6.5.1.1and 3.6.5.1.2 are not required to be performed until their next scheduled performance dates. The tests will be performed at the EPU calculated peak containment pressure or within EPU drywell bypass leakage limits, as appropriate.
(45) Through Cycle 19 or until the revised criticality safety analysis has been approved, whichever comes first, the storage cells in the GGNS SFP racks shall be categorized as either Unrestricted or Restricted.
(a) Unrestricted cells (Region I) are cells with a minimum panel B10 areal density greater than 0.0179 gm/cm2 and that have received an exposure less than 2.3E10 rads. Unrestricted cells may contain fuel assemblies up to the maximum k-infinity of 1.26 (cold core configuration).
(b) Restricted cells (Region II) are cells with either a minimum panel B10 areal density less than 0.0179 gm/cm2 or that have received an exposure in excess of 2.3E10 rads. Storage in Restricted cells shall not credit any Boraflex. Storage shall be controlled in a 10 of 16 configuration (see below). In addition, only fuel assemblies with a k-infinity of less than 1.21 (cold core configuration) may be stored in a Region II cell.
to GNRO-2012-00031 Page 2 of 5 Region II 4X4 Storage Configuration B B B
B B B
Fuel Assembly Storage Location B Location Physically Blocked to Prevent Storage (46) This license condition provides for monitoring, evaluating, and taking prompt action in response to potential adverse flow effects as a result of power uprate operation on plant structures, systems, and components (including verifying the continued structural integrity of the steam dryer) for power ascension from the CLTP (3898 MWt) to the EPU level of 4408 MWt (or 113 percent of CLTP or 115 percent of OLTP).
(a) The following requirements are placed on operation of the facility before and during the power ascension to 3898 MWt:
- 1. GGNS shall provide a Power Ascension Test (PAT) Plan for the Steam Dryer testing. This plan shall include:
- Criteria for comparison and evaluation of projected strain and acceleration with on-dryer instrument data.
- Acceptance limits developed for each on-dryer strain gauge and accelerometer.
- Tables of predicted dryer stresses at CLTP, strain amplitudes and PSDs at strain gauge locations, acceleration amplitudes and PSDs at accelerometer locations, and maximum stresses and locations.
The PAT plan shall provide correlations between measured accelerations and strains and the corresponding maximum stresses. The PAT plan shall be submitted to the NRC Project Manager no later than 10 days before start-up.
- 2. GGNS shall monitor the main steam line (MSL) strain gages and on-dryer instrumentation at a minimum of three power levels up to 3898 MWt. Based on a comparison of projected and measured strains and accelerations, GGNS will assess whether the dryer acoustic and structural models have adequately captured the response significant to peak stress projections. If to GNRO-2012-00031 Page 3 of 5 the measured strains and accelerations are not within the CLTP acceptance limits, the new measured data will be used to re-perform the full structural re-analysis for the purposes of generating modified EPU acceptance limits.
- 3. GGNS shall provide a summary of the data and evaluation of predicted and measured pressures, strains, and accelerations. This data will include the GGNS-specific bias and uncertainty data and transfer function, revised peak stress table and any revised acceptance limits. The predicted pressures shall include those using both PBLE methods (that is, Method 1 using on-dryer data, and Method 2 using MSL data). It shall be provided to the NRC Project Manager upon completion of the evaluation. GGNS shall not increase power above 3898 MWt until the NRC PM notifies GGNS the NRC accepts the evaluation or NRC questions regarding the evaluation have been addressed.
If no questions are identified within 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> after the NRC receives the evaluation, power ascension may continue.
(b) The following requirements are placed on operation of the facility during the initial power ascension from 3898 MWt to the approved EPU level (4408 MWt):
- 1. GGNS shall increase power in increments of approximately 102 MWt, hold the facility at approximately steady state conditions and collect data from available main steam line (MSL) strain gages and available on-dryer instrumentation. This data will be evaluated, including the comparison of measured dryer strains and accelerations to acceptance limits and the comparison of predicted dryer loads based on MSL strain gage data to acceptance limits. It will also be used to trend and project loads at the next test point and to EPU conditions to demonstrate margin for continued power ascension.
- 2. Following the data collection and evaluation at the plateaus at approximately 4102 MWt, 4306 MWt, and 4408 MWt, GGNS shall provide a summary of the data and the evaluation performed in Section b.1 above to the NRC Project Manager. GGNS shall not increase power above these power levels for up to 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to allow for NRC review of the information.
- 3. Should the measured strains and accelerations on the dryer exceed the level 1 acceptance limits, or alternatively if the dryer instrumentation is not available and the projected load on the dryer from the MSL strain gage data exceeds the Level 1 acceptance limits, GGNS shall return the facility to a power level at which the limits are not exceeded. GGNS shall resolve the discrepancy, evaluate and document the continued structural integrity of the steam dryer, and provide that documentation to the NRC Project Manager prior to further increases in reactor power. GGNS shall not increase power for up to 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to allow for NRC review of the information.
- a. In the event that acoustic signals (in MSL strain gage signals) are identified that challenge the dryer acceptance limits during power ascension above 3898 MWt, GGNS shall evaluate dryer loads, and stresses, including the effect of +/-10 percent frequency shift, and re-to GNRO-2012-00031 Page 4 of 5 establish the acceptance limits and determine whether there is margin for continued power ascension.
- b. During power ascension above 3898 MWt, if an engineering evaluation for the steam dryer is required because a Level 1 acceptance limit is exceeded, GGNS shall perform the structural analysis using the Steam Dryer Analysis Report, Appendix A methods to address frequency uncertainties up to +/-10% and assure that peak responses that fall within this uncertainty band are addressed.
- 4. Following the data collection and evaluation at the EPU power level, GGNS shall provide a final load definition and stress report of the steam dryer, including the results of a complete re-analysis using the GGNS-specific bias and uncertainties and transfer function. The GGNS-specific bias and uncertainties summary shall include both PBLE Method 1 and Method 2. This report shall be transmitted to the NRC within 90 days of achieving the EPU power level. Should the results of this stress analysis indicate the allowable stress in any part of the dryer is exceeded, GGNS shall reduce power to a level at which the allowable stress is met, evaluate the dryer integrity, and assess any shortcomings in the predictive analysis. The results of this evaluation, including a recommended resolution of any identified issues and a demonstration of dryer integrity at EPU conditions, shall be provided to the NRC prior to return to EPU conditions.
(c) Entergy shall implement the following actions:
- 1. Entergy shall revise the post-EPU monitoring and inspection program to reflect long-term monitoring of plant parameters potentially indicative of steam dryer failure; to reflect consistency of the facilitys steam dryer inspection program with GE SIL 644, BWR Steam Dryer Failure," Revision 2; and with BWRVIP-139, Steam Dryer Inspection and Flaw Evaluation Guidelines.
(d) Entergy shall prepare the EPU PATP to include the following and provide it to the NRC project manager before increasing power above 3898 MWt:
- 1. Level 1 and Level 2 acceptance limits for on-dryer strain gages, on-dryer accelerometers, and for projected dryer loads from MSL strain gauge data, to be used up to 113 percent of CLTP.
- 2. specific hold points and their duration during EPU power ascension
- 3. activities to be accomplished during hold points
- 4. plant parameters to be monitored
- 5. inspections and walkdowns to be conducted for steam, feedwater, and condensate systems and components during the hold points
- 6. methods to be used to trend plant parameters to GNRO-2012-00031 Page 5 of 5
- 7. acceptance criteria for monitoring and trending plant parameters and conducting the walkdowns and inspections
- 8. actions to be taken if acceptance criteria are not satisfied
- 9. verification of the completion of commitments and planned actions specified in the Entergy application and all supplements to the application in support of the EPU LAR pertaining to the steam dryer before power increase above 3898 MWt
- 10. identify the NRC PM as the NRC point of contact for providing PAT plan information during power ascension
- 11. methodology for updating limit curves (e) The key attributes of the PAT Plan shall not be made less restrictive without prior NRC approval. Changes to other aspects of the PAT Plan may be made in accordance with the guidance of NEI 99-04, "Guidelines for Managing NRC Commitments," issued July 1999.
(f) During the first two scheduled refueling outages after reaching full EPU conditions, Entergy shall conduct a visual inspection of all accessible, susceptible locations of the steam dryer in accordance with BWRVIP-139 and GE inspection guidelines.
Entergy shall report the results of the visual inspections of the steam dryer to the NRC staff within 60 days following startup.
(g) At the end of the second refueling outage following the implementation of the EPU, the licensee shall submit a long-term steam dryer inspection plan based on industry operating experience along with the baseline inspection results for NRC review and approval.
(h) This license condition shall expire upon satisfaction of the requirements in paragraph (f) provided that a visual inspection of the steam dryer does not reveal any new unacceptable flaw or unacceptable flaw growth that is caused by fatigue.