Letter Sequence Supplement |
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TAC:ME9764, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
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MONTHYEARGNRO-2012/00096, License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 12012-10-0202 October 2012 License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 1 Project stage: Request ML12289A1582012-10-15015 October 2012 Acceptance Review Email, License Amendment Request to Revise Technical Specifications and Surveillance Requirements to Support Operation with a 24-Month Fuel Cycle in Accordance with Generic Letter 91-04 Project stage: Acceptance Review ML13077A3662013-03-18018 March 2013 Email, Request for Additional Information, License Amendment Request to Revise Technical Specifications and Surveillance Requirements to Support Operation with a 24-Month Fuel Cycle in Accordance with Generic Letter 91-04 Project stage: RAI GNRO-2013/00023, Supplement to the License Amendment Request for Implementing a 24-Month Fuel Cycle2013-04-26026 April 2013 Supplement to the License Amendment Request for Implementing a 24-Month Fuel Cycle Project stage: Supplement ML13121A3912013-05-0101 May 2013 Email, Request for Additional Information, Round 2, Request to Revise Technical Specifications and Surveillance Requirements to Support Operation with a 24-Month Fuel Cycle in Accordance with Generic Letter 91-04 Project stage: RAI GNRO-2013/00038, Response to Request for Additional Information Regarding 18 to 24 Month License Amendment Request (TAC ME9764) Dated May 1, 20132013-06-0404 June 2013 Response to Request for Additional Information Regarding 18 to 24 Month License Amendment Request (TAC ME9764) Dated May 1, 2013 Project stage: Response to RAI ML13171A2252013-06-20020 June 2013 Email, Audit Plan for 6/24/13 Audit for Review of Calculations in Support of Amendment Request to Revise Technical Specifications and Surveillance Requirements for Operation with a 24-Month Fuel Cycle in Accordance with GL 91-04 Project stage: Other GNRO-2013/00024, Response to Request for Additional Information Re 18 to 24 Month License Amendment Request, Dated March 18, 20132013-08-15015 August 2013 Response to Request for Additional Information Re 18 to 24 Month License Amendment Request, Dated March 18, 2013 Project stage: Response to RAI 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 Project stage: RAI GNRO-2013/00076, Supplemental Information to Clarify License Amendment Request for Implementing a 24-Month Fuel Cycle at Grand Gulf Nuclear Station, Unit 12013-09-24024 September 2013 Supplemental Information to Clarify License Amendment Request for Implementing a 24-Month Fuel Cycle at Grand Gulf Nuclear Station, Unit 1 Project stage: Supplement L-91-004, Supplement to the License Amendment Request for Implementing a 24 Month Fuel Cycle - Addendum2013-09-26026 September 2013 Supplement to the License Amendment Request for Implementing a 24 Month Fuel Cycle - Addendum Project stage: Supplement ML13323A5512013-10-0808 October 2013 Attachment 2 to GNRO-2013/00088, JC-Q1B21-N678-1 Rev. 2 Reactor Steam Dome Pressure Scram Setpoint Project stage: Other ML13323A5522013-10-14014 October 2013 Attachment 3 to GNRO-2013/00088, JC-Q1B21-N681-1 Rev. 1 Reactor Pressure Vessel Level One Setpoint Calculation Project stage: Other GNRO-2013/00074, Response to Electronic Request for Additional Information Regarding 18 to 24 Month License Amendment Request, Dated September 16, 20132013-10-14014 October 2013 Response to Electronic Request for Additional Information Regarding 18 to 24 Month License Amendment Request, Dated September 16, 2013 Project stage: Request ML13323A5532013-10-29029 October 2013 Attachment 4 to GNRO-2013/00088, JC-Q1B21-N694-1 Rev. 1 Drywell High Pressure RCIC Isolation Setpoint Calculation Project stage: Other ML13323A5542013-11-0404 November 2013 Attachment 5 to GNRO-2013/00088, EN-IC-S-022-G Rev. 0 Instrument Performance Monitoring and Drift Trending Analysis Project stage: Other ML13323A5502013-11-0808 November 2013 Attachment 1 to GNRO-2013/00088 JC-Q1P81-90024 Rev. 3 Division III Degraded Bus Voltage Setpoint Project stage: Other GNRO-2013/00088, Supplemental Response to Request for Additional Information Regarding 18 to 24 Month Fuel Cycle License Amendment Request (TAC ME9764), Dated May 1, 20132013-11-12012 November 2013 Supplemental Response to Request for Additional Information Regarding 18 to 24 Month Fuel Cycle License Amendment Request (TAC ME9764), Dated May 1, 2013 Project stage: Supplement GNRO-2013/00094, Supplement to License Amendment Request for Implementing a 24-Month Fuel Cycle2013-12-0505 December 2013 Supplement to License Amendment Request for Implementing a 24-Month Fuel Cycle Project stage: Supplement GNRO-2013/00097, Request to Withdraw Supplement to the License Amendment Request for Implementing a 24-Month Fuel Cycle2013-12-11011 December 2013 Request to Withdraw Supplement to the License Amendment Request for Implementing a 24-Month Fuel Cycle Project stage: Supplement ML13343A1092013-12-26026 December 2013 Issuance of Amendment No. 197, Revise Technical Specifications and Surveillance Requirements to Support Operation with 24-Month Fuel Cycle in Accordance with Generic Letter 91-04 Project stage: Approval 2013-12-26
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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 - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report2019-06-25025 June 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report GNRO-2019/00028, Supplement 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.2019-06-13013 June 2019 Supplement 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-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
'4?" ~ -15 V"
--~ Entergy Entergy Operations, Inc.
P. 0. Box 756 Port Gibson, MS 39150 Kevin J. Mulligan Vice President, Operations Grand Gulf Nuclear Station Tel. (601) 437-7500 GNRO-2013/00023 April 26, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Supplement to the License Amendment Request for implementing a 24-Month Fuel Cycle Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCE:
GNRO-2012/00096: Letter, Michael Perito (Entergy) to the U. S. Nuclear Regulatory Commission, License Amendment Request for implementing a 24-Month Fuel Cycle, dated October 2, 2012 (Accession Number ML12277AO80)
Dear Sir or Madam:
In the referenced letter, Entergy Operations, lnc. (Entergy) submitted a license amendment request (LAR) to the NRC to amend the Grand Gulf Nuclear Station, Unit 1 (GGNS) Technical Speci"cations (TS) to support operation with 24-month fuel cycles in accordance with guidance contained in NRC Generic Letter (GL) 91-04. Entergy inadvertently omitted TS Surveillance Requirement SR 3.7.7.2 Main Turbine Bypass System from the LAR. This letter supplements the referenced LAR by incorporating SR 3.7.7.2 into the request.
The change in frequency for SR 3.7.7.2 from 18 months to 24 months has minimal, if any, impact on system capability, consistent with other such changes presented in the referenced LAR. A mark-up of SR 3.7.7.2 (TS page 3.7-15) is included in Attachment 1. A mark-up of the corresponding TS BASES page is also included for information only. A Clean TS page incorporating this change is included in Attachment 2.
Also included in Attachment 2 is a clean page replacement for TS page 3.3-78 that was included in the original LAR. Marked-up page 3.3-78 included with the original LAR is correct.
However, the mark-ups were not transcribed into the corresponding clean TS page correctly.
Please replace the current TS page 3.3-78 with this corrected page.
The no signi"cant hazards consideration statement that was submitted with the original LAR has been reviewed and continues to bound this supplement.
In accordance with 10 CFR 50.91(b) (1), State Consultation, a copy of this supplement is being provided to the designated Mississippi Of"cial.
GNRO-2013/00023 Page 2 of 2 There are no new commitments in this letter. lf you have any questions or require additional information, please contact Mr. Christopher R. Robinson at 601- 437-7326.
l declare under penalty of perjury that the foregoing is true and correct. Executed on April 26 201 3.
Sincerely, KJM/ceb .
Attachments: 1. GGNS TS and BASES Marked-Up Pages
- 2. GGNS TS Clean Pages cc: U.S. Nuclear Regulatory Commission ATTN: Mr. Arthur T. Howell, (w/2)
Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 7601 1-4511 U. S. Nuclear Regulatory Commission ATTN: Mr. Alan Wang, NRR/DORL (w/2)
Mail Stop OWFN 8 B1 Washington, DC 20555-0001 NRC Senior Resident inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment 1 GNRO-2013/00023 GGNS TS and BASES Marked-Up Pages
Main Turbine Byp ass System 3.7 PLANT SYSTEMS 3.7.7 Main Turbine Bypass System LCO 3.7.7 a. The Main Turbine Bypass System shall be OPERABLE with two Main Turbine Bypass Valves.
- b. The following limits are made applicable:
- 1. LCO 3.2.2, MINIMUM CRITICAL POWER RATIO (MCPR), limits for an inoperable Main Turbine Bypass System, as specified in the COLR.
9&2
- 2. LCO 3.2.3, LINEAR HEAT GENERATION RATE (LHGR), limits for an inoperable Main Turbine Bypass System, as specified in the COLR.
APPLICABILITY: THERMAL POWER 2 70% RTP ACTION CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.l Satisfy the 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> not met or Main Turbine Requirements of the Bypass System is LCO or restore the inoperable. Main Turbine Bypass System to OPERABLE status.
B. Required Action and B.l Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion to < 70% RTP.
Time not met.
SURVEILLANCE REQUIREMENTS =:
i l E ~
SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify one complete cycle of each main turbine 31 days bypass valve.
_ %&essaase~e>>i7 ass>>
SR 3.7.7.2 Perform a system functional test. at? months vi it4 S
mnlwv~>n~a_x-v<_,>>>>aw=-*>>
nv rti at GRAND GULF 3.7~l5 Amendment N0. &9%mW
Main Turbine Bypass System B 3.7.7 BASES (continued)
§_-_l If the Main Turbine Bypass System cannot be restored to OPERABLE status or the LHGR and MCPR limits for two or more inoperable Main Turbine Bypass valves are not applied, THERMAL POWER must be reduced to < 70% RTP. As discussed in the Applicability section, operation at <70% RTP results in sufficient margin to the required limits, and the Main Turbine Bypass system is not required to protect fuel integrity during the feedwater controller failure. maximum demand event. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time is reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE SR 3.7.7.;
REQUIREMENTS Cycling each Main Turbine Bypass valve through one complete cycle of full travel demonstrates that the valves are mechanically OPERABLE and will function when required. The 31 day Frequency is based on engineering judgment, is consistent with the procedural controls governing valve operation, and ensures correct valve positions. Therefore, the Frequency is acceptable from a reliability standpoint.
SR 3.7.7.2 The Main Turbine Bypass System is required to actuate Nebula. automatically to perform its design function. This SR 5 ,/".§#W~% demonstrates that, with the required system initiation
% x\"3*re T mm4.
resignals, the valves will actuate to their required position.
"rr* Thé§18'month Frequency is based on the need to perform this Surveillance under the conditions that apply during a unit outage and because of the potential for an unplanned transient if the Surveillance were performed with the f reactor at power. Operating experience has shown thefa"f Sear month Frequency, which is based on the refueling cycle, is acceptable from a reliability standpoint. .?gWWm. "R__J,,,m,>> no/~"
V/FMMWM l qvwvmwwl ftliai REFERENCES None GRAND GULF B 3.73O LBDCR 12035
Attachment 2 GNRO-201 3100023 GGNS TS Clean Pages
Main Turbine Bypass System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Main Turbine Bypass System LCO 3.7.7 a. The Main Turbine Bypass System shaTT be OPERABLE with two Main Turbine Bypass Vaives.
QR
- b. The foiiowing Timits are made appiicabiez
- 1. LCO 3.2.2, MINIMUM CRITICAL PONER RATIO (MCPR), Timits for an inoperabie Main Turbine Bypass System, as specified in the COLR.
AND
- 2. LCO 3.2.3, LINEAR HEAT GENERATION RATE <LHGR)," Timits for an inoperabie Main Turbine Bypass System, as specified in the COLR.
APPLICABILITY: THERMAL POWER 2 70% RTP ACTION ___
CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.I Satisfy the 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> not met or Main Turbine Requirements of the Bypass System is LCO or restore the inoperabie. Main Turbine Bypass System to OPERABLE status.
B. Required Action and 8.1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Compietion to < 70% RTP.
Time not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify one compiete cycie of each main turbine 31 days bypass vaive.
SR 3 7.7.2 Perform a system functionai test. 24 months l GRAND GULF 3.7-I5 Amendment No. %9%
LOP Instrumentation 3.3.8.1 SURVEILLANCE REQUIREMENTS
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _-NOTES----_-__.__-____-------___________-_
- 1. Refer to Tabie 3.3.8.I~1 to determine which SR5 apply for each LOP Function.
- 2. when a channei is piaced in an inoperabie status soTeTy for performance of required Surveiiiances, entry into associated Conditions and Required Actions may be deiayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains DO initiation capabiiity.
SURVEILLANCE FREQUENCY SR 3 3 8 1.1 Perform CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.8.1.2 Perform CHANNEL CALIBRATION. I8 months SR 3.3.8.1.3 Perform CHANNEL CALIBRATION. 24 months SR 3.3.8.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months GRAND GULF 3.378 Amendment No. 1267 ___