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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:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML22342B2802022-12-28028 December 2022 Issuance of Amendments Adoption of TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Revision 1 ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML21146A0182021-06-0808 June 2021 Issuance of Amendments to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML21040A2922021-03-0404 March 2021 Issuance of Amendments Adoption of TSTF 501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21019A2192021-02-24024 February 2021 Issuance of Amendment No. 227 Extension of Appendix J Integrated Leakage Test Interval ML21011A0682021-02-0202 February 2021 Issuance of Amendments Adoption of TSTF 439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure ML21011A0482021-02-0101 February 2021 Issuance of Amendments Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20101G0542020-04-15015 April 2020 Issuance of Amendment No. 224 One Cycle Extension of Appendix J Integrated Leakage Test and Drywell Bypass Test Interval (Exigent Circumstances) ML19308B1072019-12-11011 December 2019 Issuance of Amendments Adoption of Technical Specifications Task Force Traveler TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio) ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19123A0142019-06-18018 June 2019 Issuance of Amendment No. 220, Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML19094A7992019-06-11011 June 2019 Issuance of Amendment No. 219 to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-425, Relocate Surveillance Frequencies to Licensee Control-RITSTF Initiative 5B ML19084A2182019-05-23023 May 2019 Issuance of Amendment No. 218 to Revise Technical Specification to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control ML19025A0232019-03-12012 March 2019 Issuance of Amendment No. 216 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML18215A1962019-03-12012 March 2019 Issuance of Amendment No. 217 to Modify the Updated Safety Analysis Report to Replace Turbine First Stage Pressure Signals with Power Range Neutron Monitoring System Signals ML18306A5132018-11-30030 November 2018 Issuance of Conforming Amendment Nos. 262, 312 and 215 Transfers of Renewed Facility Operating Licenses ML17240A2322017-10-0404 October 2017 Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment No. 213 for Administrative Name Change to Licensee South Mississippi Electric Power Association (CAC No. MF9588) ML17116A0322017-06-0707 June 2017 Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment No. 212 to Adopt Technical Specifications Task Force-427, Allowance For Non-Technical Specification Barrier Degradation on Supported System Operability (CAC No. MF8692.) ML16243A0242016-12-0808 December 2016 Record of Decision - License Renewal Application for Grand Gulf Nuclear Station, Unit 1 ML16292A4622016-12-0101 December 2016 Renewed Facility Operating License for Grand Gulf Nuclear Station, Unit 1 ML16140A1332016-08-0404 August 2016 Issuance of Amendment Revision of Technical Specifications to Remove Inservice Testing Program and Clarify Surveillance Requirement Usage Rule Application ML16132A1942016-05-26026 May 2016 Correction to Amendment No. 207, Request for Changing Five Technical Specifications Allowable Levels ML16119A1482016-05-25025 May 2016 Issuance of Amendment No. 210 Re. Cyber Security Plan Milestone 8 Full Implementation Schedule ML16011A2472016-02-17017 February 2016 Issuance of Amendment No. 209 Revision of Technical Specifications for Containment Leak Rate Testing ML15336A2562015-12-17017 December 2015 Issuance of Amendment No. 208 Adoption of Technical Specification Task Force Traveler TSTF-522 ML15180A1702015-08-31031 August 2015 Issuance of Amendment Revision to Technical Specification 5.65.B to Add Reference NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density ML15229A2192015-08-31031 August 2015 Redacted, Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus License Amendment Request ML15195A3552015-08-31031 August 2015 Issuance of Amendment Request for Changing Five Technical Specifications Allowable Values ML15229A2182015-08-18018 August 2015 Redacted, Issuance of Amendment Adoption of Single Fluence Methodology ML15229A2132015-08-18018 August 2015 Redacted, Issuance of Amendment Regarding Technical Specification 2.1.1.2 of Technical Specification Section 2.1.1.2, Reactor SLs (Safety Limits) ML15104A6232015-05-12012 May 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-523 ML14311A4792014-12-12012 December 2014 Issuance of Amendment No. 200, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date ML14162A3782014-09-25025 September 2014 Redacted, Issuance of Amendment No. 199, Delete Operating License Condition 2.C(32), Partial Feedwater Heating, to Allow Plant to Operate with Final Feedwater Temperature Reduction at End of Fuel Cycle ML14106A1332014-06-30030 June 2014 Issuance of Amendment No. 198, Request to Adopt TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs, as Part of Consolidated Line Item Improvement Process 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 ML13261A3492013-09-25025 September 2013 Issuance of Amendment No. 196, Modify Updated Final Safety Analysis Report to Revise the Methodology for Standby Service Water Passive Failure ML13261A2642013-09-25025 September 2013 Redacted Version, Issuance of Amendment No. 195, Revise Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition ML13157A0292013-08-0505 August 2013 Issuance of Amendment No. 194, Revise TS Table 3.3.6.1-1 to Support Correction of Non-Conservative Allowable Value for Primary Containment and Drywell Isolation Instrumentation ML13025A3062013-03-14014 March 2013 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications ML12240A2392012-12-0505 December 2012 Issuance of Amendment No. 192, Revise Physical Protection License Condition Related to Milestone 6 of the Cyber Security Plan Implementation ML1208601492012-05-11011 May 2012 Issuance of Amendment No. 190, Revise Technical Specification 3.1.7, Standby Liquid Control (SLC) System, to Support Use of Sodium Pentaborate Solution Enriched with Boron-10 Isotope ML1207202832012-04-20020 April 2012 Issuance of Amendment No. 189, Revise Minimum Critical Power Ratio Safety Limit in Technical Specification 2.1.1.2 for Two-Loop and Single Recirculation Loop ML1117306812011-09-12012 September 2011 Issuance of Amendment No. 187, Revise Technical Specifications to Adopt TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation ML1119401652011-07-27027 July 2011 Issuance of Amendment No. 186, Revise License Condition and Approval of Cyber Security Plan and Associated Implementation Schedule ML1107304022011-04-27027 April 2011 Issuance of Amendment No. 185, Revise Surveillance Requirement Notes in Technical Specifications Associated with Condensate Storage Tank Level-Low as Reflected in TSTF-493 ML0909804292009-04-13013 April 2009 Correction to Amendment No. 182, Surveillance Requirements for Diesel Generator Slow - Start Testing (MD9641) ML0817600232008-10-14014 October 2008 Issuance of Amendment No. 178, Adoption of Technical Specifications Task Force (TSTF) Traveler No. 448, Revision 3, Control Room Envelope Habitability. ML0731902502007-10-24024 October 2007 License Amendment 177, Changes to TS SR 3.3.1.1.7, the Local Power Range Monitor Calibration Frequency ML0721405012007-08-24024 August 2007 Issuance of Amendment 176 Change to Technical Specifications to Allow Certain Types of Relief Valves to Be Used as Isolation Devices 2022-05-12
[Table view] |
Text
May 14, 2002 Mr. William A. Eaton Vice President, Operations GGNS Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150
SUBJECT:
GRAND GULF NUCLEAR STATION, UNIT 1 - ISSUANCE OF LICENSE AMENDMENT RE: CONTROL ROD SCRAM TIME TESTING FREQUENCY (TAC NO. MB1304)
Dear Mr. Eaton:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 150 to Facility Operating License No. NPF-29 for the Grand Gulf Nuclear Station, Unit 1 (GGNS). This amendment revises the GGNS Technical Specifications (TSs) in response to your application dated January 25, 2001, supplemented by letter dated February 20, 2002. The supplemental letter contained information clarifying provisions of the original submittal, and did not change the scope of the Federal Register notice published on March 21, 2001 (66 FR 15923).
The amendment authorizes an increase in the surveillance interval for performing sample tests of control rod insertion times. The surveillance interval is increased from 120 days cumulative operation in MODE 1 to 200 days cumulative operation in MODE 1.
A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
S. Patrick Sekerak, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosures:
- 1. Amendment No. 150 to NPF-29
- 2. Safety Evaluation cc w/encls: See next page
May 14, 2002 Mr. William A. Eaton Vice President, Operations GGNS Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150
SUBJECT:
GRAND GULF NUCLEAR STATION, UNIT 1 - ISSUANCE OF LICENSE AMENDMENT RE: CONTROL ROD SCRAM TIME TESTING FREQUENCY (TAC NO. MB1304)
Dear Mr. Eaton:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 150 to Facility Operating License No. NPF-29 for the Grand Gulf Nuclear Station, Unit 1 (GGNS). This amendment revises the GGNS Technical Specifications (TSs) in response to your application dated January 25, 2001, supplemented by letter dated February 20, 2002. The supplemental letter contained information clarifying provisions of the original submittal, and did not change the scope of the Federal Register notice published on March 21, 2001 (66 FR 15923).
The amendment authorizes an increase in the surveillance interval for performing sample tests of control rod insertion times. The surveillance interval is increased from 120 days cumulative operation in MODE 1 to 200 days cumulative operation in MODE 1.
A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
S. Patrick Sekerak, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-416 DISTRIBUTION:
PUBLIC RidsNrrPMPSekerak
Enclosures:
PDIV-1 Reading RidsNrrLADJohnson
- 1. Amendment No. 150 to NPF-29 RidsNrrDlpmPdiv (LBarnett) LHurley, RIV
- 2. Safety Evaluation RDennig, DRIP/RORP DBujol, RIV RidsOgcRp DLurie, DPBA cc w/encls: See next page RidsAcrsAcnwMailCenter RLandry, SRXB GHill (2)
RidsNrrDlpmPdivLpdiv1 (RGramm)
Tech Spec Pages: ML021360334 RidsRgn4MailCenter (KBrockman)
Accession No.: ML021200679 Package: ML021370276 OFFICE PDIV-1/PM PDIV-1/LA SRXB-SC DPBA RORP-SC NAME PSekerak DJohnson RCaruso DLurie RDennig DATE 5/3/02 5/1/02 5/3/02 5/1/02 5/8/02 OFFICE OGC PDIV-1/SC NAME RHoefling RGramm DATE 5/14/02 5/14/02 OFFICIAL RECORD COPY
ENTERGY OPERATIONS, INC.
SYSTEM ENERGY RESOURCES, INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION ENTERGY MISSISSIPPI, INC.
DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 150 License No. NPF-29
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Entergy Operations, Inc. (the licensee) dated January 25, 2001, as supplemented by letter dated February 20, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-29 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 150 , are hereby incorporated into this license.
Entergy Operations, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Robert A. Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 14, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 150 FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert 3.1-13 3.1-13
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 150 TO FACILITY OPERATING LICENSE NO. NPF-29 ENTERGY OPERATIONS, INC., ET AL.
GRAND GULF NUCLEAR STATION, UNIT 1 DOCKET NO. 50-416
1.0 INTRODUCTION
By letter dated January 25, 2001 (Reference 1), as supplemented by letter dated February 20, 2002 (Reference 2), Entergy Operations, Inc. (Entergy or the licensee) submitted a request for changes to the Grand Gulf Nuclear Station, Unit 1 (GGNS), Technical Specifications (TSs).
The changes would revise the TSs to increase the surveillance interval for performing sample tests of control rod insertion time from 120 days cumulative operation in MODE 1 to 200 days cumulative operation in MODE 1.
2.0 BACKGROUND
The TS governing the control rod scram time surveillance is intended to assure proper function of control rod insertion. Following each refueling outage, all control rod scram times are verified. In addition, periodically during power operation, a representative sample of control rods are randomly selected to be partially inserted to verify the insertion speed. A representative sample is defined as a sample containing at least 10 percent of the total number of control rods. The current TS stipulates that no more than 20 percent of the control rods in this representative sample can be slow during the post outage testing. In response to discussions with the Nuclear Regulatory Commission (NRC) (Reference 3), Entergy has redefined the acceptance criterion for at-power surveillance testing from 20 percent to 7.5 percent. This tightened acceptance criterion for at-power surveillance aligns with the TS 3.1.4 requirement for the total control rods allowed to have scram times exceeding the specified limit.
3.0 EVALUATION Over the course of the operating life of GGNS, the control rod insertion time test results have shown the control rod scram rates to be highly reliable. Out of 7,660 control rod insertion tests, only 12 control rods have been slower than the insertion time limit, with the exception of test data from Cycle 7, which is discussed further below. The extensive historical data base substantiates the licensees claim of high reliability of the GGNS control rod drive system. The current TS requires that 10 percent of the 193 control rods, or 20 rods, be tested via random sampling every 120 cumulative days of operation in MODE 1. Entergy has requested an extension of the surveillance interval to 200 cumulative days of operation in MODE 1.
The current TS bases states that the acceptance criteria have been met if 20 percent or fewer of the random sample control rods that are tested within the 120 day surveillance period are found to be slow. Entergy has proposed in Reference 2 that the control rod insertion time acceptance criterion for percentage of slow rods allowed, be reduced to 7.5 percent of the random at-power surveillance sample when the surveillance period is extended to 200 cumulative days of operation in MODE 1. The staff finds this to be acceptable since the more restrictive 7.5 percent acceptance criterion for testing the random sample is consistent with the TS 3.1.4 objective of ensuring that no more than 14 operable control rods are slow at any given time, and is in conformance with the Standard TS requirements for control rod insertion time acceptance.
The results of initial testing in Cycle 7 are excluded due to faulty hardware that was installed during the refueling outage for that cycle. It was found that a number of scram solenoid pilot valve tophead assemblies were replaced with units later proven to be prone to slow operation.
All tophead assemblies within that group were subsequently replaced or rebuilt so as to eradicate the slow operation. Since that time, there has not been a problem for any of the 2,344 tests that have been performed. The staff agrees that the results of the tests performed with the slow tophead assemblies can be excluded from the data base, because the subsequent control rod testing history has demonstrated that the test anomaly encountered during Cycle 7 was an isolated occurrence and is not representative of components currently installed in the plant.
3.1 Conclusion of Technical Evaluation The staff has reviewed the Entergy proposal to extend the control rod scram time surveillance interval in MODE 1 operation from 120 days to 200 days. The staff considers the extended surveillance interval to be justified by the demonstrated reliability of the GGNS control rod insertion system, based on historical control rod scram time test data, and by the more restrictive acceptance criterion for the number of slow rods allowed during at-power surveillance testing. The staff finds the proposed TS change acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Mississippi State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (66 FR 15923, published March 21, 2001). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public
7.0 REFERENCES
- 1. Letter from William A. Eaton, Entergy Operations, Inc. (GNRO-2001/00002) to NRC, "Grand Gulf Nuclear Station, Docket No. 50-416, License No. NPF-29, Control Rod Scram Time Testing Frequency, Proposed Amendment to the Operating License, LDC 2001-001," dated January 25, 2001.
- 2. Letter from William A. Eaton, Entergy Operations, Inc. (GNRO-2002/00012) to NRC, "Grand Gulf Nuclear Station, Docket No. 50-416, Supplement to Amendment Request Concerning Control Rod Scram Time Testing Frequency," dated February 20, 2002.
- 3. Telephone conference between NRC and Entergy, December 5, 2001.
Principal Contributors: R. Landry D. Lurie Date: May 14, 2002
Grand Gulf Nuclear Station cc:
Executive Vice President Attorney General
& Chief Operating Officer Department of Justice Entergy Operations, Inc. State of Louisiana P. O. Box 31995 P. O. Box 94005 Jackson, MS 39286-1995 Baton Rouge, LA 70804-9005 Wise, Carter, Child & Caraway State Health Officer P. O. Box 651 State Board of Health Jackson, MS 39205 P. O. Box 1700 Jackson, MS 39205 Winston & Strawn 1400 L Street, N.W. - 12th Office of the Governor FloorWashington, DC 20005-3502 State of Mississippi Jackson, MS 39201 Director Division of Solid Waste Management Attorney General Mississippi Department of Natural Asst. Attorney General Resources State of Mississippi P. O. Box 10385 P. O. Box 22947 Jackson, MS 39209 Jackson, MS 39225 President Vice President, Operations Support Claiborne County Entergy Operations, Inc.
Board of Supervisors P.O. Box 31995 P. O. Box 339 Jackson, MS 39286-1995 Port Gibson, MS 39150 Director Regional Administrator, Region IV Nuclear Safety Assurance U.S. Nuclear Regulatory Commission Entergy Operations, Inc.
611 Ryan Plaza Drive, Suite 1000 P.O. Box 756 Arlington, TX 76011 Port Gibson, MS 39150 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 399 Port Gibson, MS 39150 General Manager, GGNS Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 May 1999