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Category:Letter
MONTHYEARML24289A0312024-11-0808 November 2024 – Issuance of Amendments Related to the Removal of License Condition 2.F as Part of the Consolidated Line-Item Improvement Process (CLIIP) IR 05000416/20240032024-11-0606 November 2024 Integrated Inspection Report 05000416/2024003 IR 05000416/20240112024-10-16016 October 2024 – Fire Protection Team Inspection Report 05000416/2024011 ML24263A2712024-09-19019 September 2024 Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements IR 05000416/20240122024-09-17017 September 2024 License Renewal Post Approval Phase 2 Inspection Report 05000416/2024012 ML24257A0172024-09-17017 September 2024 Request for Withholding Information from Public Disclosure Unit 1 ML24254A3602024-09-10010 September 2024 Pre-Submittal Slides for License Amendment Request, Criticality Safety Analysis, Technical Specification 4.3.1, Criticality and Technical Specification 5.5.14, Spent Fuel Storage Rack Neutron Absorber Monitoring Program IR 05000416/20244022024-09-0909 September 2024 Security Baseline Inspection Report 05000416/2024402 05000416/LER-2024-003, Feedwater Inlet Check Valve Incorrectly Determined Operable2024-08-26026 August 2024 Feedwater Inlet Check Valve Incorrectly Determined Operable ML24235A0832024-08-22022 August 2024 Evaluations Performed in Accordance with 10 CFR 50.54(q) for Changes to Emergency Planning Documents IR 05000416/20240052024-08-21021 August 2024 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2024005) ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 IR 05000416/20240022024-07-29029 July 2024 Integrated Inspection Report 05000416/2024002 ML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b ML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML24204A2432024-07-23023 July 2024 Notification of Cyber Security Baseline Inspection and Request for Information (05000416/2024403) ML24191A2432024-07-0909 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operations IR 05000416/20240102024-06-27027 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000416/2024010 ML24156A1762024-06-24024 June 2024 Regulatory Audit Summary in Support of License Amendment Requests to Adopt TSTF-505, Revision 2 and 10 CFR 50.69 (Epids L-2023-LLA-0081 and L-2023-LLA-0080) ML24165A1512024-06-13013 June 2024 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk-Informe ML24163A2652024-06-11011 June 2024 Inservice Inspection Summary Report ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 05000416/LER-2024-002, Automatic Actuation of Reactor Protection System2024-05-28028 May 2024 Automatic Actuation of Reactor Protection System ML24130A0912024-05-0909 May 2024 Request for Information Letter License Renewal Phase 2 Inspection ML24128A1512024-05-0909 May 2024 Project Manager Assignment ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000416/20240012024-05-0202 May 2024 Integrated Inspection Report 05000416 2024001 ML24122C6112024-05-0101 May 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. ML24116A0372024-04-25025 April 2024 Report of Technical Specification Bases Changes ML24113A0972024-04-22022 April 2024 Annual Report of Individual Monitoring - NRC Form 5 for 2023 Per 1 0 CFR 20.2206 ML24113A0952024-04-22022 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24107B0402024-04-16016 April 2024 Notification by Entergy Operations, Inc., of Proposed Economic Performance Incentive and Reliance on Post-Event Improvements in Plant Procedures And/Or Methods of Operation in FERC ML24107A8872024-04-16016 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24100A0692024-04-0909 April 2024 Report of Changes or Errors to 10 CFR 50.46 Analysis ML24094A0992024-04-0303 April 2024 (GGNS) Core Operating Limits Report (COLR) Cycle 25, Revision O ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams 05000416/LER-2024-001, High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close2024-03-27027 March 2024 High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close IR 05000416/20220042024-03-19019 March 2024 – Amended Integrated Inspection Report 05000416/2022004 and Exercise of Enforcement Discretion ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) IR 05000416/20230062024-02-28028 February 2024 Annual Assessment Letter for Grand Gulf Nuclear Station - Report 05000416/2023006 ML24058A3512024-02-28028 February 2024 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information IR 05000416/20233012024-02-26026 February 2024 NRC Examination Report 05000416-2023301 05000416/LER-2023-002, Reactor Scram Due to Generator Stator Fault to Ground2024-02-13013 February 2024 Reactor Scram Due to Generator Stator Fault to Ground ML24043A1892024-02-12012 February 2024 Spent Fuel Storage Radioactive Effluent Release Report for 2023 ML24012A1422024-01-31031 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)) ML24043A0732024-01-29029 January 2024 2024-01 Post Examination Comments IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 2024-09-09
[Table view] Category:Safety Evaluation
MONTHYEARML24289A0312024-11-0808 November 2024 – Issuance of Amendments Related to the Removal of License Condition 2.F as Part of the Consolidated Line-Item Improvement Process (CLIIP) ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 ML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b ML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 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 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22342B2802022-12-28028 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 ML22007A3172022-01-18018 January 2022 1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML21294A0672021-10-28028 October 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1, Alternative Request for Pressure Isolation Valve Testing Frequency ML21258A4082021-09-21021 September 2021 Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of Boiling Water Reactor Vessel and Internals Project Guidelines 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 ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI 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) ML19266A5862019-10-11011 October 2019 Relief Request GG-ISI-023, Examination Coverage of Class 1 Piping and Vessel Welds ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 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 ML19018A2692019-03-12012 March 2019 Safety Evaluation Input for Grand Gulf Nuclear Station Unit 1, License Amendment Request to Implement Technical Specification Task Force-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control 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 ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 ML17285A7942017-10-30030 October 2017 Grand Gulf Nuclear Station, Unit 1 - Relief Request GG-ISI-021 Proposing An Alternative For Fourth Ten Year Inservice Inspection Program (CAC NO. MF9752; EPID L-2017-LLR-0031) 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) ML17235A5332017-08-31031 August 2017 Relief Request GG-ISI-022 to Allow Use of Later Editions and Addenda of American Society of Mechanical Engineers Code for Inservice Inspection 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.) ML16278A0172016-10-19019 October 2016 Entergy Fleet Relief Request RR-EN-ISI-15-1, Alternative to Maintain Inservice Inspection Related to Activities to the 2001 Edition/2003 Addendum of ASME Section XI Code ML16253A3222016-09-27027 September 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16140A1332016-08-0404 August 2016 Issuance of Amendment Revision of Technical Specifications to Remove Inservice Testing Program and Clarify Surveillance Requirement Usage Rule Application ML16160A0922016-06-16016 June 2016 Relief Request GG-IST-2015-1 Related to the Inservice Testing Program ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 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 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 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 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) ML15229A2182015-08-18018 August 2015 Redacted, Issuance of Amendment Adoption of Single Fluence Methodology ML15104A6232015-05-12012 May 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-523 2024-08-13
[Table view] |
Text
November 19, 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 RE: EMERGENCY PLAN CHANGE - EMERGENCY ACTION LEVELS (TAC NO. MB4707)
Dear Mr. Eaton:
In your application dated February 28, 2002, you proposed changes to Table 4-1, Emergency Action Levels for Grand Gulf Nuclear Station, Unit 1 for the U. S. Nuclear Regulatory Commission (NRC) staff review and approval prior to implementation.
Based on the information provided in the application, as discussed in the enclosed Safety Evaluation, we have found that the proposed changes to Table 4-1 are acceptable in that the changes are acceptable alternatives to the guidance provided in NUREG-0654/FEMA-REP-1, Rev. 1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," (NUREG-0654). The proposed changes conclude that the revised Emergency Action Levels meet the requirements of Section 50.47(b)(4) Emergency plans, to Title 10 of the Code of Federal Regulations (10 CFR), and 10 CFR Part 50, Domestic Licensing Of Production And Utilization Facilities, Appendix E, Emergency Planning And Preparedness For Production And Utilization Facilities.
You are requested to inform the NRC staff by letter when these changes are implemented.
Sincerely,
/RA/
David H. Jaffe, Sr. Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No.: 50-416
Enclosure:
Safety Evaluation cc: See next page
ML NRR-039 OFFICE PDIV-1/PM PDIV-1/LA DIPM/IEHB-SC PDIV-1/SC NAME DJaffe:sab DJohnson KGibson* RGramm DATE 11/19/2002 11/19/2002 11/19/2002 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON THE PROPOSED CHANGES TO THE EMERGENCY ACTION LEVELS FOR ENTERGY OPERATIONS, INC., ET.AL GRAND GULF NUCLEAR STATION, DOCKET NO. 50-416
1.0 INTRODUCTION
By letter dated February 28, 2002, Entergy Operations, Inc. (the licensee) submitted proposed changes to the Grand Gulf Nuclear Station, Unit 1 (GGNS) Emergency Action Levels (EALs)
(Reference 6.1) for the U.S. Nuclear Regulatory Commission (NRC) staff review and approval.
As required by Part 50 Domestic Licensing Of Production And Utilization Facilities, Appendix E, Emergency Planning And Preparedness For Production And Utilization Facilities,Section IV Content Of Emergency Plans, Subpart B Assessment Actions, to Title 10 of the Code of Federal Regulations (10 CFR), EALs shall be discussed and agreed to by the applicant and State and Local governmental authorities and approved by NRC. This evaluation describes the NRC staff's basis for accepting the proposed EAL Emergency Plan changes.
2.0 REGULATORY EVALUATION
The NRC staff finds that the licensee in Attachment 2 of Reference 6.1 identified the applicable regulatory requirements. The regulatory requirements which the NRC staff applied in its review of the application included: 10 CFR 50.47(b)(4), 10 CFR Part 50, Appendix E, Section IV.B, and C, and regulatory guidance provided in Regulatory Guide 1.101, Revision 2, "Emergency Planning and Preparedness for Nuclear Power Reactors," (Reference 6.2) and NUREG-0654/FEMA-REP-1, Rev. 1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants",
Sections Il.D.1 and ll.D.2 (Reference 6.3)
3.0 TECHNICAL EVALUATION
3.1 EAL 16.1 - Alert 3.1.1 Proposed Text:
"Emergency Director determines that plant conditions exist that warrant precautionary activation of the TSC [Technical Support Center] or EOF [ Emergency Operations Facility ] ."
Safety Evaluation 3.1.2 Licensees Justification:
The licensee stated in Reference 6.1 that:
With the Emergency Plan augmentation changes approved by the NRC in a letter dated September 29, 2000 (GNRI-2000/00093) [Reference 6.4], GGNS committed to activating the EOF at the Alert or higher emergency classification instead of a Site Area Emergency [SAE] or higher classification. Therefore, GGNS cannot place the EOF on standby if this EAL is used to classify the event. As a result of the augmentation change, an Alert classification under any other EAL would result in both the TSC and EOF being activated. Certain situations could however require a discretionary activation of either the TSC or the EOF but not both depending upon the nature of the event or the decision of the Emergency Director. The current wording implies that you would have to activate TSC and place personnel on standby to meet the conditions of the current EAL.
This change only requires one action to be met (activation of the TSC or EOF) to declare an ALERT, thus it is more restrictive with the end result being that all facilities are activated based on the ALERT classification.
3.1.3 NRC Staff Evaluation:
The current EAL reads: "Emergency Director determines that plant conditions exist that warrant precautionary activation of the TSC and placing the EOF and key plant personnel on standby."
This EAL cannot be implemented due to changes in on-shift augmentation staffing approved by the NRC. The proposed change brings more resources to respond to an event and potentially brings them earlier. Since the proposed EAL change is considered a more conservative alternative to the current EAL and meets the intent of the declaration of an Alert, it is therefore acceptable.
3.2 EAL - 14.1 - Site Area Emergency 3.2.1 Proposed Text:
"Emergency Director/Offsite Emergency Coordinator determines that a release is in progress or imminent that could affect the near site public.
3.2.2 Licensee's Justification:
The licensee stated in Reference 6.1 that:
With the Emergency Plan augmentation changes approved by the NRC in a letter dated September 29, 2000 (GNRI-2000/00093) (Reference 6.4), GGNS committed to activating the EOF at the Alert or higher emergency classification instead of a SAE or higher classification. If the event has progressed as expected, the EOF would have already been manned at the Alert Classification prior to reaching this SAE EAL. If the event initiates a SAE classification, activation of the EOF is still appropriate. Therefore, it is necessary to change our EAL to the proposed EAL to capture the reason for staffing the EOF as described in the definition of SAE in NUREG-0654. The proposed EAL encompasses events that would follow expected progression as well as events that initiate at a SAE, and therefore, does not reduce the effectiveness of the Plan. The proposed wording gives the actual plant condition that could require monitoring teams to
Safety Evaluation be dispatched. This wording would result in a SAE declaration, and thus require notification of offsite agencies. The offsite agencies, who have the responsibility and authority for near site and general public notification, would determine the need for public notification and actions.
3.2.3 NRC Staff Evaluation:
The current EAL reads: "Emergency Director determines that plant conditions exist that warrant: a. The activation of the EOF or b. A precautionary notification to the public near the site." This EAL cannot be implemented due to changes in on-shift augmentation staffing approved by the NRC. One of the purposes of declaring a SAE is to assure that field monitoring teams are dispatched. The proposed EAL will prompt the dispatch of the licensees field teams. Also, the proposed EAL meets the intent of the definition of SAE in NUREG-0654 which states in part, "Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary." Also, GGNS Emergency Plan Procedure 10-S-01-1, Attachment I, Revision 109, "Emergency Classifications" Section 18 has provisions for event classification based upon Emergency Director discretion. It is understood that the licensee will revise this section of their procedure to reflect the proposed wording approved by the NRC staff in this Safety Evaluation. Therefore, this EAL change is acceptable since there is no reduction in effectiveness of the classification scheme and the proposed EAL meets the intent of the declaration of a SAE.
4.0 AGREEMENT BY STATE AND LOCAL GOVERNMENTS The regulations in 10 CFR Part 50, Appendix E, Section IV. B require, in part, that EALs are to be discussed and agreed upon by State and Local government authorities. The licensee stated in Reference 6.1 that these proposed changes were discussed with State and Local governments and that these authorities agreed to these proposed changes. Based on the above, the NRC staff finds that the licensee has satisfactorily met the requirements regarding obtaining the State and Local government concurrence for the changes to the EALs.
5.0 CONCLUSION
The NRC staff concludes that the licensees emergency plan changes as proposed in Reference 6.1, are acceptable alternatives to the guidance provided in Reference 6.3. The NRC staff also concludes that the proposed revised EAL changes meet the requirements of 10 CFR 50.47(b)(4) and Appendix E to 10 CFR Part 50. Therefore, based on the information provided in Reference 6.1, the proposed EAL changes are acceptable.
6.0 REFERENCES
6.1 GNRO-2002/00014, Charles A. Bottemiller (Entergy) letter to NRC, Proposed Emergency Plan Changes - Emergency Action Levels (EALS)-LDC 2001-191, dated February 28, 2002 6.2 Regulatory Guide 1.101, Revision 2, "Emergency Planning and Preparedness for Nuclear Power Reactors,"
Safety Evaluation 6.3 NUREG-O654/FEMA-REP-1, Rev. 1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants."
6.4 NRC Letter, GNRI-2000/00093, S. Patrick Sekerak, Grand Gulf Nuclear Station, Unit 1, Proposed Emergency Plan Table 5-1 Changes (TAC NO. MA1130),
dated September 29, 2000.
Principal Contributor: Robert E. Moody Date: November 19, 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 Floor Office of the Governor Washington, 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