ML20205S202
Letter Sequence Approval | |
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Initiation
Administration Questions
Results Other: AECM-84-0252, Special Rept 83-067/3:on 830819,during Scheduled Surveillance on Four Pipe Mounted Triaxial Peak Recording Accelerographs Used for Seismic Monitoring,Instruments Damaged Due to over-ranging.Design Changes Under Way, AECM-84-0307, Submits Commitment to Evaluate Design of Certain Seismic Monitoring Instruments to Determine Location,Range & Type of Instrument Prior to Restart Following First Refueling Outage.Proposed Tech Spec Changes Will Be Submitted, AECM-86-0006, Forwards Technical Justification for Proposal to Delete Peak Recording Accelerographs Currently Installed on Reactor Piping Locations,Per Section 16.3.1 of Sser 6 (NUREG-0831).Response by 860228 Requested.Fee Paid | |
MONTHYEARAECM-82-492, Requests That License Condition 2.C.(44)(i)(a) Be Revised to Require Submittal Re Automatic Depressurization Sys Logic Mods by 821215.Previous Submittal Date of 821029 Erroneously Requested Due to Revised BWR Owners Group Schedule1982-10-21021 October 1982
[Table View]Requests That License Condition 2.C.(44)(i)(a) Be Revised to Require Submittal Re Automatic Depressurization Sys Logic Mods by 821215.Previous Submittal Date of 821029 Erroneously Requested Due to Revised BWR Owners Group Schedule Project stage: Other AECM-82-603, Comments on BWROG-8260, NUREG-0737,Item II.K.3.18,Mod of Automatic Depressurization Sys Logic. Option 4,providing Bypass Timer Delay,Will Assure Adequate Core Cooling During Worst Case Conditions1982-12-14014 December 1982 Comments on BWROG-8260, NUREG-0737,Item II.K.3.18,Mod of Automatic Depressurization Sys Logic. Option 4,providing Bypass Timer Delay,Will Assure Adequate Core Cooling During Worst Case Conditions Project stage: Other AECM-84-0252, Special Rept 83-067/3:on 830819,during Scheduled Surveillance on Four Pipe Mounted Triaxial Peak Recording Accelerographs Used for Seismic Monitoring,Instruments Damaged Due to over-ranging.Design Changes Under Way1984-05-0404 May 1984 Special Rept 83-067/3:on 830819,during Scheduled Surveillance on Four Pipe Mounted Triaxial Peak Recording Accelerographs Used for Seismic Monitoring,Instruments Damaged Due to over-ranging.Design Changes Under Way Project stage: Other AECM-84-0307, Submits Commitment to Evaluate Design of Certain Seismic Monitoring Instruments to Determine Location,Range & Type of Instrument Prior to Restart Following First Refueling Outage.Proposed Tech Spec Changes Will Be Submitted1984-05-31031 May 1984 Submits Commitment to Evaluate Design of Certain Seismic Monitoring Instruments to Determine Location,Range & Type of Instrument Prior to Restart Following First Refueling Outage.Proposed Tech Spec Changes Will Be Submitted Project stage: Other AECM-85-0014, Forwards Addl Info,Requested in ,Re Concerns Involving Transfer of Control to Remote Shutdown Panel Resulting in Change in Operating Status of Load That May Be Detrimental to Safe Shutdown1985-01-17017 January 1985 Forwards Addl Info,Requested in ,Re Concerns Involving Transfer of Control to Remote Shutdown Panel Resulting in Change in Operating Status of Load That May Be Detrimental to Safe Shutdown Project stage: Other ML20151L0531985-07-12012 July 1985 Application for Amend to License NPF-29,revising Tech Specs to Reflect Organizational Changes & Addition of Two Primary Containment Penetration Conductor Overcurrent Protection Circuit Breakers Project stage: Request ML20133P1711985-08-12012 August 1985 Proposed Tech Specs,Reflecting Design Changes & Editorial Clarification Re Leak Rate Testing of RHR to Head Spray Isolation Valve & ECCS Actuation Instrumentation Project stage: Other AECM-85-0228, Application for Amend to License NPF-29,changing Tech Specs to Reflect Design Changes & Editorial Clarifications.Fee Paid1985-08-12012 August 1985 Application for Amend to License NPF-29,changing Tech Specs to Reflect Design Changes & Editorial Clarifications.Fee Paid Project stage: Request AECM-85-0248, Withdraws 850712 Proposed Change to License NPF-29,Item 7,to Reduce Burden of Requiring Rev to OL W/Each Tech Spec Amend. Change Inconsistent W/Past NRC Practices & Procedures1985-08-12012 August 1985 Withdraws 850712 Proposed Change to License NPF-29,Item 7,to Reduce Burden of Requiring Rev to OL W/Each Tech Spec Amend. Change Inconsistent W/Past NRC Practices & Procedures Project stage: Request ML20133A7611985-09-25025 September 1985 Proposed Changes to Tech Specs 6.3.1 & 6.4.1,providing Justification for Exemption from Requirements for Senior Reactor Operator Qualifications Project stage: Request AECM-85-0304, Application for Amend to License NPF-29,supplementing 850812,23 & 30 Submittals,To Provide Justification for Exemption from Tech Spec 6.3.1 & 6.4.1 Requirements for Senior Reactor Operator Qualifications1985-09-25025 September 1985 Application for Amend to License NPF-29,supplementing 850812,23 & 30 Submittals,To Provide Justification for Exemption from Tech Spec 6.3.1 & 6.4.1 Requirements for Senior Reactor Operator Qualifications Project stage: Supplement AECM-85-0314, Provides Addl Info to Support Proposed Change to Tech Specs 4.1.3.3.b.1.b.GE Info Ltr Entitled Hydraulic Control Unit Accumulator Pressure Switches, to Support Proposed Change,Encl1985-09-26026 September 1985 Provides Addl Info to Support Proposed Change to Tech Specs 4.1.3.3.b.1.b.GE Info Ltr Entitled Hydraulic Control Unit Accumulator Pressure Switches, to Support Proposed Change,Encl Project stage: Request AECM-85-0305, Forwards Resumes of Two Individuals Appointed as Supervisors to Organization Radiation Control Function,Per Request for Addl Info Re 850712 Proposed Change to Tech Spec Figure 6.2.2.-11985-10-0202 October 1985 Forwards Resumes of Two Individuals Appointed as Supervisors to Organization Radiation Control Function,Per Request for Addl Info Re 850712 Proposed Change to Tech Spec Figure 6.2.2.-1 Project stage: Request AECM-85-0306, Responds to Request for Addl Info Re 850812 Application for Amend to License NPF-29.Prompt Resolution of Questions & Approval of Previously Submitted Tech Specs Needed for Outage Scheduled to Start on 8510121985-10-0505 October 1985 Responds to Request for Addl Info Re 850812 Application for Amend to License NPF-29.Prompt Resolution of Questions & Approval of Previously Submitted Tech Specs Needed for Outage Scheduled to Start on 851012 Project stage: Request AECM-85-0341, Forwards Addl Info Re ECCS Performance Analysis Which Supports Increase in Peak Cladding Temp of 51 F Compared to Current FSAR Analysis,Per Request.Fsar Changes Will Be Made If Design Change Implemented1985-10-22022 October 1985 Forwards Addl Info Re ECCS Performance Analysis Which Supports Increase in Peak Cladding Temp of 51 F Compared to Current FSAR Analysis,Per Request.Fsar Changes Will Be Made If Design Change Implemented Project stage: Other ML20137Q8901985-11-22022 November 1985 Forwards Safety Evaluation Re 850812 Request for Amend to License NPF-29,adding Pressure Permissive Interlocks to Control Circuits for Low Pressure ECCS Injection Valves,Item 13 of 850812 Request Should Be Revised Project stage: Approval ML20137Q8971985-11-22022 November 1985 Safety Evaluation Re Low Pressure ECCS Sys Pressure Permissive Interlocks.Exceeding ASME Code Allowable Design Pressure for Interlocks Unacceptable Project stage: Approval AECM-85-0396, Advises That Tech Spec Changes Contained in Amends 4 & 6 to License NPF-29 Will Be Effective Before Startup After First Refueling Outage,Per 850918 & 1021 Requests1985-12-0606 December 1985 Advises That Tech Spec Changes Contained in Amends 4 & 6 to License NPF-29 Will Be Effective Before Startup After First Refueling Outage,Per 850918 & 1021 Requests Project stage: Other AECM-86-0006, Forwards Technical Justification for Proposal to Delete Peak Recording Accelerographs Currently Installed on Reactor Piping Locations,Per Section 16.3.1 of Sser 6 (NUREG-0831).Response by 860228 Requested.Fee Paid1986-01-10010 January 1986 Forwards Technical Justification for Proposal to Delete Peak Recording Accelerographs Currently Installed on Reactor Piping Locations,Per Section 16.3.1 of Sser 6 (NUREG-0831).Response by 860228 Requested.Fee Paid Project stage: Other AECM-86-0082, Supplemental Application for Amend to License NPF-29, Modifying 851114 Proposed Change Re License Condition 2.C.(28) & Revising Tech Specs Concerning Design Changes to Be Implemented During First Refueling Outage.Fee Paid1986-03-21021 March 1986 Supplemental Application for Amend to License NPF-29, Modifying 851114 Proposed Change Re License Condition 2.C.(28) & Revising Tech Specs Concerning Design Changes to Be Implemented During First Refueling Outage.Fee Paid Project stage: Supplement ML20154R5461986-03-21021 March 1986 Proposed Tech Specs Revising License Condition 2.C.(28) Re Requirement for Corporate Mgt Officials on Nuclear Operations Staff & Modifying Tables 3.3.7.2-1 & 4.3.7.2-1 to Reflect Design Change Project stage: Other ML20155D8101986-04-0808 April 1986 Summary of 860401 Meeting W/Utils Re Resolution of Issue of Interlocks for ECCS Injection Valves Which Also Function as Pressure Isolation Valves.Viewgraphs & List of Attendees Encl Project stage: Meeting ML20155J9341986-05-19019 May 1986 Proposed Tech Specs Adding Undervoltage Protection Device & Emergency Override of Test Mode for Div 3 HPCS Diesel Generator & Increasing Test Loads for Div 1 & 2 Batteries Project stage: Other AECM-86-0150, Application for Amend to License NPF-29,adding Another Undervoltage Protection Device & Emergency Override of Test Mode for Div 3 Diesel Generator & Increasing Test Loads for Div 1 & 2 Batteries.Fee Paid1986-05-19019 May 1986 Application for Amend to License NPF-29,adding Another Undervoltage Protection Device & Emergency Override of Test Mode for Div 3 Diesel Generator & Increasing Test Loads for Div 1 & 2 Batteries.Fee Paid Project stage: Request ML20205S2021986-05-27027 May 1986 Forwards Safety Evaluation Supporting Util 860110 Proposal to Remove Four Peak Recording Accelerographs Installed on Reactor Piping Due to Inoperability Caused by Operating Transients & Adequacy of Other Seismic Instrumentation Project stage: Approval ML20205S2151986-05-27027 May 1986 Safety Evaluation Supporting Util 860110 Proposal to Remove Four Peak Recording Accelerographs Mounted on Reactor Piping Project stage: Approval AECM-86-0163, Provides Addl Info to 860321 Proposed Change PCOL-86/04 to License NPF-29 Re Mods to Automatic Depressurization Sys Per BWR Owners Group Evaluation of NUREG-0737,Item II.K.3.18. Info Clarifies Changes Made to Sys Initiation Circuitry1986-05-30030 May 1986 Provides Addl Info to 860321 Proposed Change PCOL-86/04 to License NPF-29 Re Mods to Automatic Depressurization Sys Per BWR Owners Group Evaluation of NUREG-0737,Item II.K.3.18. Info Clarifies Changes Made to Sys Initiation Circuitry Project stage: Request AECM-86-0111, Forwards Supplemental Info Re Design Change to Add Interlocks to ECCS Injection Valves,Per NRC 860403 Telcon. Approval of 850812 Proposed Amend to Tech Specs Also Requested1986-05-30030 May 1986 Forwards Supplemental Info Re Design Change to Add Interlocks to ECCS Injection Valves,Per NRC 860403 Telcon. Approval of 850812 Proposed Amend to Tech Specs Also Requested Project stage: Supplement AECM-86-0221, Application for Amend to License NPF-29,changing Tech Spec Seismic Monitoring Instrumentation Tables to Delete four- Peak Recording Accelerographs on Reactor Piping & Make Measurement Values Consistent.Fee Paid1986-07-15015 July 1986 Application for Amend to License NPF-29,changing Tech Spec Seismic Monitoring Instrumentation Tables to Delete four- Peak Recording Accelerographs on Reactor Piping & Make Measurement Values Consistent.Fee Paid Project stage: Request ML20207E7261986-07-15015 July 1986 Proposed Changes to Tech Spec Seismic Monitoring Instrumentation Tables 3.3.7.2-1 & 4.3.7.2-1 to Delete four- Peak Recording Accelerographs on Reactor Piping & Make Measurement Values Consistent Project stage: Request AECM-86-0234, Forwards Clarification Re Proposed Mod to License Condition 2.C(20) Concerning Standby Svc Water Sys1986-07-25025 July 1986 Forwards Clarification Re Proposed Mod to License Condition 2.C(20) Concerning Standby Svc Water Sys Project stage: Other AECM-86-0232, Forwards Tabulation & Analyses for Standby Svc Water Cooling Towers Based on Max 30-day Average Wet Bulb & Refueling Outage 18,per NRC Request for Worst Case Scenario of Util 860519 Analyses1986-07-29029 July 1986 Forwards Tabulation & Analyses for Standby Svc Water Cooling Towers Based on Max 30-day Average Wet Bulb & Refueling Outage 18,per NRC Request for Worst Case Scenario of Util 860519 Analyses Project stage: Request ML20209D1521986-08-28028 August 1986 Notice of Consideration of Issuance of Amend to License NPF-29 & Proposed NSHC Determination & Opportunity for Hearing Re Addition of Specs to Table 3.3.3-1, ECCS Actuation Instrumentation Project stage: Other ML20209D1361986-09-0202 September 1986 Requests Notice of Consideration of Issuance of Amend to License NPF-29 & Proposed NSHC Determination & Opportunity for Hearing Re Addition of Specs to Table 3.3.3-1, ECCS Actuation Instrumentation Be Expeditiously Published in Fr Project stage: Other AECM-86-0329, Submits List of Affected Tech Spec Pages,Effective Dates & Associated Amend Numbers,In Response to NRC 860827 & 1006 Requests1986-10-14014 October 1986 Submits List of Affected Tech Spec Pages,Effective Dates & Associated Amend Numbers,In Response to NRC 860827 & 1006 Requests Project stage: Other AECM-86-0332, Advises of Effective Dates for Amends 6 & 8 to License NPF-29 for Listed Tech Specs,In Response to 851021 & 860827 Requests1986-10-17017 October 1986 Advises of Effective Dates for Amends 6 & 8 to License NPF-29 for Listed Tech Specs,In Response to 851021 & 860827 Requests Project stage: Other 1985-09-26 |
ML20205S202 | |
Person / Time | |
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Site: | Grand Gulf ![]() |
Issue date: | 05/27/1986 |
From: | Butler W Office of Nuclear Reactor Regulation |
To: | Kingsley O MISSISSIPPI POWER & LIGHT CO. |
Shared Package | |
ML20205S206 | List: |
References | |
TAC-60467, TAC-61931, NUDOCS 8606120081 | |
Download: ML20205S202 (3) | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8911999-10-13013 October 1999
[Table view]Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210E3251999-07-23023 July 1999 Forwards Insp Rept 50-416/99-07 on 990622-25.No Violations Noted.Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise Was Conducted ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210B1031999-07-15015 July 1999 Forwards Insp Rept 50-416/99-08 on 990502-0612.Determined That Three Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7511999-07-0909 July 1999 Responds to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. as Result of NRC Review of Util Responses,Info Revised in Rvid & Rvid Version 2 Will Be Released ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20196K4901999-07-0101 July 1999 Discusses Relief Requests PRR-E12-01,PRR-E21-01,PRR-E22-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01 Submitted by EOI on 971126 & 990218.SE Accepting Alternatives Proposed by Util Encl ML20196J5711999-06-30030 June 1999 Advises That Versions of Submitted Info in 990506 Application & Affidavit, Re Proposed Amend to Revise Ts,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA 1999-09-09 Category:NRC TO UTILITY MONTHYEARML20062G4511990-11-21021 November 1990
[Table view]Forwards List of Unimplemented GSIs at Facility,Per Generic Ltr 90-04.Timely Completion Requested IR 05000416/19900221990-11-15015 November 1990 Forwards Insp Rept 50-416/90-22 on 901022-26.No Violations or Deviations Noted.W/O Encl ML20058E8921990-10-30030 October 1990 Forwards Insp Rept 50-416/90-20 on 900915-1019.No Violations or Deviations Noted ML20058B4321990-10-25025 October 1990 Grants 900709 Request for Relief from Requirements for Leakage Testing of RCS in ASME Code,Section Xi.Se Encl ML20062B1681990-10-19019 October 1990 Approves Scheduled Implementation of Dcrdr Mods by 920731 (Fifth Refueling Outage) ML20062B1701990-10-19019 October 1990 Confirms That Util Actions in Comply W/Generic Ltr 89-04 Guidance Re Inservice Testing Programs ML20058B0771990-10-17017 October 1990 Ack Receipt of 901002 Responses Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/90-15 ML20062B3281990-10-15015 October 1990 Advises That 900924 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2, Part 2 'Vendor Interface for Safety-Related Components,' Acceptable ML20058A5711990-10-12012 October 1990 Forwards Insp Rept 50-416/90-18 on 900917-21.No Violations or Deviations Noted ML20062B6991990-10-12012 October 1990 Requests Completion of Analyses of Liquid Samples Spiked W/ Radionuclides within 60 Days of Receipt of Ltr ML20058A2471990-10-11011 October 1990 Forwards Insp Rept 50-416/90-16 on 900827-31.No Violations or Deviations Noted ML20059N4931990-10-0101 October 1990 Informs That Util Responses to Generic Ltr 88-01 Acceptable, W/Exception to Responses Re Tech Spec Changes.Safety Evaluation & Technical Evaluation Rept Encl ML20059L3891990-09-0606 September 1990 Forwards Insp Rept 50-416/90-15 on 900721-0817 & Notice of Violation.Nrc Believes Negative Trend in Area of Attention to Detail Needs to Be Addressed ML20056B3431990-08-20020 August 1990 Forwards Insp Rept 50-416/90-13 on 900709-13.Violations Noted But Not Cited ML20058P8081990-08-15015 August 1990 Discusses Util 891221 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve (MOV) Testing & Surveillance. Recommends That Testing of MOVs in-situ Be Performed Under Design Basis Conditions ML20059A0751990-08-0606 August 1990 Advises That Rev 9 to Operational QA Manual,GGNS-TOP-1A, Acceptable,Per ML20058L5941990-07-31031 July 1990 Advises That 900717 Rev 17 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20058M4181990-07-25025 July 1990 Forwards Insp Rept 50-416/90-12 on 900616-0720.No Violations or Deviations Noted ML20055G5221990-07-18018 July 1990 Forwards Safety Evaluation Concluding That Procedures Generation Package Must Be Revised by Addressing Both Programmatic Improvements & Results of EOP Insp ML20055G5301990-07-17017 July 1990 Forwards Fr Notice of Withdrawal of Applications for Amend to License NPF-29 to Delete Certain Test,Vent & Drain Valves from Tech Spec Table 3.6.4-1 ML20055G0321990-07-16016 July 1990 Forwards Safety Evaluation Re Criticality Analysis of Fuel in Spent Fuel Racks Including Effect of Boraflex Gaps Which Could Occur Up Through Cycle 4.Storage Racks Can Safely Accomodate Max Reactivity of Unit 1 Cycle 1 Through Cycle 4 ML20055F9051990-07-16016 July 1990 Forwards Safety Evaluation Supporting Criticality Analysis for Cycle 5 Fuel in Spent Fuel Storage Racks IR 05000416/19900081990-07-12012 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/90-08 ML20055H4391990-07-0505 July 1990 Ack Receipt of Providing Scenario for Emergency Preparedness Exercise Scheduled for Wk of 900827 ML20055E5691990-07-0505 July 1990 Grants 900426 Application for Withholding of ANF-90-060(P), Criticality Safety Analysis for Grand Gulf Spent Fuel Storage Racks W/ANF-1.4 Fuel Assemblies, Per 10CFR2.790(b)(5)) ML20055E8871990-07-0202 July 1990 Forwards Notice of Withdrawal of Util 900504 Application for Amend to License NPF-29,extending Implementation Date for Amend 65 to License,Per 900606 Request ML20055F2061990-06-29029 June 1990 Advises That 900618 Rev 3 to Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20058K5161990-06-28028 June 1990 Advises That Units 1 & 2 Transferred to Project Directorate IV-1,effective 900604 ML20055E2441990-06-21021 June 1990 Grants 880630 Request to Withhold GE MDE-80-0485, Tech Spec Improvement Analysis for Reactor Protection Sys for Grand Gulf Nuclear Station,Units 1 & 2, Per 10CFR2.790 ML20059M8491990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248C9051989-09-26026 September 1989 Forwards Insp Rept 50-416/89-20 on 890828-0901.No Violations Noted ML20247N2171989-09-18018 September 1989 Requests Radius & Thickness (Rt),(Rt)Ndt Values for Reactor Vessel Flange Matl & Upper Shelf Energy Values for Matls,Per Generic Ltr 88-11,by 891015 ML20247G6681989-09-12012 September 1989 Forwards Insp Rept 50-416/89-19 on 890715-0825 & Notice of Violation ML20247G6571989-09-0808 September 1989 Advises That Rev 19 to Emergency Plan Consistent W/Planning Stds of 10CFR50.47(b) & Requirements of App E to 10CFR50 ML20247D8591989-09-0101 September 1989 Ack Receipt of 890821 & 25 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/89-17. Implementation of Corrective Actions Will Be Examined During Future Insps ML20247A9331989-08-31031 August 1989 Advises That Requalification Program Evaluation Scheduled for Wks of 891113 & 27.Facility Should Furnish Approved Items Listed in Encl 1 Ref Matl Requirements by 890915 ML20246G3541989-08-25025 August 1989 Forwards Requests for Addl Info Re Gaps in Boraflex of High Density Spent Fuel Racks.Response Requested by 891015 ML20246N0771989-08-23023 August 1989 Requests That Util Provide Ref Matls for Reactor Operator & Senior Reactor Operators Licensing Exams Scheduled for Wk of 891218.Info Must Reach NRC by 891012.Related Exam Requirements Info Encl ML20246D7961989-08-21021 August 1989 Forwards Safety Evaluation Granting Util 880524 Requests for Relief from Certain Requirements in ASME Code,Section XI Re Inservice Insp Program IR 05000416/19890101989-08-21021 August 1989 Ack Receipt of Informing NRC of Action Taken to Correct Violations Noted in Insp Rept 50-416/89-10 IR 05000416/19890141989-08-15015 August 1989 Ack Receipt of 890712 & 13 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/89-14. Implementation of Corrective Actions Will Be Examined During Future Insps IR 05000416/19890161989-08-15015 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/89-16. Implementation of Corrective Actions Will Be Examined During Future Insps ML20245K2511989-08-11011 August 1989 Advises That 890609 Rev 8 to Operational QA Program Consistent w/10CFR50.54(a) & Acceptable ML20245J7961989-08-0202 August 1989 Forwards Insp Rept 50-416/89-18 on 890710-14.No Violations or Deviations Noted ML20247P6571989-07-31031 July 1989 Provides Evaluation of Util Proposed Revised PASS Test Procedure,Per .Util Commitments to Document Changes to PASS Sampling Program Acceptable 1990-09-06 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217F8911999-10-13013 October 1999
[Table view]Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified ML20210E3251999-07-23023 July 1999 Forwards Insp Rept 50-416/99-07 on 990622-25.No Violations Noted.Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise Was Conducted ML20210B1031999-07-15015 July 1999 Forwards Insp Rept 50-416/99-08 on 990502-0612.Determined That Three Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20209D7511999-07-0909 July 1999 Responds to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. as Result of NRC Review of Util Responses,Info Revised in Rvid & Rvid Version 2 Will Be Released ML20196K4901999-07-0101 July 1999 Discusses Relief Requests PRR-E12-01,PRR-E21-01,PRR-E22-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01 Submitted by EOI on 971126 & 990218.SE Accepting Alternatives Proposed by Util Encl ML20196J5811999-06-30030 June 1999 Advises That Version of Info Submitted in 990504 Application & Affidavit Re Engineering Rept ME-98-001-00,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 as Amended ML20196J5711999-06-30030 June 1999 Advises That Versions of Submitted Info in 990506 Application & Affidavit, Re Proposed Amend to Revise Ts,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20195G3811999-06-0909 June 1999 Ack Receipt of ,Which Transmitted Emergency Plan Procedure 10-S-01-1,Rev 103,under Provisions of 10CFR50, App E,Section V ML20195G2971999-06-0909 June 1999 Ack Receipt of Re Emergency Plan Procedure 10-S-01-1,rev 104.No Violations Identified & Changes Subject to Insp to Confirm Effectiveness ML20195G3511999-06-0909 June 1999 Ack Receipt of 980831 & 1022 Ltrs,Which Transmitted Changes to Grand Gulf Emergency Plan,Rev 36 & 37,under Provisions of 10CFR50,App E,Section V ML20207D3351999-05-27027 May 1999 Forwards Insp Rept 50-416/99-05 on 990321-0501.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207A6961999-05-21021 May 1999 Forwards Insp Rept 50-416/99-06 on 990419-23.No Violations Noted.Determined That Fire Protection Program Was Implemented IAW Requirements of License & GL 86-10.One Unresolved Item Noted Re fire-induced Failures on Equipment ML20206U3851999-05-18018 May 1999 Forwards Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207A7561999-05-17017 May 1999 Ack Receipt of Which Transmitted Exercise Scenario for Emergency Plan Exercise Scheduled for 990623. Some Parts of Exercise Scenario Package Not Submitted & Being Developed ML20206N3921999-05-11011 May 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Organization Chart Encl ML20206K1261999-05-0707 May 1999 Informs That on 990407 NRC Administered Gfes of Written Operator Licensing Exam.Facility Did Not Participate in Exam.Copy of Master Exam with Answer Key Encl.Without Encl ML20206E0571999-04-29029 April 1999 Discusses EOI 960418 Request for License Amend for GGNS That Would Permit Addl Method of Fuel Movement & Loading in Core When Control Rods Removed.Determined That Insufficient Info Provided to Permit Completion of Review ML20206B0951999-04-23023 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/99-01 & NOV .Reply Found to Be Responsive to Concerns Raised in Nov.Implementation of C/As Will Be Reviewed in Future Insps ML20206B3601999-04-23023 April 1999 Forwards Insp Rept 50-416/99-04 on 990131-0320.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206E7661999-04-19019 April 1999 Submits Summary of 990415 Meeting Conducted in Port Gibson, Mi Re Results of Plant Performance Review Completed on 990211 & Transmitted on 990319.List of Attendees Encl ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205M9421999-04-13013 April 1999 Forwards Emergency Response Data System Implementation Documents.Data Point Library Updates for Kewaunee (271), San Onofre (272) & Clinton (273) Encl.Also Encl Plant Attribute Library Update for Grand Gulf (274).Without Encls IR 05000416/19980131999-04-0606 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/98-13 .Discussions on 990330 Resulted in Addl C/A Commitments to Address Violation Re Onsite Investigation ML20205J1051999-03-29029 March 1999 Forwards Objectives for Plant,Unit 1 1999 FEMA Emergency Plan Exercise Scheduled for 990623 ML20205E8701999-03-19019 March 1999 Advises of Completion of Plant Performance Review on 990211 to Develop Integrated Understanding of Safety Performance. Overall Performance Acceptable.Isolated Examples of Failure to Follow Procedures Noted ML20207L3621999-03-0303 March 1999 Advises That Effective 990217,NRC Project Mgt Responsibilities for Grand Gulf Nuclear Station Transferred to Sp Sekerak 1999-09-09 |
Text
a NAY 2 71986 Docket No. 50-416 DISTRIBUTION (Docket. File r LKintner NRC PDR M0'Brien l LPDR ACRS(10)
Mr. Oliver D. Kingsley, Jr. PD#4 Rdg. Alee Vice President,' Nuclear Operations RBernero Mississippi Power & Light Company Young, OELD
- P.O. Box 23054 EJordan Jackson, Mississippi 39205 BGrimes JPartlow
Dear Mr. Kingsley:
SUBJECT:
PEAK RECORDING ACCELER0 GRAPHS ON REACTOR PIPING RE: Grand Gulf Unit 1 l By letter dated January 10, 1986, the Mississippi Power & Light Company proposed to remove four peak recording accelerographs installed on reactor piping because they are made inoperable by operating transients and because other seismic instrumentation included in the plant design is adequate for post seismic damage evaluation.
The NRC staff has reviewed the licensee's January 10, 1986 submittal. The staff's safety evaluation is enclosed. The staff concludes that the four peak recording accelerographs which are mounted on the reactor piping do not serve any meaningful purpose for post-seismic damage evaluation and, therefore, can be deleted. The staff also concludes that with the installation of a triaxial strong motion accelerometer as required by License Condition 2.C.(7) and the other installed seismic instruments in the plant, there are sufficient seismic instruments to provide required information for post-seismic damage evaluation.
Sincerely, Original signed by Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Enclosure:
As stated cc w/ enclosure:
See next page
/
P # /PM PD#4/D LKintner:lb WButler g /,g7/86 5 /2786 B606120081 860527 PDet ADOCK 05000416 P pp
/pn'ro,v 'o UNITED STATES
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'k NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 j
k./ * ... MAY 2 7 TA5 Docket No. 50-416 Mr. Oliver D. Kingsley, Jr.
Vice President, Nuclear Operations Mississippi Power & Light Company P.O. Box 23054 Jackson, Mississippi 39205
Dear Mr. Kingsley:
SUBJECT:
PEAK RECORDING ACCELER0 GRAPHS ON REACTOR PIPING RE: Grand Gulf Unit 1 By letter dated January 10, 1986, the Mississippi Power & Light Company proposed to remove four peak recording accelerographs installed on reactor piping because they are made inoperable by operating transients and because other seismic instrumentation included in the plant design is adequate for post seismic damage evaluation.
The NRC staff has reviewed the licensee's January 10, 1986 submittal. The staff's safety evaluation is enclosed. The staff concludes that the four peak recording accelerographs which are mounted on the reactor piping do not serve any meaningful purpose for post-seismic damage evaluation and, therefore, can be deleted. The staff also concludes that with the installation of a triaxial strong motion accelerometer as required by License Condition 2.C.(7) and the other installed seismic instruments in the plant, there are sufficient seismic instruments to provide required information for post-seismic damage evaluation.
Sincerely, Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Enclosure:
As stated cc w/ enclosure:
See next page t
t
l t 1 Mr. Oliver D. Kingsley, Jr.
Mississippi Power & Light Company Grand Gulf Nuclear Staiton cc:
Robert B. McGehee, Esquire The Honorable William J. Guste, Jr.
Wise, Carter, Child, Steen and Caraway Attorney General P.O. Box 651 Department of Justice Jackson, Mississippi 39205 State of Louisiana Baton Rouge, Louisiana 70804 Nicholas S. Reynolds, Esquire Bishop, Liberman, Cook, Purcell Office of the Governor and Reynolds State of Mississippi 1200 17th Street, N.W. Jackson, Mississippi 39201 Washington, D. C. 20036 Attorney General Mr. Ralph T. Lally Gartin Building Manager of Quality Assurance Jackson, Mississippi 39205 Middle South Services, Inc.
P.O. Box 61000 Mr. Jack McMillan, Director New Orleans, Louisiana 70161 Division of Solid Waste Management Mississippi Department of Natural Mr. Larry F. Dale, Director ,
Resources Nuclear Licensing and Safety Bureau of Pollution Control
~
Mississippi Power & Light Company Post Office Box 10385 P.O. Box 23054 Jackson, Mississippi 39209 Jackson, Mississippi 39205 Alton B. Cobb, M.D.
Mr. R. W. Jackson, Project Engineer State Health Officer Bechtel Power Corporation State Board of Health 15740 Shady Grove Road P.O. Box 1700 Gaithersburg, Maryland 20877-1454 Jackson, Mississippi 39205 Mr. Ross C. Butcher President Senior Resident Inspector Claiborne County Board of Supervisors U.S. Nuclear Regulatory Commission Port Gibson, Mississippi 39150 Route 2, Box 399 Port Gibson, Mississippi 39150 Mr. Ted H. Cloninger Vice President, Nuclear Engineering Regional Administrator, Region II and Support U.S. Nuclear Regulatory Commission, Mississippi Power & Light Company 101 Marietta Street, N.W., Suite 2900 Post Office Box 23054 Atlanta, Georgia 30323 Jackson, Mississippi 39205 Mr. J. E. Cross Grand Gulf Nuclear Station Site Director Mississippi Power & Light Company P.O. Box 756 Port Gibson, Mississippi 39150 Mr. C. R. Hutchinson GGNS General Manager Mississippi Power & Light Company --
4 Post Office Box 756 Port Gibson, Mississippi 39150