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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement
Results
Other: AECM-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 Schedule, 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 Conditions, 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 Shutdown, 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 Implemented, 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 Requests, 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, AECM-86-0234, Forwards Clarification Re Proposed Mod to License Condition 2.C(20) Concerning Standby Svc Water Sys, AECM-86-0329, Submits List of Affected Tech Spec Pages,Effective Dates & Associated Amend Numbers,In Response to NRC 860827 & 1006 Requests, AECM-86-0332, Advises of Effective Dates for Amends 6 & 8 to License NPF-29 for Listed Tech Specs,In Response to 851021 & 860827 Requests, ML20133P171, ML20154R546, ML20155J934, ML20209D136, ML20209D152
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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 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-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 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 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 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 ML20205S2151986-05-27027 May 1986 Safety Evaluation Supporting Util 860110 Proposal to Remove Four Peak Recording Accelerographs Mounted on Reactor Piping Project stage: Approval 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 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-86-0163, 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-86-0221, 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 1986-01-10
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210P1611999-08-0404 August 1999 Summary of 990415 Meeting with Utils in Knoxville,Tn Re Status of Mark 3 Program Designed to Determine & Validate Submerged Structure Drag Loads of Newley Installed ECCS Strainers at Perry,Grand Gulf & Clinton Facilities ML20198G5501998-12-18018 December 1998 Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop Encl ML20155H3931998-11-0202 November 1998 Summary of 981007 Meeting with Util Re Review Status of Standard Quality Assurance Manual for All Util Sites.List of Meeting Attendees Encl ML20154C4771998-10-0202 October 1998 Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl ML20237E0271998-08-25025 August 1998 Summary of 980625 Meeting W/Entergy Operations,Inc to Discuss Bulletin 96-003 Re Installation of ECCS Suction Strainer in Ninth Refueling Outage for Plant.List of Attendees & Licensee Handout ML20236M0501998-07-0808 July 1998 Summary of 980702 Meeting W/Entergy Operations,Inc to Discuss Review Status of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20236F8171998-06-24024 June 1998 Summary of 980331 Meeting W/Util to Brief NRC on Licensee Risk Mgt of Upcoming Ninth Refueling Outage.List of Attendees & Handouts Encl ML20217K5141998-04-24024 April 1998 Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl ML20217K3461998-04-24024 April 1998 Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl ML20217F4811998-03-26026 March 1998 Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20216C6471998-03-0505 March 1998 Summary of 980123 Meeting W/Entergy Operations,Inc Re EP Changes Being Considered by Licensee.List of Meeting Attendees,Meeting Agenda & Info Provided by Licensee at Meeting in Handout Encl ML20203B5741998-02-11011 February 1998 Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda Encl ML20212G8521997-10-29029 October 1997 Summary of 971022 Meeting W/Entergy Svcs,Inc Re Development & Implementation of Common or Std QAP for All Sites.List of Meeting Attendees & Viewgraphs Encl ML20217E0131997-09-29029 September 1997 Trip Rept of 970825-26 Visit to Plant,Unit 1 for Interviews in Preparation of Salp.Agenda for Interviews Encl ML20198R3481997-09-0404 September 1997 Trip Rept of 961121 Visit to GGNS to Discuss Implementation Methodologies Employed for Graded Aq in Procurement Area ML20141H3661997-07-17017 July 1997 Summary of 970710 Meeting W/Util to Discuss Licensee Emergency Plan Change 28.001-95 & to Determine If Change Reduces Effectiveness of Emergency Plan for Plant,Unit 1. List of Attendees,Agenda & Info Provided by Licensee Encl ML20137U1331997-04-10010 April 1997 Summary of 970325 Meeting W/Util in Clariborne County,Ms to Discuss Entergy Operations,Inc MOV Thrust Methodology Used for GL 95-07 for Plant.List of Attendees & Info Provided by NRC Staff Encl ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML20132D1421996-12-17017 December 1996 Summary of 960827 Meeting W/Util in Rockville,Md Re Graded Quality Assurance Initiative at Facility.W/Attendees List, Summary of Licensee Presentation & Licensee Expert Panel Guidance Document ML20149M3611996-12-11011 December 1996 Summary of 96111 Meeting W/Licensee in Rockville,Md to Discuss Comments Developed in Response to NRC Advance Notice of Proposed Rulemaking on Financial Assurance Requirements for Decommissioning Nuclear Reactors.List of Attendees Encl ML20134N5661996-11-21021 November 1996 Summary of 961003 Meeting W/Licensee in Rockville,Md to Discuss Licensee Upcoming Eighth Refueling Outage for Ggns,Unit 1 ML20134M6611996-11-21021 November 1996 Summary of 961114 Meeting W/Listed Licensees in Rockville,Md to Discuss Results of Self Assessment of Accuracy of Info in FSARs for Four Nuclear Reactor Sites.List of Attendees & Licensee Handout Encl ML20129G5261996-07-31031 July 1996 Summary of ACRS Plant Operations Subcommittee Meeting on 960521 to Review Proposed Rule on Shutdown Operations & Associated Reg Guide as Well as Studies on Shutdown Risk at Surry & Grand Gulf Nuclear Plants ML20059C4041993-12-27027 December 1993 Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md to Discuss Licensee Proposed Changes to Security Plans for Plant,Units 1 & 2.List of Attendees Encl ML20058P4491993-12-15015 December 1993 Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md Re 931021 Submittal of Proposed Alternative to 10CFR50.55a(f) & (g),10-Year Inservice Insp & Inservice Testing Update. List of Attendees Encl ML20058G3081993-11-19019 November 1993 Summary of Operating Reactors Events Meeting 93-43 on 931117 ML20056H5721993-08-0505 August 1993 Summary of Operating Reactors Events Meeting 93-28 on 930728 ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20062H4811990-11-28028 November 1990 Summary of 901023 Meeting W/Util Re Control Room Emergency Filtration Sys.Proposed Change to TS 3/4.7.2 & Handout Encl ML20056B4161990-08-17017 August 1990 Summary of 900615 Meeting W/Licensee at Site to Discuss Licensing Activities.List of Attendees,Meeting Agenda, Handout & Licensee Comments on Draft Safety Evaluation of Fire Protection Program Encl ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML20244D8961989-06-12012 June 1989 Summary of 890518 Meeting W/Util Re Performance of Licensing Activities.Meetings Should Be Scheduled to Seek Means for Eliminating Weaknesses Identified by NRC ML20244C6441989-06-0909 June 1989 Summary of 890517 Meeting W/Seri in Rockville,Md Re Licensee Plans for Fuel Cycle 5,which Include Use of New Type of Fuel Assembly Developed by Advanced Nuclear Fuels Corp ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20246L4791989-05-11011 May 1989 Summary of 890214 Meeting W/Util in Rockville,Md Re Pipe Support Calculations.List of Attendees & Handouts Encl ML20247F8481989-05-11011 May 1989 Summary of 890214 Meeting W/Util in Rockville,Md Re Proposed Alternate DHR Sys & Proposed Exceptions to Tech Spec 3.0.4. Agenda & Related Info Encl ML20196B5971988-12-0505 December 1988 Summary of 881116 Meeting W/Util to Brief Reviewers Re Request for Tech Spec Changes Per Generic Ltr 87-09 ML20195G0741988-11-15015 November 1988 Summarizes Discussions W/Licensee During CRGR 881102-03 Visit to Plant.Util Mgt Described Licensing History,Past SALP Records & Key Issues Which Resulted in Delays & Addl Costs.Util Rept of Visit to Foreign Reactors Encl.W/O Encl ML20206E3031988-11-15015 November 1988 Summary of 881110 Meeting W/Util in Rockville,Md Re Design Criteria & Safety Aspects of Alternate DHR Sys.Attendance List & Viewgraphs Encl ML20206E6711988-11-15015 November 1988 Summary of 881101 Meeting W/Licensee at Site Re Potential Changes to Tech Specs Concerning Review of Fire Protection Program & New Auxiliary Hoist for Fuel Handling Platform Over Spent Fuel Pool ML20155H9771988-10-18018 October 1988 Summary of 880831 Meeting W/Util in Rockville,Md Re Status of Leasing Activities & Schedule for Completion of Activities.Related Info,Including Meeting Agenda & List of Attendees Encl ML20245D8411988-09-28028 September 1988 Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920 ML20154E6161988-09-14014 September 1988 Summary of 880815 Meeting W/Util Re Plans for Third Refueling Outage.Major Activities During Outage Include: Chemical Cleaning of Standby Svc Water Sys,Low Pressure Turbine Insp & Inservice Insp of RCS ML20154E6511988-09-14014 September 1988 Summary of 880815 Meeting W/Util Re Potential Changes to Tech Specs.Other Actions Discussed Includes,Status of Completion of Conditions in Operating License & Actions Taken Re Problems Identified in Info Notices ML20153E4321988-09-0101 September 1988 Summary of 880728 Meeting W/Util on Licensing Actions Re Third Fuel Reload.List of Attendees & Viewgraphs Encl ML20151R5391988-08-0808 August 1988 Summary of 880623 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines. Resolution of Issues Listed ML20151R7011988-08-0808 August 1988 Summary of 880614 & 15 Meetings W/Util Re Potential Changes to Tech Specs,Allowing Change in Operational Modes When Limiting Conditions for Operation Not Met.List of Participants & Potential Tech Spec Changes Encl ML20150E0241988-06-21021 June 1988 Summary of 880615 Meeting W/Utils Re Proposed Establishment & Licensing of Sys Energy Resource,Inc as Operators & Licensing Agent for Plants 1999-08-04
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210P1611999-08-0404 August 1999 Summary of 990415 Meeting with Utils in Knoxville,Tn Re Status of Mark 3 Program Designed to Determine & Validate Submerged Structure Drag Loads of Newley Installed ECCS Strainers at Perry,Grand Gulf & Clinton Facilities ML20198G5501998-12-18018 December 1998 Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop Encl ML20155H3931998-11-0202 November 1998 Summary of 981007 Meeting with Util Re Review Status of Standard Quality Assurance Manual for All Util Sites.List of Meeting Attendees Encl ML20154C4771998-10-0202 October 1998 Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl ML20237E0271998-08-25025 August 1998 Summary of 980625 Meeting W/Entergy Operations,Inc to Discuss Bulletin 96-003 Re Installation of ECCS Suction Strainer in Ninth Refueling Outage for Plant.List of Attendees & Licensee Handout ML20236M0501998-07-0808 July 1998 Summary of 980702 Meeting W/Entergy Operations,Inc to Discuss Review Status of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20236F8171998-06-24024 June 1998 Summary of 980331 Meeting W/Util to Brief NRC on Licensee Risk Mgt of Upcoming Ninth Refueling Outage.List of Attendees & Handouts Encl ML20217K3461998-04-24024 April 1998 Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl ML20217K5141998-04-24024 April 1998 Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl ML20217F4811998-03-26026 March 1998 Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20216C6471998-03-0505 March 1998 Summary of 980123 Meeting W/Entergy Operations,Inc Re EP Changes Being Considered by Licensee.List of Meeting Attendees,Meeting Agenda & Info Provided by Licensee at Meeting in Handout Encl ML20203B5741998-02-11011 February 1998 Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda Encl ML20212G8521997-10-29029 October 1997 Summary of 971022 Meeting W/Entergy Svcs,Inc Re Development & Implementation of Common or Std QAP for All Sites.List of Meeting Attendees & Viewgraphs Encl ML20141H3661997-07-17017 July 1997 Summary of 970710 Meeting W/Util to Discuss Licensee Emergency Plan Change 28.001-95 & to Determine If Change Reduces Effectiveness of Emergency Plan for Plant,Unit 1. List of Attendees,Agenda & Info Provided by Licensee Encl ML20137U1331997-04-10010 April 1997 Summary of 970325 Meeting W/Util in Clariborne County,Ms to Discuss Entergy Operations,Inc MOV Thrust Methodology Used for GL 95-07 for Plant.List of Attendees & Info Provided by NRC Staff Encl ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML20132D1421996-12-17017 December 1996 Summary of 960827 Meeting W/Util in Rockville,Md Re Graded Quality Assurance Initiative at Facility.W/Attendees List, Summary of Licensee Presentation & Licensee Expert Panel Guidance Document ML20149M3611996-12-11011 December 1996 Summary of 96111 Meeting W/Licensee in Rockville,Md to Discuss Comments Developed in Response to NRC Advance Notice of Proposed Rulemaking on Financial Assurance Requirements for Decommissioning Nuclear Reactors.List of Attendees Encl ML20134N5661996-11-21021 November 1996 Summary of 961003 Meeting W/Licensee in Rockville,Md to Discuss Licensee Upcoming Eighth Refueling Outage for Ggns,Unit 1 ML20134M6611996-11-21021 November 1996 Summary of 961114 Meeting W/Listed Licensees in Rockville,Md to Discuss Results of Self Assessment of Accuracy of Info in FSARs for Four Nuclear Reactor Sites.List of Attendees & Licensee Handout Encl ML20129G5261996-07-31031 July 1996 Summary of ACRS Plant Operations Subcommittee Meeting on 960521 to Review Proposed Rule on Shutdown Operations & Associated Reg Guide as Well as Studies on Shutdown Risk at Surry & Grand Gulf Nuclear Plants ML20059C4041993-12-27027 December 1993 Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md to Discuss Licensee Proposed Changes to Security Plans for Plant,Units 1 & 2.List of Attendees Encl ML20058P4491993-12-15015 December 1993 Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md Re 931021 Submittal of Proposed Alternative to 10CFR50.55a(f) & (g),10-Year Inservice Insp & Inservice Testing Update. List of Attendees Encl ML20058G3081993-11-19019 November 1993 Summary of Operating Reactors Events Meeting 93-43 on 931117 ML20056H5721993-08-0505 August 1993 Summary of Operating Reactors Events Meeting 93-28 on 930728 ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20062H4811990-11-28028 November 1990 Summary of 901023 Meeting W/Util Re Control Room Emergency Filtration Sys.Proposed Change to TS 3/4.7.2 & Handout Encl ML20056B4161990-08-17017 August 1990 Summary of 900615 Meeting W/Licensee at Site to Discuss Licensing Activities.List of Attendees,Meeting Agenda, Handout & Licensee Comments on Draft Safety Evaluation of Fire Protection Program Encl ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML20244D8961989-06-12012 June 1989 Summary of 890518 Meeting W/Util Re Performance of Licensing Activities.Meetings Should Be Scheduled to Seek Means for Eliminating Weaknesses Identified by NRC ML20244C6441989-06-0909 June 1989 Summary of 890517 Meeting W/Seri in Rockville,Md Re Licensee Plans for Fuel Cycle 5,which Include Use of New Type of Fuel Assembly Developed by Advanced Nuclear Fuels Corp ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20247F8481989-05-11011 May 1989 Summary of 890214 Meeting W/Util in Rockville,Md Re Proposed Alternate DHR Sys & Proposed Exceptions to Tech Spec 3.0.4. Agenda & Related Info Encl ML20246L4791989-05-11011 May 1989 Summary of 890214 Meeting W/Util in Rockville,Md Re Pipe Support Calculations.List of Attendees & Handouts Encl ML20196B5971988-12-0505 December 1988 Summary of 881116 Meeting W/Util to Brief Reviewers Re Request for Tech Spec Changes Per Generic Ltr 87-09 ML20206E3031988-11-15015 November 1988 Summary of 881110 Meeting W/Util in Rockville,Md Re Design Criteria & Safety Aspects of Alternate DHR Sys.Attendance List & Viewgraphs Encl ML20206E6711988-11-15015 November 1988 Summary of 881101 Meeting W/Licensee at Site Re Potential Changes to Tech Specs Concerning Review of Fire Protection Program & New Auxiliary Hoist for Fuel Handling Platform Over Spent Fuel Pool ML20155H9771988-10-18018 October 1988 Summary of 880831 Meeting W/Util in Rockville,Md Re Status of Leasing Activities & Schedule for Completion of Activities.Related Info,Including Meeting Agenda & List of Attendees Encl ML20245D8411988-09-28028 September 1988 Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920 ML20154E6161988-09-14014 September 1988 Summary of 880815 Meeting W/Util Re Plans for Third Refueling Outage.Major Activities During Outage Include: Chemical Cleaning of Standby Svc Water Sys,Low Pressure Turbine Insp & Inservice Insp of RCS ML20154E6511988-09-14014 September 1988 Summary of 880815 Meeting W/Util Re Potential Changes to Tech Specs.Other Actions Discussed Includes,Status of Completion of Conditions in Operating License & Actions Taken Re Problems Identified in Info Notices ML20153E4321988-09-0101 September 1988 Summary of 880728 Meeting W/Util on Licensing Actions Re Third Fuel Reload.List of Attendees & Viewgraphs Encl ML20151R5391988-08-0808 August 1988 Summary of 880623 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines. Resolution of Issues Listed ML20151R7011988-08-0808 August 1988 Summary of 880614 & 15 Meetings W/Util Re Potential Changes to Tech Specs,Allowing Change in Operational Modes When Limiting Conditions for Operation Not Met.List of Participants & Potential Tech Spec Changes Encl ML20150E0241988-06-21021 June 1988 Summary of 880615 Meeting W/Utils Re Proposed Establishment & Licensing of Sys Energy Resource,Inc as Operators & Licensing Agent for Plants ML20154S0341988-05-27027 May 1988 Summary of 880519 Meeting W/Middle South Utils Representatives Re Proposed Establishment & Licensing of Middle South Utils Nuclear Operating Co.Agenda Encl ML20154G8161988-05-17017 May 1988 Summary of 880510 Meeting W/Util Re Licensing Matters.Util Will Submit Commitment to Install GE Wide Range Monitor by Fourth Refueling Outage.List of Attendees Encl ML20149J9181988-02-19019 February 1988 Summary of 871202 Meeting to Brief Director & Assistant Director for Region II Reactors in NRR on Util Operations. Meeting Attendee & Handout Encl 1999-08-04
[Table view] |
Text
_-_
s, p*!t%'o g UNITED STATES 8 o I4UCLEAR REGULATORY COMMISSION E, WASHINGTON, D. C. 20555
% **.** #} APR 8W Docket no. 50-416 LICENSEE: Mississippi Power & Light Comapny (MP&L)
FACILITY: Grand Gulf Nuclear Station, Unit 1
SUBJECT:
SUMMARY
OF APRIL 1, 1986 MEETING REGARDING INTERLOCKS FOR ECCS PRESSURE ISOLATION VALVES The purpose of the meeting was to discuss resolution of an issue regarding interlocks for ECCS injection valves which also function as pressure isolation valves. Enclosure 1 is a list of attendees. Enclosure 2 is a handout prepared by the licensee. Enclosure 3 is a November 22, 1985 staff letter which defines the issue.
Prior to the meeting, the licensee had proposed Technical Specification changes (by letter dated August 12,1985) to implement a design change to add interlocks to the ECCS injection valves to prevent over pressurization of the low pressure coolant injection systems by the higher pressure reactor coolant system due to inadvertant opening of the valves. The licensee had proposed to include inter-locks for the automatic opening of the valves by a LOCA signal, but not to include interlocks for manual controls on the remote shutdown panel. Further the licensee had proposed to use a set point for the interlocks that was 110% of the reactor piping system design pressure, as defined in the ASME Code. The staff had deter-mined that the proposed design criteria, as supplemented by letters dated September 25, October 5 and October 22, 1985, were unacceptable and provided its position and alternative acceptable criteria by letter dated November 22, 1985 (Enclosure 3).
During the meeting, the licensee summarized its remote shutdown panel (RSP) design criteria, using the information presented in Enclosure 2 as an outline. The licensee stated that the SRP is not designed with the same philosophy concerning interlocks as is the control room control circuits (e.g., a pressure permissive is not required for the corresponding RSP control circuit). The RSP rooms contain only RSP equipment and each electrical division is in a separate room. Access to the rooms is administratively controlled by locked doors. Circuits in the panels are normally energized. There are only a few interlocks on valve controls on the remote shutdown panel and these are valve-to-valve interlocks and not
. pressure activated interlocks as associated with various control room circuits.
Other features are outiineo in Pages 3-6 of Enclosure 2.
. The licensee's position is that because of the security provided for these RSP rooms and infrequent use and access and because of training of operators who are authorized to use the panels, inadvertant operation of these ECCS valves from the RSP is unlikely and pressure permissive interlocks should not be required.
Regarding the set points for interlocks on control room circuits, the licensee's position is that the 1974 ASME Code for which Grand Gulf is designed allows tran-sients to raise the system pressure to 110% of design pressure (sizing and setting 8604170437 860408 PDR ADOCK 05000416 P PDR ,
o
relief valves for overpressurization transients). The 1977 ASME Code which first addressed setpoints for interlocks and specifies use of design pressure for the set point is not a requirement for the Grand Gulf plant because the construction permit was issued in 1974. The licensee has estimated that lowering the interlock setpoint 50 psi to the design pressure of the low pressure system would increase the calculated peak cladding temperature following a LOCA by 6 F (to 2157'F) and that this would unnecessarily reduce the margin to the limiting 2200 F thus reducing the margin available for operational enhancements. The licensee's position is summarized on Page 2 of Enclosure 2. The calculation of the interlock setpoints is shown on Page 7 of Enclosure 2.
At the conclusion of the meeting, the licensee proposed alternative positions which are similar to the alternative positions indic~ated in staff's November 22, 1985 letter (Enclosure 3). The licensee proposed the use of key lock switches at the remote shut down panel (not the motor control center) because of the poor access of the motor control center if operation of the ECCS valves was needed for shut down. The licensee indicated that they were confident the low design pressure ECCS systems could withstand 110% of design pressure for the transients resulting from a LOCA or inadvertant manual opening of the valves during plant heatup or cooldown. However, the licensee did not believe the major analytical effort necessary to increase the ASME Code design pressure rating by 50 psi was needed. The staff said it would consider the information presented in the meeting and inform the licensee of its conclusion by telephone.
By telephone on April 3,1986, the staff informed the licensee that the alter-natives proposed in the April 1, 1986 meeting appeared to be acceptable. The staff indicated that the key locked control switches should be separate from the present spring-return-to-auto control switches and that relevant infor-mation regarding design of the switches and administrative controls should be provided in the supplemental letter. The staff also said that a statement should be provided to the effect that pressures equivalent to the upper analytical limit of the setpoint will satisfy ASME Code stress allowable values for the piping, valves and other components of the ECCS systems.
L. L. Kintner, Project Manager '
BWR Project Directorate No. 4 Division of BWR Licensing Enclcsures:
As stated ct: See next page
relief valves for overpressurization transients). The 1977 ASME Code which first addressed setpoints for interlocks and specifies use of design pressure for the set point is not a requirement for the Grand Gulf plant because the construction permit was issued in 1974. The licensee has estimated that lowering the interlock setpoint 50 psi to the design pressure of the low pressure system would increase the calculated peak cladding temperature following a LOCA by 6 F (to 2157 F) and that this would unnecessarily reduce the margin to the limiting 2200 F thus reducing the margin available for operational enhancements. The licensee's position is summarized on Page 2 of Enclosure 2. The calculation of the interlock setpoints is shown on Page 7 of Enclosure 2.
At the conclusion of the meeting, the licensee proposed alternative positions which are similar to the alternative positions indicated in staff's November 22, 1985 letter (Enclosure 3). The licensee proposed the use of key lock switches at the remote shut down panel (not the motor control center) because of the poor access of the motor control center if operation of the ECCS valves was needed for shut down. The licensee indicated that they were confident the low design pressure ECCS systems could withstand 110% of design pressure for the transients resulting from a LOCA or inadvertant manual opening of the valves during plant heatup or cooldown. However, the licensee did not believe the major analytical effort necessary to increase the ASME Code design pressure rating by 50 psi was needed. The staff said it would consider the information presented in the meeting and inform the licensee of its conclusion by telephone.
By telephone on April 3, 1986, the staff informed the licensee that the alter-natives proposed in the April 1,1986 meeting appeared to be acceptable. The staff indicated that the key locked control switches should be separate from the present spring-return-to-auto control switches and that relevant infor-mation regarding design of the switches and administrative controls should be provided in the supplemental letter. The staff also said that a statement should be provided to the effect that pressures equivalent to the upper analytical limit of the setpoint will satisfy ASME Code stress allowable values for the piping, valves and other components of the ECCS systems.
Orleind siened ty L. L. Kintner, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing Enclosuret:
As stated
. DISTRIBUTION cc: See next page . Docket. File- ACRS(10)
NRC POR NRC Participants local PDR PD#4 Reading
- WButler
/ LKintner PD#4 PM PD#4/D [ Young, OELD LKintner:lb WButler i EJordan 04/[/86 04 /86'4 BGrimes
Mr. Oliver D. Kingsley, Jr.
Mississippi Power & Light Company Grand Gulf Nuclear Staiton ec:
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 1 Mr. Ralph T. Lally Gartin Building i 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 i 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 9
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 l Mississippi Power & Light Company '
Post Office Box 756 Port Gibson, Mississippi 39150 y - _-
, , . _ . . . _ , -,-c.- -- . , - -,r
Enclosure 1 ATTENDEES NRC - MP&L Meeting - April 1, 1986 .
NRC MP&L l L. L. Kintner Sam H. Hobbs Charles C. Graves Wayne Russell Wayne Hodges Thomas Barnett Jim Lombardo Mike Withrow Horace Shaw Joe Hendry W. Butler
B. Si'egel*
M. Srinivasan* i Bob Stevens Illinois Power Company P. J. Telthorst l
t' I
j l
O w r.,- - -- - .-, .e-,. , , . . , _ . - - . . . , - ._ -
,- 3 - -
Enclosure 2 LOW PRESSURE ECCS PRESSURE PERMISSIVE INTERLOCK MEETING AGENDA MP&L/NRC BETHESDA, MARYLAND APRIL 1, 1986 I. OVERVIEW 0F ISSUES REQUIREMENT OF LICENSE CONDITION 2.C.(18)
NO INTERLOCKS ON RSP LPCI/LPCS SETPOINT AB0VE 500 PSIG i GGNS COMMITMENTS /NRC SAFETY EVALUATIONS CURRENT INDUSTRY PRACTICES II. REMOTE SHUTDOWN PANEL
-III. LPCI/LPCS SETPOINT AB0VE 500 PSIG IV. MP&L'S POSITION J16 MISC 86031301 - 1
/
l
. l
.(. l III. MP&L'S POSITION DESIGN CHANGE GOES BEYOND THE DESIGN BASIS OF GG
- 1) INSTALLATION OF INTERLOCKS TO THE VALVE CONTROL CIRCUITS IN THE REMOTE SHUTDOWN PANEL TECH SPEC CHANGE DOES COMPLY WITH SRP 7.4 4
TECH SPEC SETPOINT DOES COMPLY WITH GGNS SSER2, SECTION 6.3.4 e
i
- MPal HAS AND ALWAYS WILL UTILIZE ACCEPTABLE INDUSTRY PRACTICES PURSUANT TO ASME CODE PCT INCREASE OF 6*F NOT NECESSARY l
I l
l
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JI6 MISC 86031301 - 9 g l
= - - _ , _ - , , , - .-. ._ --,, - _ - , . - . . - . . . . - - - . _ _ .
l l
3 1
II. GGNS REMOTE SHUTDOWN PANEL (RSP) !
l 4
DESIGN BASIS .
CONFIGURATION 1 .
RSP OPERATION J
1 GGNS REMOTE. SHUTDOWN PANEL /JMD/l 3
, * , , - - . - - ~ _ . . . , , - - - - - - -
GGNS RSP DESIGN BASIS RSP REQUIRED BY 10CFR50, APPENDIX A, GDC 19 RSP UTILIZED FOR SHUTDOWN WITH CONTROL ROOM UNINHABITABLE .
DESIGN BASIS ACCIDENTS ASSUMED NOT TO OCCUR CONCURRENT WITH CONTROL ROOM EVACUATION AUTOMATIC CONTROLS CONTINUE TO FUNCTION AFTER EVACUATION RSP CONTROLS OPERATE IN PARALLEL WITH CONTROL ROOM CONTROLS RSP CONTROLS DESIGNED TO BE COMPATABLE WITH CONTROL ROOM CIRCUITS .
RSP CONTROLS DESIGNED FOR MANUAL SHUTDOWN I
i GGNS' REMOTE SHUTDOWN PANEL /JMD/2 -
L/
- - ~:-
GGNS RSP CONFIGURATION TWO BASIC TYPES OF CONTROL CIRCUITS 4
NORMALLY ENERGIZED RSP ARRANGEMENT / ADVANTAGES l RSP LOCATIONS / DETAILS l1 4
4 t
I i
1 i
1 4
- GGNS REMOTE SHUTDOWN PANEL /JMD/3 -
p
l 1
GGNS RSP OPERATION 4
ACCESS CONTROLS PROCEDURES
!l 4
i GGNS REMOTE SHUTDOWN PANEL /JMD/4 b
PRESSURE INTERLOCK SETPOINTS FOR LOW PRESSURE ECCS AUT0r1ATIC INITI ATION UPPER ANALYTICAL LIMIT ==<============== 550 psig Adj ustments for inst. loop accuracy and calibration allowances MAX. ALLOWABLE YALUE ==1(============= 534 psig
( Tech. Spec. Setpoint )
Adjustments for drift and leave-as-is margin NOMINAL TRIP SETPOINT ==lf============= 516 psig
( Tech. Spec. Setpoint )
Adjustment for system
, static head NTS including system head = = ^c ^ =
correction = =)(============= 489 psig
Y
Additional adjustments to NTS (higher or lover) for inst. Acceptable setpoint range head correction as required LOWER NTS ==)(============= 470 psig Adjustments for drift and leave-as-is margin LOWER ALLOWiBLE VALUE ==
A=n=========== 432 psig (Tech, Spec Setpoint)
Adjustments for inst. loop accuracy and calibration allovences LOWER ANALYTICAL LIMIT ==n============= 436 psig f
7
- d. M, . .1w d"%
8-A1 UNITED STATES Enclosure 3
- NUCLEAR REGULATORY COMMISSION s
- p .W ASHINGTON, D. C. 20555
\ . . . . . *#g November 22, 1985 Docket No.: 50-416 Mr. Jackson B. Richard Senior Vice President Mississippi Power and Light Company P.O. Box 23054 Jackson, Mississippi 39205
Dear Mr. Richard:
Subject:
Grand Gulf Unit 1 - Low Pressure Emergency Core Cooling System (ECCSI Pressure Permissive Interlocks By letter dated August 12, 1985, Mississippi Power and Light Company requested an amendment to the Grand Gulf Nuclear Station, Unit I operating license in order to implement a design change which would add pressure permissive interlocks to the control circuits for low pressure ECCS injection valves. This change is required by License Condition 2.C.(18) to be implemented prior to startup following the first refueling. Technical Specification changes proposed to implement this design change were proposed in Item 13 of the Attachment to the August 12, 1985, letter.
During its review of the proposed Technical Specification changes, the NRC l staff requested additional information regarding the pressure interlocks. !
The licensee provided some of the requested information, including a revised !
ECCS performance analysis (by letter dated October 22,1985), a description '
of the logic incorporated in the pressure permissive interlocks and a piping and . instrument diagram (by letter dated October 5,1985), and a proposed surveillance requirement on ECCS valve opening time (by letter dated September 25, 1985). However, the licensee declined to provide additional information regarding:
(1) the addition of interlocks to the valve control circuits in the remote shutdown panel or alternate means to minimize the potential for inadvertent overpressurization of the low design pressure systems, and (2) changing the interlock pressure setpoints to values below the ECCS piping design pressure.
The purpose of this letter is to request additional information and to provide the NRC staff's safety evaluation and position regarding interlocks for ECCS valve controls on remote shutdown panels and the pressure setpoint for inter-locks on low design pressure ECCS piping. The staff's safety evaluation and !
positions, including acceptable alternatives to interlocks on tho remote shut-down panel, is enclosed.
The staff concludes that the proposed Technical Specification change in Item 13 of tho licensee's August 12, 1985, letter, as supplemented by letters dated September 25, October 5, and October 22, 1985, is unacceptable because it does not meet the NRC staff position regarding pressure N
N -w vv'w *"m
. - =. x u. a ,x n Y ^ . ,
. Novemb r 22, 1985 Mr. Jackson B. Richard pennissive interlocks for the remote shutdown panel cont Review interlocks Plan do notSection meet the 7.4.III),
staff positand because the proposed setrol circuits below the ECCS piping design pressure (ion requiring interlock setpoints t Evaluation Supplement 2, Section 6.3.4, NUREG-0831) Grand Gulf Nuclea to the enclosed staff positions.You are requested to revise Item Based on its preliminary review, the NRC s license in the manner proposed in the August 12 issue
, 1985, submittal. mend the operating i
The staff will resultingreissue theevaluation.
from its safety notice in this matter due n to the need of receipt of this letter.this letter in the new notice, you should submi significant hazards conditions for any revised 50.91 (a) of 10 CFR 50. proposal purs o Section letter, of the 12, the August staff intends 1985, letter. to deny the request for licensIn the absen e amendment in Item 13 Sincerely, Thomas Novak, Assistant Director 'i for licensing {
Enclosure:
Division of I.icensing i As stated cc: See next page i.
m , +
Mr. Jackson B. Richard 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, Esoufre Bishop, Liberman, Cook, Purcell Mr. Oliver D. Kingsley, Jr.
and Reynolds Vice President, Nuclear Operations 1200 17th Street, N.W. Mississippi Power & Light Company Washington, D. C. 20036 P.O. Box 23054 Jackson, Mississippi 39205 Mr. Ralph T. Lally ,
j Manager of Quality Assurance Office of the Governor Middle South Services, Inc. State of Mississippi P.O. Box 61000 Jackson, Mississippi 39201 New Orleans, Louisiana 70161 Attorney General Mr. Larry F. Dale, Director Gartin Building
, Nuclear Licensing and Safety Jackson, Mississippi 39205 Mississippi Power & Light Company P.O. Box 23054 Mr. Jack McMillan, Director l Jackson, Mississippi 39205 Solid Waste Mississippi State Board of Health Mr. R. W. Jackson, Project Engineer 880 Lakeland Bechtel Power Corporation Jackson, Mississippi 39206 15740 Shady Grove Road Gaithersburg, Maryland 20760 A lton B. Cobb, M.D.
State Health Officer Mr. Ross C. Butcher State Board of Health Senior Resident Inspector P.O. Box 1700 U.S. Nuclear Regulatory Commission Jackson, Mississippi 39205 '
Route 2, Box 399 Port Gibson, Mississippi 39150 President Claiborne County Board of Supervisors Regional Administrator, Region II Port Gibson, Mississippi 39150 U.S. Nuclear Regulatory Commissior,,
101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Mr. J. E. Cross, General Manager Grand Gulf Nuclear Station Mississippi Power & Light Company P.O. Box 756 Port Gibson, Mississippi 39150
Enclosure SAFETY EVALUATION GRAND GULF UNIT 1 LOW PRESSURE ECCS SYSTEM PRESSURE PERMISSIVE INTERLOCKS Facility Operating License NPF-29, Condition 2.C.(18) requires the licensee to implement isolation protection against overpressurization of the low pressure emergency core cooling systems (RHR/LPCI and LPCS) through the implementation of reactor vessel pressure permissive interlocks. The licensee has proposed Technical Specification (T.S.) changes t'o support the required design change.
The Instrumentation and Control Systems Branch (ICSB) focused its review on the revisions to T.S. Tables 3.3.3-1 and 4.3.3.1-1. The Reactor Systems Branch with the assistance of the Mechanical Engineering Branch focused its attention on systems and piping design aspects of the proposed changes.
Instrumentation and Control Systems Aspects The licensee proposes to include the new high/ low pressure permissive inter- -
locks for the low pressure ECCS injection valves in T.S. Table 3.3.3-1 (ECCS Actuation Instrumentation). The Technical Specifications will require a minimum of three channels operable for all operating conditions with Action 31 (declare ADS trip system or ECCS inoperable) applicable for Operating Conditions 1, 2, and 3 and Action 35 (trip inoperable channel after one hour or declare associated systems inoperable) applicable for Operating Conditions 4 and 5. Upon request, the licensee provided information (Letter dated October 5,1985) to clarify what constitutes a channel for the pressure gm n ~ 4 ys IV\WVd I /
. - , -_ ~ _.
2 pennissive interlocks. The licensee states that the minimum requirement of 3 operating channels per trip function is applicable to the "one-out-of-two twice" logic utilized in the design change and is adequate to assure operability of the required low pressure injection function considering the diversity of injection systems and logic channels available (four per trip function).
The licensee also proposes to add the surveillance requirements for the new interlock channels to T.S. Table 4.3.3.1-1 (ECCS Actuation Instrumentation Surveillance Requirements). The surveillance frequencies will be once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for channel check, once per month for channel functional test, and once per refueling cycle for channel calibration for all operating conditions.
Based on the above information, the staff finds the channel operability require-ments proposed for revised T.S. Table 3.3.3-1 to be acceptable. We also find the channel surveillance frequencies proposed in T.S. Table 4.3.3.1-1 to be acceptable.
After implementation of the proposed design, the high/ low pressure. permissive interlocks for the low pressure ECCS injection valves will be active for both automatic and manual control room operaticn. The licensee has proposed not to include such an interlock for.the remote shutdown panel (RSP) control circuits for the ECCS injection valves. Based on the current information provided by the licensee, the staff finds the requested interlock omission to be unacceptable.
a .
It is the staff's position that pressure permissive interlocks should be installed as part of the RSP control circuits consistent with the corresponding control room control circuits. This position is based on the Standard Review Plan (SRP Section 7.4) interpretation of GDC 19 which requires that the remote shutdown station equipment be designed to the same standards as the corre-sponding equipment in the main control room. Also, Section 6.3.4 of the Grand Gulf, Unit 1 SER Supplement No. 2 requires that interlocks be present at all times for both manual and automatic actuation unless the reactor vessel pressure is lower than the design pressure of the ECCS involved. Thus, without special control over the operation of these valves, inadvertent operation must l
~
be assumed from the RSP which could resu1t in overpressurization of the low
] pressure ECCS.
The following is an acceptable alternative (method of special control) to the implementation of pressure permissive interlocks for the RSP control circuits associated with the low pressure ECCS injection valves:
(1) the provision of spring-return-to-normal control switches on
, the RSPs which would alleviate the concern related to the change-of-state of equipment upon transfer of control to the RSP and
^
(2) (A) Continue to implement special Technical Specification 4.4.3.2.2.b for LPCS and LPCI outboard check valves to ensure integrity since the licensee takes credit for these valves as part of the omission justification, or
(B) Implementation of a keylocked control switch separate from the RSP controls (preferably at.MCC) which would block operation of the valve via the RSP control. This should include administrative controls to ensure that RSP control of the valve is actually blocked when the valve is closed.
Also, valve position indication should not be negated in the control room or at the RSP by the implementation of this special control scheme.
Systems and Piping Design
- The licensee has proposed Technical Specification (TS) changes regarding the low pressure ECCS injection system, in response to an NRC position regarding the prevention of an intersystem LOCA which was expressed in Supplement No. 2 to the Grand Gulf Nuclear Station (GGNS) Safety Evaluation Report (NUREG-0831) and which became License Condition 2.C.(18).. These TS changes would implement design changes adding pressure interlocks to the injection valves on the low pressure ECCS systems, require respective trip setpoints, and require periodic surveillance of associated ECCS actuation instrumentation.
Two of the proposed changes are administrative in nature. For instance, in connection with the installment of pressure interlocks, an additional trip function has been added to the ECCS low pressure systems. The minimum number of operable channels, applicable operational conditions, and action to be
taken are supplied for the new trip function (see Tables I and 2). Instru-mentation surveillance intervals are also designated for this function (see Table 3). These proposals are acceptable to us, as discussed above.
In the original submittal, MP&L proposed to delete ECCS response times for low pressure systems. Subsequently, in a letter dated September 25, 1985, MP&L proposed to use "f 29 seconds" as response times for both LPCI and LPCS injection valves. This is acceptable to us because this response time is within the value used in analyses of loss of coolant accidents.
One issue that has not been resolved is the interlock setpoint for the high pressure to low pressure interface valve. The setpoint 534 psig, is above the design pressure of the low pressure system, 500 psig. The ASME Code, dated 1977, which was the first Code edition to address such interlocks, required the interlocks to prevent the pressure from exceeding the design pressure of the low pressure side. Section 6.3.4 of GGNS SSER's (June 1982),
states that the valves in question should be " interlocked to prevent opening unless the reactor vessel pressure is lower than the design pressure of the 1
ECCSs involved." From discussions with the licensee, we understand that main-taining the setpoint below the design pressure will result in increased peak cladding cemperature for the postulated loss ok ,a,c.;A e-~T cident from 2151*F to )/
2157*F, which is still less than the limiting value of 2200 F required by 10 CFR 50.46.
The staff concludes that exceeding the Code allowable design
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pressure for the interlocks is unacceptable because the Code position can be
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i met without reducing the acceptable margin of safety for-peak cladding temperature.
If meeting the Code requirement results in a hardship, the hardship should be described and justification should be provided for our consideration. Include in the justification the results of an analysis to show that pressure in the ECCS piping equal to the upper analytical limit of the interlock setpoint will satisfy the ASME Code stress allowable values for the piping, valves and other components of the affected portions of the ECCS.
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