Letter Sequence Approval |
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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-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-86-0329, 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, ML20209D136, ML20209D152, ML20210L795, ML20215E405
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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 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 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-85-0304, 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 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-85-0306, 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 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 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 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 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 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-86-0208, Forwards Addl Info Re Emergency Containment Venting in Response to Item 1.1 of 860527 Request.Encl Rev 1 to ...Emergency Procedures Upgrade Program Procedures Generation Package Addresses Remaining Request1986-07-15015 July 1986 Forwards Addl Info Re Emergency Containment Venting in Response to Item 1.1 of 860527 Request.Encl Rev 1 to ...Emergency Procedures Upgrade Program Procedures Generation Package Addresses Remaining Request 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 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 ML20210L7951986-08-28028 August 1986 Notice of Consideration of Issuance of Amend to License NPF-29 & Proposed Nhsc Determination & Opportunity for Hearing Re 850812,0925,1005 & 22 Requests for Revs to Listed Tech Spec Tables on 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 ML20215E4051986-10-0606 October 1986 Amend 20 to License NPF-29,revising Tech Specs to Reflect Installation of Pressure Interlocks for Injection Valves in Low Pressure ECCS & Mod to Automatic Depressurization Sys Actuation Logic Project stage: Other ML20215E4131986-10-0606 October 1986 Safety Evaluation Supporting Amend 20 to License NPF-29 Project stage: Approval 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 1986-10-14
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- j WASHING TON, D. C. 20555 November'22, 1985 Docket No.
- 50-416 Mr. Jackson B. Richard b
Senior Vice President Mississippi Power and Light Company
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P.O. Box 23054 Jackson, Mississippi 39205
Dear Mr. Richard:
Subject:
Grand Gulf Unit 1 - Low Pres'sure Emergency Core Cooling System (ECCS) Pressure Permissive Interlocks By letter dated August 12, 1985, Mississippi Power and Light Company requested an amendment to the Grand Gulf Nuclear Station, Unit 1 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.
to be implemented prior to startup following the first refueling.This Specification changes proposed to implement this design change were proposed Technical in Item 13 of the Attachment to the August 12, 1985, letter.
During its review of the proposed Technical Specification changes, the NRC 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 and instrument diagram (by letter dated October 5,1985),
surveillance requirement on ECCS valve opening time (by letter dated September 25, 1985).
information regarding:However, the licensee declined to provide additional circuits in the remote shutdown panel or alternate means to minim potential for inadvertent overpressurization of the low design pressure systems, and (2) changing the in the ECCS piping design pressure.terlock pressure setpoints to values below 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 down panel, is enclosed. positions, including acceptable alternatives to interlocks on The staff concluded Specification change in Item 13 of the licensee's Augustthat the proposed Technical supplemented by letters dated September 25, October 5, and October 12, 1985, letter, as unacceptable because it does not meet the NRC staff position regarding pressure 22,1985, is DECIGNATED ORIGIN /J, 3
7 B512050378 851122 Certified By PDR ADOCK 05000416
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November 22, 1985 Mr. Jackson B. Richard permissive interlocks for the remote shutdown panel control circuits (Standard Review Plan Section 7.4.III), and because the proposed setpoints for pressure interlocks do not meet the staff position requiring interlock setpoints to be below the ECCS piping design pressure (Grand Gulf Nuclear Station Safety Evaluation Supplement 2, Section 6.3.4, NUREG-0831).
You are requested to revise Item 13 of the August 12, 1985, submittal to respond to the enclosed staff positions. Based on its preliminary review, the NRC staff issued a notice in the Federal Register of its intent to amend the operating license in the manner proposed in the August 12, 1985, submittal. The staff will reissue the notice in this matter due to the need for substantive changes resulting from its safety evaluation.
In order to include the response to this letter in the new notice, you should submit your response within 30 days of receipt of this letter. Your response should include an analysis of significant hazards conditions for any revised proposal pursuant to Section 50.91 (al of 10 CFR 50.
In the absence of an acceptable response to this letter, the staff intends to deny the request for license amendment in Item 13 of the August 12, 1985, letter.
Sincerely, Thomas Novak, Assistant Director for licensing Division of licensing
Enclosure:
As stated cc: See next page l
l l
/,-
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, Escuire 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 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 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 Alton B. Cobb, M.D.
State Health Officer Mr. Ross C. Butcher State Board of Health Senior Resident Inspector P.O. Bnx 1700 U.S. Nuclear Regulatory Commission Jackson, Mississippi 39206 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 Comission, 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 l
,o November 22, 1985 Ncket No.: 50-416 Mr. Jackson B. Richard Senior Vice President Mississippi Power and Light Company P.O. Box 23054 Jackson, Mississippi 39205 j
Dear Mr. Richard:
Subject:
Grand Gulf Unit 1 - Low Pressure Emergency Core Cooling System (ECCS) Pressure Pennissive Interlocks By letter dated August 12, 1985, Mississippi Power and Light Company requested an amendment to the Grand Gulf Nuclear Station, Unit 1 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 staff requested additional infor: nation 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.
l The purpose of this letter is to request additional information and to provide l
the NRC staff's safety evaluation and position regarding interlocks for ECCS valve controls on remote shutdown panels and the pressure setpoint for inter-I locks on low design pressure ECCS piping. The staff's safety evaluation and l
_ positions, including acceptable alternatives to interlocks on the remote shut-down panel, is enclosed. The staff concludes that the proposed Technical Specification change in Item 13 of the 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 l
l
[
November 22, 1985
~ Mr. Jackson B. Richard >
permissive interlocks for the remote shutdown panel control circuits (Standard Review Plan Section 7.4.III), and because the proposed setpoints for pressure interlocks do.not meet the staff position requiring interlock setpoints to be below the ECCS piping design pressure (Grand Gulf Nuclear Station Safety Evaluation Supplement 2, Section 6.3.4, NUREG-0831).
You are requested to revise Item 13 of the August 12, 1985, submittal to respond to the enclosed staff positions. Based on its preliminary review, the NRC staff issued a notice in the Federal Register of its intent to amend the operating license.in the manner proposed in the August 12, 1985, submittal. The staff will reissue-the notice in this matter due to the need for substantive changes resulting from its safety evaluation.
In order to include the response to this letter in the new notice, you should submit your response within 30 days of receipt of this letter. Your response should include an analysis of significant hazards conditions for any revised proposal pursuant to Section 50.91 (a) of 10 CFR 50.
In the absence of an acceptable response to this letter, the staff intends to deny the request for license amendment in Item 13 of the August 12, 1985, letter.
Sincerely.
Original signed by ThomasM.Novak Thomas Novak, Assistant Director for Licensing Division of Licensing
Enclosure:
As stated DISTRIBUTION Docket File W. Hodges cc: See next page NRC PDR R. Stevens PRC System V. Panciera
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