Letter Sequence Other |
|---|
|
Results
Other: GO2-86-104, Forwards Addl Info Re Fire Protection Program,Per 861020 Request,Including Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency), GO2-86-310, Forwards Advance Copy of Update of App F Re Fire Protection Evaluation for Facility Fsar.Update Will Be Formally Submitted as Amend 37,currently Scheduled for Issue in June 1986, GO2-86-656, Responds to 860314 SER Implying That App R Analysis Requirements Performed for high-pressure-to-low-pressure Sys Interfaces Must Assume That Two Spurious Actuations Occur Simultaneously.Position Contrary to Generic Ltrs, GO2-87-019, Forwards Info Re Mods Proposed to Ensure Isolation of RHR-V-8 or RHR-V-9 Valve & Schedule for Completion of Mods, Per 870513 Request Re Generic Ltr 86-10 Interpretation of High/Low Pressure Interface Concerns, GO2-87-034, Forwards Fire Protection Program Description in Response to 870113-15 Fire Protection Insp to Facilitate Implementation of License Condition 2.C(14), GO2-87-179, Forwards Response to Unresolved Items Noted in Insp Rept 50-397/87-02.Corrective Actions:Independent Insp by Consultants Confirmed That Detection Sys Meets Requirements for safety-related Areas, GO2-87-232, Responds to Generic Ltr 86-10.Util Determined That Providing Transfer Switch on Remote Shutdown Panel for RHR-V-8 Valve Preferred Method for Ensuring Isolation of Either RHR-V-8 or V-9 in Event of Control Room Fire, GO2-88-008, Responds to Inconsistencies Noted in Introduction to SER Forwarded by Gw Knighton .Ser Addressed Fire Protection & Safe Shutdown Capability Per Amend 37 to FSAR, GO2-88-111, Informs That Rev to Plant Procedure 1.3.10, Fire Protection Program, Committed to in 870128 Response to Insp Rept 50-397/86-25,currently in Process to Incorporate Listed Addl Changes.Procedure Will Be Revised by 880513, GO2-88-136, Informs That Calculation Analyzing Structural Integrity of Specific Support Steel Configurations for Instrument Sensing Lines Rescheduled for Completion from 880515 to 880715 Due to Unavailability of Supporting Resources, GO2-88-155, Forwards Calculation Analyzing Structural Integrity of Specific Support Steel Configurations for Instrument Sensing Lines Re Fire Protection & Safe Shutdown Capability Response to SER, GO2-88-156, Provides Schedule for Completion of Fire Protection Issues from Insp Rept 50-397/88-16.Installation of Scuppers on South Doors Leading Outside Diesel Generator Bldg Will Be Completed by 880801, GO2-88-157, Forwards Completed Executive Summary of App R High Impedance Fault Analysis,Per NRC 880606 Request, GO2-88-168, Responds to NRC Re Violations Noted in Insp Rept 50-397/88-19.Corrective Actions:Instrument Rack Termination Procedure PPM 10.25.19 Will Be Revised by 890315 to Include Examples of Acceptable Crimp Configuration, GO2-88-209, Submits Revised Response to SER Question 25 Re Fire Protection & Safe Shutdown Capability.Analysis Performed to Identify high-to-low Pressure Interface Valve Motor Power Feeder Requiring Protection Against Fire Related Reconnects, GO2-88-214, Forwards Updated Schedule of Commitments for Completion of Fire Protection Issues,Per Concerns Noted in Insp Rept 50-397/88-16 & Open Items Noted During Fire Protection Audit on 880606-10, GO2-88-222, Submits Revised Response to Insp Rept 50-397/88-16 Re Fire Protection & Safe Shutdown Capability.Fire in Drywell Expansion Gap Has Very Low Probability of Starting, GO2-89-035, Provides Revised Schedule Dates for Commitments Made in Response to Violations Noted in Insp Repts 50-397/87-19 & 50-397/88-41.Plant Procedures 10.25.19 & 11.2.1.2 Will Be Issued by 890417, ML17278B122, ML17278B182, ML17279A257, ML17279A778
|
MONTHYEARGO2-86-310, Forwards Advance Copy of Update of App F Re Fire Protection Evaluation for Facility Fsar.Update Will Be Formally Submitted as Amend 37,currently Scheduled for Issue in June 19861986-04-0404 April 1986
Forwards Advance Copy of Update of App F Re Fire Protection Evaluation for Facility Fsar.Update Will Be Formally Submitted as Amend 37,currently Scheduled for Issue in June 1986
Project stage: Other
GO2-86-656, Responds to 860314 SER Implying That App R Analysis Requirements Performed for high-pressure-to-low-pressure Sys Interfaces Must Assume That Two Spurious Actuations Occur Simultaneously.Position Contrary to Generic Ltrs1986-07-16016 July 1986
Responds to 860314 SER Implying That App R Analysis Requirements Performed for high-pressure-to-low-pressure Sys Interfaces Must Assume That Two Spurious Actuations Occur Simultaneously.Position Contrary to Generic Ltrs
Project stage: Other
ML17278B0471986-10-20020 October 1986
Forwards Request for Addl Info Re Current Condition of Unit 2 Compared to Regulations,License & Commitments to Fire Protection Program.Requests Response within 30 Days of Ltr Receipt
Project stage: RAI
ML17278B0461986-10-21021 October 1986
Discusses 861002 Meeting W/Ofc of General Counsel & Plant Sys Branch Re Plant Approved Fire Protection Program.Meeting Concluded That Program Includes Written Communications Docketed Prior to Issuing OL
Project stage: Meeting
ML17278B1221986-11-17017 November 1986
Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency)
Project stage: Other
GO2-86-104, Forwards Addl Info Re Fire Protection Program,Per 861020 Request,Including Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency)1986-12-0101 December 1986
Forwards Addl Info Re Fire Protection Program,Per 861020 Request,Including Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency)
Project stage: Other
GO2-87-034, Forwards Fire Protection Program Description in Response to 870113-15 Fire Protection Insp to Facilitate Implementation of License Condition 2.C(14)1987-01-29029 January 1987
Forwards Fire Protection Program Description in Response to 870113-15 Fire Protection Insp to Facilitate Implementation of License Condition 2.C(14)
Project stage: Other
ML17278B1821987-02-0505 February 1987
Informs That Attachment to Will Be Considered Approved Fire Protection Program.Approval of Program Contingent on Timely Submittal of License Amend Request Per Generic Ltr 86-10
Project stage: Other
ML17278B1881987-02-10010 February 1987
Proposed Tech Specs Re Deletion of Fire Protection Requirements
Project stage: Other
GO2-87-046, Application for Amend to License NPF-21,modifying License Condition 2.C.(14) to Incorporate Std Fire Protection License Condition & Remove Fire Protection Tech Specs,Per Generic Ltr 86-10.Fee Paid1987-02-10010 February 1987
Application for Amend to License NPF-21,modifying License Condition 2.C.(14) to Incorporate Std Fire Protection License Condition & Remove Fire Protection Tech Specs,Per Generic Ltr 86-10.Fee Paid
Project stage: Request
ML17279A2571987-05-13013 May 1987
Advises That Util Required to Implement Appropriate Mods to Isolation Valves RHR-V-8 & RHR-V-9 to Meet Objectives of App R to 10CFR50 Re Prevention of LOCAs at High/Low Pressure Interfaces.Submittal of Schedule Requested
Project stage: Other
GO2-87-179, Forwards Response to Unresolved Items Noted in Insp Rept 50-397/87-02.Corrective Actions:Independent Insp by Consultants Confirmed That Detection Sys Meets Requirements for safety-related Areas1987-05-27027 May 1987
Forwards Response to Unresolved Items Noted in Insp Rept 50-397/87-02.Corrective Actions:Independent Insp by Consultants Confirmed That Detection Sys Meets Requirements for safety-related Areas
Project stage: Other
GO2-87-019, Forwards Info Re Mods Proposed to Ensure Isolation of RHR-V-8 or RHR-V-9 Valve & Schedule for Completion of Mods, Per 870513 Request Re Generic Ltr 86-10 Interpretation of High/Low Pressure Interface Concerns1987-06-0303 June 1987
Forwards Info Re Mods Proposed to Ensure Isolation of RHR-V-8 or RHR-V-9 Valve & Schedule for Completion of Mods, Per 870513 Request Re Generic Ltr 86-10 Interpretation of High/Low Pressure Interface Concerns
Project stage: Other
GO2-87-232, Responds to Generic Ltr 86-10.Util Determined That Providing Transfer Switch on Remote Shutdown Panel for RHR-V-8 Valve Preferred Method for Ensuring Isolation of Either RHR-V-8 or V-9 in Event of Control Room Fire1987-08-20020 August 1987
Responds to Generic Ltr 86-10.Util Determined That Providing Transfer Switch on Remote Shutdown Panel for RHR-V-8 Valve Preferred Method for Ensuring Isolation of Either RHR-V-8 or V-9 in Event of Control Room Fire
Project stage: Other
ML17279A5771987-10-0202 October 1987
Recommends That Meeting Be Held to Ensure Completion of Mods to Preclude Spurious Opening of High Low Interface Valves in Event of Control Room Fire,Per NRC 870513 Request & Util 870820 Response
Project stage: Meeting
ML20236N1261987-11-11011 November 1987
Safety Evaluation Supporting Amend 37 to FSAR Re Fire Protection Program
Project stage: Approval
ML17279A7781987-12-23023 December 1987
Discusses 871002 Response to Re Util Preferred Course of Action for Precluding Spurious Opening of high-low Interface Valves RHR-V 8 & RHR-V-9 in Event of Control Room Fire.No Submittal on Subj Received to Date
Project stage: Other
GO2-88-008, Responds to Inconsistencies Noted in Introduction to SER Forwarded by Gw Knighton .Ser Addressed Fire Protection & Safe Shutdown Capability Per Amend 37 to FSAR1988-01-11011 January 1988
Responds to Inconsistencies Noted in Introduction to SER Forwarded by Gw Knighton .Ser Addressed Fire Protection & Safe Shutdown Capability Per Amend 37 to FSAR
Project stage: Other
ML17279A7751988-01-13013 January 1988
Notification of 880119 Meeting W/Util in Bethesda,Md to Discuss Fire Protection Plan & Util Responses to NRC Comments on Plan
Project stage: Meeting
ML17279A8881988-03-0909 March 1988
Summary of 880119 Meeting W/Util in Bethesda,Md Re Util Responses to 28 Fire Protection Questions Raised in NRC .Attendee List Encl
Project stage: Meeting
GO2-88-111, Informs That Rev to Plant Procedure 1.3.10, Fire Protection Program, Committed to in 870128 Response to Insp Rept 50-397/86-25,currently in Process to Incorporate Listed Addl Changes.Procedure Will Be Revised by 8805131988-05-0606 May 1988
Informs That Rev to Plant Procedure 1.3.10, Fire Protection Program, Committed to in 870128 Response to Insp Rept 50-397/86-25,currently in Process to Incorporate Listed Addl Changes.Procedure Will Be Revised by 880513
Project stage: Other
GO2-88-136, Informs That Calculation Analyzing Structural Integrity of Specific Support Steel Configurations for Instrument Sensing Lines Rescheduled for Completion from 880515 to 880715 Due to Unavailability of Supporting Resources1988-06-0303 June 1988
Informs That Calculation Analyzing Structural Integrity of Specific Support Steel Configurations for Instrument Sensing Lines Rescheduled for Completion from 880515 to 880715 Due to Unavailability of Supporting Resources
Project stage: Other
GO2-88-157, Forwards Completed Executive Summary of App R High Impedance Fault Analysis,Per NRC 880606 Request1988-07-15015 July 1988
Forwards Completed Executive Summary of App R High Impedance Fault Analysis,Per NRC 880606 Request
Project stage: Other
GO2-88-155, Forwards Calculation Analyzing Structural Integrity of Specific Support Steel Configurations for Instrument Sensing Lines Re Fire Protection & Safe Shutdown Capability Response to SER1988-07-15015 July 1988
Forwards Calculation Analyzing Structural Integrity of Specific Support Steel Configurations for Instrument Sensing Lines Re Fire Protection & Safe Shutdown Capability Response to SER
Project stage: Other
GO2-88-156, Provides Schedule for Completion of Fire Protection Issues from Insp Rept 50-397/88-16.Installation of Scuppers on South Doors Leading Outside Diesel Generator Bldg Will Be Completed by 8808011988-07-15015 July 1988
Provides Schedule for Completion of Fire Protection Issues from Insp Rept 50-397/88-16.Installation of Scuppers on South Doors Leading Outside Diesel Generator Bldg Will Be Completed by 880801
Project stage: Other
GO2-88-163, Submits Clarification of Approved Fire Protection Program Per 880610 Exit Meeting,Covering Plant Design,Door Openings, Fire Barriers,Fire Dampers & Doors & Safe Shutdown Capability1988-07-26026 July 1988
Submits Clarification of Approved Fire Protection Program Per 880610 Exit Meeting,Covering Plant Design,Door Openings, Fire Barriers,Fire Dampers & Doors & Safe Shutdown Capability
Project stage: Meeting
GO2-88-168, Responds to NRC Re Violations Noted in Insp Rept 50-397/88-19.Corrective Actions:Instrument Rack Termination Procedure PPM 10.25.19 Will Be Revised by 890315 to Include Examples of Acceptable Crimp Configuration1988-07-29029 July 1988
Responds to NRC Re Violations Noted in Insp Rept 50-397/88-19.Corrective Actions:Instrument Rack Termination Procedure PPM 10.25.19 Will Be Revised by 890315 to Include Examples of Acceptable Crimp Configuration
Project stage: Other
GO2-88-209, Submits Revised Response to SER Question 25 Re Fire Protection & Safe Shutdown Capability.Analysis Performed to Identify high-to-low Pressure Interface Valve Motor Power Feeder Requiring Protection Against Fire Related Reconnects1988-09-30030 September 1988
Submits Revised Response to SER Question 25 Re Fire Protection & Safe Shutdown Capability.Analysis Performed to Identify high-to-low Pressure Interface Valve Motor Power Feeder Requiring Protection Against Fire Related Reconnects
Project stage: Other
GO2-88-214, Forwards Updated Schedule of Commitments for Completion of Fire Protection Issues,Per Concerns Noted in Insp Rept 50-397/88-16 & Open Items Noted During Fire Protection Audit on 880606-101988-10-0707 October 1988
Forwards Updated Schedule of Commitments for Completion of Fire Protection Issues,Per Concerns Noted in Insp Rept 50-397/88-16 & Open Items Noted During Fire Protection Audit on 880606-10
Project stage: Other
GO2-88-222, Submits Revised Response to Insp Rept 50-397/88-16 Re Fire Protection & Safe Shutdown Capability.Fire in Drywell Expansion Gap Has Very Low Probability of Starting1988-10-28028 October 1988
Submits Revised Response to Insp Rept 50-397/88-16 Re Fire Protection & Safe Shutdown Capability.Fire in Drywell Expansion Gap Has Very Low Probability of Starting
Project stage: Other
GO2-88-250, Clarifies Min Staffing Needed for Safe Shutdown Re Insp Rept 50-397/88-16 Dtd 880725.Util Understands That Any Combination of Personnel Meeting 10CFR50,App R Requirements Acceptable1988-11-28028 November 1988
Clarifies Min Staffing Needed for Safe Shutdown Re Insp Rept 50-397/88-16 Dtd 880725.Util Understands That Any Combination of Personnel Meeting 10CFR50,App R Requirements Acceptable
Project stage: Meeting
GO2-89-035, Provides Revised Schedule Dates for Commitments Made in Response to Violations Noted in Insp Repts 50-397/87-19 & 50-397/88-41.Plant Procedures 10.25.19 & 11.2.1.2 Will Be Issued by 8904171989-03-0606 March 1989
Provides Revised Schedule Dates for Commitments Made in Response to Violations Noted in Insp Repts 50-397/87-19 & 50-397/88-41.Plant Procedures 10.25.19 & 11.2.1.2 Will Be Issued by 890417
Project stage: Other
GO2-89-050, Submits Supplemental Info Re Request for Amend to License Condition 2.C.14 & Removal of Fire Protection Requirements from Tech Specs.Util Requests That NRC Not Act on Request to Delete Paragraphs 6.5.2.8.e & H & 6.8.1.g from Tech Specs1989-03-31031 March 1989
Submits Supplemental Info Re Request for Amend to License Condition 2.C.14 & Removal of Fire Protection Requirements from Tech Specs.Util Requests That NRC Not Act on Request to Delete Paragraphs 6.5.2.8.e & H & 6.8.1.g from Tech Specs
Project stage: Supplement
1987-06-03
[Table View] |
Text
Q'llREGog O~*0O z+
+w*w+
~
v UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 February 5, 1987 Docket No. 50-397 Mr. G.
C. Sorensen, Manager Regulatory Programs Washington Public Power Supply System P.O.
Box 968 3000 George Washington Way Richland, Washington 99352
Dear Mr. Sorensen:
Subject:
Fire Protection Program for WPPSS Nuclear Proiect No. 2-License No. NPF-21
Reference:
Letter G02-87-034,
- Sorensen, Supply System to Document Control
- Desk, NRC,
Subject:
Fire Protection
- Program, dated
)anuary 29, 1987 For the purpose of your license condition, P.C.(14>, the attachment; to your referenced letter will be considered your approved fire protection program.
Our approval is contingent on your timely submittal of a license amendment request pursuant to the guidance of Generic Letter 86-10.
Sincerely, cc:. See next page I,4<<'linor G. Adensam, Director BWR Proiect Directorate No.
3 Division of BWR Licensing j(w'4
+ /~
~a.c. PC<
dome /
pQg I
(
870213039q 87020'DR ADOCK 0500039T "
F PDR
'v J
ii Ig i(
4.
Mr. G.
C. Sorensen, Manager Washington Public Power Supply System WPPSS Nuclear Project No.
2 (WNP-2)
CC:
Nicholas 'S. Reynolds, Esq.
Bishop, Liberman,
- Cook, Purcell 5 Reynolds 1200 Seventeenth
- Street, N.W.
Washington, D.C.
20036 Mr. G. E. Doupe, Esquire Washington Public Power Supply System P. 0.
Box 968 3000 George Washington Way Richland, Washington 99532 Mr. Curtis Eschels, Chairman Energy Facility Site Evaluation Council Mail Stop PY-ll Olympia, Washington 98504 P. L. Powell, Licensinq Manager Washington Public Power Supply System P. 0.
Box 968, MD 956B Richland, Washington 99352 Mr.
W. G.
Conn Burns and Roe, Incorporated c/o Washington Public Power Supply System P. 0.
Box 968, MD 994E Richland, Washington 99352 R. B. Glasscock, Director Licensing and Assurance Washington Public Power Supply System P. 0.
Box 968, MD 280 Richland, Washington 99352 Mr. C.
M. Powers WNP-2 Plant Manager Washington Public Power Supply System P. 0.
Box MD 927M Richland, Washington 99352 Regi onal Administrator, Regi on V
U.S. Nuclear Regulatory Commission
,1450 Maria Lane, Suite 210 Walnut Creek, California 94596 35
4 4
X~
II
'll ll P
a
