Letter Sequence Other |
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Results
Other: ML17328B057, ML19249A376, ML19249A382, ML19317H481, ML19340D243, ML19343B503, ML19343B506, ML19350E266, ML20003D588, ML20009C888, ML20024E960, ML20069N118, ML20076H115, ML20080G331, ML20086C757, ML20132F461, ML20151H856, ML20206M021
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MONTHYEARML19261C5191979-02-27027 February 1979 Forwards Safety Evaluation Rept for Fire Protection Program. Concludes Program,W/Scheduled Mods,Meets General Design Criterion 3 & Is Therefore Acceptable Project stage: Approval ML19261C5211979-02-27027 February 1979 Fire Protection Safety Evaluation Rept. Until Scheduled Improvements Are Made,Present Fire Protection Tech Specs Provide Sufficient Protection Against Fire Threatening Safe Shutdown Project stage: Approval ML19249A3761979-07-26026 July 1979 Amend 18 to License NPF-3,adding License Condition Re Completion of Facility Mod for Fire Protection & Modifying Tech Specs to Require Five Individuals W/Fire Protection Training on Site Project stage: Other ML19249A3781979-07-26026 July 1979 Fire Protection Safety Evaluation Supporting Amend 18 to License NPF-3 Project stage: Approval ML19249A3821979-07-26026 July 1979 Notice of Issuance & Availability of Amend 18 to License NPF-3 Project stage: Other ML19249A3721979-07-26026 July 1979 Forwards Amend 18 to License NPF-3,safety Evaluation & Notice of Issuance & Availability Project stage: Approval ML19317H4811980-05-19019 May 1980 Forwards Proposed Rule Entitled, Fire Protection Program for Nuclear Power Plants Operating Prior to 790101. Rule Adds New Section 50.48 & App R to 10CFR50 & Is Expected to Be Published in Fr by End of May Project stage: Other ML19351D6201980-10-0707 October 1980 Application for Amend to License NPF-3,providing Tech Specs for Fire Detection Sys Per License Condition 2.c(4) Project stage: Request IR 05000346/19800161980-11-18018 November 1980 IE Insp Rept 50-346/80-16 on 800609-11 & 1020-24.No Noncompliance Noted.Major Areas Inspected:Refueling Outage Maint,Plant Operations Review & Equipment Calibr Project stage: Request ML19343B5061980-11-18018 November 1980 Notice of Issuance & Availability of Amend 34 to License NPF-3 Project stage: Other ML19343B5031980-11-18018 November 1980 Amend 34 to License NPF-3,modifying Tech Specs to Include Fire Detection Instrumentation Mods Project stage: Other ML19340D2431980-11-24024 November 1980 Forwards Revised 10CFR50.48 & App R to 10CFR50 Re Five Protection Features of Nuclear Power Plants.Rules Take Effect 810217.Summary Listing of Open Items Re Fire Protection Features of Facility Encl Project stage: Other ML17328B0571980-11-24024 November 1980 Ltr to All Power Reactor Licensees W/Plants Licensed Prior to 790101.Forwards Revised Section 10CFR50.48 & App R Re Fire Protection Features in Nuclear Power Plants & List of Requirements for Resolution of Open Issues.W/O Encl Project stage: Other ML20151B3601980-12-26026 December 1980 Application for Amend of License NPF-3 Changing Tech Specs Re Fire Detection Sys,Decay Heat Removal Capabilities,Low Temp RCS Overpressure Event,Axial Power Shaping Rod Insertion Limits & Util Reorganization Project stage: Request ML20003D5881981-03-19019 March 1981 Responds to Re Submittal of Plans,Schedules & Design Descriptions of 10CFR 50,App R,Mod for Fire Protection.Forwards Design Description of Alternate Svc Water Capability Project stage: Other ML19350E2661981-06-10010 June 1981 Requests re-evaluation of Class III Fees Assessed for 810319 Proposal for Alternate Svc Water Capability.Review of Amend 18,Item B Requirements Stated No License Amend Fee Required for Response to Proposal.Class III Fee Encl Project stage: Other ML20009C8881981-07-10010 July 1981 Marked-up Revised Tech Specs 3.4.2,4.4.2,3.4.3,4.4.3, 3.8.1.2,4.8.1.2,4.8.1.1.2,4.8.1.1.2.C.2,3.1.3.6,3/4.2,3.2.1, 4.2.1,3.2.5,6.5.2.2,6.5.2.3,6.5.2.4,6.5.2.5,6.5.2.6, 3/4.7.10,3.7.10,4.7.10,Pages 3/4.7-5,B 3/4.4-19 & 3.8.1.2 Project stage: Other ML20009C8871981-07-10010 July 1981 Application for Amend of License NPF-3,revising Tech Specs for Auxiliary Feedwater Pump Turbine Speed Switches,Setpoint Index for Pressurizer Electromatic Relief & Code Safety Valves,Emergency Diesel Generator & Administrative Errors Project stage: Request ML20009C8841981-07-10010 July 1981 Forwards Application for Amend of License NPF-3,requesting Revisions to Tech Specs Project stage: Request ML20054C9511982-04-0808 April 1982 Submits List of Drawings Needed for Consideration Re Proposed Facility Mods for App R,Per 820323 Meeting Project stage: Meeting ML20053E5221982-06-0202 June 1982 Forwards Safety Evaluation of Util Requested Mods to Comply w/10CFR50 App R Sections Iii.G,Iii.J & Iii.O Re Alternate Svc Water Capability.Proposed Mods Acceptable Project stage: Approval ML20053E5241982-06-0202 June 1982 Safety Evaluation Supporting Requested Mods to 10CFR50 & 10CFR50.48 App R Project stage: Approval ML20067C1711982-11-23023 November 1982 Safety Evaluation Supporting Exemption from Certain Requirements of App R to 10CFR50 Project stage: Approval ML20069N1181982-11-23023 November 1982 Notifies That Alternate Dedicated Svc Water Sys Will Be Installed within 30 Months of NRC 820602 Acceptance Date,Per 10CFR50.48(c)(4) Project stage: Other ML20076H1151983-08-26026 August 1983 Forwards Plans & Evaluation Addressing Understanding Findings Identified by NRC Following 830725-29 Fire Protection Audit,Per 830816,18 & 22 Requests.Adequate Fire Protection Features in Place to Return to Cycle 4 Operation Project stage: Other ML20024E9601983-08-31031 August 1983 Forwards Revised Action Summary Table to Util 830826 Evaluation of NRC 830725-29 App R Audit Findings & Corrective Action Plan Project stage: Other ML20080G3311983-09-13013 September 1983 Forwards Revised Evaluation of NRC 830725-29 App R Audit Findings & Corrective Action Plan,Superseding Info Submitted w/830826 & 31 Ltrs.Findings & Plan Justify Continued Operation Project stage: Other ML20151H8561983-09-19019 September 1983 Reviews Licensee short-term & long-term Compensatory Actions on Insp Findings Re 10CFR50,App R Shutdown/Fire Protection deficiencies.Short-term Actions Acceptable Project stage: Other ML20086C7571983-11-23023 November 1983 Forwards Revised Schedule for Plan to Address Findings of NRC 10CFR50,App R Audit.Schedule Updates 830913 Commitment. Extension Needed to Incorporate Concerns of IE Info Notice 83-69, Improperly Installed Fire Dampers.. Project stage: Other ML20155C9641984-08-0606 August 1984 Summary of 840612 Meeting W/Util in Bethesda,Md Re Program to Correct Fire Protection Deficiencies in Facility Fire Protection Features & non-compliance W/Respect to Requirements of App R to 10CFR50.Related Info Encl Project stage: Meeting ML20132F4611985-09-26026 September 1985 Forwards List of Facility Change Requests Re Fire Protection Scheduled for Completion at End of Fifth Refueling Outage to Begin in Sept/Oct 1986.List Prioritized 25 Most Important to Nuclear Safety Project stage: Other ML20212P2741987-01-21021 January 1987 Responds to Stolz 861217 Request for Addl Info Re Fire Protection & Meeting to Discuss Issues.Fire Protection Program in Conformance W/App a to BTP Apcsb 9.5-1 as Accepted by 790726 Ser.Meeting Schedule to Be Established Project stage: Meeting ML20206M0211987-04-0909 April 1987 Advises That Fire Protection & Alternate Shutdown Sys Mods Required to Meet 10CFR50.48 Scheduled to Be Completed by End of Sixth Refueling Outage,Per Generic Ltr 86-10, Implementation of Fire Protection Requirements Project stage: Other 1982-11-23
[Table View] |
Text
I o
r TOLEDO
%mm EDISON Docket No. 50-346 A<*.ic P Cacuse Lic.ense No. NPF-3 CU" Serial No. 697 m9esm March 19, 1981
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[M[ Wh Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz j.)
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Operating Reactor Branch No. 4 Gj Ygh"# /[j Division of Operating Reactors United States Nuclear Regulatory Commission
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Washington, D.C.
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Dear Mr. Stolz:
This submittal is in response to your letter dated February 20, 1981 (Log No. 664), concerning the submittal of plans, schedules and design descriptions of 10CFR50 Appendix R, modification for fire protection at the Davis-Besse Nuclear Power Station Unit 1 (DB-1).
Under 10CFR50.48(b), DB-1 is an operating nuclear power plant licensed prior to January 1, 1979 that received a NRC review and safety evaluation report satisfying Appendix A to Branch Iechnical Position 9.5-1.
A NRC letter of November 24, 1980 (Log No. 636) verified there were no "open items" remaining from that review. The post modification design will meet the requirements of our safety evaluation report and Section III.G.,
III.J and III.0 of Appendix R to 10CFR50.
Currently all fire protection system modifications have been completed except the alternate to the service water system (SWS) identified in Volume I, Section 4, Paragraph Fil and Volume II Response to NRC Ques-tion No. 11 in the DB-1 Fire Protection Safety Evaluation Report. The previous schedule had reflected a mid-1984 completion of this alternate capability.
In response to 10CFR50, Appendix R, we have revised that schedule.
It is our current intention to provide this alternate prior to startup after the next refueling outage. This constitutes our next planned outage and is therefore consistent with Appendix R.
The refuel-ing outage is currently scheduled to begin the end of February 1982.
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II THE TCLEDO EDISON COMPANY EDISON PLAZA 300 MAO SON AVENUE TOLEDO. OHIO 43652 w
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. The design description of the alternate service water capability is attached for your review. This includes discussions of the mechanical, ventilation and electrical design modifications.
This submittal is considered responsive to both Appendix R and your letter of February 20, 1981. If you have any questions concerning this effort you are requested to contact us Unmediately. Due to the large magnitude of the plant modification and the shortness of the schedule we are proceeding with its implementation.
Yours very truly,.
9
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RPC:TWH Enclosures bj d/4-5 cc:
DB-1 Resident Inspector
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DESIGN DESCRIPTION FOR THE ALTERNATE SERVICE WATER CAPABILITY j
The basic approach to providing an alternate service water capability at DB-1 is to modify or replace an existing dilution pump to supply water to the service water system (SWS) without utilizing equipment located in the same fire area as the service water system (SWS) pumps and will be powered independent from off-site supplies.
Specifics of the modification are discussed below and are compared between Figure 1 (current design) and Figure 2 (post modification design).
MECHANICAL DESCRIPTION The existing dilution pump P180 (10,250 gpm @ 70 feet) located in the intake structure is being modified to a pump that duplicates the existing service water pump capacity (10,250 gpm 0 160 feet). This new pump will serve as the dilution pump during normal plant operation. Following a postulated fire in the service water pump room this pump will also provide adequate flow to the SWS without utilizing equipment common to the affected fire area.
A piping sketch for the new pump and system arrangement is provided as Figure 2 attached. A branch line is provided to tie into the existing service water system. A strainer is being provided to protect the service water system components. The associated valving is manual consistent with discussions in Volume II response to NRC Question No. 11 of the Fire Hazards Analysis Report for DB-1.
HVAC DESIGN Assured fire separation necessitates some modifications to the intake structure interior walls and requires changes to the existing EVAC systems.
Figure 2 attached shows a plan view of the intake structure after the modification. The walls shown along Column IB and ID separate the dilution pump from the service water pumps and valves respectively.
These walls are being upgraded to a three hour fire rating. This requires sealing the existing ventilation openings in the column line 1B wall.
This modification eliminates the natural convective air flow path through thr:e openings and out a roof top penthouse currently relied on during loss of function of the non-safety related fans located on column line ID.
To compensate for.the loss of convective air flow, ventilation systems in both the Screen House and the service water pump room will be modified.
In the screen house:
, a.
A new roof top exhaust fan will be added.
b.
The new fan will be able to be supplied by on-site power.
For the se vice water pump roem:
a.
existing exhaust fans will be upgraded to safety related including seismic design, power supplies and control.
b.
Tornado missile protection will be provided.
ELECTRICAL DESIGN The modified dilution pump and its asse:iated ventilation system will operate following a loss of off-site power. All associated equipment and cables will be located outside the service water pump room. This requires some conduit rerouting. The new roof exhaust fan for the screen house area will be supplied'from essential MCC E12C. This is located in the diesel fire pump room. The modified dilution pump will remain powered from 4160V, Bus C2.
Because the same bus powers the station lighting system, DB-1 Emergency Procedure No. 1202.02, " Station Blackout", provides for manual loading of this bus onto Diesel Generator No. I'from the control room.
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