Letter Sequence Other |
|---|
|
Results
Other: ML20151L968, ML20196A234, ML20206A735, ML20207L533, ML20209F820, ML20211B995, ML20213A567, ML20214J698, ML20214J930, ML20214J973, ML20234C463, ML20234E291, ML20235J298
|
MONTHYEARML20138D9431985-10-17017 October 1985
Notification of 851022 Meeting W/Util & S&W in Bethesda,Md to Discuss Fire Protection Deviation Requests
Project stage: Meeting
ML20206J0051986-06-23023 June 1986
Forwards Documentation of Attendees at 841130 & 1207,850117, 0820,0919 & 1022 Meetings W/Util Re Structural Engineering, Geosciences Issues,Pressure Isolation Valves,Power Sys, Computer Code Multiflex & Fire Protection,Respectively
Project stage: Meeting
ML20215K7361986-10-23023 October 1986
Notification of 861105 Meeting W/Util in Bethesda,Md to Discuss Issues Re Fire Protection,Including Util Deviations from Staff Technical Position
Project stage: Meeting
ML20214D3181986-11-18018 November 1986
Summary of 861105 Meeting W/Util,Stone & Webster & Franklin Research Inst Re Fire Protection Issues.Draft Sser 3,list of Deviations from SRP 9.5.1,agenda & List of Attendees Encl
ML20207L5331987-01-0606 January 1987
Forwards Updated FSAR Fire Protection Matl in Preparation for Upcoming NRC Fire Protection Audit.Submittal Contains Info for Resolution of SER Open Item 5 & Confirmatory Item 48c.Matl Will Be Incorporated Into Amend 14 to FSAR
Project stage: Other
ML20207N1901987-01-0808 January 1987
Notification of 870129 Meeting W/Util in Shippingport,Pa to Conclude 4-day Site Review of Fire Protection Issues.Issues Identified as Confirmatory Issue 48 & Backfit Issue 7 in Sser 3
Project stage: Meeting
ML20213A5671987-01-27027 January 1987
Requests Security Passes Be Provided to Personnel for 4-day Site Review to Begin on 870108 Re Fire Protection Issues
Project stage: Other
ML20209F8201987-01-30030 January 1987
Forwards Amend 14 to Fsar,Consisting of Updated FSAR Fire Protection Info Provided in Author .Info Affects Section 9.5.1 of SER
Project stage: Other
ML20155H2511987-02-0505 February 1987
Summary of 870130 Meeting W/Util & S&W in Bethesda, MD to Conclude NRC Fire Protection Site Review of 870127-29.List of Attendees Encl
Project stage: Meeting
ML20211B9951987-02-11011 February 1987
Forwards Addl Info Re Fire Protection,Including Info Re SRP Deviation on Structural Steel & Vendor Justification of Thickness Requirements for HVAC Ductwork Fire Wrap,Per NRC 870126-30 Fire Protection Site Visit
Project stage: Other
ML20210C3141987-04-30030 April 1987
Forwards Request for Addl Info Re Confirmatory Issue 46, Fire Protection Deviations & Confirmatory Issue 46, Control Room Isolations on High Radiation Signals. Encl Provides Background Info for Telcon.No Response Required
Project stage: RAI
ML20214J6981987-05-18018 May 1987
Describes Fire Detection & Suppression Sys at Facility (Ref NRC ).Present Capability of Sys Adequate & Overall Plant Safety Would Not Be Significantly Increased by Modifying Suppression Sys Alarm Circuits.W/Four Figures
Project stage: Other
ML20214J9301987-05-18018 May 1987
Forwards Changes Expected to Occur in Next Rev to Amend 18 of Fsar,Section 9.5 Re Fire Protection
Project stage: Other
ML20214J9731987-05-20020 May 1987
Provides Compensatory Measures to Deal W/Fire Zones Containing Equipment Necessary for Tech Spec Equipment Operability Where fire-rated Assemblies Incomplete.Hourly Fire Patrols Conducted When Necessary
Project stage: Other
IR 05000412/19870371987-05-28028 May 1987
Insp Rept 50-412/87-37 on 870420-0501.No Violations Noted. Major Areas Inspected:Preoperation & Startup Test Program, Startup Test Procedure Review,Qa Interfaces & Emergency Diesel Generator Instrumentation Vibration
Project stage: Request
ML20234C4631987-06-24024 June 1987
Forwards Util Comments on Low Power License for Facility, Including Discussion of Fire Protection & Plant Safety Monitoring Sys.Util Will Work W/Nrc Project Manager to Resolve Comments
Project stage: Other
ML20235J2981987-07-0606 July 1987
Responds to Questions Posed by D Kubicki in Telecon Re Fire Protection Supervisory Circuits & Schedule for Completion
Project stage: Other
ML20235Q7051987-09-30030 September 1987
Forwards Testing Status of CO2 Fire Suppression Sys. Overpressure Problems Associated w/CO2 Discharge Testing Eliminated by Installation of Back Draft Dampers.Expected Completion Date Revised to 871231
Project stage: Draft Other
ML20151L9681987-12-31031 December 1987
1987 Annual Rept of Facility Changes,Tests & Experiments
Project stage: Other
ML20234E2911987-12-31031 December 1987
Advises That CO2 Concentration Testing Successfully Completed for All Eight Zones,Per 870930 Commitment to Provide Schedule for Completion of Unfinished Fire Protection Items
Project stage: Other
ML20196A2341988-06-20020 June 1988
Concludes That Based on Licensee Annual Rept of Facility, Changes,Tests & Experiments & 880608 Site Visit, Changes,Tests & Experiments Meet Criteria in 10CFR50.59. Lists Improvements Recommended to Licensee During Visit
Project stage: Other
ML20206A7351988-11-0808 November 1988
Advises That Util 880722 Submittal of 1987 Rept of Facility Changes,Tests & Experiments Meet Criteria in 10CFR50.59 & Acceptable.Comments Listed
Project stage: Other
1987-02-11
[Table View] |
Text
, ---
V as
'Af (412) 393-6000 One Oxford Centre ktNurgh, P 15279 U.
S.. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
~
Beaver Valley Power Station, Unit No. 2
Subject:
Docket No. 50-412, License No..NPF-73 Carbon Dioxide Fire Suppression System Acceptance Testing
Reference:
DLC Letter 2NRC-7-205, dated' September. 30, 1987, Mr..J. J. Carey to U. S. Nuclear Regulatory Commission Gentlemen:
In
.the above-noted ' reference, Duquesne Light Company (DLC) provided a'
schedule for completion of unfinished fire protection items.
We are pleased to inform you that CO2 concentration testing has been successfully completed for-all eight (8) zones.
The systems were placed in operation-prior to the ! scheduled. due date of December 31, -1987.
The backup. Cog storage tank for providing adequate. reserve capacity has been installed.
Logic testing is in.
progress-and will be completed within a few days.
This does not affect the operation of the system since the backup tank is normally isolated and in standby mode.
During the CO2 testing of ZoneL3 (Cable Vault Area, Elev. 755),
it became necessary to interlock Zone 7
(Relay Room) which is a sub-area within Zone 3.
The automatic feature for electrically interlocking the two zones has been completed and is functional.
The remaining work involves interlocking the manual actuation feature (pull station function)
- which, in the event of a
fire in the respective zones, would not affect the operation of the system.
If there are any questions, please contact my staff.
Very truly yours, I
L b Aala-8801080021 871R31 J. D. Sieber PDR ADOCK ObbsO412 F
PDR Vice President 48 Nuclear Group
,3 cc:
Mr. J. Beall, Sr. Resident Inspector D
Mr. W. T. Russell, NRC Region I Administrator i
Mr. P. Tam, Project Manager Q_-______-_-_---_
_