ML20138R046
| ML20138R046 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/26/1985 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8512300257 | |
| Download: ML20138R046 (5) | |
Text
_____________________________ - - ____
e Put>he Service Electnc and Gas Company C:rtin A. McNeill, Jr.
Put>hc Semco Electnc and Gas Company P O Bos 236.Hancocks Ondge. NJ 08038 609 339 4800 vwe preuset -
fJudear December 26, 1985 Director of Nuclear Itoactor Regulation United Staten Nuclear Regulatory Comminnion 7920 Norfolk Avenue llothenda, Maryland 20814 Attention:
Mo. Elinor Adonnam, Director Project Directorato 3 Division of DWR Liconning Daar Mn. Adonnam:
RADIATION MONITORING SYSTEM COMPLETION STATUS Il0PE CREEK GENERATING STATION (llCGS )
DOCKET No. 50-354 In ronponno to your lottor of November 21, 1985 concerning the ntatun of the llope Crcok Itadiation Monitoring Syntom (itMS), Public Servico Electric and Gan Company (PSE&G) hereby nubmits for NRC review Attachment I which details the current HMS completion statun.
Por thono HMS componentn identifiod in Attachment I a
nafoty evaluation will bo performed to onnuro that the proponed configuration of the componentn ponen no unduo rink to tho health and nafoty of the public.
Iloth the Station Operation Hoview Committoo (SOHC) and offnito Safety Review Group (OSR) will review onch nafety ovaluation.
The renultn of thono nafoty evaluationn will be furninhed to the NRC at loant 30 dayu prior to tho anticipated fuel load dato.
I:xpedited review of thin updated doferral requont in nooded to nupport PSI:&O'n ef fortn to load f uoi at 11C08 on Pobruary 15, 19116.
Public Sorvico Electric and can in ready to moot with tho cognizant NRC pornonnel to review thono mattern nhould you require additional information.
Sincoroly,
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Director of Nuclear 2
Reactor Regulation e
Attachmont C
D.!!. Wagner USNRC Licensing Project Manager R.W. Borchardt USNRC Senior Itosident Inspector J.
Strosnider USNRC Section Chief II. Bicohouso USNitC Radiation Specialist v
I
i ATTACilMENT I RMS COMPLETION STATUS AT 5% POWER l
The Following provides the Radiation Monitoring System (RMS) completion status at 5% power.
Each item identified below is correlated to its respective roman numeral designator as identified in Attachment II of our September 10, 1985 submittal.
I.
Reactor Building Ventilation Exhaust (RBVSE) -
RMS The RBVSE radiation monitors will be functional locally prior to achieving 5% power.
II.
Turbine Building Exhaust (TBE), Turbine Building Compartment Exhaust (TBCE) and Gaseous Radwaste Area Exhaust (GRAE) - RMS The TBE, TBCE, and GRAE radiation monitors will be functional locally prior to achieving 5% power.
l III.
Radwaste Exhaust System (RES) and Radwaste Area Exhaust System (RAE) - RMS I
The RES and RAE radiation monitors will be functional j
locally prior to achieving 5% power.
IV.
Technical Support Center Ventilation (TSCV)
RMS The TSCV radiation monitors will be functional locally prior to achieving 5% power.
V.
Reactor Auxiliary Cooling System (RACS), Safety Auxiliary Cooling System (SACS), IIcating Steam Condensate Decontamination System (llSCD), Turbine Building Circulating Water System (TBCW) - RMS These radiation monitors will be functional locally prior to achieving 5% power.
VI.
Reactor Building Doors, llatches and Airlocks -
The door alarm and monitoring system provides door status including hatches and airlocks (open/
closed) via communication paths from the Local l
Radiation Processor (LRP) to the Central Radiation l
Processor (CRP).
The door alarm and monitoring system portion of the CRP will not be available prior to exceeding 5% power (see item VIII).
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r-However, PSE&G will monitor door status by utilizing the plant security system where applicable.
The doors of concern are normally maintained in the closed position with the exception of the airlock.
Administrative controls will be established prior to fuel load to ensure that appropriate plant personnel are informed of a change in door status from the central alarm station.
Since the details of this alternative method for monitoring door status affects the Hope Creek security plan, specifics will be provided for NRC review under separate cover.
'VII.
Drywell Leak Detection (DLD) - RMS The radiation detection installed on the DLD radiation monitor at fuel load is only designed to operate at temperatures up to 120*F.
A replacement radiation detector designed for 150'F will be available 150 days after fuel load.
VIII.
Central Radiation Processor (CRP)
The CRP will be fully functional 180 days after fuel load.
Prior or on this date, certain functions of the CRP will be available, however, these functions will not be available prior to 5% power.
These CRP functions include the following:
1.
The RM-11 computer, which acts as a data collector and provides the control room operators with measurements, alarms, and operational status for all radiation monitors, will be operational 120 days after fuel load.
2.
The Micro Vax II computer which provides the Regulatory Guide 1.21 reports and the emergency dose assessment report will be operational 60 days after fuel load.
3.
The balance of the CRP is comprised of the VAX 11/750 computer which provides input to the SPDS and CRIDS plant computer.
The VAX 11/750 will be operational 180 days after fuel load.
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I IX.
Emergency Response Facilities -
This issue is' acceptable as documented in your letter of November 21, 1985.
]
X.
Safety Parameter Display System (SPDS)
All radiation monitoring system values and the suppression pool temperature monitoring will be functional as-input to the SPDS 180 days after fuel load.
-XI.
Seismic Qualification Reports -
The seismic Qualification Reports for the Sample Flow Splitter skid for the Filtration Recirculation Ventilation System Vents and Suppression Pool Temperature Monitoring Input and Multiplex Circuit boards will be available prior to exceeding 5%
,i power.
XII.
Preoperational Testing -
i Those RMS components identified as not being available at fuel load will be preoperationally tested in accordance with a Detailed Test Procedure and proven functional prior to service.
The Detailed Test Procedure shall ensure that those RMS components meet the acceptance criteria presented in FSAR Sections 14.2.12.1.41 and 14.2.12.1.46.
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