ML20112H325

Provides Followup to 850326 Meeting & Forwards Revised Pages to Tables Re Status of Environ Qualification of Equipment Important to Safety.Oct 1985 Unscheduled Outage Confirmed

ML20112H325
Person / Time
Site:	Oyster Creek
Issue date:	03/27/1985
From:	Wilson R GENERAL PUBLIC UTILITIES CORP.
To:	Zwolinski J Office of Nuclear Reactor Regulation
References
RFW-0446, RFW-446, NUDOCS 8504020221
Download: ML20112H325 (8)

Text

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GPU Nuclear Corporation NUOIMf 100 Interpace Parkway Parsippany, New Jersey 07054-1149 (201)263-6500 TELEX 136-482 Writer's Direct Dial Number:

March 27, 1985 RFW-0446 Mr. John Zwolinski, Chief Operating Reactor Branch No. 5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555 1

Subject:

GPU Nuclear Corporation (GPUN)

Oyster Creek Nuclear Generating Station (0CNGS)

Docket No. 50-219 Environmental Qualification of Equipment Important to Safety This letter is a follow-up to our meeting with the NRC Staff on March 26, 1985, regarding the equipment environmental qualification status for the Oyster Creek Station. As we had indicated at the meeting, we have, in the past year, completely reviewed the total Oyster Creek EQ program, including updating of the Master Equipment List in the September / October 1984 time frame. This review resulted in substantial additions to the Master List.

These additions resulted from considerations of associated circuits, the potential for spurious or faulty information misleading the operator, the conversion of Oyster Creek to symptom oriented procedures in 1984, Reg. Guide 1.97 items and a very thorough review of updated accident analyses and sequences.

I am enclosing revised pages from the March 26 briefing, reflecting our assessment of some of the issues raised at the meeting. We have been able to conclude that the acoustic valve monitoring systems previously included on the list for the plant safety valves (16 valves) are not required to be environmentally qualified. We have further been able to develop a qualifica-tion approach for the remaining five acoustic valve position indicators on the EMRV's such that we have high confidence the work can be accomplished prior to November 30.

In addition, we are examining, based on Staff comments 8504020221 850327 PDR ADOCK 05000219 P

PDR GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation f (

)

F Mr. John Zwolinski, Chief March 27, 1985 Page Two at the meeting,'our ability to qualify,'by combined analysis and test, the Rockbestos cable before November 30, 1985. We have accordingly moved the indicated time span on those two items into the "Before November 30" category on the attached tables. All of these changes were reviewed by telephone with Mr. J. Donohew, NRC Oyster Creek Project Manager, on March 27, 1985. We are enclosing with this letter revised copies of the briefing charts used during the presentation which reflect these changes. As you can see, these changes make a substantial impact on the total qualification picture for Oyster Creek and allows us to have the majority of work completed prior to November 30, 1985.

We had also indicated at the meeting that outage planning for Oyster Creek, based on a number of considerations, was focusing on a major refueling outage starting on April 12, 1986, but with a planned, limited scope, mini-outage in October, 1985. This letter confirms the mini-outage planning for October, 1985, and we feel that based on available information the items indicated on our status sheet in the categories of "Before November 30, 1985" and

" Unscheduled Outage (Or Mini-Outage)" can be accomplished before or during the mini-outage (before November 30,1985). We are continuing to examine the remaining 19 items still indicated as being accomplished during the next refueling outage but at this time, are unable to be more definitive because of the complexity of the work and ongoing discussions with vendors about hardware and potential delivery dates. We will keep you posted on these issues as definitive information becomes available to us.

ery t ly yours,

~

w\\Am

. F. Wi son Vice President Technical Functions RFW/al ATT

i Mr. J3hn Zwolinski, Chief March 27, 1985 Page Three cc: Administrator Region I.

'U.S. Nuclear Regulatory Comission 631 Park Avenue King of Prussia, Pa.

19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, N. J. 08731 4

't l

l l

k

(Revised) 0YSIERCREEKEQSTATUS (StatusEndofMarch1985)

Replace Or Relocate Analysis Test Iotal Qualified 57 202 0

259 (2)

BeforeNovember30,1985 51 20 2

73 UnscheduledOutageorMini-Outage (beforelll30/85) 32 0

0 32 (3)

NextRefuelingOutage 19 0

0 19 (1) 10TAL 383 (1)

Iotaldecreasedby12deletionsfromFebruary22,1985MasterList,and by48deletionsfromtheSafetyValveMonitoringSystem.

(2)

AttemptingtoenvironmentallyqualifyRockbestoscablebasedonexisting data.

(3)

Ifnotpracticalbefore.

l-1

(Revi* sed)

OYSTER CREEK EQ DETAIL STATUS (Before 11/30 - Shutdown Required)

I I

I l

Component l

l Plant Material l

Engineering l

Type l Nunber l

System l

Status Status l

Remarks l

I i

i Differential Pressure 1 2

l Reactor Plant l August,1985 l October,1985 l Replacement with new mounting Trcnsuitters Rosemount l

l Instrumentation I

details and electrical l

l System l

modi fications.

I I

Differential Pressure l

2 Reactor Plant August,1985 October, 1985 l Replacement with new mounting Pressure Transmitters l

l Instrumentation l

l l details and electrical GE I System l

l l modifications.

I I

I I

I Pressure Transmitters l

2 i Reactor Plant l August, 1985 l October,1985 l Replacement with new mounting Rosemount l

l Instrumentation l

l l details and electrical l

l System l

l l modifications.

I I

I I

I Limitorque Motor l

2 l Drywell and l On-Site l Complete l

Operator Limit l

l Suppression l

l l

Switch:s l

l System l

l l

1 I

I I

I Li::;itorque Motor l

4 l Main Steam System l On-Site l May Operator Limit Switches l l

l l

l Differtntial Pressure 2

Drywell and August,1985 Release for l Replacement with new mounting Switch - ITT Barton l

l Suppression l

l Construction l detail and tubing fit up l

i System l

l August, 1985 l modification.

l 1

I I

I Leval Indicating l

3 l Reactor Plant i August,1985 l Release for l Replacement with new mounting Switches - Yarway l

l Instrumentation l

1 Construction l detail and tubing fit up l

l System l

l August, 1985 I modification.

I I

I I

I

, Valve Monitoring l

5 l Relief Valve l Readily 1 May l Test failure 1

l l Monitoring System l Available l

l l

l System-Connector 4

l l

l l

1 I

I I

I I

Valve Monitoring l

5 l Relief Valve l TBD TBD l

System - Line Driver l

l Monitoring System l I

i l

I

Valve Monitoring l

5 Relief Valve l TBD l TBD l

l l System - Terminal Blockl l Monitoring System l l

l l

TOTAL i 32 I..

OYSTER CREEK EQ DETAIL STATUS (Replace During Refuel Outage) 1 I

I I

I Component l

l Plant l

Ma terial l

Engineering l

Type l Number l

Systems l

Status l

Status l

Remarks l

I I

I I

Pr:sure Switches and l

5 l Core Spray and l TBD l Conceptual l

Contrsliers l

l ADS l

l Engineering Under l l

l l

l Way i

I I

I I

I Level Transmitters l

2 l Emergency l Transmitters -

l Release for l Detailed engineering under way.

l l Condenser System l August, 1985 l Construction l E4, Appendix R, R.G. 1.97 and l

l l

l Process August,1985 l operational requirements issues l

l l Electronics l being addressed.

l l

l Uncertain l

l 1

I I

I I

Flow Transmitters l

2 l Core Spray and l Transmitters -

l Release for l Detailed engineering under way.

l I ADS l August,1985 l Construction i EQ, Appendix R, R.G. 1.97 and l

l l Process l August, 1985 l operational requirements issues l

l l Electronics l

l being addressed.

l l

l Uncertain l

l 1

I I

I I

Flow Transmitters l

2 l Containment Spray l Transmitters -

l l Detailed engineering under way.

l l System l August, 1985 l Release for l EQ, Appendix R, R.G. 1.97 and l

l l Process l Construction l operational requirements issues l

l Electronics August, 1985 being addressed.

l l Uncertain l

I I

I I

Leval Transmitters l

4 l Reactor Plant l Transmitters -

l Release for l Detailed engineering under way.

I l Instrument System l August,1985 l Construction l EQ, Appendix R, R. G.1.97 and l

l l Process l August, 1985 l operational requirements issues l

l l Electronics l

l being addressed.

l l

l Uncertain l

l 1

1 I

I I

Lovel Transmitters i

2 l Reactor Plant l Transmitters -

l l Detailed engineering.under way.

Prcssure Transmitters l 2

l Instrument Systeurl August,1985 l Release for i EQ, Appendix R, R.G. 1.97 and l

l Feedwater Control l Process l Construction operational requirements issues l

l l Electronics l August, 1985 being addressed.

l l

l Uncertain l

I i

0YSTER CREEK EQ DETAIL STATUS (Replace During Refuel Outage) l I

I i

l Component l

l Plant l

Material l

Engineering i

Type i Nunber l

Systems l

Status l

Status l

Remarks l

I I

I I

Valv3 Monitoring l

0 l Safety Valve l

l l

l System Line Drivers l

l Monitoring System I i

l i

Valva Monitoring l

0 Safety Valve l

System Tenninal Blocks l l Monitoring System l l

l l

l TOTAL i

19 l

l e

0YSIER CREEK FUKRE OllIAGE PLMING 0

Outage Workscopeverylarge DominatedbyAppendixR,DrywellWork Extensiveinspections-ExEquipment, piping,RxVessel Desire to do recirc piping IHSI, convert to H water chemistry 2

0 BylawcannotscheduleshutdownNovember30throughApril'.1 0

Considerations Formajoroutage/refuelingnotreadyuntilSpring1986 Desiretodosomeequipmentinspectionsearly Iokeeprefuelingoutagereasonablydoable-mustdocajorwork duringoperation/beforerefuelingoutage.

0 TentativeConclusion

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SchedulerefuelingoutageApril12,1986 Schedulemini-outageOctober1,1985limitedto4 weeks i