ML18010A507

Initial Part 21 Rept Re Deficiency in Actuator to Main Feedwater Preheater Bypass Isolation Valves.On 920107,2 H Surveillance Interval Was Commenced to Verify Actuator Components Were Functioning Properly

ML18010A507
Person / Time
Site:	Harris
Issue date:	01/16/1992
From:	Oleyik C CAROLINA POWER & LIGHT CO.
To:	NRC
References
REF-PT21-91 NUDOCS 9201240211
Download: ML18010A507 (8)

Text

ACCELERATED D'RIBUTION DEMONSTTION SYSTEM RECIPIENT ID CODE/NAME PD2-1 LA MOZAFARI,B.

COPIES 'ECIPIENT LTTR ENCL ID CODE/NAME 1

1 PD2-1 PD 1

1 COPIES LTTR ENCL 1

1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9201240211 DOC.DATE: 92/01/16 NOTARIZED:

NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina

'AUTH.NAME

=

AUTHOR AFFILIATION OLEYIK,C.

Carolina'ower

& Light Co.

RECIP.NAME RECIPIENT AFFILIATION NRC No Detailed AffiliationGiven

SUBJECT:

Initial Part 21 rept re deficiency in actuator to main feedwater preheater bypass isolate.on valves. On 920107,2 h

surveillance interval was commenced to verify actuator components were functioning properly.

DISTRIBUTION CODE:

IE27D COPIES RECEIVED:LTR g ENCL Q SIZE:

. 5 TITLE: 50.55(e)

Construction Deficiency Report NOTES:Application for permit renewal filed.

DOCKET 05000400 D

/

05000400 A

D D

INTERNAL: ACRS NRR/DLPQ/LPEB10 NRR/DOEA/OGCB11 OGC/HDS1 RES/DSIR/EIB EXTERNAL: NRC PDR 6

6 1

.1 1

'1 1

1 1

1 DEDRO NRR/DOEA/OEAB11 NRR/DRISiRVIB RE IIIE~

RGN2 FI-L-OX NSIC SILVER 1

1 1

1 1

1 1

1 1

l.

1 1

S D

NOTE TO ALL"RIDS" RECIPIENTS D

D PLEASE HELP US TO REDUCE ivASTE! CONTACT THE DOCU~IENT CONTROL DESK, ROOb I Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 20 ENCL 20

JAN-16-92 THU 15:29 P. 01 TELECOPY COVER SHEET DATE SENTt TIME SENTt CFOUL P ~

Oo BOX 165 ~

NEW HILL~

N ~ C ~

27562 THIS IS A SHARP FO-5200 FAX OUR TELECOPY PHONE NO. IS 919/362-6950.

FROMt 4

TELECOPY TO)

TELECOPY PHONE NO:

VERIFICATION NOl CITY AND STATE:

NO.

OF PACES FOLLOWING COVER SHEET:

IF ANY PROBLEMS OCCUR DURING TRANSMISSION, PLEASE CONTACT OFFICE SERVICES AT 919/362-2708a 920i2402ii 920iih PDR ADOCK 05000400 8

PDR OPERATOR NAME:

HEM/FAX/1/OSI

JAN-l6-92 TW'16'29 P. 02 SUBZZCT:

10CFR21 INITIAL NOTIFICATION SHEARON HARRIS NUCLEAR POWER PLANT ITEM:

DEFICIENCY XN THE ACTUATOR TO THE MAIN FEEDHATER PREHEATER BYPASS XSOLATXON VALVES.

Plant Identification numbers:

2AP V156 SAB'1 2AP-V157 SAB-1 2AF-V158 SAB-1 The-Harris Plant (3 loap Westinghouse NSSS) has model D-4 steam generators (SGs).

These SGs have a split feed arrangement where at.

100% full power, approximately 824 of the needed SG feed flow is dix'ected to the sG preheatex section located immediately above the SG tube sheet, and the remaining 184 is directed to the SG upper U-tube region via the same line used fox'uxiliary feedwater (AFW) flow.

The containment isolation valve for the 184 feed flaw path is the Main Feedwatex Px'cheater Bypass Xsalatian Valve.

SUPPLIED BY:

ANCHOR DARLXNG SUPPLXEO VALVE AND ACTUATOR PACKAGE HILLER ACTUATOR MODEL g 12 SA-A029 ATURE oF DEFIcIENcY: (see attached drawing)

The valve and actuator for the 3 Main Feedwater Preheatex'ypass Isolation Valves were specified, puxchased, and installed for a Q

Class application.

During review of a proposed plant modification, it was determined that several actuator companents wexe in fact non-Q.

A potential failure mechanism existed whex'e the failure af a nan-Q component cauld result in the inability of a Q-class component to perfaxm as designed.

Specifically, a postulated failure of the air pump (f6 in drawing), could cause a situation where normal leakage af the accumulator (item 1) from its normal 150 psig pressure would ga undetected by redundant pressure switches (PS A and B).

These switches provide the valves an auto close signal when pressure drops ta 66 psig in the input air header.

The valves are containment isolation valves and are required ta close within 10 seconds of a

feedwater isolation sign~i,

-If accumulator pressure drops from its normal 150 psig to below 122 psig, it may'ot close within the required time.

Xf accumulator pressure drops to approximately 20

psig, thexe may not be sufficient force ta reposition the valve and maintain it closed against maximum differential,pressure,

JNl-16-S2 THU 15:30 P. 03 REpoRT 6

sx This design deficiency could have compromised the containment boundarys'apability to prevent or mitigate the consequences of accidents resulting in offsite exposures.

xtmEDIATE coRRE Ivy AcTIoN; Upon discovery'f this condition on January 7,

1992 a two hour surveillance interval was commenced to verify the actuators'omponents were functioning properly and the accumulators were fullypressurized.

On January 12, 1992, all non-Q components were replaced with suitable components and tested satisfactorily.

Following this the two hour surveillance interval was suspended.

An engineering review was in progress during this time to determine the 10CFR21 reportability.

On January 15I 1992 the Harris Plant Nuclear Safety Committee determined a

10CFR21 report was appropriate..

FOT.LONUP ACTION:

A Written repOrt Will be Submitted by February 14, 1992':

i Failures of Hiller Actuators Upon Gradual Loss of Air Pressure.

oINT 0F coNTAc chuck olexik, Manager Regulatory compliance, Harris Plant 919-362-2718.

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