ML18010A570

Initial Part 21 Rept Re Defect in Anchor Darling Supplied Main Feedwater Preheater Bypass Isolation Valves.On 920112, All non-Q Components Replaced W/Suitable Components & Tested Satisfactorily.Next Rept Will Be Submitted by 920214

ML18010A570
Person / Time
Site:	Harris
Issue date:	03/23/1992
From:	CAROLINA POWER & LIGHT CO.
To:
References
REF-PT21-92 NUDOCS 9203230009
Download: ML18010A570 (6)

Text

ACCELERATED DISTIUBUTION DEMONSTjRATION SYSTEM REGULATC INFORMATION DISTRIBUTION STEM (RIDS.)

ACCESSION NBR:9203230009 DOC.DATE: 92/03/23 NOTARIZED: NO DOCKET ¹ FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION

• Carolina Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

Initial Part 21 rept re defect in Anchor Darling supplied main feedwater preheater bypass isolation valves. On 920112, all non-Q components replaced w/suitable components & tested satisfactorily. Next rept will be submitted by 920214.

DISTRIBUTION CODE: IE19D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Part 21 Rept (50 DKT)

NOTES:Application for'ermit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 0 PD2-1 PD 1 1 MOZAFARI,B. 1 1 INTERNAL: AEOD/DSP/ROAB 1 1 NR ~8E CB11 2 2 NRR/DRIS/RVIB9D 1 1 G 1 1 RES/DSIR/EIB 1 1 RGN 1 1 RGN2 1 1 RGN3 1 1 RGN4 1 1 RGN5 1 1 SECY VANDERMEL 1 1 EXTERNAL: ZNPO RECORD CTR 1 1 NRC PDR 1 1 NSZC SILVER,E 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 17

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P. 02 3&kI6-S2 THU 15:29

SUBJECT:

10CFR21 INITIAL NOTIFICATION SHEARON HARRIS NUCLEAR POWER PLANT ITEN: DEFICIENCY IN THE ACTUATOR TO THE HAIN FEEDWATER PREHEATER BYPASS ISOLATION VALVES.

Plant Identification. numbers:

2AF-U156 SAB 1 2AP-V3.57 SAB-1 2AP-V158 SA8-1 The Harris Plant (3 loop Westinghouse NSSS) has el D-4 steam model as mo generators (SGs), These SGss have a split feed arrangement where at 100% fu ul1 power, ow approximately 824 of the needed directed to the SG p reheateer ssect>on located immediately above the SG feed ee fl ow 1s u e sheet, and the remaining 184 is directed to the sG upper U-u e region via the same line used for auxiliary feedwater (AFW) ow. The containment isolation valve for the 184 feed flow ath s the Main Feedwater Preheater Bypass Isolation Valve.

SUPPLIED BY: ANCHOR DARLING SUPPLIED VALVE AND ACTUATOR PACKAGE HILLER ACTUATOR MODEL P 12 SA-A029 NATURE 0F DEFIcIENcY: (see attached drawing)

The valve and actuator for thee 3 Main Feedwater Preheater Bypass Isolation on Valves wer specified, purchased, and installed for a Q a ves were ass application. During review of a proposed plant modification, it was determined that several actuator components vere in fact A potential failure mechanism existed where the failure of a in e znabxlity of a Q-class component to orm as esxgned. Specifically, a postulated failure of the air p ~z6 g), could cause a s~tuation where normal leak age o e accumulator f ite m 1) from its normal 150 psig pressure would undet goo un etected by redundant pressure switches (Ps A an d B)) . These switches provide the valves an auto close signal when e drops to 66 psig in the input air header The valves are containment isolation valves and are requ'r seconds of a feedwater isolation signal.

i e d Ifo accumulator pressure drops from its normal 150 psig to below 122 psig, it may not close within the required time.

o approximately 20 psig, me.

there may not l be If accumulator p

su c1ent force to reposition the valve and maintain against maximum differential pressure.

it closed

., igpQ+~9 920aaSOOO9 9aOSaa PDR ADOCK 05000400 8 PDR

P,03

'JAN;-16-92 THU 15:30 r,

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

IHNEoIATE coRRE IvE AcTIoN: Upon discovery of this condition Qn January 7, 1992 a two hour surveillance interval was commenced to verify the actuators'omponents were functioning properly and the accumulators were fully pressurized. on zanuary 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 15, 1992 the Harris Plant Nuclear Safety Committee determined a 10CFR21 report was appropriate.

FGLLGNUP cTloN: A written report will be submitted by February 14 i 1992, Fa'ilures of Hiller Actuators Upon Gradual Loss of Air Pressure.

OINT OF CONTAC  : Chuck Olexik, Manager Regulatory Compliance, Harris Plant 919-362-2718.

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