ML18010A570
| 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 FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION Carolina Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION DOCKET ¹ 05000400
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 ID CODE/NAME PD2-1 LA MOZAFARI,B.
COPIES LTTR ENCL 1
0 1
1 RECIPIENT ID CODE/NAME PD2-1 PD COPIES LTTR ENCL 1
1 INTERNAL: AEOD/DSP/ROAB NRR/DRIS/RVIB9D RES/DSIR/EIB RGN2 RGN4 SECY VANDERMEL EXTERNAL:
ZNPO RECORD CTR NSZC SILVER,E 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 NR ~8E G
RGN RGN3 RGN5 NRC PDR CB11 2
2 1
1 1
1 1
1 1
1 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 NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 18 ENCL 17
0 r
C
3&kI6-S2 THU 15:29 P. 02
SUBJECT:
10CFR21 INITIALNOTIFICATION 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 model generators (SGs),
These SGs as mo el D-4 steam 100% ful1 ow s have a split feed arrangement where at u
p er sect>on located immediately above the ee 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)
Isolation Valves wer The valve and actuator for thee 3 Main Feedwater Preheater Bypass on a ves were specified, purchased, and installed for a Q
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 o
e accumulator ite p
~z6 g), could cause a s~tuation where normal leak o undet f
m 1) from its normal 150 psig pressure would age switches go un etected by redundant pressure switches (Ps A
d B) provide the valves an auto close signal when e
an
).
These drops to 66 psig in the input air header The valves are containment isolation valves and are requ'r d
seconds of a
feedwater isolation signal.
If i e o
accumulator pressure drops from its normal 150 psig to below 122 psig, it may not close within the required time.
If l
me.
o approximately 20
- psig, there may not be su c1ent force to reposition the valve and maintain it closed against maximum differential pressure.
., igpQ+~9 920aaSOOO9 9aOSaa PDR ADOCK 05000400 8
'JAN;-16-92 THU 15:30 r,
P,03 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 fullypressurized.
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.
~ ~
z PJ ql.
QI2 Ha@ Q-CI ASS S
SI9= 6 S GB'C VfHH~I <<CPS HON~~ /4 Q2 CXI QUIP RKPQ f IN L I 5 gag~: C ) p e ~ ~ get PI'r AIg PSlS Qs Q} CO S ASCO fk5 VA ION O-)ao. IOS I ~, KLKCTRClt. OATA
- t. SOLKNOC VAU~- fRI VO.C-
+ 12') -Qfo QOLTQE (NTER MUTANT SERVlCE dPF~ONS DIP Qa g Qsc f4 4tPg A&44$08+4 t-g+i $0 soot/AK~ C1 JVr4 t4f-it g4 ogf~Pt'A AQf icfit I HORMAL OPKRAYLNG hbhQSTMENT (SKY PK FhCKQLY) R I;. PII:IRK/8%4.01EIA B $ 70 PKLB. N}F'l'LPIIIAPRE4.0TKM VS ) ZD PS14-g4. NECK VALVE(AM i4 > t)<~h <> 4>>>>~>> ~'"" tT ~ 2.Q N
Tamil bESCQPTeg BASIC AN~~ g, ~ g~ NTH ACCVglaA~. 'y-+ear Ve.m NOAORKN %MAC MOM-fN, ROA KXHhUW'HE a IVLOSl%.L MOOR@. NO KM"R aH~sr emm8 Outre:.RC sOOIL bOW FlON COf4 %ALVK AKPUSJC HOMAL g. NOISC 88S-0 AN PLNAP HASCEL. MOOEL IDIO. AAO-5 Itg AN AKQULATM eeew seoac re. o-eoa-os< + FLTER-I'4QLhmd, 4L V~ -3NIY Samae Oe6etRa mph NN NIISL'O.~ N5 VA NNNau.Y cLegm tOA lOS I3 E O't40 HI1 AAOLC lg+<P~~ CZCAh lOA 5%%+ 70l~ Qlo 0-$ 40 &Stan Ce4V4R ~W er4ah g .NocARIas A tQ-o~g goy gg'tt.>tC V1c.ve ~ sol:geuu o <e-no<-ops C}~500 P%l QAVQC <<Ibl TO hCCVH ~ /tie 544% 4'8 K /z. ~ 4 N'H ~ Q CIIA ~ BOO " NOtbt K VAvvf~ b11MN Iec. + M-9O--Io OKCR NLVK + Sgg INQF AN. CIRCNT 8%lWN NTH 'AK ACTUNOR I N. ffS NORMAL PfAOII (AKfRACYKO) tA) f(aiemaenm. ItCATKS ~ QESNHATKN AS OH, QILVK5. It& ~0 ~ 4 ~ ~ ~ ~ COl5%MY ~ ~ ~ AIR CAQgf 0 %NIMS ONCRIN 0% KKt IR SA'AOP J. ~}}