ML19332D142

LER 89-031-00:on 891024,closing Times for Two in-series Primary Containment Isolation Valves Exceeded Acceptance Criteria During Shutdown Testing.Cause Undetermined.Closing Time Retested W/Satisfactory results.W/891122 Ltr

ML19332D142
Person / Time
Site:	Pilgrim
Issue date:	11/22/1989
From:	Basilesco G, Bird R BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
89-170, LER-89-031, LER-89-31, NUDOCS 8911300068
Download: ML19332D142 (5)

Text

g ,

,4 '

~

" 10 CFR 50,73

,~. .

D  !

.t .

Pilgrim Nuclear Power station

Rocky Hill Road . .

Plymouth. Massachusetts 02360 Ralph G. Bird November.22, 1989-senior Vice President - Nuclear BECo Ltr.89-170 ,

j U.S._ Nuclear. Regulatory Commisslon ,

Attn:- Document Control Desk Hashington, D.C. 20555 Docket No. 50-293 License No. DPR-35 l

Dear $1r:

The enclosed Licensee. Event Report (LER) 89-031-00, " Closing Time for Two In-Series. Primary Containment Isolation Valves in Excess of Technical

//' Specification Limits During Testing While Shutdown", is submitted in accordance with 10 CFR Part 50.73.

i Please do not hesitate to contatt me if you have any questions regarding this' subject.

R.G. Bird ,

-GJB/bal

Enclosure:

LER 89-031-00

> cc: Mr. Hilliam Russell ,

Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19406 Sr. Resident Inspector - Pilgrim Station Standard BECo LER Distribution i

3911300068 891122 ,

gDR. ADOCK0500g3 I \

l

y~.'

NRC Foge 306 U.S. NUCLEA;4 hE1ULATORY COMMIS$10N

,- APPROVED OMS NO 3140 0104

. LICENSEE EVENT REPORT (LER) ' "P'at ' 85 '

F ACILITY NAME H) DOCKET NUMSER til PAGE (3s Piler'im NP % nP PoweV> Stnrinn 0 [5 l 0 l0 l 0 lo h 1 < 1 loFl 014 Closing Tilne for Two In-Series Prirrary Containment Isolation Valves in Excess of Techn!nni Snei N entinn 1 %ite rxmine Testine whih 9huth I EVENT DATE (5) LER NUMBER IG) REPORT DATE (7) OTHER F ACILITIES INVOtVED tSi MONTH YEAR YEAR 5t G n' MONT H DAY YEAR T V N AMES DOCKET NUMBER 181 DAY g (AL 0 15101010 1 l l

~ ~

1l0 Eh Ro Rl 0 0l 9 l 1 do 1l1 2l2 8l9 01 5 0:0:0 1 1 I THIS REPORT 18 9USMITTED PUR8UANT TO THE REQUIREMENTS OF 10 CFR $: (Chere one er more of the foltosympp till OPERATING

[- MODE 19)

M 20 402(b) . 20 4061st to.734elt2Hal 73.71th)

R 20.408teH11til 60.36(eH1) 60.73teH2Hul T3.711s) t sol Oi 0 [0 20 40ei.niHe

.0.3.isH2i

.0.n eH2H..:

_ gHE gs g ,j, g 20.405(eH1 Hell 60.734 H2H63 B _

""""2"*"^' 3"d' 20.4054sH1H6v) 50.736eH2H61) 80.73teH2HvtitHR) 20.406teH1Het 60,73teH2H644) 50.72(el(2Hal LICENSEE CONTACT FOR THl$ LER liti NAME TELEPHONE NUMBER ARE A CODE Gary J. Basilesco, Plant Engineer Sio i 8 7: 4,7i-i8 I 51314 COMPLETE ONE LINE FOR E ACH COMPONENT F AILURE DESCRIEID IN TH18 REPORT 113)

CAUSE COMPONENT U C' L MAN AC- R RTA E f SYSTEM " O hPR $ CAU$4 $YSTEM COMPONENT y pp a

X I F i .,. i q 1, ni ntnl 6 Y I I I I I I I -

I l 1 1 I i l l l 1 l l l l SUPPLEMENTAL REPORT EXPECTED (14) MON 1H DAY YEAR YES til ves comprete EXPLCTED SUOMISSION CA Til NO l l l A T:. ACT m,-, ,. .# co e . e.,,.e-e,, ,,,,se,, ,,,,,,0 <e ,,-,,,,,, m,0., o.,

On October 24, 1989 at approximately 0020 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />, the closing times for two in-series primary containment isolation valves (CV-5065-91 and -92) exceeded acceptance criteria during testing conducted while shutdown.

The closing time for the isolation valves is considered an isolated occurrence based on the performance history of the valve. A review of valve performance data has determined that the closing time for these valves was an anomaly.

The isolation valves are one-inch globe type valves and were manufactured by G.H. Dahl Co., Inc.

The closing time for the valves was retested in accordance with procedure on October 26, 1989 with satisfactory results. Corrective action is dictated by the ASME Boiler and Pressure Vessel Code Section XI for in-service testing of pumps and valves. Those requirements are administered via Boston Edison's Inservice Testing (IST) Program. The valves are continually monitored for degradation, and performance data is trended and analyzed to ensure

! operability.

The test was performed while shutdown with the reactor mode selector switch in the SHUTDOWN position. The control rods were in the inserted position. The Reactor Vessel (RV) water temperature was 120 degrees Fahrenheit and the RV pressure was zero psig. The reactor power level was zero percent. The closing times for the isolation valves posed no threat to the health and safety of the public, and this report is submitted in accordance with 10 CFR 50.73(a)(2)(1)(B).

NRC #erm 356 G8Ji-

, g

.~ -

AsetC Feesi 3eSA - U S. NUCLli;l KEIUts.TOaY COMMtBSION  ;

" ~

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION movep out No aisodio.

[ ., EXPtRES: B/31/WI

" Et';tLITY NAR8E (1) DOCILET NUMBER Qi LER NUMBER ($1 PAOL 13) uma "MP .

"E*.70 Pile; rim Nuclear Power Station ~

olsl0l0l0 2 l 9l 9 9l0 -

0l9 l 1 -

ol0 0l 2 OF 0 l4 TEXT f# enom apoco e pseusvd, see esMoons/ #4C Form JABA W (17)

EVENT DESCRIPTION

-y" On October 24, 1989 at approximately 0020 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />, the closing time for two in-series primary containment isolation valves (CV-5065-91 and -92) exceeded acceptance criteria during testing conducted while shutdown.

The valves were being timed in accordance with Procedure 8.7.4.1 (Rev. 2),

" PASS ated2 H /02 Analyzer Valves Quarterly Operability". The procedural acceptance criteria for the closing time of these valves is less than or equal to four seconds. Technical Specification 3.7.A.2.b (Table 3.7-1) specifies a closing time of five seconds. The closing time for valves CV-5065-91 and -92 was'approximately 8.4 and 11.8 seconds, respectively. 1

' failure and Malfunction Report 89-406 was written to document the failure of the valves to meet the acceptance criteria for closing time. The valves are one-inch globe type valves manufactured by G.H. Dahl Company, Inc.

The test was performed while shutdown with the reactor mode selector switch in

.the SHUTDOWN position. The control rods were in the inserted position. The Reactor Vessel (RV) water temperature was 120 degrees Fahrenheit and the RV pressure was zero psig. The reactor power level was zero percent.

CAUSA The cause of this event is unknown. The closing time for these valves is-considered an isolated occurrence based on valve performance since test '

trending began in.1985. No evidence exists to indicate that thess valves should not close in the specified time. Trend records for these valves indicates no evidence of' valve degradation.

The closing time for the valves (CV-5065-91 and -92) was most recently tested with satisfactory results in accordance with procedure (8.7.4.1) on September 23, 1989. At that time, the closing time for valves CV-5065-91 and -92 was approximately 3 (three) to 3.5 (three and one-half) seconds.

CQRRECTIVE ACTION The closing time for the valves was retested in accordance with procedure (8.7.4~.1) on October 26, 1989 with satisfactory results. Corrective action regarding the valves is within the scope of the Inservice Testing (IST)

Program. The valves are continually monitored for evidence of degradation.

While trending reveals no evidence of existing degradation for the subject valves (CV5065-91 and -92), the test frequency has been increased from quarterly to monthly. No additional action is planned at the present time.

Future valve performance will dictate any additional corrective action in ,

accordance with the IST program.

l l-

" " " ~ ^

a-- -

m -

GenC form SEGA VS. NUCLEJ.3 CEIULAs0RY COMMIS$10N LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AnRoveo oms No. mo-om EXPIRES- s?31/W1 FACILif V NAM 411) DOCKEY NUMBER (3) LER NUMBER (S) PAOS (3) viAa " W,0. "S*J:

Pilgrim Nuclear Power Station 0l510l0101 2{ @3 8 19 O l 3l1, -

0 10 013 oF 0 l4 sexsou e m m omcmsewim,

.The IST program implements the requirements of ASME Boiler and Pressure' Vessel-Code,Section XI for inservice testing of pumps and valves and is administered via Station Procedure No. 8.I.1, " Administration of Inservice Pump and Valve Te3 ting". The program trends valve performance by maintaining records and by analyzing test data.

l

$_AFETY CONSIOUENCES 4 The closing times for the valves posed no threat to the health and safety of the public.

The objective of the Reactor Pressure Boundary Leak Detection System includes monitoring airborne radioactivity levels in the Drywell portion of primary ,

containment. The system includes two permanently installed and redundant  !

panels, C-19A (West) and C-19B (East). The panels return their gaseous l samples to the Drywell via a common one-inch pipe that penetrates the Orywell  !

at penetration (X-32A). The pipe includes in-series valves CV-5065-91 and -92 5 that provide an automatic (or manual) isolation function. The valves are normally.open and both are outboard of primary containment. j Although the testing showed the valves to close in times greater than the j Technical Specification limits, the isolation function provided by these valves was still available. 4 This report is submitted in accordance with 10 CFR 50.73(a)(2)(1)(B) because the closing time for the isolation valves exceeded the Technical Specification ,

Table 3.7-1 closing time of five seconds. The closing time for the valves -i (CV-5065-91 and -92) was satisfactory when the valves were last tested during power operation on September 23, 1989. A controlled plant shutdown was  ;

completed on October 13, 1989 for planned testing and maintenance. Therefore, 1 Technical Specification 3.7.A.2.b may have (unknowingly) not been complied with since September 23, 1989 in that the in-series valve (CV-5065-91 or -92) was not closed and deactivated. ,

SJJilLARITY TO PREVIOUS EVENTS A' review was conducted of Pilgrim Station Licensee Event Reports submitted since January 1984. The review focused on LERs that involved the closing time for valves CV-5065-91 or -92. The review revealed no previous instance of the closing time (s) exceeding the specified limit.

4 t

s

- , -- v - . 3 p.v.+ .

, y seAC Pe o 8884 U 8. NUCLE A3 KE1ULATCf.Y COMWESION h

"~ '

- LICENSEE EVENT REPORT (LER) TEXT CONTINUATION - Amovio ous No. 3 iso-oio4 EXPIRES: 8'31/88 PAcettTY esAME (t) . DOCKET NUMBER Q) LIR NUMSER 141 PA0613) .

TIA" ':

• $NO'

tE*

uaN iP11EJ'im Nuclear Power Station 015 l o l o l o 121913 819 -

01311 -

Ol0 01 4 0F 014 ,

TEXT f# mom ausse 4 reevisst see adsenenst NAC poms and W (17) p ENERGY INDUSTRY IDENTIFICATION SYSTEM (EILS) CODES The EIIS codes-for this' report are as follows:,

F' '

COMPONENTS CODES ,

a Valves, Isolation (CV-5065-91, -92) ISV

~ SYSTEMS-

!~# c

' Reactor' Pressure Boundary Leak Detection System IK i Primary Containment System (PCS) JH-T r

P k

'?

k l: .

t

.'r o

I l .: n :c romu seen

'- M