05000280/LER-1980-004-01, /01T-0:on 800108,during Routine Startup,Check Valve 1-FW-89 in Discharge Line of Auxiliary Feed Pump Stuck Open.Cause to Be Evaluated by Vendor.Feed Pump & Motor Operated Valves Cycled to Close Valve

/01T-0:on 800108,during Routine Startup,Check Valve 1-FW-89 in Discharge Line of Auxiliary Feed Pump Stuck Open.Cause to Be Evaluated by Vendor.Feed Pump & Motor Operated Valves Cycled to Close Valve

ML18136A411
Person / Time
Site:	Surry
Issue date:	01/22/1980
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18136A409	List: 05000280/LER-1980-004, Forwards LER 80-004/01T-0 05000280/LER-1980-004-01, /01T-0:on 800108,during Routine Startup,Check Valve 1-FW-89 in Discharge Line of Auxiliary Feed Pump Stuck Open.Cause to Be Evaluated by Vendor.Feed Pump & Motor Operated Valves Cycled to Close Valve
References
LER-80-004-01T, LER-80-4-1T, NUDOCS 8001230118
Download: ML18136A411 (2)

LER-1980-004, /01T-0:on 800108,during Routine Startup,Check Valve 1-FW-89 in Discharge Line of Auxiliary Feed Pump Stuck Open.Cause to Be Evaluated by Vendor.Feed Pump & Motor Operated Valves Cycled to Close Valve

Event date:
Report date:
2801980004R01 - NRC Website

text

N...R.C fQ~f},1,366 (7-77)

U.S. NUCLEAR REGULATORY COMMISSION * *

- LICENSEE EVENT REPORT e

CONTROL BLOCK: L I r.j\\

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

Ll -..L---'---'---L-.-L._.J6 \\,.,V

~

I vi A! s1 Pl Sj 1101 ° I O I - I O I O I O I O I O I - I O I O 1014 11 11 11 I 1 101 I 10 7

8 9

LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T [il2J 7

. 8

~~~~~ U© I O I 5 I O I O I O I 2 I 8 I O 101 60 61 DOCKET NUMBER 68 69 01 11 01 Bl Bl 01@1 01 11 212 I sl o!G) 74 75 REPORT DATE 80 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCc:S@

l During routine startup operations, check valve l-FW-89 in a discharge line of the.

Aux. Feed pumps stuck open.

If the valve remained open, this would appear to impact

~

on the previous analysis of the secondary side high energy line break.

Procedural steps do exist to effect necessary isolation following a line break, therefore, the [Q))] I health and safety of the public would not have been affected.

[ITD

[§li]

7 8 9

~

7 8

SYSTEM CODE IC I H j@

9 10 LER/RO CVENT YEAR REPORT I s, OJ NUMBER 21 22

CAUSE

CAUSE COMP.

CODE SUBCODE COMPONENT CODE SUBCODE

~@ ~@ I v I A I L I v I E I x 18 L.9 11 12 13 18 19 SEQUENTIAL OCCUR REN CE REPORT REPORT NO; CODE TYPE VALVE SUBCODE

~@

... 20 I I I O I O I 4 1 I /I I O 11 I L:.J l.=1 23 24 26 27 28 29 30 31 ACTION FUTURE EFFECT SHUTDOWN r;;)

ATTACHMENT NPRD-4 PRIME C.OMP.

REVISION NO.

~

32 COMPONENT MANUFACTURER 80 TAK:&'.N ACjON ON PLANT METHOD HOURS ~ SUBMITTED FORM 5UB.

SUPPLIER u@u@ LJ@ tJ I 0 1 °1 °1 I l!J@ ~@ ~@

33 34 35 36 3 7 40 41 42 43 I c I 6 16 15 1 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

44 47 I The Aux. Feed pump and MOV' s were cycled, which resulted in the successful closure of [II)) I l-FW-89.

The NSS vendor has been contacted and an evaluation will be performed.

ITIII m::D ITill 7

8 9

FACILITY STATUS

% POWER OTHER STATUS @

METHOD OF A

80 OE L.9 1 o1 o1 01@)._j _NA _____ -'

8 9

10 12 13 DISCOVERY DISCOVERY DESCRIPTION

~~~l __

Op_e_r_a_t_o_r_O_b_s_e_rv_a_t_i_o_n ___

44 ACTIVITY CONTENT t::;;\\

RELrSED OF RELEASE AMOUNT OF ACTIVITY

[:EJ L:J @) l:..J@._I __

NA ______

7 8

9 10 11 7

45 46 BO NA LOCATION_ OF RELEASE @

44 45 80 PERSONNEL EXPOSURES Q\\

O NU~BER.O A TYPE DESCRIPTION~

E1zJ I I u I J0l!J@L....-__

NA _____________________

7 8

9 11 12 13 PERSONNEL INJURIES

/41) 80 ONU~BER DESCRIPTION~

[QI] I I I O !@.__ ________________________

7 8

9 11 12 80 LOSS OF OR DAMAGE TO FACILITY '43' T'2'E DESCR'NA'ON

~

~

L:J~"---~-----------~---~---~~------'

7 8

9 10

~

80 PUBL1c1TY r::;;-..

oO 012 80 I I g NRc usE ONLY r::;-r;:;"1 2

O lrSUEr~

44 LD-ES_C_tl,l_lf-T-IO_N_~_

4 5

~

N CY_

NA I I I I I I I I I I I I I~

7 8

9 1 0 6 8 6 9 80

• 0:

T PHnNI=*

C80/t) 3 51 3 J8 !1 0 a.

e (ATTACHMENT, PAGE 1 OF 1)

SURRY POWER STATION, UNIT 1 DOCKET NO:

50-280 REPORT NO: 80-004/0lT-O EVENT DATE:

1/8/80 TITLE OF EVENT:

Aux. Feed Valve (l~FW-80) Malfunction

1.

DESCRIPTION OF EVENT

e During routine startup operations, a check valve (l-FW-89) in a discharge line of the Auxiliary Feed pump stuck open.

The event is reportable in accordance with Technical Specification 6.6.2.a.5.

2.

PROBABLE CONSEQUENCES/STATUS OF REDUNDANT SYSTEMS The Safety Analysis Report evaluates the effects on following a secondary side high energy line break.

the check valve rema.ined open, more than one steam affected.

The NSS vendor is evaluating the event.

3.

CAUSE

only one steam generator It is possible that if generator could have been The reason that the valve stuck open is unknown at this time.

4.

IMMEDIATE CORRECTIVE ACTIONS

The successful method of closing the check valve involved the cycling of the Steam Generator "C" Aux. Feed MOV's, utilizng an Aux. Feed pump as the driving force.

It was verified that the valve had closed by observing that the level in all steam generators returned to normal.

5.

SCHEDULED CORRECTIVE ACTIONS An evaluation has been initiated by the NSS vendor to assess impact of the event.

The valve will also be inspected at the next scheduled shutdown.

6.

ACTION TAKEN TO PREVENT RECURRENCE The return of all steam generator levels to normal following the Aux. Feed MOV evolution indicated that the valve had returned to its normal state.

Following a reactor trip later in the startup operation, it was observed that the valve functioned properly.

The valve in question is scheduled for inspection during the next scheduled shutdown.

7.

GENERIC IMPLICATIONS An evaluation by the NSSS vendor will be performed to assess the generic implications of this event.