ML19095A501

Submit Licensee Event Report No. LER 78-016/03L-0 Re Valve MOV-RH-100 Was Not Opening

ML19095A501
Person / Time
Site:	Surry
Issue date:	07/21/1978
From:	Stallings C Virginia Electric & Power Co (VEPCO)
To:	O'Reilly J NRC/RGN-II
References
Serial No. 414 LER 1978-016-03L-0
Download: ML19095A501 (3)

Text

., ' ', **~ -~ '

.r;:*  :**~**

. ~. .' . ' *,

.. ' :y~,Rf3I~i~':E~EC~RIC .

,:AND'* Po:wE~ *c;?.~.

-~f~Y: .* ::-:, .

• *RicliMoNn,VIHGINI~*~a261  :*;. * ,;:.*

. r.._,

1* .

.. : .. \Ju.ly*

.. 21,

_1978,'... *

' ...,.... .' ~~-: : :~;

.**-* ~ , .

. ..-i_~-:.i

(';'_I,

. -Hr. James p.* ** O'R~iii.1.: Dir.ectof. :' *,:.: ::* '. ... . . S~rlal Ho.--:414 *.

. ' Off ice of Inspect:1.oo. . mid Enforcement . . . .: PO&M/DLB :das *: -

.. u~ *"s *. N~clear. Regulatory . CooimisSicm . . :.- bocket i-16 .. *50;.:.2ao Region II; Sµite 818  : *.. ':*... .  : . .

• Lice1isc*, ffo~,' DPR.;.J2

.*230. Peachtree. Street*,. 1:l'orti{west *. , ..

At.ianta, .Georgia" 30303 . . . . .

Ilear_: Hr~ . 0 'Re:ilJ~y i *.. *...* * . ' .' . ~' . .

1'11.irst~~~t** to. Surry Power St:ation *Techid.c.al- s'pec1!:1.c*1tionf!;. the ijii:rgini..t . I Electric ru:i.d* Power (;ompany)1ereby* eiubm:l:ts f.:he Jollcr.r.lzj.g. Lic~nse~ ]ti!t:mt- llepc..rt .

. *... for- Surry>Vnit Mo~ i. *, -;:* *.*. _:. *. *." .. * ': _::_* ... * *.: . . : ,: : . . . . .. . . . .* I

.**Report }\o .: .. ,~. *.

I LER~7$-~0l6/03L:~O****

.

• This repo.~t 'l:µls be~i 'i-evie~ed* **t,y' ~he -'Sta.t'ion

• N'uciear'. *safety and . Ope:i:at.:.mg

• Gom..mitte~ ~mi' will be' placed on the: agenC:h:t* fqr the next me.et.:ing .of. the Syst:a 1:facle~~. Safety a~d Operating* Committee.* ' .. . . . . . . . .. . .

• .~ *, , .

.* r};;~J!;~P;

\_fl' :11£.aas ,. ,/ , ,

.aud .

• _oduct:ion Operation~

.' .- ~ - .

cc*:.* .. Dr; Ernst \l~lgeuau, Dir~ctor '(:30* copi~s) ..

Of ii'?¢ 'of I11.spect'iort' and _Enforcement . .,: . , .

0

.~b: >wf11~~11 G.

HcDo~sid ,.. Dir~ct~-r (1 .cqpfes} i/

Of :i; ic~; of ' 1'1amtge-.nent:. tnf ornuit'.;(ou*'.: . . . .

-:;. and ~rcigram :eontroi .. ' .. . .

I

' ,' :, ~;... '

"\  :,?  ;'.

• Li

./. ,,

., *J*

. *'i- ... *:. ;_,*.,

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (7-77)

• LICENSEE EVENT REPORT e CONTROL BLOCK:

L---'--~----'-_.__..__....,6J \..'..) fi' (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~

8 I vlA Is IP Isl 9 LICENSEE CODE 1 101 14 15 o I o I - I o I o I o-1 o I a I - I O I O 101 4 LICENSE NUMBER . 25 26 11 11 11 11 101 LICENSE TYPE 30 I 10 57 CAT 58 CON'T

[ili]

7 8

~~~~~ ~©I oI s I o I o I o I 2 I s I o 101 60 61 DOCKET NUMBER 68 69

°I 6 I 2 I 2 I 7 I 8 7410175o I 7 I 2 I o I 7 is 80IG)

EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@ .

I With unit at refueling shutdown durjng cond11ct of Tvpe C testing, conditions indicated!

[QJI) that valve MOV-RH-100 was not opening. Valve was disassembled and found with the

[QJI] disc seated and not engaged to the stem. The condition is reportable in accordance

[Q]IJ I with T.S. 6.6.6.2.b.(3). Since this valve is normally shut, and not required to~.

~ / o p e r a t e in accident or post-accident operation, the health and safety of the public

[£II] I were not affected.

[II))

7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

[£TI] . I C I F I ~ w@ L£.J@ IV I Al Lj VI El x1@ W w@

7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCUR REN CE REPORT REVISION

(:;':;\ LEA/RO LVENT YEAR REPORT NO. CODE TYPE NO.

\.:..V REPORT NUMBER 17 I I 8 Io 11 I6 I I/ I I o 13 I LhJ l.=J l_Q_J 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM SUB. SUPPL! ER MANUFACTURER li.J@LLJ@

33 34 I.LJ@

35 u.J Io 10 I oI oI 36 37 40

!Ll@

41 W@ ~ .IA i 2 i O l O I 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

QI§] Inuring assembly after maintenance, the disc apparendy became disengaged from the stem I CIII] !during the manipulation of assembly. The valve was opened, corrected. and reassembJedJ ITEi8 7 9 80 FACILITY METHOD OF ~

STATUS  % POWER OTHER STATUS 1'1SCOVERY DISCOVERY DESCRIPTION ~

o:=EJ l.B.J@ l Ol Ol O l@I____N~/A_______ W@._l__,,T....v""p""e"'--"'C'--"'L""e""a'"'k___.T.,.e""s.,.t_ _-----------1 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT Q RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE @

[IE] w@) ILJ@)I N/A 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES ~

NUMBER r::;:;., TYPE~ DESCRIPTION~

~ IO l O I 0J0WL-------N=A,________________________,

8 9 11 12 13 80 PERSONNEL INJURIES Q NUMBER DESCRIPTION6

[iliJ I O l O l O l@'-------=N<--=-A;:_____________________;__________,

7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY '43' TYPE DESCRIPTION ~

[Q}J8 9~{§)...__ ______~N/~A=---------------------------'

10 so ISSU=~~~;;CRIPTION@ NRC USE ONLY "'

[iliJ LlU~'-------_;;,N""--/A::,.__ _ _ _ _ _ _ _ _ _ _ _ _ _ ____. I II II II II II I I ~

7 8 9 10 68 69 80 ;;;

NAME OF PREP AR ER __T;:..:..-=L...:.._B.a,**a __:U..,__.__

c_om_ _ _ _ _ _ _--'---- PHONE: (804) 357-3184

_J

Surry Power Station, Unit 1 Docket No: 50-280 Report No: 78-016/03L-0 Event Date: 6-22-78 Valve Improperly Assembled

1. Description of Event:

With the unit in refueling shutdown condition in the course of Type C Leak testing, it was found that 6-inch gate valve MOV-RH-100 (Residual Heat Removal discharge to Refueling Water Storage Tank) did not appear to be open-ing when actuated. Further checking showed that no water would pass the valve when the valve was opened manually. The valve was disassembled and was found with the stem disengaged from the disc and the disc fully seated.

2. Probable C~nsequences/Status of Redundant Systems:

During normal operation this valve is shut. It is opened only to provide a means of pumping the reactor cavity to RWST following refueling. The valve is not involved in any accident or post-accident operations. The fact that the valve was shut and could not be opened was a conservative condition, therefore, the health and safety of the general public were not affected.

3. Cause:

The valve had been previously disassembl~d during the current outage for maintenance. The valve was assembled by a qualified workman using an approved procedure. In the manipulation of reassembly the disc became disengaged from the stem.

4. Immediate Corrective Action:

The valve was opened and reassembled. The reassembly was verifed by QC.

Following reassembly the valve operated properly.

5. Subsequent Corrective Action:

None was required since the problem was corrected by the immediate action.

6. Action to be Taken to Prevent Recurrence:

None is anticipated. Investigation of the event indicated that the mechanic used due care in the assembly and was working according to an approved procedure.

7. Generic Implications None. This is an isolated event.