05000338/LER-1980-015-03, /03L-0:on 800116,during Reactor Physics Testing Following Refueling Outage,Reactor Was Critical W/Rcs Tavg Under 541 F.Caused by Cooldown While Attempting to Maintain RCS Temp During Testing.Heat Release Valve Closed

/03L-0:on 800116,during Reactor Physics Testing Following Refueling Outage,Reactor Was Critical W/Rcs Tavg Under 541 F.Caused by Cooldown While Attempting to Maintain RCS Temp During Testing.Heat Release Valve Closed

ML19260D969
Person / Time
Site:	North Anna
Issue date:	02/11/1980
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19260D965	List: 05000338/LER-1980-015, Forwards LER 80-015/03L-0 05000338/LER-1980-015-03, /03L-0:on 800116,during Reactor Physics Testing Following Refueling Outage,Reactor Was Critical W/Rcs Tavg Under 541 F.Caused by Cooldown While Attempting to Maintain RCS Temp During Testing.Heat Release Valve Closed
References
LER-80-015-03L, LER-80-15-3L, NUDOCS 8002120681
Download: ML19260D969 (1)

LER-1980-015, /03L-0:on 800116,during Reactor Physics Testing Following Refueling Outage,Reactor Was Critical W/Rcs Tavg Under 541 F.Caused by Cooldown While Attempting to Maintain RCS Temp During Testing.Heat Release Valve Closed

Event date:
Report date:
3381980015R03 - NRC Website

text

...

Rd 70.4Pt 366 U. S. NUCLEAR REGLLATORY CCMMISSION 7 77)

LICENSEE EVENT REPORT CONTROL 8LCCK; l I

I l

l l

l (PLEASE PRINT OR TYPE ALL RECUlRED INFORMATIOND i

i V I A I N l A I 5 l 1 l@l 010 l-10 101010 10 (- lo 10 I@l4 11 11 11 11 l@l I

u ar 24 @

oti 7

4 9 uctsset cCCE i4

s ucessa soses a

2e ucEssa rvee a CON T

"G"[ I !@l 0 l 5 l 0 l 0 l0 l 3 l 3 l 8Gl Of II 1l 6l 81p@lOi21Il1181Ol@

01i 3

,c F

6 53 61 CCCKET NyugER 64 (d

EVENT CATE 74

'S REPORT CATE 83 EVENT OESC6tPTION AND PRCBAOLE CONSEQUENCES h o 12. l During reactor physics testing following the refueling outage. the reactor as ertticall a,3 ; lwith RCS TAVG less than 541*F.

This event is contrary to T.S. 3.1.1. 5.

The RCS TAVG l 0,4 was restored to greater than 541*F within the 15 minute time allowance of the action I

oi3 istatement.

The. health and safety of the general public were affected.

This,. ant is !

l reportable as per T.S. 6.9.1.9.b.

I 3,6 ai7 l l

1 a 44 so 7

SYSTEM

CAUSE

CAUSE COMP VA LV E CCCE CCCE SU8CCCE CCMPCNENT CODE SusCCOE SUSCCCE ofC l Rl Cl@ l 4@]@l Zl Zl Zl Zl Zl Zl Q l Zl @ [ Zl @

7 e

3 10 11 12 13 is 19 20 SE Ciw"E N TI A L OCCURRENCE REPORy R E VI$1C N ggg EVENTYEAR REPCRT NO.

CCCE TYPE NO.

@,ang.Ro Ial0j j_j l0l1l5l l-l 10 l3 l [1, l

[_j g

u

,,,, 21 22 23 24 26 27 28 23 30 31 32 T

N AC C PLA T vtT MCUR$ 22 SS I POR S.

$UPPLI E R MANL 8A RER X I@l Z i@

l Z i@

lZl@

1010101 I

lY l@

I N lg l Zl@

lZ l9 l9 l9 [Q 3J J4 35 06 31 40 41 42 4J 4A 47 CAUSE DESCRIPTtCN AND CORRECTIVE ACTIONS @

lThe cause of the reactor being critical with an RCS TAVC less than 541*? was a cooldownl i

3

lwhile attempting to maintain RCS temperature during reactor ohvsics testine.

Correc tM

1 4i

action was to close the decay heat release valve and the main steam trip valve byeasses!

,,3 jand to cease feeding the steam generators until the te rperature was restored.

I l

I i

4 7

3 9 80 5

% PCWER CTNER STATUS C5O RV CISCOVERY oESCRIPTION l 3lg l 0 l 0 l 0 l@l Physics Testing l l Al@l Operator Observation l

5 A

VITY CC TENT RELEASED Op aELIASE AMOUNT OF ACTIVITY LOCAftCN OF RELEASE NA i

l NA l

i ia II

@ E,J@l d 3 10 11 a4 45 30 PER$CNNEL E1*CSuaES Nyvsgo Tvet CESCRIPTTCN 101010 l@lZ l@l NA l

i-8ERSONNEL INJ RIES NU C E SCRIPTICN l 0 10" gem l0 l@l NT l

t i4 3 )

11

'2 30 Loss Op CR cavaGE "o FAC:Lify Tveg O E SCpipTION NA l

IIj@l

' la ust2Tv 80 02120 6Sl NRc usE cNLv a

itg.ga C E 3C.h *TICN j

2 Q lN I NA l

[!!Illl I!!Ii1 y

3 3 13 68 69 30

• O unass es sosanoso..

n a. y a. i..

pH t1N F-