05000249/LER-1980-002-03, /03L-0:on 800122,while Performing LPCI Monthly surveillance,MO-3-1501-11B Valve Would Not Close. Reoccurrence on 800213.Investigation Revealed No Cause

/03L-0:on 800122,while Performing LPCI Monthly surveillance,MO-3-1501-11B Valve Would Not Close. Reoccurrence on 800213.Investigation Revealed No Cause

ML17192A519
Person / Time
Site:	Dresden
Issue date:	02/14/1980
From:	Zirwas K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17192A520	List: 05000249/LER-1980-002, Forwards LER 80-002/03L-0 05000249/LER-1980-002-03, /03L-0:on 800122,while Performing LPCI Monthly surveillance,MO-3-1501-11B Valve Would Not Close. Reoccurrence on 800213.Investigation Revealed No Cause
References
LER-80-002-03L-03, LER-80-2-3L-3, NUDOCS 8002280384
Download: ML17192A519 (2)

LER-1980-002, /03L-0:on 800122,while Performing LPCI Monthly surveillance,MO-3-1501-11B Valve Would Not Close. Reoccurrence on 800213.Investigation Revealed No Cause

Event date:
Report date:
2491980002R03 - NRC Website

text

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~* e Commonwe'9 Edison "Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS LTR 1180-122 February 13, 1980 James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report ll80-2/03L-0,. Docket 11050-249, is being submitted to your off ice in accordance with Drescl,en Nu~lear Power Station Technical Speci,fication 6.6.B.2(b), conqiti6ns leading to operation in a degraded mode permitted by a limiting cond.ition for operation or plant shutdown required by a limiting condition for operation.

BBS:lcg Enclosure teph nson Station Superintendent Dre~den Nuclear Power Station cc:

Director of Inspection & Enforcement Director of Management Information & Program Control File/NRG

• n n ?. 40~0 f\\:"" I Aoo~

s 1//

NRc*i=oRf;i366*-*

11-n1 *

~=-----t1:*s; NUCLEAR REGULATORY COMMISSION

9CENSEE EVENT REPORT

• 9

...__..__l._*_.__~__.l.___.l G)

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6 [il2J Ir IL In IR Is I 3 101 o I o I - I o I o I o I o ! o I-Io Io 10)14 I 1 I 1 I 1. Ii 101 I 10 7

8 9

LICENSEE CODE 14 15 LICENSE NUM8Ef'.I 25 26 LICENSE TYPE JO 57 CAT 58 CON'T [IT!]

~~~~~~. L!:J© I o I 5 I o I o I o I. 2 I 4 I 9 K?)I o I l I 2.I 2 I s *.1 o I© I o I 2 11-I 4 I s Io I G) 7

8.

. - *.*:so 61 DOCKET NUMBER.

68 69 EVENT DATE 74 75 REPORT DATE

. 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

inuring normal operation while performing LPCI monthly surveillance, M0-3-1501-llB

!]:ill !valve would not close.

(T.S.J.5.B.3) Thermal overload contacts were manually reset I*

[9J]J land the valve was successfully cycled 3 times~

On February 13, 1980, the valve again IillJ 1would not. close.

• There was no affect on the health and safety of public since valve

~

1could be manually operated, and the other containment cooling subsystem was operable.

~

!This is the first occurrence of this type.

. IT))]

8 9 80 illil 7

8 SYSTEM CODE IS IF I@

9 10 LEA/AO LVENT YEAR REPORT I 8 I 0 I NUMBER

. 21 22

CAUSE

CAUSE CODE SUBCOOE COMPONENT COOE L!.J@ w@ le IK IT IB IK. IR* 18 11 12 lJ 18 SEQUENTIAL OCCURRENCE REPORT NO.

CODE I I Io Io 12 I I /I I o I 3 I 2J 24 26 27 28 29 COMP.

SUB CO OE w@

19 REPORT TYPE LU 30 VALVE SUB CODE w@

20 31 PRIME COMP.

TAKEN ACTION ON PLANT.

METHOD HOURS SUBMIT.TEO FORM :;us.

SUPPLl.EA

• REVISION NO.

L9J 32 COMPONENT MANUFACTURER ACTION FUTURE EFFECT SHUTDOWN

@ ATTACHMENT NPRD-4 Ll@~@ ~@ ~@ 1°1°1° I I ~@ L:J(§ JJ J4 35 36 J 7 40 41 42

~ I GI 0 I 8 I 0 I@

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

4J 44 47

• [JJ]J I An investigation by Electrical Maintenance Dept. after the initial occurrence did not reveal any cause.

The investigation is continuing and the results will be reported in o::::IIJ a supplementary LER.

[ill]

1 a 9 80 FACILITY STATUS

% POWER

. OTHER STATUS [ill] ~@ I 0 I 6 I 8 l@)l.._ __

N_/A ___

8 9

10 12

• l'l ACTIVITY CONTENT

(.;;;\\

RELEASED OF RELEASE AMOUNT OF ACTIVITY~

Ci:ill LU @ W(§......

1 _NA ______

7 8

9 10 11 METHOD OF DISCOVERY DESCRIPTION @

DISCOVERY LUI Surveillance testing 44 45 46 80 LOCATION OF RELEASE @

NA 44 45 80 PERSONNEL EXPOSURES

. t.::;'\\

N.UMBER TYPE

DESCRIPTION

[JI2J I 0 I 0 I 0 l@LJ@~_N_A _________ -----------------'

a 9 11 12

• 13 80 PERSONNEL INJURIES r:;:-.

NUMBER DESCRIPTION~

[i}TI jO IO IO j@).__ ___

N_A _____ -------------------

1 a 9 11 12 LOSS OF OR CAMAGE TO FACILITY~

TYPE *

DESCRIPTION

i.:::::J CiJI) ~@

NA 80 7

8 9

10 30 PUBLICITY Q.

NRC USF. ONLY ISSUEOQ DESCRIPTION~

ITITJ LJLl6 NA 1111111111111~

8 9

10 K. R. Zirwas NAME OF PREPARER---------------------

• s8 69 SO*;

0

?HONE: __

X_-_5_2_9 ___

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