ML17192A519: Difference between revisions

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                               *.*:so            61 5I oI o            I o I .2 I 4 I DOCKET NUMBER .
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  ~ !This is the first occurrence of this type .
  ~ !This is the first occurrence of this type .
.IT]]]
.IT))]
   '      8 9                                                                                                                                                                        80 SYSTEM                  CAUSE              CAUSE                                                    COMP.          VALVE CODE                  CODE            SUBCOOE                  COMPONENT COOE                  SUB CO OE      SUB CODE illil                              IS      IF I@ L!.J@ w@ le IK IT IB IK. IR* 18                                                          w@ w@
   '      8 9                                                                                                                                                                        80 SYSTEM                  CAUSE              CAUSE                                                    COMP.          VALVE CODE                  CODE            SUBCOOE                  COMPONENT COOE                  SUB CO OE      SUB CODE illil                              IS      IF I@ L!.J@ w@ le IK IT IB IK. IR* 18                                                          w@ w@
7      8                        9            10              11                12            lJ                            18          19            20 SEQUENTIAL                      OCCURRENCE            REPORT                    REVISION LEA/AO LVENT YEAR                                              REPORT NO.                          CODE                TYPE                        NO.
7      8                        9            10              11                12            lJ                            18          19            20 SEQUENTIAL                      OCCURRENCE            REPORT                    REVISION LEA/AO LVENT YEAR                                              REPORT NO.                          CODE                TYPE                        NO.
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K. R. Zirwas NAME OF P R E P A R E R - - - - - - - - - - - - - - - - - - - - -                                          ?HONE: _ _      X_-_5_2_9_ _ _~..,-~~-
K. R. Zirwas NAME OF P R E P A R E R - - - - - - - - - - - - - - - - - - - - -                                          ?HONE: _ _      X_-_5_2_9_ _ _~..,-~~-
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                                                                                                                                                                                           "}}
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Latest revision as of 17:00, 18 March 2020

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


Text

-.,..~l~~--*11"_~

e

. '\...; Commonwe'9 Edison "Dresden Nuclear Power Station

~* R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 February 13, 1980 BBS LTR 1180-122 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.

teph nson Station Superintendent Dre~den Nuclear Power Station BBS:lcg Enclosure 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*-* ~=-----t1:*s; NUCLEAR REGULATORY COMMISSION 11-n1 *

9CENSEE EVENT REPORT *9

...__..__l._*_.__~__.l.___.l G) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6

[il2J Ir IL In IR Is I3 101 o Io I- Io IoIo 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!]

7 8.

~~~~~~.

L!:J© I o I

  • .*:so 61 5I oI o I o I .2 I 4 I DOCKET NUMBER .

9 68 K?)I 69 o I l I 2 .I 2 EVENT DATE I s *.1 o I© I o 74 75 I 2 11- I 4 I s Io IG)

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 1 would not. close.

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

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

1

~ !This is the first occurrence of this type .

.IT))]

' 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCOOE COMPONENT COOE SUB CO OE SUB CODE illil IS IF I@ L!.J@ w@ le IK IT IB IK. IR* 18 w@ w@

7 8 9 10 11 12 lJ 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LEA/AO LVENT YEAR REPORT NO. CODE TYPE NO.

@ REPORT NUMBER .

I8 I0 I I I Io Io 12 I I /I I oI 3 I LU L9J ACTION TAKEN FUTURE ACTION 21 22 EFFECT ON PLANT.

2J SHUTDOWN METHOD 24 26 HOURS

@27 28 ATTACHMENT SUBMIT.TEO 29 NPRD-4 FORM :;us.

30 PRIME COMP.

31 SUPPLl.EA

  • 32 COMPONENT MANUFACTURER Ll@~@

JJ J4

~@

35

~@

36 1°1°1° I 40I 41~@

J7 L:J(§ 42

~ I GI 0 I 8 I 0 I@

4J 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

  • [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 METHOD OF STATUS  % POWER . OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION @

[ill] ~@ I 0 I 6 I 8 l@)l..___N_/A_ _ ___. LUI Surveillance testing 8 9 10 . 12

  • l'l 44 45 46 80 ACTIVITY CONTENT (.;;;\

RELEASED OF RELEASE AMOUNT OF ACTIVITY~ LOCATION OF RELEASE @

Ci:ill LU @ W(§ 1. . . _NA_ _ _ _ _ _____ NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES . t.::;'\

N.UMBER TYPE DESCRIPTION

[JI2J I 0 I 0 I0 l@LJ@~_N_A_ _ _ _ _ _ _ _ _- - - - - - - - - - - - - - - - - '

a 9 11 12

  • 13 80 PERSONNEL INJURIES r:;:-.

NUMBER DESCRIPTION~

[i}TIa 9jO IO IO 11j@).__

1 12

_ _ _N_A_ _ _ _ _- - - - - - - - - - - - - - - - - - -

80 LOSS OF OR CAMAGE TO FACILITY~

TYPE

  • DESCRIPTION i.:::::J CiJI) ~@ NA 7 8 9 . 10 30 PUBLICITY Q. NRC USF. ONLY ISSUEOQ DESCRIPTION~ <>*

ITITJ LJLl6 8 9 10 NA

  • s8 1111111111111~

69 SO*;

K. R. Zirwas NAME OF P R E P A R E R - - - - - - - - - - - - - - - - - - - - - ?HONE: _ _ X_-_5_2_9_ _ _~..,-~~-

0

"