ML17252B533: Difference between revisions
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=Text= | =Text= | ||
{{#Wiki_filter:l i | {{#Wiki_filter:l i 1 | ||
()s6 e | ()s6 e | ||
... Commonwealt.son ,': | ... Commonwealt.son ,': | ||
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Ii#'\* | Ii#'\* | ||
LJj}_uif-c | LJj}_uif-c | ||
,...._ .. D. J. Scott | ,...._ .. D. J. Scott | ||
* Station Superintendent Dresden Nuclear Power Station DJS:lg Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control U.S. NRC, Document Mgt. Branch File/NRC | |||
Station Superintendent Dresden Nuclear Power Station DJS:lg Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control U.S. NRC, Document Mgt. Branch File/NRC | |||
NRC FORM 366 * ** u~ S. NUCLEAR REGULATORY COMMISSION 17-771 | NRC FORM 366 * ** u~ S. NUCLEAR REGULATORY COMMISSION 17-771 | ||
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I I I I 10 6 | I I I I 10 6 | ||
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI | (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI | ||
; l2:TIJ | ; l2:TIJ | ||
.* 8 I I I LID IR I s I 2 9 L.ICENSEE CO.OE 101 0 | .* 8 I I I LID IR I s I 2 9 L.ICENSEE CO.OE 101 0 | ||
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[ill] :~~~~ W©I o Is I 0-1 *o Io I 2 I 3 I 1 l(?)I ol ii ol sl al 11@!0 1*1I2 I 9 I a I 1 I@ | [ill] :~~~~ W©I o Is I 0-1 *o Io I 2 I 3 I 1 l(?)I ol ii ol sl al 11@!0 1*1I2 I 9 I a I 1 I@ | ||
' 7 8 60 61 DOCKET NUMBER 6B 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION A~.o PROBABLE CONSEQUENCES @ . * | ' 7 8 60 61 DOCKET NUMBER 6B 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION A~.o PROBABLE CONSEQUENCES @ . * | ||
((ill !During Unit 2 refueling outage LPCI Test Spray yalye failed to shut electrically. | |||
(]:I!] !One set of thermal. contacts would not reset. The safety significance was minimal C2:TIJ I since the valve could be manually shut and the reactor was in cold shutdown. There I l:[TIJ !was no effect on public health or safety. This is the first occurrance of this type | (]:I!] !One set of thermal. contacts would not reset. The safety significance was minimal C2:TIJ I since the valve could be manually shut and the reactor was in cold shutdown. There I l:[TIJ !was no effect on public health or safety. This is the first occurrance of this type | ||
((TI] lfor this valve I. | |||
[ill] | [ill] | ||
((IlJ 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VAL.VE CODE CODE SUBCOOE COMPONENT CODE SUBCOOE SUBCOOE ITIIr Is IF I@ UJ@ w@ Iv IA IL IV 10 IP I@ ~ w@ | |||
7 8 9 . 10 11 .12 13 18 19 20 SEQUENTIAL. OCCURRENCE REPORT REVISION | 7 8 9 . 10 11 .12 13 18 19 20 SEQUENTIAL. OCCURRENCE REPORT REVISION | ||
~ L.E A/RO. CV ENT VEAR REPORT NO. COO& TYPE NO. | ~ L.E A/RO. CV ENT VEAR REPORT NO. COO& TYPE NO. | ||
Line 63: | Line 59: | ||
43 IL 12* 10 lo 44 47 I | 43 IL 12* 10 lo 44 47 I | ||
CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @ | CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @ | ||
DJ!J !The cause of failure was stuck auxiliary contacts.. The auxiliary contacts. were ITTIJ 1replaced and valve operated prope'r.if>: .. !'fotor Contactor breaker cornpartment.s w.ill II | DJ!J !The cause of failure was stuck auxiliary contacts.. The auxiliary contacts. were ITTIJ 1replaced and valve operated prope'r.if>: .. !'fotor Contactor breaker cornpartment.s w.ill II))] !continue to be checked* during outages; per e~ tab lis~e:.;d;;...ip~r:.:o:;.;c::.;e::.;d::.;u::.r:..e=s.:..- - - - - - - . . . - - - _ . | ||
Cilil 7 8 9 80 FACIL.ITY t3i)\ METHOO OF . ~ | Cilil 7 8 9 80 FACIL.ITY t3i)\ METHOO OF . ~ | ||
. STATUS % POWER OTHER STATUS i..::::J* OISCOVERV OISCOVERV OESCRIPTION ~ | . STATUS % POWER OTHER STATUS i..::::J* OISCOVERV OISCOVERV OESCRIPTION ~ | ||
Line 82: | Line 78: | ||
7 8 9 . 10 68 I 69 I I I I I I I I I I I I~ | 7 8 9 . 10 68 I 69 I I I I I I I I I I I I~ | ||
0 NAMEOFPREPARER--.K_._z_i_rw_a_s_ _ _ _ _ _ _~~--- PHONE: 815-942-2 920 Ext. 422 Q. | 0 NAMEOFPREPARER--.K_._z_i_rw_a_s_ _ _ _ _ _ _~~--- PHONE: 815-942-2 920 Ext. 422 Q. | ||
e | e | ||
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*l* | *l* | ||
~ | ~ | ||
C'a rbriioiiweatth | C'a rbriioiiweatth Edison. | ||
Edison. | |||
* DVR DEVIATION REPORT | * DVR DEVIATION REPORT | ||
.STA D UNIT YEAR 2 - 81- 3 NO. | .STA D UNIT YEAR 2 - 81- 3 NO. | ||
Line 104: | Line 97: | ||
. REPORTABLE OCCURRENCE ACTION ITEM NO. PROMPT ON-SITE NOTIFICATION NUMBER | . REPORTABLE OCCURRENCE ACTION ITEM NO. PROMPT ON-SITE NOTIFICATION NUMBER | ||
- R. H. RAGAN l/7l81 .. | - R. H. RAGAN l/7l81 .. | ||
:lGCK- 80-02/031.-0 Tl TLE DATE TIME TITLE DATE TIME | :lGCK- 80-02/031.-0 Tl TLE DATE TIME TITLE DATE TIME 24-HOUR NRC NOTIFICATION PROMPT OFF-SiTE NOTIFICATION DTPH F. A. PALMER 1/7/81 4:54 . | ||
REGION I I I DATE TIME Tl TLE DATE TIME DTCi'.1 REGION I I I & DOL CATE TIME Tl TLE DATE TIME RESPONSIBLE COMPANY OFFICER INFORMED OF IOCFR21 TIME CONDITIONS AND THEIR REPORT TO NRC Tl TLE DATE REVIEW AND COMPLETED JOHN WUJCIGA .. l/.6/8L. | |||
24-HOUR NRC NOTIFICATION PROMPT OFF-SiTE NOTIFICATION DTPH F. A. PALMER 1/7/81 4:54 . | |||
REGION I I I DATE TIME Tl TLE DATE TIME DTCi'.1 REGION I I I & DOL CATE TIME Tl TLE DATE TIME | |||
RESPONSIBLE COMPANY OFFICER INFORMED OF IOCFR21 TIME CONDITIONS AND THEIR REPORT TO NRC Tl TLE DATE REVIEW AND COMPLETED JOHN WUJCIGA .. l/.6/8L. | |||
OPERATING ENGlN~ER | OPERATING ENGlN~ER | ||
* DATE ACCEPTANCE BY STATION REVIEW AS REQUIRED D'ATE RESOLUTION APPROVED AND AUTHORIZED FOR DISTRIBUTION}} | * DATE ACCEPTANCE BY STATION REVIEW AS REQUIRED D'ATE RESOLUTION APPROVED AND AUTHORIZED FOR DISTRIBUTION}} |
Latest revision as of 13:34, 18 March 2020
ML17252B533 | |
Person / Time | |
---|---|
Site: | Dresden ![]() |
Issue date: | 02/02/1981 |
From: | Scott D Commonwealth Edison Co |
To: | James Keppler NRC/RGN-III |
References | |
DJS LTR 81-107 LER 81-020/03L-0 | |
Download: ML17252B533 (3) | |
Text
l i 1
()s6 e
... Commonwealt.son ,':
,, Dresden Nuclear Po R.R. #1
. tation
- 1-.. J Morris, Illinois. 60450
-~b Telephone 815/942-2920
.... February 2, 1981 DJS LTR 1/81-107 James G. Keppler, Regional Director Directorate of Regulatory Operations Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, I.L 60137 Reportable Occurrence Report l/81-02/03L-0, Docket 11050-237 is being submitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.2.(b), .conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required .by a limiting condition for operation.
~*
Ii#'\*
LJj}_uif-c
,...._ .. D. J. Scott
- Station Superintendent Dresden Nuclear Power Station DJS:lg Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control U.S. NRC, Document Mgt. Branch File/NRC
NRC FORM 366 * ** u~ S. NUCLEAR REGULATORY COMMISSION 17-771
.ICENSEE EVENT REPORT e
,;;..CJ ltONTROL BLOCK: l 1
I I I I 10 6
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI
- l2
- TIJ
.* 8 I I I LID IR I s I 2 9 L.ICENSEE CO.OE 101 0
. . .14 15*
I 0 I - I 0 I 0 I 0 I 0 I 0 I - I 0 I 01014 11 11 11 11 101 L.ICENSE NUMBER
- 25 2B L.ICENSE TYPE . JO I I© 57 CAT 58 Wn
[ill] :~~~~ W©I o Is I 0-1 *o Io I 2 I 3 I 1 l(?)I ol ii ol sl al 11@!0 1*1I2 I 9 I a I 1 I@
' 7 8 60 61 DOCKET NUMBER 6B 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION A~.o PROBABLE CONSEQUENCES @ . *
((ill !During Unit 2 refueling outage LPCI Test Spray yalye failed to shut electrically.
(]:I!] !One set of thermal. contacts would not reset. The safety significance was minimal C2:TIJ I since the valve could be manually shut and the reactor was in cold shutdown. There I l:[TIJ !was no effect on public health or safety. This is the first occurrance of this type
((TI] lfor this valve I.
[ill]
((IlJ 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VAL.VE CODE CODE SUBCOOE COMPONENT CODE SUBCOOE SUBCOOE ITIIr Is IF I@ UJ@ w@ Iv IA IL IV 10 IP I@ ~ w@
7 8 9 . 10 11 .12 13 18 19 20 SEQUENTIAL. OCCURRENCE REPORT REVISION
~ L.E A/RO. CV ENT VEAR REPORT NO. COO& TYPE NO.
~ REPORT NUMBER.
I 21 8 I 1I
- 22 I
23 I I 0 *I0 I 2 I 24 26 I /"I 27 I0 I 3 I 28 29 L1J 30 I I 31 L.QJ 32 ACTION FUTURE EFFECT . SHUTDOWN I::;'.:;\ ATTACHMENT NPRQo4 PRIME C.OMP. COMPONENT TAKEN ACTION ON PL.ANT METHOD HOURS ~ SUBMITTED FORM SUB. SUPPL.I ER MANUFACTURER W@LLJ@
33 34 lz_J@
35 LLI 38 lo lo lo lo 37 40 I W@ 41 W@
42 W@
43 IL 12* 10 lo 44 47 I
CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @
DJ!J !The cause of failure was stuck auxiliary contacts.. The auxiliary contacts. were ITTIJ 1replaced and valve operated prope'r.if>: .. !'fotor Contactor breaker cornpartment.s w.ill II))] !continue to be checked* during outages; per e~ tab lis~e:.;d;;...ip~r:.:o:;.;c::.;e::.;d::.;u::.r:..e=s.:..- - - - - - - . . . - - - _ .
Cilil 7 8 9 80 FACIL.ITY t3i)\ METHOO OF . ~
. STATUS % POWER OTHER STATUS i..::::J* OISCOVERV OISCOVERV OESCRIPTION ~
[ill] l!!J@ I 0 I 0 I 0 l@I....*--=N...,/A.....__ __.I LA..J@I Operator. Obseryation ..
7 8 9 10 12* 1'.3 44 45 . 46 . . . 80 ACTIVITY CONTENT t:::;\
REL.EASED OF REL.EASE AMOUNT OF ACTIVITY ~ L.OCATION OF REL.EA$E @
[ill] ~@ LI@I . N/A N/A 7 8 9 10 11 44 45 80 PERSONNEL. EXPOSURES r.:;;..,
NUMBER ~TYPE~ DESCRIPTION
[ill]
7 8 9 I ol ol ok~W~~--------------N~A~---------------...J 11 12 13 80 PERSONNEL. INJURIES I::\
NUMBER DESCRIPTION6
9 12 . 80 L.OSS OF OR DAMAGE TO FACIL.ITY TYPE DESCRIPTION
'4J' i,;:;;:;
9 l.Ll@ .. . . N/A.
7 8 9 10 . 80 ISSU=~~~[s"CRIPTION@ . NRC USE ONL y "'
IIIIJ l!Ll~--~------------~. . . . .u-~--------,__.
7 8 9 . 10 68 I 69 I I I I I I I I I I I I~
0 NAMEOFPREPARER--.K_._z_i_rw_a_s_ _ _ _ _ _ _~~--- PHONE: 815-942-2 920 Ext. 422 Q.
e
~ . . . ........ ********* - . - ..... *- ..... .
- l*
~
C'a rbriioiiweatth Edison.
- DVR DEVIATION REPORT
.STA D UNIT YEAR 2 - 81- 3 NO.
OCCURRED 1-5-81 1500 c OF LPCI TEST SPRAY VALVE 2-1501-20B. DATE
- TIME SYSTEM AFFECTED 1500 PLANT CONDITIONS TESTING LPC! D IXJ
. MODE SffiJTPOWN PWR MWT * . 0 LOAD MWf.. 0 YES NO DESCRIPTION_ OF EVENT VALVE 2-1501-20B WOULD NQT CLOSE ELECTRICALLY, ONE SET .OF AUXILIARY CONTACTS WOULD NOT DESCRIPTION OF CAUSE IINJ{NQWN AT THIS TIME.
OTHER APPLICABLE INFORMATION REACTOR IN COLD SHUTDOWN, LOW PRESSURE EC_CS NOT ~QlJ.IRED EQUIPMENT rD YES OR NO. WR NO.
. J. Fideler 1/5/81 FAILURE ONO Dl0923 c RESPONSIBLE SUPERVISOR
- DATE
. PART 2 I OPERATING ENGINEERS COMMENTS FAILURE OCCURED WHILE REACTOR WAS IN COLD SHUTDOWN. PRIMARY _CONTAINMENT WAS. NOT . REQUIRED *
. I SAFETY-TYPE OF DEVIATION EVENT OF POTENTIAL TECH SPEC NON-REPORTABLE ANNUAL RELATED REPORTABLE OCCUR~ENCE -PUBLIC INTEREST VIOLATION OCCURRENCE REPORTING WR ISSUED D 14 DAY D 10CFR21 YES {!]* YES ~
. [!] 30 DAY ~~6~'~2~~10N D D D NO D NO D
. REPORTABLE OCCURRENCE ACTION ITEM NO. PROMPT ON-SITE NOTIFICATION NUMBER
- R. H. RAGAN l/7l81 ..
- lGCK- 80-02/031.-0 Tl TLE DATE TIME TITLE DATE TIME 24-HOUR NRC NOTIFICATION PROMPT OFF-SiTE NOTIFICATION DTPH F. A. PALMER 1/7/81 4:54 .
REGION I I I DATE TIME Tl TLE DATE TIME DTCi'.1 REGION I I I & DOL CATE TIME Tl TLE DATE TIME RESPONSIBLE COMPANY OFFICER INFORMED OF IOCFR21 TIME CONDITIONS AND THEIR REPORT TO NRC Tl TLE DATE REVIEW AND COMPLETED JOHN WUJCIGA .. l/.6/8L.
OPERATING ENGlN~ER
- DATE ACCEPTANCE BY STATION REVIEW AS REQUIRED D'ATE RESOLUTION APPROVED AND AUTHORIZED FOR DISTRIBUTION