ML17252B533: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:----... ,, l i 1 ' e Commonwealt.son  
{{#Wiki_filter:l    i
,': Dresden Nuclear Po . tation R.R. #1 Morris, Illinois.
* 1
60450
----                                                         '
* J Telephone 815/942-2920 1-.. .... 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 * ()s6 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#'\* DJS:lg Enclosure
()s6 e
,...._ .. ;:: LJj}_uif-c D. J. Scott
  ...                   Commonwealt.son                 ,':
* Station Superintendent Dresden Nuclear Power Station cc: Director of Inspection  
      ,,                Dresden Nuclear Po R.R. #1
& Enforcement Director of Management Information  
                                                . tation
& Program Control U.S. NRC, Document Mgt. Branch File/NRC NRC FORM 366 17-771 * ** S. NUCLEAR REGULATORY COMMISSION .ICENSEE EVENT REPORT e ltONTROL BLOCK: l I I I I 10 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI  
                                                        *1-.. J Morris, Illinois. 60450
,;; .. CJ 1 6 . ; l2:TIJ I I I LID IR I s I 2 101 0 I 0 I -I 0 I 0 I 0 I 0 I 0 I -I 0 I 01014 11 11 11 11 101 I I© .
-~b                    Telephone 815/942-2920
* 8 9 L.ICENSEE CO.OE ... 14 15* L.ICENSE NUMBER
                ....                                             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.
* 25 2B L.ICENSE TYPE . JO 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 PROBABLE CONSEQUENCES  
Ii#'\*
@ . * [[ill !During Unit 2 refueling outage LPCI Test Spray yalye failed to shut electrically.
LJj}_uif-c
(]: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.
                            ,...._ ..                           D. J. Scott   *
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 ITIIr 7 8 SYSTEM CODE Is IF I@ 9 . 10 CAUSE CAUSE COMP. VAL.VE CODE SUBCOOE COMPONENT CODE SUBCOOE SUBCOOE UJ@ w@ Iv IA IL IV 10 IP I@ w@ 11 .12 13 18 19 20 SEQUENTIAL.
                            ;::
OCCURRENCE REPORT L.E A/RO. CV ENT VEAR REPORT NO. COO& TYPE REPORT I 8 I 1 I I I I 0
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
* I 0 I 2 I I /"I I 0 I 3 I L1J I I NUMBER. 21
 
* 22 23 24 26 27 28 29 30 31 ACTION FUTURE EFFECT . SHUTDOWN I::;'.:;\
NRC FORM 366                                                                                                                                     * ** u~  S. NUCLEAR REGULATORY COMMISSION 17-771
ATTACHMENT NPRQo4 PRIME C.OMP. REVISION NO. L.QJ 32 COMPONENT MANUFACTURER 80 TAKEN ACTION ON PL.ANT METHOD HOURS SUBMITTED FORM SUB. SUPPL.I ER W@LLJ@ lz_J@ LLI lo lo lo lo I W@ W@ W@ 33 34 35 38 37 40 41 42 43 IL 12* 10 lo I CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @ 44 47 DJ!J !The cause of failure was stuck auxiliary contacts..
                                                                                .ICENSEE EVENT REPORT                                                           e
The auxiliary contacts.
        ,;;..CJ ltONTROL BLOCK:           l 1
were ITTIJ 1replaced and valve operated prope'r.if>:  
I I I I                       10 6
.. !'fotor Contactor breaker cornpartment.s w.ill II]]] !continue to be checked* during outages; per tab  
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI
-------...---_.
                                                                                                                                                                                                    .
Cilil 7 8 9 FACIL.ITY t3i)\ METHOO OF . . STATUS % POWER OTHER STATUS i..::::J*
; l2:TIJ
OISCOVERV OISCOVERV OESCRIPTION [ill] l!!J@ I 0 I 0 I 0 l@I .... * --=N...,/A....._
  .*          8 I I I LID IR I s I 2 9        L.ICENSEE CO.OE 101 0
__ _.I LA..J@I Operator.
                                                    . . .14        15*
Obseryation
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
.. 7 8 9 10 12* 1'.3 44 45 . 46 . . . ACTIVITY CONTENT t:::;\ REL.EASED OF REL.EASE AMOUNT OF ACTIVITY [ill] LI@I . N/A 7 8 9 10 11 80 80 44 45 L.OCATION OF REL.EA$E @ N/A 80 PERSONNEL.
* 25         2B           L.ICENSE TYPE . JO I I© 57 CAT 58 Wn
EXPOSURES r.:;;.., NUMBER DESCRIPTION
[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] I ol ol 7 8 9 11 12 13 PERSONNEL.
'   7         8                       60           61                 DOCKET NUMBER                     6B     69         EVENT DATE                       74         75         REPORT DATE           80 EVENT DESCRIPTION               A~.o PROBABLE CONSEQUENCES @                                       . *
INJURIES I::\ NUMBER DESCRIPTION6
[[ill         !During Unit 2 refueling outage LPCI Test Spray yalye failed to shut electrically.
*rr:I:TI IO IO IO 7 8 9 11 12 . L.OSS OF OR DAMAGE TO FACIL.ITY
(]: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
'4J' TYPE DESCRIPTION i,;:;;:; 9 l.Ll@ . . . . 80 80 N/A. 7 8 9 10 . 80 . NRC USE ONL y "' IIIIJ
[[TI] lfor this valve                                                                                                                                                                                               I.
.........
[ill]
I I I I I I I I I I I I 7 8 9 . 10 68 69 NAMEOFPREPARER--.K_._z_i_rw_a_s
[[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
PHONE: 815-942-2 920 Ext. 422 0 Q. "
                  ~      L.E A/RO. CV ENT VEAR                                           REPORT NO.                                   COO&                         TYPE                               NO.
e C'a rbriioiiweatth Edison. -* DVR *l* .. . ---. ....... . ........ *********  
                  ~      REPORT NUMBER.
-. -..... *-..... . DEVIATION REPORT .STA UNIT YEAR NO. D-12 81-3 OCCURRED 1-5-81 OF LPCI TEST SPRAY VALVE 2-1501-20B.
I 21 8 I 1I
DATE
* 22 I
* 1500 c TIME SYSTEM AFFECTED 1500 PLANT CONDITIONS LPC! . MODE SffiJTPOWN PWR MWT * . 0 LOAD MWf.. 0 DESCRIPTION_
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@
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 EQUIPMENT rD YES OR NO. FAILURE ONO WR NO. Dl0923 . J. Fideler RESPONSIBLE SUPERVISOR
33            34 lz_J@
* TESTING D IXJ YES NO 1/5/81 DATE c . PART 2 I OPERATING ENGINEERS COMMENTS --FAILURE OCCURED WHILE REACTOR WAS IN COLD SHUTDOWN.
35 LLI 38 lo lo lo lo 37                          40 I W@ 41 W@
PRIMARY _CONTAINMENT WAS. NOT . REQUIRED * . I SAFETY-TYPE OF DEVIATION EVENT OF POTENTIAL TECH SPEC NON-REPORTABLE ANNUAL RELATED REPORTABLE -PUBLIC INTEREST VIOLATION OCCURRENCE REPORTING WR ISSUED D 14 DAY D 10CFR21 YES {!]* YES . [!] 30 DAY D D D NO D NO D . REPORTABLE OCCURRENCE ACTION ITEM NO. PROMPT ON-SITE NOTIFICATION NUMBER l/7l81 -R. H. RAGAN . Tl TLE DATE TIME . :lGCK-80-02/031.-0 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 c REGION I I I & DOL CATE TIME Tl TLE DATE TIME RESPONSIBLE COMPANY OFFICER INFORMED OF IOCFR21 CONDITIONS AND THEIR REPORT TO NRC Tl TLE DATE TIME c REVIEW AND COMPLETED ACCEPTANCE BY STATION REVIEW AS REQUIRED D'ATE RESOLUTION APPROVED AND AUTHORIZED FOR DISTRIBUTION JOHN WUJCIGA .. OPERATING
42 W@
* l/.6/8L. DATE}}
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
  *rr:I:TI 7        8 IO IO IO 11l@).___~~---~~~-----~~~~_..:.;.;N/~A;...._~--.~~-------~~----~~
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}}

Revision as of 20:05, 29 October 2019

LER 81-020/03L-0 for Dresden, Unit 2 Re During Refueling Outage LPCI Test Spray Valve Failed to Shut Electrically, One Set of Thermal Contacts Would Not Reset
ML17252B533
Person / Time
Site: Dresden Constellation icon.png
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

{{#Wiki_filter: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] ] !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

 *rr:I:TI 7         8 IO IO IO 11l@).___~~---~~~-----~~~~_..:.;.;N/~A;...._~--.~~-------~~----~~

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}}