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| issue date = 06/05/1980
| issue date = 06/05/1980
| title = LER 80-017/03L-0 for Dresden, Unit 2 Re Double Valve Indication Was Observed on the HPCI Inboard Isolation Valve. Upon Trying to Cycle the Valve, the Valve Failed to Close
| title = LER 80-017/03L-0 for Dresden, Unit 2 Re Double Valve Indication Was Observed on the HPCI Inboard Isolation Valve. Upon Trying to Cycle the Valve, the Valve Failed to Close
| author name = Stephenson B B
| author name = Stephenson B
| author affiliation = Commonwealth Edison Co
| author affiliation = Commonwealth Edison Co
| addressee name = Keppler J G
| addressee name = Keppler J
| addressee affiliation = NRC/RGN-III
| addressee affiliation = NRC/RGN-III
| docket = 05000237
| docket = 05000237
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:e Commonwec9 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. /180-476 June 5, 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 /180-17/031-0, Docket /1050-237, is being submitted to your office in accordance with Dresden Nuclear Power Station Technical Specific*ation 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. BBS/nh Enclosure B. B. Station Superintendent Dresden Nuclear Power Station cc/ Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC LICENSEE EVENT REPORT I
{{#Wiki_filter:***
* I 10 (PLEASE PRIN.T ORTYPAIL REQUIRED 1----.1....,_..1-__.....__._...._;;;._-'s\..!J .# ., CONTROL BLOCK: I I I L I D I R I s I 2 101 0 I 0 I -I 0 I 0 I 0 I 0 I 0 I -I 0 I 0 IQ)I 4 11 I 1 11 I 1 1 G)I I I.@ 9 LICENSEE. CODE . 14 15
e Commonwec9 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 June 5, 1980 BBS Ltr. /180-476 James G. Keppler, Regional Director Directorate of Regulatory Operations - Region. III U.S. Nuclear Regulatory Commission*
* LlCENSE NUMBER 25 26. LICENSE TYPE. JO 57 CAT 58 . CON'T } o I 2 I j 0 13 I: l 0 14 I o I s 1 o I o I o I 2 13 11 101 o 1 s 1 1 1 2 I a 1 o I© 1 o I 6. 1 o I s I a I o 1 G) 60 61 DOCKET NUMBER 68 69 . EVENT DATE 74 75 REPORT DATE ao EVENT DESCRIPTION A":'D PROBABLE_CONSEQUENCES@ I *Following a uni"t scram, double* valve indication was observed on the HPCI-inboard isolation valve *. Upon trying to cycle. the valve, the valve failed to close (T.S.3.7.D.l). The health and safety of the public was not endangered because the ) 0 I sJ I HPCI steam line was isolable _ via the outboard isolation valve and other ECCS systems -0 Is I* were operable. 'J'his -is the first occurrence of* this type. l a ,,7 r I 1Cr'Tal". 9 80 SYSTEM CAUSE CAUSE COMP. CODE COiJE SUBCOOE COMPONENT.CODE SUB CODE ISIFI@ L!J@ w@ lvlAILlvlolPI@ L!J@) 9 . 10 11 12 13 18 19 SEQUENTIAL OCCURRENCE AEPOP.T LEA/AO CV ENT YEAR. REPORT NO. CODE TYPE .REPORT I 8 I 0 I I l I 0 I l I 7 I I ........ , I 0 I 31 LEJ NUMBER .
799 Roosevelt Road Glen Ellyn, IL         60137
* _ 21 22 23 24 . 26 27 28 29 JO VALVE SUBCOOE w@ 20 1=J 31 REVISION. NO. ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPR0-4 TAKEN ACT.ION' ON PLANT METHOD . . HOURS' ''_SUBMITTED FORM :;us. PRIME COMP. SUPPLIER. COMPONENT MANUFACTURER ----**-* . L:J@ L.:J@ I 0 I 0 I 0 I I L!:J@ l:J<&sect; 33 . 34 ' . 35 . 35* . J-7 40. 41 . . 42 I L I 2 I 0 I 0 I@ . 44 . . . . 47 -.CAUSE DESCRIPTION AND CORRECTIVE ACTIONS@ . 43 , , I 0 I r The failure was due to a packing leak on the valve' causing water to enter the valve ) 1 11 t .I _motor operator. The mo.tor dr:!,ed out and the valve was and. cycled 1-) 1 I 2 I successfully. N_o further action deemed necessary. ............... _,.. ..... _._ ................ ..,_...;.. ............... -.--.--.--.--.---'-.-..--.--.--.--.--.--..,..-.--,---,---,---,---,---,---,---,---,---,---.,..-,---,--..--,---.--.-....... _ 80* FACILITY 13Q\ STATUS % POWER OTHER STATUS re uu@
*Reportable Occurrence Report /180-17/031-0, Docket /1050-237, is being submitted to your office in accordance with Dresden Nuclear Power Station Technical Specific*ation 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.
* 1 0 I o_ I 0 l@).._I ..;,;,.N:..:.I 0* 9 10 12 n ACTIVITY CONTENT (.;;;'\ RELEASED OF RELEASE. AMOUNT OF ACTIVITY 7161 .. LU@ W(&sect; ..... 1 __ _,__ __ _.,....l 9 10 11 44 METHOD OF (:;':;\ DISCOVERY DISCOVERY OESCRIPTlON _ ......... ............................................................... ___.*I 45 46 80 LOCATION OF N/A 45. 80 ?ERSONNEL EXPOSURES * . *-Q_ NUMBER A TYPE . OESCRIPTlON  m. ro 1 o 1 o ___ ...:..;N..:...;/ A:.:.... __ .....;_ ____ ._,.;.__ _____________ ----' 8 9 11 12 13 so PERSONNEL INJURIES* * (,;"";\ NUMBER OESCRIPTION6 :CW* I 0 I 0 I 0 __ * -*_N..;,._/ A ________________________ _,___, 8 9 11 12.
                                        ,~~?~.
* 00 LOSS OF OR DAMAGE TO FACl.LJTY f'43\ TYPE DESCRIPTION* ".:::::) 3TI: LU@ . 8-9 10 PUBLICITY (';;;\ 80. "' NR.C USE ONLY ISSUED/,;";;\ :IT&#xa3;J;. l.::J'6 N /A 8. 9 IQ. K. Zirwas N A,'/i E CF PP. E P .t\ RE A 1,....,_,_,....':;miiimi--t"-"llAilliiiii_ii!l _ _.,.limiilll .. r'"*W;iiill'll 68 69 80*; 0 a. X-529}}
B. B. Stephenson~
Station Superintendent Dresden Nuclear Power Station BBS/nh Enclosure cc/ Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC
 
LICENSEE EVENT REPORT
          ., CONTROL BLOCK:                                                  I*
1----.1....,_..1-__.....__._...._;;;._-'s\..!J       I10                      (PLEASE PRIN.T ORTYPAIL REQUIRED                                  INFORMATIO~J
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~            9       LICENSEE. CODE             . 14       15
* LlCENSE NUMBER                             25       26.       LICENSE TYPE. JO                             57 CAT 58 .
CON'T
~                  :;~~~; ~&#xa9;I                      o I s 1o I o I o I 2 13 11 101 o1 s 1 1 12 I a 1o I&#xa9; 1 o I 6. 1 o I s I a I o 1G)
~                                60             61                 DOCKET NUMBER                                   68     69         . EVENT DATE               74       75         REPORT DATE                                       ao EVENT DESCRIPTION A":'D PROBABLE_CONSEQUENCES@
}o  I 2 I I *Following                 a uni"t scram, double* valve indication was observed on the HPCI-inboard j 0 13 I:        isolation valve *. Upon trying to cycle. the valve, the valve failed to close (T.S.3.7.D.l).                       The health and safety of the public was not endangered because the l0  14 I
) 0 I sJ I       HPCI steam line was                               isolable _ via the outboard isolation valve and other ECCS systems
- 0 Is I*       were operable.                       'J'his - is the first occurrence of* this type.
I l a ,,7 r 1Cr'Tal". L,___;_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,__,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_-,---,-..,_-,-..,_..,_...:.._..,_..,_..,_..,_..,_..,_..,_..,_~
~            9                                                                                                                                                                                                                                                    80 SYSTEM                  CAUSE                CAUSE                                                                              COMP.             VALVE CODE                    COiJE          SUBCOOE                                    COMPONENT.CODE                          SUB CODE            SUBCOOE ISIFI@ L!J@ w@ lvlAILlvlolPI@ L!J@)
9        . 10            11                    12                          13                                    18            19 w@
20 SEQUENTIAL                                          OCCURRENCE              AEPOP.T                                          REVISION.
              ~      LEA/AO CV ENT YEAR.                                                     REPORT NO.                                             CODE                  TYPE                                                  NO.
              ~    .REPORT NUMBER I 8 I.0 I*                  I l                  I        0      I l I 7I            I ........ ,        I 0 I 31                LEJ                1=J                              ~
_          21            22            23                    24                      . 26        27                  28        29            JO                31 ACTION      FUTURE                  EFFECT              SHUTDOWN                                              ~            ATTACHMENT          NPR0-4          PRIME COMP.                                     COMPONENT TAKEN      ACT.ION'             ON PLANT                METHOD .                           .     HOURS'              ''_SUBMITTED        FORM :;us.           SUPPLIER.                             MANUFACTURER - ---**-*
            . 33~@~@* . 34        '        . 35 L:J@.                   L.:J@
35*      .
I J-7 0
I 0 I 0 I 40.I L!:J@        41 .     .
l:J<&sect; 42
                                                                                                                                                                                  -~.                              I L I 2 I 0 I 0 I@ .
44            .      .              .. 47 -   -~-
43
            .CAUSE DESCRIPTION AND CORRECTIVE ACTIONS@                                                                                      .
, , I0 I      r  The failure was due to a packing leak on the valve' causing water to enter the valve
) 1 11    t .I  _motor operator.                         The mo.tor dr:!,ed out and the valve was                                                          rep~cked and.                 cycled                                                                  1-successfully.                       N_o further action deemed necessary.
) 1 I2 I
::IJJ]*'L,_;._;_-.,--.,--.,--.,-_;__-.,--.,--.,--.,--.,--.,--.,--.,--.,--.,--.,--.,--.,-~-.,--.,-~-.,--.,--.,--.,--.,------.,-~~~~~
~8-9~..............._,......._._..................,_...;.................-.--.--.--.--.---'-.-..--.--.--.--.--.--..,..-.--,---,---,---,---,---,---,---,---,---,---.,..-,---,--..--,---.--.-....... _
~                                                                                                                                                                                                                                                              80*
FACILITY                                                                                        13Q\ METHOD OF                                                                                          (:;':;\
re uu@ *1 I 0*
STATUS 9
ACTIVITY 10 0
CONTENT
                                  % POWER o_
12        n OTHER STATUS I 0 l@).._I..;,;,.N:..:.IA=--------~
                                                                                                          ~
(.;;;'\
DISCOVERY 45              46 DISCOVERY OESCRIPTlON ~ _
ll.JQ2)~1.........~O~p~e~r~a~t~or-=-O~b~s~e~rv;;;...;..;a~t~1~*o~n-=-...............................................................___.*I 80 RELEASED OF RELEASE.                            AMOUNT OF ACTIVITY                          ~                                                        LOCATION OF        RELEA~E@
7161.. LU@                  W(&sect; 1. . ._..;N~/-=A_ __,___ __.,....l                                                                            N/A
~            9              10            11                                                                  44            45.                                                                                                                              80
                ?ERSONNEL EXPOSURES                        *          . *-Q_
: m. ro  8    9 NUMBER 1 o 1o 11 A
                                'l2J@~
TYPE 12
                                                    . OESCRIPTlON 13
                                                                                ...:..;N..:...;/A:.:...._ _.....;__ _ _ _._,.;.___ _ _ _ _ _ _ _ _ _ _ _ _- - - - '
so PERSONNEL INJURIES* *                    (,;"";\
:CW*  8    9 NUMBER I0 I 0 I0 11 I@~---
OESCRIPTION6 12.
__* -*_N..;,._/A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __,___,
* 00 LOSS OF OR DAMAGE TO FACl.LJTY                  f'43\
TYPE        DESCRIPTION*                      ".:::::)
3TI: LU@
8- 9              10
                                                        .            ~/A 80.
PUBLICITY                  (';;;\
NR.C USE ONLY ISSUED/,;";;\ DESCRIPTION~
:IT&#xa3;J;. l.::J'6                                        N /A                                                                                                                            1111111111111~
: 8. 9            IQ.                                                                                                                                                    68    69                                                                    80*;
K. Zirwas                                                                                                  X-529                                                                                  0 a.
N A,'/i E CF PP. E P.t\ RE A 1,....,_,_,....':;miiimi--t"-"llAilliiiii_ii!l__.,.limiilll. .r'"*W;iiill'll}}

Latest revision as of 10:44, 4 February 2020

LER 80-017/03L-0 for Dresden, Unit 2 Re Double Valve Indication Was Observed on the HPCI Inboard Isolation Valve. Upon Trying to Cycle the Valve, the Valve Failed to Close
ML17252B552
Person / Time
Site: Dresden Constellation icon.png
Issue date: 06/05/1980
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS LTR 80-476 LER 80-017/03L-0
Download: ML17252B552 (2)
v • d • e


Text

e Commonwec9 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 June 5, 1980 BBS Ltr. /180-476 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 /180-17/031-0, Docket /1050-237, is being submitted to your office in accordance with Dresden Nuclear Power Station Technical Specific*ation 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.

,~~?~.

B. B. Stephenson~

Station Superintendent Dresden Nuclear Power Station BBS/nh Enclosure cc/ Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC

LICENSEE EVENT REPORT

., CONTROL BLOCK: I*

1----.1....,_..1-__.....__._...._;;;._-'s\..!J I10 (PLEASE PRIN.T ORTYPAIL REQUIRED INFORMATIO~J

~ I II L I D I R I s I 2 101 0 I 0 I - I 0 I 0 I 0 I 0 I 0 I - I 0 I 0 IQ)I 4 11 I 1 11 I 1 1G)I I I.@

~ 9 LICENSEE. CODE . 14 15

  • LlCENSE NUMBER 25 26. LICENSE TYPE. JO 57 CAT 58 .

CON'T

~  :;~~~; ~©I o I s 1o I o I o I 2 13 11 101 o1 s 1 1 12 I a 1o I© 1 o I 6. 1 o I s I a I o 1G)

~ 60 61 DOCKET NUMBER 68 69 . EVENT DATE 74 75 REPORT DATE ao EVENT DESCRIPTION A":'D PROBABLE_CONSEQUENCES@

}o I 2 I I *Following a uni"t scram, double* valve indication was observed on the HPCI-inboard j 0 13 I: isolation valve *. Upon trying to cycle. the valve, the valve failed to close (T.S.3.7.D.l). The health and safety of the public was not endangered because the l0 14 I

) 0 I sJ I HPCI steam line was isolable _ via the outboard isolation valve and other ECCS systems

- 0 Is I* were operable. 'J'his - is the first occurrence of* this type.

I l a ,,7 r 1Cr'Tal". L,___;_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,__,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_-,---,-..,_-,-..,_..,_...:.._..,_..,_..,_..,_..,_..,_..,_..,_~

~ 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE COiJE SUBCOOE COMPONENT.CODE SUB CODE SUBCOOE ISIFI@ L!J@ w@ lvlAILlvlolPI@ L!J@)

9 . 10 11 12 13 18 19 w@

20 SEQUENTIAL OCCURRENCE AEPOP.T REVISION.

~ LEA/AO CV ENT YEAR. REPORT NO. CODE TYPE NO.

~ .REPORT NUMBER I 8 I.0 I* I l I 0 I l I 7I I ........ , I 0 I 31 LEJ 1=J ~

_ 21 22 23 24 . 26 27 28 29 JO 31 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPR0-4 PRIME COMP. COMPONENT TAKEN ACT.ION' ON PLANT METHOD . . HOURS' _SUBMITTED FORM :;us. SUPPLIER. MANUFACTURER - ---**-*

. 33~@~@* . 34 ' . 35 L:J@. L.:J@

35* .

I J-7 0

I 0 I 0 I 40.I L!:J@ 41 . .

l:J<§ 42

-~. I L I 2 I 0 I 0 I@ .

44 . . .. 47 - -~-

43

.CAUSE DESCRIPTION AND CORRECTIVE ACTIONS@ .

, , I0 I r The failure was due to a packing leak on the valve' causing water to enter the valve

) 1 11 t .I _motor operator. The mo.tor dr:!,ed out and the valve was rep~cked and. cycled 1-successfully. N_o further action deemed necessary.

) 1 I2 I

IJJ]*'L,_;._;_-.,--.,--.,--.,-_;__-.,--.,--.,--.,--.,--.,--.,--.,--.,--.,--.,--.,--.,-~-.,--.,-~-.,--.,--.,--.,--.,------.,-~~~~~

~8-9~..............._,......._._..................,_...;.................-.--.--.--.--.---'-.-..--.--.--.--.--.--..,..-.--,---,---,---,---,---,---,---,---,---,---.,..-,---,--..--,---.--.-....... _

~ 80*

FACILITY 13Q\ METHOD OF (:;':;\

re uu@ *1 I 0*

STATUS 9

ACTIVITY 10 0

CONTENT

% POWER o_

12 n OTHER STATUS I 0 l@).._I..;,;,.N:..:.IA=--------~

~

(.;;;'\

DISCOVERY 45 46 DISCOVERY OESCRIPTlON ~ _

ll.JQ2)~1.........~O~p~e~r~a~t~or-=-O~b~s~e~rv;;;...;..;a~t~1~*o~n-=-...............................................................___.*I 80 RELEASED OF RELEASE. AMOUNT OF ACTIVITY ~ LOCATION OF RELEA~E@

7161.. LU@ W(§ 1. . ._..;N~/-=A_ __,___ __.,....l N/A

~ 9 10 11 44 45. 80

?ERSONNEL EXPOSURES * . *-Q_

m. ro 8 9 NUMBER 1 o 1o 11 A

'l2J@~

TYPE 12

. OESCRIPTlON 13

...:..;N..:...;/A:.:...._ _.....;__ _ _ _._,.;.___ _ _ _ _ _ _ _ _ _ _ _ _- - - - '

so PERSONNEL INJURIES* * (,;"";\

CW* 8 9 NUMBER I0 I 0 I0 11 I@~---

OESCRIPTION6 12.

__* -*_N..;,._/A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __,___,

  • 00 LOSS OF OR DAMAGE TO FACl.LJTY f'43\

TYPE DESCRIPTION* ".:::::)

3TI: LU@

8- 9 10

. ~/A 80.

PUBLICITY (';;;\

NR.C USE ONLY ISSUED/,;";;\ DESCRIPTION~

IT£J;. l.::J'6 N /A 1111111111111~
8. 9 IQ. 68 69 80*;

K. Zirwas X-529 0 a.

N A,'/i E CF PP. E P.t\ RE A 1,....,_,_,....':;miiimi--t"-"llAilliiiii_ii!l__.,.limiilll. .r'"*W;iiill'll

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