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=Text=
=Text=
{{#Wiki_filter:~DRM36o i7) ------*u.s.'.NUCLEAFfREGUL.ATc:iRY
{{#Wiki_filter:~DRM36o                                                                                                                                                 - ----- *u.s.'.NUCLEAFfREGUL.ATc:iRY _COMMISSION i7)
_COMMISSION
* LICENSEE EVENT REPORT                                               A COl\'7RD:.. ELOCK.:             1....-......1-_..1..-.......L.-..._\_..._!____,J C
* LICENSEE EVENT REPORT A COl\'7RD:..
8                     (PLEASE PRINT OR TYP~L REQUIRED INFORMATION)
ELOCK.: 1....-......1-_..1..-.......L.-..._\
TI I V I A I s Ip Is 12 101 ° I O I - I O I O I O IO IO I- 1° I O 101 4 11 11 11 11 101 I I © 8     9         LICENSEE CODE                       1.t.       1S                         LICENSE NUMBER                                 2S         26       LICENSE TYPE     30   57 CAT SB ON'T
_..._! ____,J 8 (PLEASE PRINT OR TYP~L REQUIRED INFORMATION)
  ~8                 :;:~~~ ~ I oI s I o I o I o I 2 I s 11 101 11 11 o 111 s I o l©J 1 11 Io 11 1s i o IG) 60               61                     DOCKET NUMBER                       68     69           EVENT DATE                     74     7S     REPORT DATE           80 EVENT DESCRIPTIDN AND PROBABLE CONSEQUENCES                                                     {,o)
C TI I V I A I s I p Is 1 2 101 ° I O I -I O I O I O I O I O I-1° I O 101 4 1 1 1 1 1 1 1 1 101 I I © 8 9 LICENSEE CODE 1.t. 1S LICENSE NUMBER 2S 26 LICENSE TYPE 30 57 CAT SB ON'T 8 :;:~~~ ~I o I s I o I o I o I 2 I s 11 101 11 11 o 111 s I o l©J 1 11 Io 11 1 s i o I G) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 7S REPORT DATE 80 EVENT DESCRIPTIDN AND PROBABLE CONSEQUENCES
* I With         the unit at hot shutdown, it was'-di.scovered that MOV-FW-251B could not be closed fran the Control Room.                                           Th-i.s event is reportable per T.S. 6.6.2.b. (2).                                                       Nonnal feed control was Js~lishetl and the auxiliary feedwater system was secured.                                                                                                     Hence, MOV-FW-LE] I                               .                                       .                                                                                                       .
{,o)
251B was not requiretl to.be closetl to control steam generator level.                                                                                               Therefore, the health and safety of the public were not affectetl.
* I With the unit at hot shutdown, it was'-di.scovered that MOV-FW-251B could not be closed fran the Control Room. Th-i.s event is reportable per T.S. 6.6.2.b. (2). Nonnal feed control was Js~lishetl and the auxiliary feedwater system was secured. Hence, MOV-FW-LE] I . . . 251B was not requiretl to.be closetl to control steam generator level. Therefore, the health and safety of the public were not affectetl.
80 SYSTEM                       CAUSE              CAUSE                                                                        COMP.        VALVE
SYSTEM CODE ,c jH I@ 9 10 c:;.... LE R/RO LVENT YEAR v.:.J REPORT 1 8 i O i NUMBER 21 . 22 CAUSE CAUSE COMP. CODE . SUBCODE COMPONENT CODE SUBCODE ~@ l.£...1@ IVIAjLIVIE IX I@ LI 11 12 13 18 19 SEQUENTIAL OCCURRENCE REPORT REPORT NO. CODE TYPE VALVE SUBCOOE ~@ 20 I I 10 I 3 l 6 I I ......-1 10 13 I Ll.l I I 23 24 26 27 28 29 30 31 -REVISION NO. LQ_J 32 80 ACTION FUTURE EFFECT SHUTDOWN r:;;:;.. ATTACHMENT NPR04 PRIME COMP. TAKEN ACTION ON PLANT METHO_D HOURS SUBMITTED FORM SUB. SUPPLIER _COMPONENT MANUFACTURER  
                                    ,c jH I@
@J@l!.J@ W@ ~ *1 o Io Io Io I I.LJ@-. LliJ@) ~@ 33 34 . 3S 36 37 40 41 . 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ lw I o! 3 lo I 44 47 !The limitorque cover was found not to be placetl and three control wires brolcen. The IDJ I r~on for the cover not being placeo and wires broken can not be dete:rmineo.
9 CODE 10 CODE         . SUBCODE
These I wires* were replaced and the valve testetl satisfactorily.
                                                                        ~@ l.£...1@ IVIAjLIVIE IX I@ LI ~@
The cover was also replacetl.
11                 12                 13 COMPONENT CODE 18 SUBCODE 19 SUBCOOE 20 SEQUENTIAL                                   OCCURRENCE                 REPORT                   -REVISION c:;.... LE R/RO LVENT YEAR                                                    REPORT NO.                                         CODE                     TYPE                         NO.
Im -ill] :ill] 8 9 FACILITY . 'Jo' STATUS % POWER OTHER STATUS 1-:::::J QI] ~J@ I O I O I O l@'"-1 _N_/A ___ _ METHOD OF . A DISCOVERY
v.:.J REPORT NUMBER 1  8 O i i                    I       I         10   I 3l 6 I               I ......-1         1028 13         I           Ll.l         I     I       LQ_J 21              22                23                 24                 26         27                               29             30           31           32 ACTION FUTURE                         EFFECT                   SHUTDOWN                                   r:;;:;.. ATTACHMENT                 NPR04         PRIME COMP.           _COMPONENT TAKEN         ACTION                 ON PLANT                   METHO_D                           HOURS ~              SUBMITTED             FORM SUB.           SUPPLIER           MANUFACTURER
-DISCOVERY DESCRIPTION
            @J@l!.J@
~--1 __ 0per ____ a_ti_' ona_l_~_en_t
33            34          .
_______ -..J 80 8 9 10 12 1'3 . ACTIVITY
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                                                                                ~ *1 o Io Io Io I I.LJ@- . LliJ@) ~@ lw I o! 3 lo I 36               37                           40       41                   . 42               43             44                    47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS                                               @
            !The       limitorque cover was found not to be placetl and three control wires brolcen.                                                                                                   The IDJ Ir~on                     for     the         cover not being placeo and wires broken can not be dete:rmineo.                                                                               These wires* were replaced and the valve testetl satisfactorily.                                                                                     The cover was also replacetl.
Im I-ill]
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8     9                                                                                                                                                                                                         80 FACILITY STATUS                 % POWER OTHER STATUS
                                                                                                    'Jo' 1-:::::J METHOD OF DISCOVERY
                                                                                                                                                            -      DISCOVERY DESCRIPTION A
QI] ~J@ I O I O I O l@'"-1_N_/A_ _ __                                                                            ~--1__0per                  ____a_ti_'ona_l_~_en_t_ _ _ _ _ _ _                                  -..J 8     9                 10                   12           1'3           .                           44    4S              46                                                                                BO ACTIVITY
* CONTENT :
* CONTENT :
* t:';\ REL.EASED OF RELEASE. . AMOUNT OF ACTIVITY  w @) W(§)I N/A 8 9 10
* t:';\
* 11 4S 46 44 .44 4S N/A . _LOCATION OF RELEASE @ BO 80 PERSONNEL EXPOSURES  
w @) W(§)I REL.EASED OF RELEASE. .                                   AMOUNT OF ACTIVITY                                                                           . _LOCATION OF RELEASE
--:
  ~                                                                          N/A                                                                  N/A 8     9                 10
* Q.. NUMBER TYPE
* 11                                                           .44             4S                                                                                         80 PERSONNEL EXPOSURES                                     - - :
* DESCRIPTION lo Io Io l0tu@~____..=------------------------'
* Q..
8 9 11-12. 13 * : * . : -' PERSONNEL INJURIES (:":;\ .. . -NUMBER OESCRIPTION6
NUMBER           ~ TYPE
: .. *.: iliJ j O j O j O l@L...:-*
* DESCRIPTION
_* ___ N;;..;::/~A.:...*  
~8 lo     9 Io Io l0tu@~____..=------------------------'
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11-     12.                 13       * :* . : - '                                                                                                                                   80 PERSONNEL INJURIES                               (:":;\ ..       .-
80 8 9 ,, 12 . LOSS OF 0~ DAMAGE TO FACILITY '4J' *.,
NUMBER                 OESCRIPTION6 : . . *.:
* TYPE wESCRIPTION
iliJ8    j9 O j O j O ,,l@L...:-*     12
:. \::::;J . :. W@ =*\* NA' 80 8 9 PUBLl~~TY  
_*___. N;;..;::/~A.:. .*._.- - - - - - - - - - - - - - - - - - - - - - '
':.'CYo tI\ 1~030 7 2-3 NRC USE ONLY ISSUEO~DESCRIPTION,'~,.o VI ~I . *. . ,0 IT£] l.!..J~ ' ' N A . . . I I I I I I I I I I I I I ! 80 a 9 10 --~ ____ ! ~_£_:_~~:t~
80 LOSS OF 0~ DAMAGE TO FACILITY '4J'                                     *.,
9~----------
* TYPE           wESCRIPTION :.                           \::::;J       . :.
---~--________ ---.---..
~          W@                             =*\*                           NA' 8     9                                                                                                                                                                                                         80 PUBLl~~TY ISSUEO~DESCRIPTION,'~,.o
____ :_s_ .. ______ ***-----*---*----_a~  
                                          ':.'CYo             tI\
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                                                                                                                                                                                                                          ,0 IT£] l.!..J~                               ''                             N A . ..                                                                                                 II IIIIIII                I I I     I!
a     9             10                   --~ ____         ! ~_£_:_~~:t~9~---------- ---                         ~--         ________ ---.---.. ~~?.~L-,~~-~~~~§~_ _ :_s_. ______           ***-----*---*----_a~ ~--
 
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* ATI'ACHMENT 1 (PAGE 1 OF 1. SURRY POWER STATION, UNIT 2 DOCKET NO; 50-281 REPORI' NO; 80-036/031r-0 EVENT ,DATE: 11-01-80 SUBJECT':
* ATI'ACHMENT   1 (PAGE 1 OF 1 .
MOV-FW-251B INOPERABLE
SURRY POWER STATION, UNIT 2 DOCKET NO;     50-281 REPORI' NO;     80-036/031r-0 EVENT ,DATE:   11-01-80 SUBJECT':       MOV-FW-251B INOPERABLE
: 1. EVENT DESCRIPI'ION:  
: 1. EVENT DESCRIPI'ION:
' With the unit at hot shutdown following a reactor trip, MOV-FW-251B was in a position to fulfill its required safety function, subsequently it*was discovered that MOV-FW-251B would not respond to control switch operation.  
With the unit at hot shutdown following a reactor trip, MOV-FW-251B was in a position to fulfill its required safety function, subsequently it*was discovered that MOV-FW-251B would not respond to control switch operation. 'Ibis event is reportable per T.S. 6.6.2.b.(2).
'Ibis event is reportable per T.S. 6.6.2.b.(2).
: 2. PROBABLE *cON~S:
: 2. PROBABLE *cON~S: This valve is one of six valves that are used to control steam generator level when the auxiliary feedwater systan is in operation.
This valve is one of six valves that are used to control steam generator level when the auxiliary feedwater systan is in operation. With MOV-Th,._251B failed in the open position, existing procedures provide for on-off control of aux.
With MOV-Th,._251B failed in the open position, existing procedures provide for on-off control of aux. feed pumps to control S/G level. Hc:wever, long before this was necessary, nonnal feed was re-established and the auxiliary feed systanwas removed from service. Therefore, the health and safety of the public were not affected.
feed pumps to control S/G level. Hc:wever, long before this was necessary, nonnal feed was re-established and the auxiliary feed systanwas removed from service.
: 3. CAUSE: The limitorque cover was found not to be placed and three control wires broken. The reason for the cover not being placed and wire broken can not be detennined.
Therefore, the health and safety of the public were not affected.
: 4. IMMEDIATE (X)RREx::'I'IVE ACI'ION: The imnediate corrective action:was to transfer steam generator level control to. the main feed system. 5. -SUBSEOOENT  
: 3. CAUSE:
*coRREx::TIVE ACI'ION: The subsequent corrective action was to repair the broken wires and replace the cover. The MOV was subsequently tested satisfactorily.
The limitorque cover was found not to be placed and three control wires broken.
The reason for the cover not being placed and wire broken can not be detennined.
: 4. IMMEDIATE (X)RREx::'I'IVE ACI'ION:
The imnediate corrective action:was to transfer steam generator level control to. the main feed system.
: 5.   -SUBSEOOENT *coRREx::TIVE ACI'ION:
The subsequent corrective action was to repair the broken wires and replace the cover. The MOV was subsequently tested satisfactorily.
: 6. ACI'ION TAKEN 'TO PREVEm' 'RECURRENCE:
: 6. ACI'ION TAKEN 'TO PREVEm' 'RECURRENCE:
None. 7. GENERIC IMPLICATIONS:
None.
: 7. GENERIC IMPLICATIONS:
None.}}
None.}}

Latest revision as of 01:18, 3 February 2020

LER 80-036/03L-0:on 801101,discovered That MOV-FW-251B Could Not Be Closed from Control Room.Caused by Misplacement of Limitorque Cover & Three Broken Control Wires.Cover & Wires Replaced
ML18139A866
Person / Time
Site: Surry Dominion icon.png
Issue date: 11/01/1980
From: Joshua Wilson
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139A865 List:
References
LER-80-036-03L-02, LER-80-36-3L-2, NUDOCS 8012030723
Download: ML18139A866 (2)


Text

~DRM36o - ----- *u.s.'.NUCLEAFfREGUL.ATc:iRY _COMMISSION i7)

  • LICENSEE EVENT REPORT A COl\'7RD:.. ELOCK.: 1....-......1-_..1..-.......L.-..._\_..._!____,J C

8 (PLEASE PRINT OR TYP~L REQUIRED INFORMATION)

TI I V I A I s Ip Is 12 101 ° I O I - I O I O I O IO IO I- 1° I O 101 4 11 11 11 11 101 I I © 8 9 LICENSEE CODE 1.t. 1S LICENSE NUMBER 2S 26 LICENSE TYPE 30 57 CAT SB ON'T

~8  :;:~~~ ~ I oI s I o I o I o I 2 I s 11 101 11 11 o 111 s I o l©J 1 11 Io 11 1s i o IG) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 7S REPORT DATE 80 EVENT DESCRIPTIDN AND PROBABLE CONSEQUENCES {,o)

  • I With the unit at hot shutdown, it was'-di.scovered that MOV-FW-251B could not be closed fran the Control Room. Th-i.s event is reportable per T.S. 6.6.2.b. (2). Nonnal feed control was Js~lishetl and the auxiliary feedwater system was secured. Hence, MOV-FW-LE] I . . .

251B was not requiretl to.be closetl to control steam generator level. Therefore, the health and safety of the public were not affectetl.

80 SYSTEM CAUSE CAUSE COMP. VALVE

,c jH I@

9 CODE 10 CODE . SUBCODE

~@ l.£...1@ IVIAjLIVIE IX I@ LI ~@

11 12 13 COMPONENT CODE 18 SUBCODE 19 SUBCOOE 20 SEQUENTIAL OCCURRENCE REPORT -REVISION c:;.... LE R/RO LVENT YEAR REPORT NO. CODE TYPE NO.

v.:.J REPORT NUMBER 1 8 O i i I I 10 I 3l 6 I I ......-1 1028 13 I Ll.l I I LQ_J 21 22 23 24 26 27 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN r:;;:;.. ATTACHMENT NPR04 PRIME COMP. _COMPONENT TAKEN ACTION ON PLANT METHO_D HOURS ~ SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

@J@l!.J@

33 34 .

W@

3S

~ *1 o Io Io Io I I.LJ@- . LliJ@) ~@ lw I o! 3 lo I 36 37 40 41 . 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

!The limitorque cover was found not to be placetl and three control wires brolcen. The IDJ Ir~on for the cover not being placeo and wires broken can not be dete:rmineo. These wires* were replaced and the valve testetl satisfactorily. The cover was also replacetl.

Im I-ill]

ill]

8 9 80 FACILITY STATUS  % POWER OTHER STATUS

'Jo' 1-:::::J METHOD OF DISCOVERY

- DISCOVERY DESCRIPTION A

QI] ~J@ I O I O I O l@'"-1_N_/A_ _ __ ~--1__0per ____a_ti_'ona_l_~_en_t_ _ _ _ _ _ _ -..J 8 9 10 12 1'3 . 44 4S 46 BO ACTIVITY

  • CONTENT :
  • t:';\

w @) W(§)I REL.EASED OF RELEASE. . AMOUNT OF ACTIVITY . _LOCATION OF RELEASE

~ N/A N/A 8 9 10

  • 11 .44 4S 80 PERSONNEL EXPOSURES - - :
  • Q..

NUMBER ~ TYPE

  • DESCRIPTION

~8 lo 9 Io Io l0tu@~____..=------------------------'

11- 12. 13 * :* . : - ' 80 PERSONNEL INJURIES (:":;\ .. .-

NUMBER OESCRIPTION6 : . . *.:

iliJ8 j9 O j O j O ,,l@L...:-* 12

_*___. N;;..;::/~A.:. .*._.- - - - - - - - - - - - - - - - - - - - - - '

80 LOSS OF 0~ DAMAGE TO FACILITY '4J' *.,

  • TYPE wESCRIPTION :. \::::;J . :.

~ W@ =*\* NA' 8 9 80 PUBLl~~TY ISSUEO~DESCRIPTION,'~,.o

':.'CYo tI\

VI 1~030 ~I .*. . 7 2-3 NRC USE ONLY

,0 IT£] l.!..J~ N A . .. II IIIIIII I I I I!

a 9 10 --~ ____  ! ~_£_:_~~:t~9~---------- --- ~-- ________ ---.---.. ~~?.~L-,~~-~~~~§~_ _ :_s_. ______ ***-----*---*----_a~ ~--

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  • ATI'ACHMENT 1 (PAGE 1 OF 1 .

SURRY POWER STATION, UNIT 2 DOCKET NO; 50-281 REPORI' NO; 80-036/031r-0 EVENT ,DATE: 11-01-80 SUBJECT': MOV-FW-251B INOPERABLE

1. EVENT DESCRIPI'ION:

With the unit at hot shutdown following a reactor trip, MOV-FW-251B was in a position to fulfill its required safety function, subsequently it*was discovered that MOV-FW-251B would not respond to control switch operation. 'Ibis event is reportable per T.S. 6.6.2.b.(2).

2. PROBABLE *cON~S:

This valve is one of six valves that are used to control steam generator level when the auxiliary feedwater systan is in operation. With MOV-Th,._251B failed in the open position, existing procedures provide for on-off control of aux.

feed pumps to control S/G level. Hc:wever, long before this was necessary, nonnal feed was re-established and the auxiliary feed systanwas removed from service.

Therefore, the health and safety of the public were not affected.

3. CAUSE:

The limitorque cover was found not to be placed and three control wires broken.

The reason for the cover not being placed and wire broken can not be detennined.

4. IMMEDIATE (X)RREx::'I'IVE ACI'ION:

The imnediate corrective action:was to transfer steam generator level control to. the main feed system.

5. -SUBSEOOENT *coRREx::TIVE ACI'ION:

The subsequent corrective action was to repair the broken wires and replace the cover. The MOV was subsequently tested satisfactorily.

6. ACI'ION TAKEN 'TO PREVEm' 'RECURRENCE:

None.

7. GENERIC IMPLICATIONS:

None.