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{{#Wiki_filter:* NRC FORM 366 .LICENSEE EVENT REPORT U.S. NUCLEAR REGULA. TORY COMMISSION li-7') ** CONTROL BLOCK: ' I',\ (PLEASE P~INT OR TYPE ALL REOUIREC INFORMATION) l--..... _ ...............
{{#Wiki_filter:~
_..._ __ ---,!6 \.!.I ! V ! A I S I P I SI 2 IQ)l O I OJ ; S 9 L.ICSNSEE COOE 14 7S -I o I 01 01 01 01 -I 01 o 1014 11 J 1 1111101 l I© LICENSE NUMBER 2S . 25 L.ICENSE TYPE JO S7 CAT SS CON"7 ~-7 6 LI© I o I s l o l o I o I 21 s 1 1 101. o I s 1 1 I 4 I s I 1 l© I o I 6 I o I s Ls I 1 10 60 61 DOCKET NUMBER 6S 69 EVENT DATE 74 7S REPORT OA, = BO EVENT DESCRIPTION AND PR06ASLE CONSEQUENCES@
* NRC FORM 366 li-7')
I With Unit No. 2 at 100% power, PT-27C revealed*
CONTROL BLOCK: l--.....
that amn readino for heat tracing .III!]. J Panel 9, circuit 20C, was below the acceptance criteria stipulated in the PT. This ([II] I event is contrary to T.S. 3.2.B.5 and is reportable per T.s: 6.6.2.b(2)  
                              ! V ! A I S I P I SI
.. ~he [TI]] _I redundant.
                                                              '
heat tracing circuit was operable, therefore, the health* and safety of the J .. [£I[] I public were not affected, IITil L.....------------------------------------___..
2
wIJ 7 B 9 .. rrm ' 8 SYSTSM CODE !S IHI@ 9 10 C\ LER/RO LVENT YEAR \!..:.J REPORT I 8 I 1 ! NUMBEFI 21 22 CAUSE CAUSE CODE SUBCOOE COMPONENT CODE , El@ liJ@ , H, E, A, T, E, R ,e 11 12 13 18 SEQUENTIAL OCCURRENCE REPORT NO, cooe I o I 21 21 *I ,I Io I 3 I 24 26 27 28 29 COMP. SUBCOOE W 19 REPORT TYPE lliJ 30 VALVE SUBCOOE w@ 20 1:=l 31 BO REVISION NO. w 32 COMPONENT ACTION l'UTURE EF;:ECT *SHUTOOWN ATTACHMENT NPRc-4 PRIMECOMP.
_
TAKEN ACTION ON PLANT METHOD . HOURS SUBMITTED FORMliUB.
                                                                                              .LICENSEE EVENT REPORT
SUPPI.IER MANUl'ACTURER  
                                                                            ..............._...___---,!6 IQ)l           O I OJ I',\
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                                                                                                      -I oI 01 01 01 01 -I 01 o2S1014
~'20' W I* o l o I o I o I* t!J@* L!U@) . W-. 33 S!V 34 3S JS 37 ' 40 41 42
                                                                                                                                                              **
U.S. NUCLEAR REGULA. TORY COMMISSION (PLEASE P~INT OR TYPE ALL REOUIREC INFORMATION) 11 J 1 1111101                     l SSI©
            ;          S      9          L.ICSNSEE COOE              14        7S                          LICENSE NUMBER                         . 25       L.ICENSE TYPE       JO     S7 CAT CON"7
          ~-
7           6
                                        ~;~~~~    LI© I oI s l o l o I oI 21 s 11 60            61                  DOCKET NUMBER                      6S 101. o I s 1 1 I 4 I s I 1 l© I o I 6 I o I s Ls 69     EVENT DATE           74       7S       REPORT OA,     =
I 1 10 BO EVENT DESCRIPTION AND PR06ASLE CONSEQUENCES@
I     With Unit No. 2 at 100% power, PT-27C revealed* that amn readino for heat tracing
        .III!]. J Panel 9, circuit 20C, was below the acceptance criteria stipulated in the PT.                                                                                                           This
([II] I                   event is contrary to T.S. 3.2.B.5                                                   and is reportable per                 T.s:       6.6.2.b(2) .. ~he
[TI]]           _I     redundant. heat tracing circuit was operable, therefore, the health* and safety of the                                                                                       J ..
[£I[] I                 public were not affected, IITil L.....------------------------------------___..
wIJ 7           B     9                                                                                                                                                                                 BO SYSTSM                 CAUSE                 CAUSE                                                       COMP.          VALVE
                                                                                  , El@ liJ@ , H, E, A, T, E, R,e CODE                    CODE              SUBCOOE                    COMPONENT CODE                SUBCOOE          SUBCOOE
        . rrm
            '          8 9
                                                      !S IHI@    10              11                 12                 13                           18 W
19 w@
20 SEQUENTIAL                           OCCURRENCE           REPORT                          REVISION C\        LER/RO LVENT YEAR                                                REPORT NO,                               cooe               TYPE                            NO.
                              \!..:.J  REPORT NUMBEFI I I !
21 8 1 22 I o I 21 2126 24
                                                                                                                                  *I ,I 27 Io 28 I 3 29I          lliJ 30 1:=l 31 w
32 ACTION       l'UTURE               EF;:ECT             *SHUTOOWN                                 ~      ATTACHMENT         NPRc-4         PRIMECOMP.               COMPONENT TAKEN         ACTION               ON PLANT                 METHOD                 .       HOURS ~        SUBMITTED       FORMliUB.         SUPPI.IER             MANUl'ACTURER       ',.-, ,.,, '
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                        . 33            S!V 34
                                                                  ~'20' 3S      ~
W JS I* o l o I o I o I* t!J@* L!U@) . W- *-l*T *l l'*Ws.j s!@.
37       '             40   41             42
* 43
* 43
* CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @ D:I]J j The loss of heat tracing was aue to excessive heat. The defective heat trac;n2 was o:::IIJ replaced and tested. A design change has been initiated tq change tbe manner by !III! which these borated lines are heat traced. I 1-., _____________
* 44        ,,
__:._~;:.;;..;;~-------------------
* 47      ..
o:TIJ l..l -------------------------------------.-J t!El ., 8 9 FACILITY '3Q1 . STATUS % POWER OTHER STATUS \:::::) 1ITI1 -~@ .1 1 I O I O '"""'' __ N.;.../ A ___ __ 8 9 10 1:Z 13 '4 ACTIVITY CONTENT IC\ . RELEASED OF RELEASE AMOUNT OF ACTIVITY [2EI Ll.l@ W@I , N/A , a 9 10 11 7 METHOOOF . A DISCOVERY OISCO~ERY DESCRIPTION
CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS                                         @
-~ W@I Routine Test. 45 46 N/A ,LOCATIO~
D:I]J j               The loss of heat tracing was aue to excessive heat. The defective heat                                                                                 trac;n2 was o:::IIJ                 replaced and tested.                                   A design change has been initiated tq                                     change       tbe manner by which these borated lines are heat traced.                                                                                                                                     I
OF RELEASE 80 PERSONNEL EXPOSURES Q i NUMBER t:::;\ TYPE~ DESCRIPTION I!'' EITI J, 0 I O I O lLl.J~I..----*
            !III!              1-.,_ _ _ _ _ _ _ _ _ _ _ _ __ _ : . _ ~ ; : . ; ; . . ; ; ~ - - - - - - - - - - - - - - - - - - -
_..;,;N~/A~--------------------"' , a 9 , , 12 1: so . PERSONNEi.
o:TIJ -------------------------------------.-J l..l
INJURIES :.,* ,, I\IUMBER' CESCRll'TION6 . ETIJ _.I O IO IO !@1.-.. _____ ...;;~.;,:..~/A~-----------------,-~ . , a s
          .,
* 11 12 110 .* , ..*... ,, *" ,, .* ,.,, '*l:.OSS"OF OR DAMAGE TO FAC:11..ITY t:::'13 . .TYPE . DESCRIPTION : 13}3* L~J@1--. __ . _______ r....;.~/_A
t!El8 9
____________________ * , ..
          .
* a s* 10 so *
FACILITY STATUS               % POWER                                 OTHER STATUS \:::::)
* PUBLICITY C\ NRC USE ONLY * **** : .* ISSUEOQ DESCRIPTION~  
                                                                                                                '3Q1        METHOOOF                                                        . A DISCOVERY                          OISCO~ERY DESCRIPTION - ~
., Im] LEJ~----------~N_/A=--------------
1ITI1 -~@ .1 1 I O I O '"""''__N.;.../A_ _ ___ W@I 7          8     9                 10                 1:Z     13                                         '4     45        46 Routine Test.
I l I l *l I l I l l I I I ! . 7 S 9 10 . 68 6S 80 ; ~AME OF P=e? ARER _..;:J'=..*;....:L:.:.*
ACTIVITY           CONTENT                                                         IC\
_W=i=l-=s=o=n:.....
                    . RELEASED OF RELEASE                               AMOUNT OF ACTIVITY ~                                                              ,LOCATIO~ OF RELEASE
________ _ (804) 357~3184
[2EI Ll.l@ W@I                                                                 , N/A                                             N/A
* ATTACHMENT 1 SURRY POWER STATION, UNIT No. 2 DOCKET NO: 50-281 REPORT NO: 81-022/03L-0 EVENT DATE: 05-14-81 TITLE OF EVENT: HEAT TRACING FAILURE 1. DESCRIPTION OF EVENT:
            ,         a       9               10           11                                                                                                                                               80 PERSONNEL EXPOSURES                                       Q NUMBER         t:::;\ TYPE~ DESCRIPTION                   ~
* With Unit No. 2 at 100% power, PT-27C revealed that the amp reading for heat tracing Panel 9, circuit 20C (".C" BAST recirc. line), was below the acceptance criteria stipulated in the PT. This event is contrary to Technical Specification 3.2.B.5, and is reportable per Technical Specification 6.6.2.b(2).
'         EITI
: 2. PROBABLE CONSEQUENCES and STATUS of REDUNDANT EQUIPMENT:
          ,          a 9 J, 0 I OI O, ,lLl.J~I..----*
12            1:
_ . . ; , ; N ~ / A ~ - - - - - - - - - - - - - - - - - - - - "so'
                    .               PERSONNEi. INJURIES                      ~
:.,*   ,,         I\IUMBER'             CESCRll'TION6
    .. ETIJ,          a s
_.I OIO
* IO 11!@1.-.. 12
_ _ _ _ _...;;~.;,:..~/A~-----------------,-~                                                                                                 110
, ..*... ,, *" ,, .*,.,, '*l:.OSS"OF OR DAMAGE TO FAC:11..ITY                 t:::'13
                    .         .TYPE . DESCRIPTION                             ~
: 13}3* L~J@1--.__                                 . _______r....;.~/_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~
    * , ..
* a s*                           10                                                                                                                                                                 so
                *
* PUBLICITY               C\                                                                                                                           NRC   USE   ONLY
    * ****       :       .* ISSUEOQ DESCRIPTION~                                                                                                                                                                   .,
    .
Im]
7          S 9 LEJ           10 .
                                                  ~ - - - - - - - - - - ~ N _ / A = - - - - - - - - - - - - - -68 6SI l                                                                   I l *l I l I l l I I 80I !;
                                              ~AME OF P=e? ARER               _..;:J'=..*;....:L:.:.*_W=i=l-=s=o=n:....._________                                          (804) 357~3184                           ~
 
ATTACHMENT 1 SURRY POWER STATION, UNIT No. 2
                                                                    *
* DOCKET NO:                 50-281 REPORT NO:                 81-022/03L-0 EVENT DATE:               05-14-81 TITLE OF EVENT:               HEAT TRACING FAILURE
                                                                      ~
: 1.         DESCRIPTION OF EVENT:
With Unit No. 2 at 100% power, PT-27C revealed that the amp reading for heat tracing Panel 9, circuit 20C (".C" BAST recirc. line), was below the acceptance criteria stipulated in the PT. This event is contrary to Technical Specification 3.2.B.5, and is reportable per Technical Specification 6.6.2.b(2).
: 2.         PROBABLE CONSEQUENCES and STATUS of REDUNDANT EQUIPMENT:
The heat tracing circuits are intended to maintain a fluid temperature above that needed for flow. The redundant heat tracing.circuit was operable, therefore, the health and safety of the public were not affected.
The heat tracing circuits are intended to maintain a fluid temperature above that needed for flow. The redundant heat tracing.circuit was operable, therefore, the health and safety of the public were not affected.
: 3. CAUSE: The loss o:1; heat tracing was due to excessive heat. 4. U1MEDIATK CORRECTIVE ACTION: The irrnnediate corrective action was to verify that the redundant circuit was operable.
: 3.         CAUSE:
: 5. SUBSEQUENT CORRECTIVE ACTION: The defective heat tracing tape-was** replaced and tested within the time span specified by Technical Specifications.
The loss o:1; heat tracing was due to excessive heat.
: 6. ACTION TAKEN TO PREVENT RECURRENCE:
: 4.         U1MEDIATK CORRECTIVE ACTION:
The irrnnediate corrective action was to verify that the redundant circuit was operable.
: 5.         SUBSEQUENT CORRECTIVE ACTION:
The defective heat tracing tape- was** replaced and tested within the time span specified by Technical Specifications.
: 6.         ACTION TAKEN TO PREVENT RECURRENCE:
No additional actions were deemed necessary.
No additional actions were deemed necessary.
: 7. GENERIC IMPLICATIONS:
: 7.         GENERIC IMPLICATIONS:
A task force has reviewed the total spectrum of the Heat Tracing system and a Design Change is being prepared as a result of the Task Force's study. Long lead items are being procured.  
A task force has reviewed the total spectrum of the Heat Tracing system and a Design Change is being prepared as a result of the Task Force's study.
*.:..:~~.:;._.::._  
Long lead items are being procured.
..... ---:--~----,,. . . --. . *-. . . --____ j
*.:..:~~.:;._.::._ ..... -- -:- -~- - - -,,. .. - -. . *- .   .             .
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*:e.ode -~\\*-~;:iP-. --... ;-; '.:.:-~ ,,;,:<',4*;;',.:;;<*:'.",:,, ;;:-~"""='. , .. ,.,. .. *.:..12. l4. . Componen_t 0.code l5. Component -sti.bcoae  
 
-**:.-* . .l6. Valve -subcode. . -*-:c: . .;;. 18. Action taken c.. 19. Future action I-20. Effect on plant i* 21. Shutdown method c:::-22. Hours 0 23. Attachments  
                                                                                                      ,':..
-* -**-----24. *.25., .. --::-,-*.:  
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                                                                                      *...>.... -
.. ;--.:--.. --*.~~-..:..-.--.~~~_. . ....=___.  
::11~ *.:.:-System *:e.ode -~\\*-     ~;:iP-. ~ s~~                                            - -... ;-; '.:.:-~ ,,;,:<',4*;;',.:;;<*:'.",:,,                     ;;:-~"""='. , .. ,.,. ..
-.-:*..:*.'.:..~(::'.(:'=\.--::  
  *.:..12.
.. : *-* NPRD Form ;ir,~-h:l:v~ . I -'{I Prime component supplier -;G, ~-26. Component manufacturers  
l4. . Componen_t .code 0
-'--tR(2. v'LM 28. 31. s k,; . ~----Method of discovery Q 0_ v, 1 ..... E l I . Facility status 33. Activity -:released  
l5. Component -sti.bcoae
-34. Contents of .release 35. Amount of activity
                                          -**:.-*.
* 38. Personnel exposure type 42. Type damage/loss L}}
    .l6. Valve -subcode.   .-*-:c:..;;.
: 18. Action taken       c..
: 19. Future action         I-
: 20. Effect on plant         ~                                                                                                              i*
: 21. Shutdown method           c:::-
: 22. Hours               0
: 23. Attachments
                                                                                                                                                                                  -*       -**-----
: 24. NPRD Form                              .. - -::-,-*.: ~*' -                                                                             , -r . ..:?     .
                                                                                                                                                --*.~~-..:..-.--.~~~_......=___.
                                                                                                                                                                                  --*_;,-.:..;-- .:-- ~..
                                                                                                                                                                                    -.-:*..:*.'.:..~(::'.(:'=\.--::.. : *-*
    *.25., Prime component supplier                -;G, ~- ;ir,~-h:l:v~ I - ~  '{I
                                                                                    .
: 26. Component manufacturers               -'--tR(2. v'LM ~
: 28. Facility status s k,; ~ . ~----
: 31. Method of discovery                   Q   0_   v , 1 ..... E       l ~I               .
  -  33.
34.
Activity -:released Contents of .release
: 35. Amount of activity
* 38. Personnel exposure type
: 42. Type damage/loss L}}

Revision as of 03:12, 21 October 2019

LER 81-022/03L-0:on 810514,amp Reading for Heat Tracing Panel 9,circuit 20C,found Below Acceptance Criteria.Caused by Excessive Heat.Tracing Replaced & Tested.Design Change Initiated
ML18139B388
Person / Time
Site: Surry  Dominion icon.png
Issue date: 06/05/1981
From: Joshua Wilson
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139B384 List:
References
LER-81-022-03L-01, LER-81-22-3L-1, NUDOCS 8106090559
Download: ML18139B388 (3)
v • d • e


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U.S. NUCLEAR REGULA. TORY COMMISSION (PLEASE P~INT OR TYPE ALL REOUIREC INFORMATION) 11 J 1 1111101 l SSI©

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~;~~~~ LI© I oI s l o l o I oI 21 s 11 60 61 DOCKET NUMBER 6S 101. o I s 1 1 I 4 I s I 1 l© I o I 6 I o I s Ls 69 EVENT DATE 74 7S REPORT OA, =

I 1 10 BO EVENT DESCRIPTION AND PR06ASLE CONSEQUENCES@

I With Unit No. 2 at 100% power, PT-27C revealed* that amn readino for heat tracing

.III!]. J Panel 9, circuit 20C, was below the acceptance criteria stipulated in the PT. This

([II] I event is contrary to T.S. 3.2.B.5 and is reportable per T.s: 6.6.2.b(2) .. ~he

[TI]] _I redundant. heat tracing circuit was operable, therefore, the health* and safety of the J ..

[£I[] I public were not affected, IITil L.....------------------------------------___..

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20 SEQUENTIAL OCCURRENCE REPORT REVISION C\ LER/RO LVENT YEAR REPORT NO, cooe TYPE NO.

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21 8 1 22 I o I 21 2126 24

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32 ACTION l'UTURE EF;:ECT *SHUTOOWN ~ ATTACHMENT NPRc-4 PRIMECOMP. COMPONENT TAKEN ACTION ON PLANT METHOD . HOURS ~ SUBMITTED FORMliUB. SUPPI.IER MANUl'ACTURER ',.-, ,.,, '

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CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @

D:I]J j The loss of heat tracing was aue to excessive heat. The defective heat trac;n2 was o:::IIJ replaced and tested. A design change has been initiated tq change tbe manner by which these borated lines are heat traced. I

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FACILITY STATUS  % POWER OTHER STATUS \:::::)

'3Q1 METHOOOF . A DISCOVERY OISCO~ERY DESCRIPTION - ~

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ACTIVITY CONTENT IC\

. RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ ,LOCATIO~ OF RELEASE

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ATTACHMENT 1 SURRY POWER STATION, UNIT No. 2

  • DOCKET NO: 50-281 REPORT NO: 81-022/03L-0 EVENT DATE: 05-14-81 TITLE OF EVENT: HEAT TRACING FAILURE

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1. DESCRIPTION OF EVENT:

With Unit No. 2 at 100% power, PT-27C revealed that the amp reading for heat tracing Panel 9, circuit 20C (".C" BAST recirc. line), was below the acceptance criteria stipulated in the PT. This event is contrary to Technical Specification 3.2.B.5, and is reportable per Technical Specification 6.6.2.b(2).

2. PROBABLE CONSEQUENCES and STATUS of REDUNDANT EQUIPMENT:

The heat tracing circuits are intended to maintain a fluid temperature above that needed for flow. The redundant heat tracing.circuit was operable, therefore, the health and safety of the public were not affected.

3. CAUSE:

The loss o:1; heat tracing was due to excessive heat.

4. U1MEDIATK CORRECTIVE ACTION:

The irrnnediate corrective action was to verify that the redundant circuit was operable.

5. SUBSEQUENT CORRECTIVE ACTION:

The defective heat tracing tape- was** replaced and tested within the time span specified by Technical Specifications.

6. ACTION TAKEN TO PREVENT RECURRENCE:

No additional actions were deemed necessary.

7. GENERIC IMPLICATIONS:

A task force has reviewed the total spectrum of the Heat Tracing system and a Design Change is being prepared as a result of the Task Force's study.

Long lead items are being procured.

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l4. . Componen_t .code 0

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18. Action taken c..
19. Future action I-
20. Effect on plant ~ i*
21. Shutdown method c:::-
22. Hours 0
23. Attachments

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24. NPRD Form .. - -::-,-*.: ~*' - , -r . ..:? .

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28. Facility status s k,; ~ . ~----
31. Method of discovery Q 0_ v , 1 ..... E l ~I .

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34.

Activity -:released Contents of .release

35. Amount of activity
  • 38. Personnel exposure type
42. Type damage/loss L
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