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* UPDATE REPORT PREVIOUS REPORT D~ 5/15/78 Palisades
* UPDATE REPORT PREVIOUS REPORT D~ 5/15/78 Palisades NRC FORM36!i                                                                                                                            U.S. NUCLEAR REGULATORY COMMISSION 11-n1 LICENSEE EVENT REPORT CONTROL BLOCK:            I                                      1G)                      (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1                                      6
* NRC FORM36!i                                                                                                                            U.S. NUCLEAR REGULATORY COMMISSION 11-n1 LICENSEE EVENT REPORT CONTROL BLOCK:            I                                      1G)                      (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1                                      6
     ~          I M I r I P I A IL I 1 101 o I o I ol o I o I o I o I oI o I o Io 1@14 I 1 I                                                          l Il  I 1 101        I I© 7      B  9        LICENSEE CODE              14        ~5
     ~          I M I r I P I A IL I 1 101 o I o I ol o I o I o I o I oI o I o Io 1@14 I 1 I                                                          l Il  I 1 101        I I© 7      B  9        LICENSEE CODE              14        ~5
* LICENSE NUMBER                            25      26      LICENSE TYPE      ~O    57 CAT SB CON'T WIJ                ~~~~~ ~I o 15                            I o I o I oI 2 I 515 l(?)I o I 4 12 11 I 7 I 81@ I 011 I o I 3 I 7 I 9 IG) 7      B                    60            61                  DOCKET NUMBER                    68    69        EVENT DATE            74      75      REPORT DATE        80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES                                      (,0)
* LICENSE NUMBER                            25      26      LICENSE TYPE      ~O    57 CAT SB CON'T WIJ                ~~~~~ ~I o 15                            I o I o I oI 2 I 515 l(?)I o I 4 12 11 I 7 I 81@ I 011 I o I 3 I 7 I 9 IG) 7      B                    60            61                  DOCKET NUMBER                    68    69        EVENT DATE            74      75      REPORT DATE        80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES                                      (,0)
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[]JI] 1 valve can provide containment integrity, this event is                                                                                      deem~d        to have had I          I I
[]JI] 1 valve can provide containment integrity, this event is                                                                                      deem~d        to have had I          I I
I I
I I
(]]]] I no adverse effect on public health or safety.                                                                                                                                I  I
(]]]] I no adverse effect on public health or safety.                                                                                                                                I  I 7      8 9                                                                                                                                                                          80 SYSTEM                  CAUSE            CAUSE                                                          COMP.        VALVE CODE                    CODE          SUBCODE                      COMPONENT CODE                  . SUB CODE      SUBCODE
                                                                                                                                                                                            . !
7      8 9                                                                                                                                                                          80 SYSTEM                  CAUSE            CAUSE                                                          COMP.        VALVE CODE                    CODE          SUBCODE                      COMPONENT CODE                  . SUB CODE      SUBCODE
[ill]                          I SID I@ LI@ [!j@ I z1z I z1z 1z1z 1@ ~@ ~@
[ill]                          I SID I@ LI@ [!j@ I z1z I z1z 1z1z 1@ ~@ ~@
7      8                      9 .        10              11              12                13                                18        19            20 SEQUENTIAL                              OCCURRENCE          REPORT                    REVISION r.::..
7      8                      9 .        10              11              12                13                                18        19            20 SEQUENTIAL                              OCCURRENCE          REPORT                    REVISION r.::..
* LER/AO LVENTYEAA                                          REPORT NO.                                  COOE              TYPE                      NO.
LER/AO LVENTYEAA                                          REPORT NO.                                  COOE              TYPE                      NO.
                 ~      REPORT NUMBER I7 I 8 I                    I    I        I o11 I 31                  I.....-1        I28o I 1129          W            l=I          11..J 21          22              23              24                26        27                                  30            31          32 ACTION    FUTURE              EFFECT                SHUTDOWN                              ~        ATTACHMENT        NPA04        PRIME COMP.          COMPONENT TAKEN      ACTION            ON PLANT                METHOD                      HOURS    ~          SUBMITTED        FOAM sue.      SUPPLIER          MANUFACTURER Lll@L!J@                      ~@                    ~              I o 10 Io I o40I L!J@                        __ 42 W@              L2J@          1z 19 19 19 I@
                 ~      REPORT NUMBER I7 I 8 I                    I    I        I o11 I 31                  I.....-1        I28o I 1129          W            l=I          11..J 21          22              23              24                26        27                                  30            31          32 ACTION    FUTURE              EFFECT                SHUTDOWN                              ~        ATTACHMENT        NPA04        PRIME COMP.          COMPONENT TAKEN      ACTION            ON PLANT                METHOD                      HOURS    ~          SUBMITTED        FOAM sue.      SUPPLIER          MANUFACTURER Lll@L!J@                      ~@                    ~              I o 10 Io I o40I L!J@                        __ 42 W@              L2J@          1z 19 19 19 I@
33          34                35.              . - 36              37                                41        .                      43            44            47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS                                @
33          34                35.              . - 36              37                                41        .                      43            44            47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS                                @
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7      8  9                11      12                                                                                                                                            80 LOSS O~ OR DAMAGE TO FACILITY                14:i\
7      8  9                11      12                                                                                                                                            80 LOSS O~ OR DAMAGE TO FACILITY                14:i\
                                                             '.:::::J
                                                             '.:::::J
*
(!]2J      TYPE        DESCRIPTION L!J@).._._N~/A          ______________________________________________________.
(!]2J      TYPE        DESCRIPTION L!J@).._._N~/A          ______________________________________________________.
I 7I so 7      8  9 ISSUED~
I 7I so 7      8  9 ISSUED~
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Attachment to Licensee Event Report 78-013-01-X-l Consumers Power Company
Attachment to Licensee Event Report 78-013-01-X-l Consumers Power Company
                                                   ~*.-                          .,
                                                   ~*.-                          .,
                                                                                    '
Palisades Nuclear Plant Docket 50-255 During p rformance of CRDM main enance on April 21, 1978, the manually-operated valve whi    supplies air to the  ntainment building was opened in order to provide br thing air to the repai en performing the maintenance. \Opening this valve breach d containment integrit as defined by Technical Specifi~tion 1.4.a.
* Palisades Nuclear Plant Docket 50-255 During p rformance of CRDM main enance on April 21, 1978, the manually-operated valve whi    supplies air to the  ntainment building was opened in order to provide br thing air to the repai en performing the maintenance. \Opening this valve breach d containment integrit as defined by Technical Specifi~tion 1.4.a.
Because the re ctor was in the hot sh ~down condition, the Limiting Cd~i  ti on for Operation o Technical Specificatio'h 3.6.1.a was exceeded.
Because the re ctor was in the hot sh ~down condition, the Limiting Cd~i  ti on for Operation o Technical Specificatio'h 3.6.1.a was exceeded.
Intermittent openi    of the service air val    has been analyzed in the F    ,
Intermittent openi    of the service air val    has been analyzed in the F    ,
Line 69: Line 64:
The Combustion Enginee ing Standard Technical S*ecifications also permit o of selected containment 'solation valves provide adequate administrative occurrence              oversight of supervisory              In order stre* then administrative cont ls over the opening of                air valve,.
The Combustion Enginee ing Standard Technical S*ecifications also permit o of selected containment 'solation valves provide adequate administrative occurrence              oversight of supervisory              In order stre* then administrative cont ls over the opening of                air valve,.
and t                              of containment integrity equirements as app 'ed tion valves, a status boa  notation will be made to of contai ent isolation valves whi      do not meet the require Specificat n 1.4. Appropriate trainx g will be conducted and      ocedure revisions made to ass          personnel will unde tand and comply with these requirements *
and t                              of containment integrity equirements as app 'ed tion valves, a status boa  notation will be made to of contai ent isolation valves whi      do not meet the require Specificat n 1.4. Appropriate trainx g will be conducted and      ocedure revisions made to ass          personnel will unde tand and comply with these requirements *
                                                                                      *
                                                                                      *


~-
~-
  .
Attachment to Licensee Event Report 78-013-01-X-l Consumers Power Company Palisa~s N~"Clear Plant Docket 50-255.
* Attachment to Licensee Event Report 78-013-01-X-l Consumers Power Company Palisa~s N~"Clear Plant
                                                          *                    ..
                                                                                    .. '
Docket 50-255.
During performance of CRDM maintenance on April 21, 1978, the manually-operated valve which* supplies air to the containment building was opened in order to provide breathing air to the repairmen performing the maintenance. Opening this valve breached containment integrity as defined by Technical Specification 1.4.a.
During performance of CRDM maintenance on April 21, 1978, the manually-operated valve which* supplies air to the containment building was opened in order to provide breathing air to the repairmen performing the maintenance. Opening this valve breached containment integrity as defined by Technical Specification 1.4.a.
Because the reactor was in the hot shutdown condition, the Limiting Condition for Operation of Technical Specification 3.6.1.a was exceeded.
Because the reactor was in the hot shutdown condition, the Limiting Condition for Operation of Technical Specification 3.6.1.a was exceeded.

Revision as of 14:04, 3 February 2020

LER 78-013/01X-1 on 780421:containment Bldg Air Valve Was Opened During Hot Shutdown Resulting in a Breach of Containment Integrity,Caused by Personnel Error.Notice Posted & Personnel Instructed Re Proper Procedures
ML18043A381
Person / Time
Site: Palisades Entergy icon.png
Issue date: 01/03/1979
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML18043A380 List:
References
LER-78-013-01X, LER-78-13-1X, NUDOCS 7901100179
Download: ML18043A381 (3)
v • d • e


Text

....

  • UPDATE REPORT PREVIOUS REPORT D~ 5/15/78 Palisades NRC FORM36!i U.S. NUCLEAR REGULATORY COMMISSION 11-n1 LICENSEE EVENT REPORT CONTROL BLOCK: I 1G) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

~ I M I r I P I A IL I 1 101 o I o I ol o I o I o I o I oI o I o Io 1@14 I 1 I l Il I 1 101 I I© 7 B 9 LICENSEE CODE 14 ~5

  • LICENSE NUMBER 25 26 LICENSE TYPE ~O 57 CAT SB CON'T WIJ ~~~~~ ~I o 15 I o I o I oI 2 I 515 l(?)I o I 4 12 11 I 7 I 81@ I 011 I o I 3 I 7 I 9 IG) 7 B 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (,0)

[]JI] I During performance of CRDM maintenance, the valve supplying service air

  • to the containment building was opened in order to provide breathing air to the repairmen. Opening this valve breached containment integrity (T.S.I l.4a), and since the reactor was in hot shutdown, the LCO of T.S. 3.6.la was exceeded. Because a check valve in series with the manual isolation

[]JI] 1 valve can provide containment integrity, this event is deem~d to have had I I I

I I

(]]]] I no adverse effect on public health or safety. I I 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE . SUB CODE SUBCODE

[ill] I SID I@ LI@ [!j@ I z1z I z1z 1z1z 1@ ~@ ~@

7 8 9 . 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION r.::..

LER/AO LVENTYEAA REPORT NO. COOE TYPE NO.

~ REPORT NUMBER I7 I 8 I I I I o11 I 31 I.....-1 I28o I 1129 W l=I 11..J 21 22 23 24 26 27 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPA04 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FOAM sue. SUPPLIER MANUFACTURER Lll@L!J@ ~@ ~ I o 10 Io I o40I L!J@ __ 42 W@ L2J@ 1z 19 19 19 I@

33 34 35. . - 36 37 41 . 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

DJ]] I This event was caused by personnel oversight. T,o prevent recurrence, the Control Room status board will be used to note the condition of contain-ment isolation valves which do not meet the re~uirements of TS 1.4.

Personnel will be instructed and procedure changes made to assure that OJI] 11...-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~---i the status board is properly used.

[TI!]

7 8 9 BO

~~un STATUS  % POWER OTHER STATUS

~

l.:::;:I M~OO~

DISCOVERY DISCOVERY DESCRIPTION ~

A

[JTIJ 7 B 1..£.J 9

I 01 0 I 01@1 N/A 10 12 13 44 I ~~~l~O~p_e_r_a_t_o_r~O_b_s_e_r_v_a_t_i_*o_n~~~~~~---i 45 46 80 ACTIVITY CONTENT ~

RELEASED OF RELEASE I AMOUNT OF ACTIVITY LOCATION OF RELEASE @

!ill] i.£J@ l..E@I NA . I N/A 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES f.::\

ONUM~EA  ?(.;'.;\ TY!t (':;;:;., DES<J.(fiXON rr:I2]

7 8 9 I I I Je,tl..::J~.._~~~~~~~~~~~~~~~~~~~~~~~~~

11 12 13 80 PERSONNEL INJURIES ~

NUMBER DESCAIPTION6 o::IT] lol bl d@)~N~A.....__ _________________________________________________.

7 8 9 11 12 80 LOSS O~ OR DAMAGE TO FACILITY 14:i\

'.:::::J

(!]2J TYPE DESCRIPTION L!J@).._._N~/A ______________________________________________________.

I 7I so 7 8 9 ISSUED~

10 PUBLICITY DESCR1710N C\

~

7 10 I (0 0 NRC USE ONLY fil§J 7 8 9 W610I...._N-'-A-------*--------~68 69I I I I I I I I I I I I80I

Attachment to Licensee Event Report 78-013-01-X-l Consumers Power Company

~*.- .,

Palisades Nuclear Plant Docket 50-255 During p rformance of CRDM main enance on April 21, 1978, the manually-operated valve whi supplies air to the ntainment building was opened in order to provide br thing air to the repai en performing the maintenance. \Opening this valve breach d containment integrit as defined by Technical Specifi~tion 1.4.a.

Because the re ctor was in the hot sh ~down condition, the Limiting Cd~i ti on for Operation o Technical Specificatio'h 3.6.1.a was exceeded.

Intermittent openi of the service air val has been analyzed in the F ,

which states that in equent opening of this lve while at power is perJWssable.

The Combustion Enginee ing Standard Technical S*ecifications also permit o of selected containment 'solation valves provide adequate administrative occurrence oversight of supervisory In order stre* then administrative cont ls over the opening of air valve,.

and t of containment integrity equirements as app 'ed tion valves, a status boa notation will be made to of contai ent isolation valves whi do not meet the require Specificat n 1.4. Appropriate trainx g will be conducted and ocedure revisions made to ass personnel will unde tand and comply with these requirements *

~-

Attachment to Licensee Event Report 78-013-01-X-l Consumers Power Company Palisa~s N~"Clear Plant Docket 50-255.

During performance of CRDM maintenance on April 21, 1978, the manually-operated valve which* supplies air to the containment building was opened in order to provide breathing air to the repairmen performing the maintenance. Opening this valve breached containment integrity as defined by Technical Specification 1.4.a.

Because the reactor was in the hot shutdown condition, the Limiting Condition for Operation of Technical Specification 3.6.1.a was exceeded.

Intermittent opening of the service air valve has been analyzed in the FS.AR, which states that infrequent opening of this valve while at power is permissable.

The Combustion Engineering Standard Technical Specifications also permit opening of selected containment isolation valves provided adequate administrative controls exist.

This occurrence was caused by oversight of supervisory personnel.* In order to strengthen administrative controls over the opening of the service air valve,.

and to prevent future violations of containment integrity requirements as applied to isolation valves, a status board notation will be made to note the condition of containment isolation valves which do not meet the requirements of Technical Specification 1. 4. Appropriate training will .be conducted and procedure revisions made to assure that personnel will understand and comply with these requirements.

  • ...__. _.*
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