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{{#Wiki_filter:.
{{#Wiki_filter:- .. ....:..
-.. ....:.. consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 * (517) 788-0550 June 19, 1981 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -LICENSEE EVENT REPORT NO Sl-020 -PCS UNIDENTIFIED LEAKAGE GREATER TH.A..."l'
            . *~-;;;:.
: 1. 0 GPM On the reverse side is Licensee Event Report No 81-20 (PCS Unidentified Leakage Greater Than l.O GPM) which is reportable under Technical Specification 6*.9.2.b.
consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 * (517) 788-0550 June 19, 1981 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR                 PALISADES PLANT - LICENSEE EVENT REPORT NO Sl-020 -
(2). Brian D Johnson Senior Licensing Engineer CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector-Palisades Plant  
PCS UNIDENTIFIED LEAKAGE GREATER TH.A..."l' 1. 0 GPM On the reverse side is Licensee Event Report No 81-20 (PCS Unidentified Leakage Greater Than l.O GPM) which is reportable under Technical Specification 6*.9.2.b. (2).
.2 2 1981 PALISADES NRC FORM 366 (7-771 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: ._I _..__ ........ _.....__..._..._-ii G) 1 6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION!
Brian D Johnson Senior Licensing Engineer CC       Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector-Palisades Plant
[il2J IM Ir I PIA 1111 101olo1-1 olo Iola lo I-lo lo 1014 11111111101 I 10 7 8 9 LICENSEE CODE 14 . LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T WJJ ' a I 5 I o I o I o I 215 I 5 GI o I 5 I 21 2 I a 11 IG)lo I 6 I l I 9 I 8 I i I G) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
                                                                                                            ~JUN .2 2 1981
[]]]]I During normal plant operation, results of daily PCS leak rate calculation!
 
[]]]] I indicated PCS unidentified leak;age to be 8,l)proximately 1.2 gpm which exceeds the limit of TS 3.1.5. Containment entry resulted in finding leak from packing on auxiliary spray line stop valve (CV 2117). Leak r::Q:EJ [QTIJ [ill] [IT2J isolated by closure of isolation valve in leakoff line. Event reportable I per TS 6.9.2.B2.
PALISADES NRC FORM 366                                                                                                                                 U.S. NUCLEAR REGULATORY COMMISSION (7-771 LICENSEE EVENT REPORT CONTROL BLOCK:               ._I_ . . _ _........_.....__..._..._-ii G)                       (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION!
No threat to public health or safety resulted.
1                                            6
ITill 1 a s [ID] 7 B SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE . SUBCODE COMPONENT CODE SUBCODE SUBCODE le I JI@ Ll;J@ L12.J@ Iv !AIL Iv I EIX I@ 112.J@ UJ@ 9 10 11 12 13 1B 19 20 SEQUENTIAL OCCURRENCE REPORT REPORT NO. CODE TYPE I I Io I 2 Io I I /I I o I 31 LlJ 1=l 23 24 26 27 28 29 30 31 r.:;-,, LE RIRO CVENT YEAR l..:.:,J REPORT I 8 I 1 I NUMBER 21 22 REVISION NO. LQ.J 32 COMPONENT BO ACTION FUTURE EFFECT SHUTDOWN r:;::;., ATTACHMENT NPAD-1 PRIME COMP. TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FOAM SUB. SUPPLIER MANUFACTURER Lx.J@W@ Lz.J@ LzJ I ala Io lo I Ll!.J@ LI..1@) lliJ@ 33 34 35 36 37 40 41 42 43 IB 1212 I 0 ' CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ 44 47 . I Leakage attrubuted packing degradation.
[il2J IM Ir I PIA 1111 101olo1-1 olo Iola lo I-lo lo 1014 11111111101                                                                                                             I   10 7       8   9           LICENSEE CODE                 14     . ~5                          LICENSE NUMBER                     25     26     LICENSE TYPE       30   57 CAT 58 CON'T WJJ
Valve scheduled to be repacked IIIT] [ill] [ill] during 1981 refueling outage. 1 a s OTHER STATUS @ FACILITY STATUS % POWER [ill] l_]J@ I 0 I 9 I 3 l@l.___--=N=A
  '       a
___ _. a 9 10 12 13 44 ACTIVITY CONTENT Q._ RELEASED OF RELEASE AMOUNT OF ACTIVITY e [2:EJ Ul@) NA I 7 B 9 10 11 44 PERSONNEL EXPOSURES r:;;:;.., BO METHOD OF (.;::;\ DISCOVERY DISCOVERY DESCRIPTION 45 46 80 LOCATION OF RELEASE@ NA 45 BO NUMBER (.;':;\TYPE DESCRIPTION ITI?J I ol ol
                        ~~~~~~ ~10 I 5 I o I o I I 215 I 5 GI o I 5 I 21 2 I 60            61                  DOCKET NUMBER o                  68    69        EVENT DATE a11    74 IG)lo I 6 I l I 9 I 8 I i IG) 75     REPORT DATE           80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
______
[]]]]I               During normal plant operation, results of daily PCS leak rate calculation!
______________
[]]]] I             indicated PCS unidentified leak;age to be 8,l)proximately 1.2 gpm which r::Q:EJ              exceeds the limit of TS 3.1.5.                                                     Containment entry resulted in finding
--..J 7 B 9 11 12 13 PERSONNEL INJURIES 80 NUMBER r:2:liJ I 01 01 0 l@.___ ________ ........=!N:..:.A
[QTIJ                leak from packing on auxiliary spray line stop valve (CV 2117).                                                                                           Leak
_______________
[ill]                 isolated by closure of isolation valve in leakoff line.                                                                                 Event reportable I
---J a 9 11 12 LOSS O< OR DAMAGE TO FACILITY t4j\ TYPE DESCRIPTION
[IT2J                per TS 6.9.2.B2.                                   No threat to public health or safety resulted.
\::;I EI2J
ITill 1     a   s                                                                                                                                                                               BO SYSTEM                   CAUSE               CAUSE                                                     COMP.         VALVE CODE                     CODE       . SUBCODE                     COMPONENT CODE                   SUBCODE         SUBCODE
____________
[ID]                                le I JI@ Ll;J@ L12.J@ Iv !AIL Iv I EIX I@ 112.J@                                                                           UJ@
NA B 9 10 PUBLICITY C\ NRC USE ONLY 80 BO ISSUED I2I&#xa3;] Ll!..J{&sect;).__
7      B                          9           10               11                 12             13                             1B         19             20 SEQUENTIAL                         OCCURRENCE           REPORT                     REVISION r.:;-,,    LE RIRO CVENT YEAR                                                REPORT NO.                             CODE               TYPE                           NO.
___________
l..:.:,J REPORT NUMBER I 8 I1 I                    I     I           Io I 2 Io I             I/I           I o I 31             LlJ           1=l           LQ.J 21          22                23                 24           26         27           28       29           30           31             32 ACTION FUTURE                       EFFECT                 SHUTDOWN                               r:;::;., ATTACHMENT         NPAD-1         PRIME COMP.             COMPONENT TAKEN         ACTION             ON PLANT                 METHOD                       HOURS   ~        SUBMITTED       FOAM SUB.         SUPPLIER           MANUFACTURER Lx.J@W@
.........,A
33            34 Lz.J@
________ __. I I I I I I I I I I I I I a 9 10 68 69 BO}}
35 LzJ 36 I ala Io lo 40I 37 Ll!.J@
41 LI..1@)
42 lliJ@
43 IB 1212 I 047 44
                                                                                                                                                                                                '.
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS                                         @
I Leakage attrubuted packing degradation.                                                                       Valve scheduled to be repacked during 1981 refueling outage.
IIIT]
[ill]
[ill]
1       a s                                                                                                                                                                                 BO METHOD OF                                                          (.;::;\
FACILITY STATUS                 % POWER                               OTHER STATUS          @        DISCOVERY                              DISCOVERY DESCRIPTION ~
[ill] l_]J@ I 0 I 9 I 3 l@l.___--=N=A_ _ __.                                                              lJLl~l.._~P~C~S"'--"L~e~ak=-~R~a~t~e'--"'C~a=l~cu~l~a~t~i~*o~n""-~~--r a   9                 10               12         13                                   44     45          46                                                                  80 ACTIVITY RELEASED OF RELEASE CONTENT AMOUNT OF ACTIVITY             e Q._
LOCATION OF RELEASE@
[2:EJ Ul@) ~@I                                                          NA                         I                                     NA 7     B   9                 10           11                                                   44           45                                                                        BO PERSONNEL EXPOSURES                                     r:;;:;..,
NUMBER         (.;':;\TYPE         DESCRIPTION ITI?J       I ol ol           ok~_:.,Lz_J@.____ _ _ _ _ _~,,.___ _ _ _ _ _ _ _ _ _ _ _ _ _- - . . J 7       B   9                   11       12           13                                                                                                                                 80 PERSONNEL INJURIES                       ~
NUMBER               DESCRIPTION~.
r:2:liJ I 01             01 0 l@.____ _ _ _ _ _ _ _. . . . =!N:. :.A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _---J a   9                   11       12                                                                                                                                               80 LOSS O< OR DAMAGE TO FACILITY                       t4j\
                                                                  \::;I EI2J       TYPE
              ~@).__
DESCRIPTION
____________NA B   9               10                                                                                                                                                             BO PUBLICITY               C\                                                                                                                       NRC USE ONLY ISSUED           DESCRIPTION~
I2I&#xa3;] Ll!..J{&sect;)._____________. . . . .,A_ _ _ _ _ _ _ ___.                                                                                                     II IIIIIIII II              I a   9             10                                                                                                                             68   69                         BO
\~}}

Revision as of 10:21, 20 October 2019

LER 1981-020-00 for Palisades Nuclear Plant, Pcs Unidentified Leakage Greater than 1.0 Gpm
ML18346A247
Person / Time
Site: Palisades Entergy icon.png
Issue date: 06/19/1981
From: Johnson B
Consumers Power Co
To: James Keppler
NRC/RGN-III
References
LER 1981-020-00
Download: ML18346A247 (2)
v • d • e


Text

- .. ....:..

. *~-;;;:.

consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 * (517) 788-0550 June 19, 1981 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LICENSEE EVENT REPORT NO Sl-020 -

PCS UNIDENTIFIED LEAKAGE GREATER TH.A..."l' 1. 0 GPM On the reverse side is Licensee Event Report No 81-20 (PCS Unidentified Leakage Greater Than l.O GPM) which is reportable under Technical Specification 6*.9.2.b. (2).

Brian D Johnson Senior Licensing Engineer CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector-Palisades Plant

~JUN .2 2 1981

PALISADES NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (7-771 LICENSEE EVENT REPORT CONTROL BLOCK: ._I_ . . _ _........_.....__..._..._-ii G) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION!

1 6

[il2J IM Ir I PIA 1111 101olo1-1 olo Iola lo I-lo lo 1014 11111111101 I 10 7 8 9 LICENSEE CODE 14 . ~5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T WJJ

' a

~~~~~~ ~10 I 5 I o I o I I 215 I 5 GI o I 5 I 21 2 I 60 61 DOCKET NUMBER o 68 69 EVENT DATE a11 74 IG)lo I 6 I l I 9 I 8 I i IG) 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

[]]]]I During normal plant operation, results of daily PCS leak rate calculation!

[]]]] I indicated PCS unidentified leak;age to be 8,l)proximately 1.2 gpm which r::Q:EJ exceeds the limit of TS 3.1.5. Containment entry resulted in finding

[QTIJ leak from packing on auxiliary spray line stop valve (CV 2117). Leak

[ill] isolated by closure of isolation valve in leakoff line. Event reportable I

[IT2J per TS 6.9.2.B2. No threat to public health or safety resulted.

ITill 1 a s BO SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE . SUBCODE COMPONENT CODE SUBCODE SUBCODE

[ID] le I JI@ Ll;J@ L12.J@ Iv !AIL Iv I EIX I@ 112.J@ UJ@

7 B 9 10 11 12 13 1B 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION r.:;-,, LE RIRO CVENT YEAR REPORT NO. CODE TYPE NO.

l..:.:,J REPORT NUMBER I 8 I1 I I I Io I 2 Io I I/I I o I 31 LlJ 1=l LQ.J 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN r:;::;., ATTACHMENT NPAD-1 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FOAM SUB. SUPPLIER MANUFACTURER Lx.J@W@

33 34 Lz.J@

35 LzJ 36 I ala Io lo 40I 37 Ll!.J@

41 LI..1@)

42 lliJ@

43 IB 1212 I 047 44

'.

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

I Leakage attrubuted packing degradation. Valve scheduled to be repacked during 1981 refueling outage.

IIIT]

[ill]

[ill]

1 a s BO METHOD OF (.;::;\

FACILITY STATUS  % POWER OTHER STATUS @ DISCOVERY DISCOVERY DESCRIPTION ~

[ill] l_]J@ I 0 I 9 I 3 l@l.___--=N=A_ _ __. lJLl~l.._~P~C~S"'--"L~e~ak=-~R~a~t~e'--"'C~a=l~cu~l~a~t~i~*o~n""-~~--r a 9 10 12 13 44 45 46 80 ACTIVITY RELEASED OF RELEASE CONTENT AMOUNT OF ACTIVITY e Q._

LOCATION OF RELEASE@

[2:EJ Ul@) ~@I NA I NA 7 B 9 10 11 44 45 BO PERSONNEL EXPOSURES r:;;:;..,

NUMBER (.;':;\TYPE DESCRIPTION ITI?J I ol ol ok~_:.,Lz_J@.____ _ _ _ _ _~,,.___ _ _ _ _ _ _ _ _ _ _ _ _ _- - . . J 7 B 9 11 12 13 80 PERSONNEL INJURIES ~

NUMBER DESCRIPTION~.

r:2:liJ I 01 01 0 l@.____ _ _ _ _ _ _ _. . . . =!N:. :.A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _---J a 9 11 12 80 LOSS O< OR DAMAGE TO FACILITY t4j\

\::;I EI2J TYPE

~@).__

DESCRIPTION

____________NA B 9 10 BO PUBLICITY C\ NRC USE ONLY ISSUED DESCRIPTION~

I2I£] Ll!..J{§)._____________. . . . .,A_ _ _ _ _ _ _ ___. II IIIIIIII II I a 9 10 68 69 BO

\~

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