ML18346A247: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(2 intermediate revisions by the same user not shown)
Line 16: Line 16:


=Text=
=Text=
{{#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
\~}}

Latest revision as of 03:55, 17 March 2020

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)


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

\~