ML18346A247: Difference between revisions

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-.. ....:.. 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.
(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
.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!
[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@
[]]]]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.
No threat to public health or safety resulted.
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.
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 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
______
______________
--..J 7 B 9 11 12 13 PERSONNEL INJURIES 80 NUMBER r:2:liJ I 01 01 0 l@.___ ________ ........=!N:..:.A
_______________
---J a 9 11 12 LOSS O< OR DAMAGE TO FACILITY t4j\ TYPE DESCRIPTION
\::;I EI2J
____________
NA B 9 10 PUBLICITY C\ NRC USE ONLY 80 BO ISSUED I2I&#xa3;] Ll!..J{&sect;).__
___________
.........,A
________ __. I I I I I I I I I I I I I a 9 10 68 69 BO}}

Revision as of 17:50, 12 September 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-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.

(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

.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!

[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@

[]]]]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.

No threat to public health or safety resulted.

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.

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 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

______

______________

--..J 7 B 9 11 12 13 PERSONNEL INJURIES 80 NUMBER r:2:liJ I 01 01 0 l@.___ ________ ........=!N:..:.A

_______________

---J a 9 11 12 LOSS O< OR DAMAGE TO FACILITY t4j\ TYPE DESCRIPTION

\::;I EI2J

____________

NA B 9 10 PUBLICITY C\ NRC USE ONLY 80 BO ISSUED I2I£] Ll!..J{§).__

___________

.........,A

________ __. I I I I I I I I I I I I I a 9 10 68 69 BO

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