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{{#Wiki_filter:,. consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
{{#Wiki_filter:,.                                                           8 0052006 91 consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
* Area Code 517 788-0550 May 14, 1980 Mr James G Keppler Office of Inspection  
* Area Code 517 788-0550 May 14, 1980 Mr James G Keppler Office of Inspection & Enforcement Region III U S Nuclear Regulatory Commission 199 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LICENSEE EVENT REPORT 80-011 - IMPROPER RETURN-TO-SERVICE OF PORV's On the reverse side is Licensee Event Report 80-011 which is reportable under Technical Specification 6.9.2.B.3 and 3.1.8.
& Enforcement Region III U S Nuclear Regulatory Commission 199 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -LICENSEE EVENT REPORT 80-011 -IMPROPER TO-SERVICE OF PORV's 8 0052006 91 On the reverse side is Licensee Event Report 80-011 which is reportable under Technical Specification 6.9.2.B.3 and 3.1.8. David P Hoffman (Signed) David P Hoffman Nuclear Licensing Administrator CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector  
David P Hoffman (Signed)
-Palisades
David P Hoffman Nuclear Licensing Administrator CC   Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector - Palisades
* PALISADES PLANT NRC FORM 366 (7-77) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: .... I CD 1 6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 8 I M I I I p I A I L I 1 101 0 I 0 I -I 0 I 0 I 0 I 0 I 0 I -10 9 LICENSEE CODE 14 LICENSE NUMBER 1°101411l1l1l1l©I I I@ 26 LICENSE TYPE 30 57 CAT 58 CON'T [ill] 7 B LLJ© I o 15 I o I o Io I 2 I 5 I 5 101 a 60 61 DOCKET NUMBER 68 69 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
 
I 4 h I E1 s I ol©lo I 5 I 1 I 41 s I a 10 EVENT DATE 74 75 REPORT DATE BO I Following modifications to PORV power supplies, the valves were stroked perf C2:IfJ test procedure and declared operable.
                                                                                                                                                                                  --
However, because required ad-CQID ministrative reviews of the modification package had not been completed,thel
NRC FORM 366
[Q]]] fORVs should not have been declared operable.
* PALISADES PLANT U.S. NUCLEAR REGULATORY COMMISSION (7-77)
Subsequent administrative rej [QJ:[] fiews revealed no discrepancies in the modification package; therefore, the I were capable of performing their intended safety function during []]]] IDeriod in question.
LICENSEE EVENT REPORT I
Tech Spec 3.1.8 and Tech Spec 6.9.2.B.3 apply. 8 9 [ill] 7 8 SYSTEM CODE le I JI@ 9 10 CAUSE CAUSE COMP. VALVE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE w@ w@ IZ lzlz IZI ZIZ I@ 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT r:;., LER/RO CVENT YEAR REPORT NO. CODE TYPE 18 21 Io 22 1 I I I o I l I l I I .....-1 I o I 3 I l1.J I I 23 24 26 27 28 29 30 31 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. REVISION, NO. LQJ 32 COMPONENT MANUFACTURER I 80 --TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER LHJ@W@ LI@ W I 01 g 01 01 !Ll@ l!J@ l]J@) 33 34 35 36 37 40 41 42 43 I z I 919 I 91@ CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ 44 47 of administrative review requirements by plant management 1JJJJ (Personnel.
CONTROL BLOCK: ...._,___.__~_.__,.__...JI 1                                 6 CD                  (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
Upon discovery
~8 I9 MI I LICENSEE 7
(-"'-' 24 hours after test completion) one valve was I [IJ:lJ open to satisfy T/S 3.1.8 requirements.
I p I A I L I 1 101 0 I 0I - I 0 I 0I 0 I 0 I 0 I - 10 1°101411l1l1l1l©I I I@
Management personnel involv 1 o::IIJ jed have reviewed administrative requirements related to returning safety-ITJI] !related systems to service. a 9 FACILITY '3Q\ STATUS % POWER OTHER STATUS [Iill ill....I I 0 I 0 I 0 l@)I .... _N_A ____ a 9 10 12 13 44 ACTIVITY CONTENT t:::;\ RELEASED OF RELEASE AMOUNT OF ACTIVITY 12::0 lzJ @ W@'-'I N=A=---______ _. 7 a 9 10 11 44 PERSONNEL EXPOSURES Q., METHOD OF DISCOVERY W@I Review 45 . 46 NA 45 BO DISCOVERY DESCRIPTION 80 LOCATION OF RELEASE @ 80 NUMBER DESCRIPTION fil7.J lo I 0 I
CODE          14    ~5                      LICENSE NUMBER                        ~5      26       LICENSE TYPE 30       57 CAT 58 CON'T
______________________
[ill]
_J 7 8 9 11 12 13 PERSONNEL INJURIES Q 80 NUMBER E:TIJ lo I olo
7     B
_______________________
                  ~~~~~      LLJ© I o 15 60            61 I oDOCKET I o Io   I 2 I5 I 5 6810169a I 4EVENT NUMBER h I E1 s I ol©lo I 5 I 1 I 41 s I a 10 DATE             74       75     REPORT DATE     BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
-----1 1 a 9 11 12 LOSS OF OR DAMAGE TO FACILITY t4:J'I TYPE DESCRIPTION i.::::J 80 [2TIJ NA 7 a 9 PUBLICITY Q\ ISSUED(,;\
I Following modifications to PORV power supplies, the valves were stroked perf C2:IfJ       ~re-op        test procedure and declared operable. However, because required ad-CQID ministrative reviews of the modification package had not been completed,thel
NRC USE ONLY u::I£J 1..!.Jei NA I I I I I I I I I I I I I 1 a 91 *o------------------------------l6B 69 BO}}
[Q]]] fORVs should not have been declared operable. Subsequent administrative rej
[QJ:[] fiews revealed no discrepancies in the modification package; therefore, the I
~ ~alves                    were capable of performing their intended safety function during
[]]]] IDeriod in question.                                     Tech Spec 3.1.8 and Tech Spec 6.9.2.B.3 apply.                                                                 I 8 9                                                                                                                                                                   80 SYSTEM           CAUSE           CAUSE                                                           COMP.         VALVE CODE             CODE        SUBCODE                   COMPONENT CODE                       SUBCODE         SUBCODE
[ill]                          le I JI@ w@ w@ IZ lzlz IZI ZIZ I@ ~ ~@
7      8                      9          10          11             12             13                               18           19             20 SEQUENTIAL                             OCCURRENCE             REPORT                   REVISION, r:;.,   LER/RO CVENT YEAR                                   REPORT NO.                                 CODE                 TYPE                   NO.
            ~ ~~~~~~            1821 Io 221            I I 23 I o I l Il I 24            26 I.....-1 27 I oI 3 I 28        29 l1.J 30 I I 31 LQJ 32 ACTION     FUTURE               EFFECT           SHUTDOWN                           ~          ATTACHMENT         NPRD-4         PRIME COMP.       COMPONENT TAKEN     ACTION             ON PLANT           METHOD                   HOURS ~              SUBMITTED       FORM SUB.           SUPPLIER         MANUFACTURER LHJ@W@ LI@
33        34                  35 W
36 I 01 g 01 37 01 40
                                                                                                              !Ll@
41 l!J@
42 l]J@)
43 I z I 919 I 91@
44            47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS                           @
            ~isunderstanding                        of administrative review requirements by plant management 1JJJJ (Personnel.                         Upon discovery (-"'-' 24 hours after test completion) one valve was I
[IJ:lJ       ~agged          open to satisfy T/S 3.1.8 requirements.                                                       Management personnel involv1 o::IIJ jed have reviewed administrative requirements related to returning safety-ITJI] !related systems to service.
a     9                                                                                                                                                               BO
                                                                                '3Q\
FACILITY STATUS             % POWER                         OTHER STATUS     ~
METHOD OF DISCOVERY                                  DISCOVERY DESCRIPTION
[Iill       ill....I I 0 I0            I 0 l@)I...._N_A_ _ _ _~                          W@I Review a   9             10               12     13                               44     45 .          46                                                                80 ACTIVITY       CONTENT                                             t:::;\
RELEASED OF RELEASE                       AMOUNT OF ACTIVITY                                                           LOCATION OF RELEASE      @
12::0a lzJ @ W@'-'IN=A=---_ _ _ _ _ __.
7           9             10           11                                         44           45 NA 80 PERSONNEL EXPOSURES                               Q.,
NUMBER       ~TYPE              DESCRIPTION fil7.J     lo     I0 I     ol0u@~N=A..____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __J 7     8   9               11       12         13                                                                                                                         80 PERSONNEL INJURIES                 Q DESCRIPTION~
E:TIJ       lo NUMBER I olo     l@)~NA;.;._        _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-----1 1     a   9               11       12                                                                                                                                     80 LOSS OF OR DAMAGE TO FACILITY           t4:J'I TYPE       DESCRIPTION                 i.::::J
[2TIJ ~@                  NA 7     a   9           ~lo~--------------------------------------....Jso PUBLICITY               Q\
ISSUED(,;\ DESCRIPTION~                                                                                                                          NRC USE ONLY u::I£Ja 1..!.Jei 1
NA 91*o------------------------------l6B                                                                                                     I I II III III II I 69                     BO}}

Revision as of 10:03, 20 October 2019

License Event Report 1980-011-00 Re Improper Return-to-Service of Porv'S
ML18347B210
Person / Time
Site: Palisades Entergy icon.png
Issue date: 05/14/1980
From: Hoffman D
Consumers Power Co
To: James Keppler
NRC/RGN-III
References
LER 1980-011-00
Download: ML18347B210 (2)
v • d • e


Text

,. 8 0052006 91 consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

  • Area Code 517 788-0550 May 14, 1980 Mr James G Keppler Office of Inspection & Enforcement Region III U S Nuclear Regulatory Commission 199 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LICENSEE EVENT REPORT 80-011 - IMPROPER RETURN-TO-SERVICE OF PORV's On the reverse side is Licensee Event Report 80-011 which is reportable under Technical Specification 6.9.2.B.3 and 3.1.8.

David P Hoffman (Signed)

David P Hoffman Nuclear Licensing Administrator CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector - Palisades

--

NRC FORM 366

  • PALISADES PLANT U.S. NUCLEAR REGULATORY COMMISSION (7-77)

LICENSEE EVENT REPORT I

CONTROL BLOCK: ...._,___.__~_.__,.__...JI 1 6 CD (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~8 I9 MI I LICENSEE 7

I p I A I L I 1 101 0 I 0I - I 0 I 0I 0 I 0 I 0 I - 10 1°101411l1l1l1l©I I I@

CODE 14 ~5 LICENSE NUMBER ~5 26 LICENSE TYPE 30 57 CAT 58 CON'T

[ill]

7 B

~~~~~ LLJ© I o 15 60 61 I oDOCKET I o Io I 2 I5 I 5 6810169a I 4EVENT NUMBER h I E1 s I ol©lo I 5 I 1 I 41 s I a 10 DATE 74 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

I Following modifications to PORV power supplies, the valves were stroked perf C2:IfJ ~re-op test procedure and declared operable. However, because required ad-CQID ministrative reviews of the modification package had not been completed,thel

[Q]]] fORVs should not have been declared operable. Subsequent administrative rej

[QJ:[] fiews revealed no discrepancies in the modification package; therefore, the I

~ ~alves were capable of performing their intended safety function during

[]]]] IDeriod in question. Tech Spec 3.1.8 and Tech Spec 6.9.2.B.3 apply. I 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

[ill] le I JI@ w@ w@ IZ lzlz IZI ZIZ I@ ~ ~@

7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION, r:;., LER/RO CVENT YEAR REPORT NO. CODE TYPE NO.

~ ~~~~~~ 1821 Io 221 I I 23 I o I l Il I 24 26 I.....-1 27 I oI 3 I 28 29 l1.J 30 I I 31 LQJ 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM SUB. SUPPLIER MANUFACTURER LHJ@W@ LI@

33 34 35 W

36 I 01 g 01 37 01 40

!Ll@

41 l!J@

42 l]J@)

43 I z I 919 I 91@

44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

~isunderstanding of administrative review requirements by plant management 1JJJJ (Personnel. Upon discovery (-"'-' 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after test completion) one valve was I

[IJ:lJ ~agged open to satisfy T/S 3.1.8 requirements. Management personnel involv1 o::IIJ jed have reviewed administrative requirements related to returning safety-ITJI] !related systems to service.

a 9 BO

'3Q\

FACILITY STATUS  % POWER OTHER STATUS ~

METHOD OF DISCOVERY DISCOVERY DESCRIPTION

[Iill ill....I I 0 I0 I 0 l@)I...._N_A_ _ _ _~ W@I Review a 9 10 12 13 44 45 . 46 80 ACTIVITY CONTENT t:::;\

RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE @

12::0a lzJ @ W@'-'IN=A=---_ _ _ _ _ __.

7 9 10 11 44 45 NA 80 PERSONNEL EXPOSURES Q.,

NUMBER ~TYPE DESCRIPTION fil7.J lo I0 I ol0u@~N=A..____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __J 7 8 9 11 12 13 80 PERSONNEL INJURIES Q DESCRIPTION~

E:TIJ lo NUMBER I olo l@)~NA;.;._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-----1 1 a 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY t4:J'I TYPE DESCRIPTION i.::::J

[2TIJ ~@ NA 7 a 9 ~lo~--------------------------------------....Jso PUBLICITY Q\

ISSUED(,;\ DESCRIPTION~ NRC USE ONLY u::I£Ja 1..!.Jei 1

NA 91*o------------------------------l6B I I II III III II I 69 BO

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