ML18045A326: Difference between revisions
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~ ~o be lower than permitted by TS 3.16. PS-ldOl-1804 sense containment IT:EJ !pressure and are used to initiate RPS tri us (one switch contact) and SIS/ | ~ ~o be lower than permitted by TS 3.16. PS-ldOl-1804 sense containment IT:EJ !pressure and are used to initiate RPS tri us (one switch contact) and SIS/ | ||
C2:II) pant. isol/cont gpray (other contact). The procedure (RI-04) required | C2:II) pant. isol/cont gpray (other contact). The procedure (RI-04) required | ||
[ | [)))) §etting both switches to operate at less than 5 psig \RPS setpoint I.AW l1JIJ ~S 2.3); whereas ESFAS required setpoint per TS 3.16 is 5.0 to 5.75 psig. | ||
III | III)) ICondH.-ipp did. not preyent EffF' systems f'rom f'imctionjn~ properlv. __J 7 8 9 SC SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE suacoo~ COMPONENT CODE SUB CODE SUBCOCE | ||
[ill] Is IHI@ IJLl@ I z I@ LI IN Is IT IR I u1e L§J@ L~@. | [ill] Is IHI@ IJLl@ I z I@ LI IN Is IT IR I u1e L§J@ L~@. | ||
7 8 9 10 11 12 13 18 19 2C SEQUENTIAL OCCURRENCE REPORT REVISION | 7 8 9 10 11 12 13 18 19 2C SEQUENTIAL OCCURRENCE REPORT REVISION | ||
Line 70: | Line 70: | ||
.........A - - - - - - - - - - - - - - - - - - - - - - - '68 6£.l I I I I I I UJ8*J | .........A - - - - - - - - - - - - - - - - - - - - - - - '68 6£.l I I I I I I UJ8*J | ||
Genlinsl Offlc.n: 212 West Mlchlg11n Avenue, Jeckson, Michigan 4Sl201 * (517) 788-0650 July l, 19/jQ Mr James G Keppler Office of Inspection and Enforcement Region III U S Ni..;,clear Regulatory Commission 799 Roosevelt Road Glen Elly:i., IL 60137 DOCKET 50-255 - LICENSE DPR PALIS.AI::ES PU.JfT - LICENSEE EVENT RE~ORT 80-019 - SIRW T.4.HK LEVEL On the reverse sid.e is Licensee Event Renert 80-019 't1hi*~h is re-;:orta-::;le tue.der Technical Specification 6.9.2.A.8. | Genlinsl Offlc.n: 212 West Mlchlg11n Avenue, Jeckson, Michigan 4Sl201 * (517) 788-0650 July l, 19/jQ Mr James G Keppler Office of Inspection and Enforcement Region III U S Ni..;,clear Regulatory Commission 799 Roosevelt Road Glen Elly:i., IL 60137 DOCKET 50-255 - LICENSE DPR PALIS.AI::ES PU.JfT - LICENSEE EVENT RE~ORT 80-019 - SIRW T.4.HK LEVEL On the reverse sid.e is Licensee Event Renert 80-019 't1hi*~h is re-;:orta-::;le tue.der Technical Specification 6.9.2.A.8. | ||
:Ca:;id. ? Hoffman Nuclear :Uicensing Ad...'!i.inistrator CG Director, Cffice of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement | :Ca:;id. ? Hoffman Nuclear :Uicensing Ad...'!i.inistrator CG Director, Cffice of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement | ||
Line 76: | Line 75: | ||
"I'.~" | "I'.~" | ||
PALISAJJES PLANT NRC FORM366 . U.S. N.UCLEAR REGULATORY COMMISSION f7*771 LICENSEE EVENT REPORT CONTROL BLOCK:* !-1_*.;..*.._1_...._....._.:._-1..---il0 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 | PALISAJJES PLANT NRC FORM366 . U.S. N.UCLEAR REGULATORY COMMISSION f7*771 LICENSEE EVENT REPORT CONTROL BLOCK:* !-1_*.;..*.._1_...._....._.:._-1..---il0 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 | ||
[ili] IM I | [ili] IM I | ||
* 7 8 9 I I pI LICENSEE CODE Al L I 1 101 14 ~5 0 I 0 I- I0 I 0 I 0 I 0 t..ICENSE NUMBER I 0 I- I0 I 0 101 4 11 I 11 1 11 101 25 26 LICENSE TY~E JO I | * 7 8 9 I I pI LICENSEE CODE Al L I 1 101 14 ~5 0 I 0 I- I0 I 0 I 0 I 0 t..ICENSE NUMBER I 0 I- I0 I 0 101 4 11 I 11 1 11 101 25 26 LICENSE TY~E JO I | ||
57 CAT !;II I 0 CON'T | 57 CAT !;II I 0 CON'T | ||
[TIIJ 7 8 | [TIIJ 7 8 | ||
~G~~~ UJ©I 01 s I oI 01 oI 21 s Is K2)1 o I 6 Io 1*9 I 81 o IG)I 01 T I o1.i I 8 I o 10 60 61 OOCICET NUMBER 68 69 EllENT CATE 7' 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@ . | ~G~~~ UJ©I 01 s I oI 01 oI 21 s Is K2)1 o I 6 Io 1*9 I 81 o IG)I 01 T I o1.i I 8 I o 10 60 61 OOCICET NUMBER 68 69 EllENT CATE 7' 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@ . | ||
Line 88: | Line 85: | ||
[§JI] ld11r;pg safety ;pjectfop. '1'.S. 3.3 reqpjr<=>s tenk total cqprents rq be | [§JI] ld11r;pg safety ;pjectfop. '1'.S. 3.3 reqpjr<=>s tenk total cqprents rq be | ||
[Ill] 1250,000 gal; consequently when RAS occurs, less than 250,000 gal would be | [Ill] 1250,000 gal; consequently when RAS occurs, less than 250,000 gal would be | ||
[ | [)))) !injected. This condition adversely affects post acc1dent containment lr:l;'1 | ||
~ 1press.ure ana ..., ysis. I Reportability determination made on. 6-16-80. | ~ 1press.ure ana ..., ysis. I Reportability determination made on. 6-16-80. | ||
cmJ8 9 80 SYSTEM CAUSE CAUSE COMP, VALVE CODE cooE SUSCOOE COMPONENT CODE SUS CODE suscooE. | cmJ8 9 80 SYSTEM CAUSE CAUSE COMP, VALVE CODE cooE SUSCOOE COMPONENT CODE SUS CODE suscooE. | ||
Line 105: | Line 102: | ||
3~ | 3~ | ||
LZ.J I 36 37 01 OI o Io I 40 lli.J@ | LZ.J I 36 37 01 OI o Io I 40 lli.J@ | ||
llU@ | llU@ | ||
42 | 42 | ||
Line 111: | Line 107: | ||
4J I z ! 9 I 9 19 I@ | 4J I z ! 9 I 9 19 I@ | ||
"' 47 CAUSE DESCRIPTION ANO CORREC"rlVE ACTIONS @ | "' 47 CAUSE DESCRIPTION ANO CORREC"rlVE ACTIONS @ | ||
[J | [J))J I Wo-rdinll of T.:'. 1 1 1a was not snffjcient1y prerise Cnrrentlv. tank | ||
):'* | ):'* | ||
IIJil I volume is being administratively controlled to maintain 250,000 gal above D:lJJ RAS setpojnt. SIRW tank Jqw ]<=>yel aJara setpqjpt wiJl be chang<=>cl r_o o::m reflect new limit. Need for T.S. Change will be further evaluated. | IIJil I volume is being administratively controlled to maintain 250,000 gal above D:lJJ RAS setpojnt. SIRW tank Jqw ]<=>yel aJara setpqjpt wiJl be chang<=>cl r_o o::m reflect new limit. Need for T.S. Change will be further evaluated. | ||
Line 134: | Line 130: | ||
NA ______________________________ ---:--e~c LOSS O< OR CAMAGE TO FACILITY r.;J'\ | NA ______________________________ ---:--e~c LOSS O< OR CAMAGE TO FACILITY r.;J'\ | ||
* TYPE DESCRIPTION '\:.:::,J. | * TYPE DESCRIPTION '\:.:::,J. | ||
C2TIJa W@ ~10~---~---o.i.a."---------------------------------~s~o 9 | |||
PUBLICITY C\ NRC USE ONLY ISSUED(:".:;\ DESCR1irr10N ~ | PUBLICITY C\ NRC USE ONLY ISSUED(:".:;\ DESCR1irr10N ~ | ||
[1TIJ Lli.Jo . | [1TIJ Lli.Jo . | ||
a 9 ~10--------~-~-------------------~sa N!\ I I I I I I I I 6~9..;,,,..i....;._._,.;,,.,,_._._. . . . . _. .I_,aoI | a 9 ~10--------~-~-------------------~sa N!\ I I I I I I I I 6~9..;,,,..i....;._._,.;,,.,,_._._. . . . . _. .I_,aoI | ||
' ~-, | ' ~-, | ||
General Offices: 212 West Michigan Avenue, Jackson, Mlchl911n 49201 * (517) 788-0650 Ju~y l, l.9ti0 Mr .James G Keppler Office of Inspection and Enforcement Region III U S Nuclear Regulatory CoI1JII1ission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - L~CENSE DPR PALISJ-\~ES ?LftJfT - LICENSEE EVENT REPORT 80-019 - SIRW T.AJ:IK LEV'EL On the reYerse sid.e is Licensee Event Report 80-019 'N"hich is reportable 1m.d.er Technical Specification 6.9.2.A.8. | |||
Da*;id. ? Hoffman Nuclear Licensing A;ln;j nistrator ... | Da*;id. ? Hoffman Nuclear Licensing A;ln;j nistrator ... | ||
*:1 CC Director, Office of Nuclear Reactor Regulation Director, Office o:., Inspection and Enforcement Tu"RC Resident Inspector - Palisades FJUL 3 1980 | *:1 CC Director, Office of Nuclear Reactor Regulation Director, Office o:., Inspection and Enforcement Tu"RC Resident Inspector - Palisades FJUL 3 1980 | ||
Line 175: | Line 169: | ||
43 I Z! 9 l 9 I 9 I@) | 43 I Z! 9 l 9 I 9 I@) | ||
.... 47 CAUSE DESCRIPTION ANO CORRec*nve ACTIONS @ | .... 47 CAUSE DESCRIPTION ANO CORRec*nve ACTIONS @ | ||
((((] I Wo..-dinji qf T.S. 1 3 la was DO'" s11fffrjently precjc::e. C1p*re:itl v tank ITJJJ volume is being administratively controlled to maintain 250,000 gal above RAS setpojnt. SIRW tapk Jaw l<=>y<>l alarm 5i:>tpoint wi11 be cbff'"'f;Pd t"Q reflect new limit. Need for T.S. Change will be further evaluat:ed. | |||
c:ma 9 80 FACIL1~ . rjQ\ METHOD OF (.;:;\ | c:ma 9 80 FACIL1~ . rjQ\ METHOD OF (.;:;\ | ||
STATUS % POWER OTHER STATUS '.::;:/ OISCOVERY OISCOVERY OESCRIPTION 'CJ UiiJ W@ I ol 9 I sl@L.____...N....,A_ _ _--' LAJ~~I~-~~~~*~S~*....;B~a~s~i~s=--R~e~v~i~e~w:....~~~~~~~-' | STATUS % POWER OTHER STATUS '.::;:/ OISCOVERY OISCOVERY OESCRIPTION 'CJ UiiJ W@ I ol 9 I sl@L.____...N....,A_ _ _--' LAJ~~I~-~~~~*~S~*....;B~a~s~i~s=--R~e~v~i~e~w:....~~~~~~~-' |
Latest revision as of 21:54, 17 March 2020
ML18045A326 | |
Person / Time | |
---|---|
Site: | Palisades |
Issue date: | 07/03/1980 |
From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
Shared Package | |
ML18045A328 | List: |
References | |
LER-80-017-03X, LER-80-17-3X, NUDOCS 8007090319 | |
Download: ML18045A326 (6) | |
Text
consumers
- Area Code 517 788-0550 July 3, 1980 1YIT J &'!le s G Keppler Office of Ir:.spectior. and Enforcement
}\egion I I I U S Nuclear :Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 6013'(
DOCKET 5~-255 - LICENSt: :C.PR-~20 -
P.i\I,IS*.A.DES ?L..4.NT - UP~..~TE OF LICEJ:JSEE
]~'i.EI,TT RE~PORT 80-01 7 I.iicensee Eirent Report (LEI\) 30--0lT was submitted. to the ~:EC, ?.egion III ofr':'...ce CJn ~Jur1e 13, l9b0. C!l the ye*verse side is an upda.te o~ I..icen:=ee f~-ve!it Feport 80-017. Changes are indicated b;-f a vertical line in the righ-'.:. har:.d ma::-gin.
Rog~~!' \{ Hustor~
Senior Licensing ~ngineer CC fiirector, Office of Nuclear Reactor Regulation Director, Office of Inspection ar:.d EEforcement IIBC :5:.esident Inspector - Pali sad*.=s r.IUL 7
?0070 /0319 1980
(
LTPDATE REPORT - PREVIOUS REPORT DATE - June 13, 1980 PALISADES PL.ANT NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION*
(7-77)
LICENSEE EVENT REPORT CONTROL BLOCK: i-1_..__.__..__.__.__-,!IQ (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
~IMI IIPIAILlllG)lolol.-lulololol Ol-lo!OIG)l4111111111©L I I 7 8 9 LICENSEE CODE 14 ~5 LICENSE NUMBER 25 26 LICENSE TYPE* JO 57 CAT 5B CON'T CITTI ~:~~; U;J© I o I 5 I u I o I 01 Cl I 5 I 5 101 o ! 5 11 Io I 8 I o I@ I o 17
- I o I3 I 8 I o IG)
' a 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
~eview of PS testing procedures revealed the setpoint of PS-1801 thru 1804
~ ~o be lower than permitted by TS 3.16. PS-ldOl-1804 sense containment IT:EJ !pressure and are used to initiate RPS tri us (one switch contact) and SIS/
C2:II) pant. isol/cont gpray (other contact). The procedure (RI-04) required
[)))) §etting both switches to operate at less than 5 psig \RPS setpoint I.AW l1JIJ ~S 2.3); whereas ESFAS required setpoint per TS 3.16 is 5.0 to 5.75 psig.
III)) ICondH.-ipp did. not preyent EffF' systems f'rom f'imctionjn~ properlv. __J 7 8 9 SC SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE suacoo~ COMPONENT CODE SUB CODE SUBCOCE
[ill] Is IHI@ IJLl@ I z I@ LI IN Is IT IR I u1e L§J@ L~@.
7 8 9 10 11 12 13 18 19 2C SEQUENTIAL OCCURRENCE REPORT REVISION
(';:;\ LE RiRO CV ENT YEAR REPORT NO. CODE TYPE NO.
\;.:.J REPORT !8 I0 I l.=J 101117 I 1......-1 I 013 I W l=.l Ll-.J NUMBER ~I 22 23 24 26 2i. 28 29 30 J1 32 AC710N FUTURE EFFECT SHUTDOWN (.;';;\ ATTACHMENT NPRD~ 'PRIME C:OMP. COMPONENT TAKEN ACTION ON PLANT METHOD
- HOURS ~ SUBMITTED FOAM SUB, SUPPLIER MANUFACTURER W@lzJ@) W@ W I o Io I o I 01 L!J@ L..!J(§ ~@ 1u p 17 !5 i@
33 34 35 36 37 40 41 42 43 44 .,
CAUSE OESCRIPTION AND CORRECTIVE ACTIONS @
LOri.,:inal procedure author apparently did not recognize different setpoint
[JJJJ req'iirements of TS 2. 3 and 3 .16. Procedure has been revised such that bot4
!IITI 'T'S ? *3 and 3 .16 are satisfied. \Each switch can be independently set).
[i]JJ Reuortable under TS 6.9.2.B.1.
lJJil 7 8 9 80 FACILITY STATUS % POWER OTHER STATUS tJOI
\::::,/
METHOD OF DISCOVERY DISCOVERY DESCRIPTION @
f1EJ IG ! 1010 101@IN ...... A
. . _ _ _ _ __. ~@ NA 7 8 9 10 12 13 44 45 46 so ACTIVITY CONTENT ~
RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE @
~ I z I @ Li@ I....._r-r_.A_ _ _ _ _ ____. I..___ NA 7 8 9 10 11 44 45 so PERSONNE~ EXPOSURi':S Q..
NUMBER A TYPE DESCRIPTION
[Q2]
7 8 9 lo Io I ollz 11 12 I@1~3~~-----------~----~-~--------~-----'80 NA PERSONNEL INJURIES (.;";\
NUMBER DESCRIPTION~
~
7 8 l...QJ_QJ_QJ@)I 9 11 12 NA - - - - - - - - - - - - - - - - - - - - - - - - - - so '
LOSS O< OR DAMAGE TO FACILITY t;;'1 TYPE DESCRIPTION '..:::;J GTIJ Lzj@)
7 8 9 NA 1~0~~----~------------~----~--------~----~-----'80 PUBLICITY (;;;\
NRCUSEONLY ISSUEDr:;":;\ DESCRIPTION~
[ili] LlL.l~:V-9 iO
.........A - - - - - - - - - - - - - - - - - - - - - - - '68 6£.l I I I I I I UJ8*J
Genlinsl Offlc.n: 212 West Mlchlg11n Avenue, Jeckson, Michigan 4Sl201 * (517) 788-0650 July l, 19/jQ Mr James G Keppler Office of Inspection and Enforcement Region III U S Ni..;,clear Regulatory Commission 799 Roosevelt Road Glen Elly:i., IL 60137 DOCKET 50-255 - LICENSE DPR PALIS.AI::ES PU.JfT - LICENSEE EVENT RE~ORT 80-019 - SIRW T.4.HK LEVEL On the reverse sid.e is Licensee Event Renert 80-019 't1hi*~h is re-;:orta-::;le tue.der Technical Specification 6.9.2.A.8.
- Ca:;id. ? Hoffman Nuclear :Uicensing Ad...'!i.inistrator CG Director, Cffice of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement
- NRC Resident Inspector - Palisades f.JUL 3 1980
"I'.~"
PALISAJJES PLANT NRC FORM366 . U.S. N.UCLEAR REGULATORY COMMISSION f7*771 LICENSEE EVENT REPORT CONTROL BLOCK:* !-1_*.;..*.._1_...._....._.:._-1..---il0 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
[ili] IM I
- 7 8 9 I I pI LICENSEE CODE Al L I 1 101 14 ~5 0 I 0 I- I0 I 0 I 0 I 0 t..ICENSE NUMBER I 0 I- I0 I 0 101 4 11 I 11 1 11 101 25 26 LICENSE TY~E JO I
57 CAT !;II I 0 CON'T
[TIIJ 7 8
~G~~~ UJ©I 01 s I oI 01 oI 21 s Is K2)1 o I 6 Io 1*9 I 81 o IG)I 01 T I o1.i I 8 I o 10 60 61 OOCICET NUMBER 68 69 EllENT CATE 7' 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@ .
ID11rjpg review of basis for T.S. 3 3 jt was deternjped that the SIRW tank
[]JI] 1should contain enough borated water to provide 250,000 gal of injection
[§JI] ld11r;pg safety ;pjectfop. '1'.S. 3.3 reqpjr<=>s tenk total cqprents rq be
[Ill] 1250,000 gal; consequently when RAS occurs, less than 250,000 gal would be
[)))) !injected. This condition adversely affects post acc1dent containment lr:l;'1
~ 1press.ure ana ..., ysis. I Reportability determination made on. 6-16-80.
cmJ8 9 80 SYSTEM CAUSE CAUSE COMP, VALVE CODE cooE SUSCOOE COMPONENT CODE SUS CODE suscooE.
[ill]
7 8 Is 9
!Bl@ 10 w@ w@ I z I z I z I z I z1z1e w@ w@
11 12 lJ IS IS :;:a SEQUENTIAL OCCURRENCE REPORT REVISION
@ LER'RO CVENTYEAR REPORT NO. CODE. TYPE NO.
REPORT .
NUMBER I8I0I
- 1l :;*
I ! I aI J I 21 1.....-1 I a I , 29I . L1:J 1=J l.Q.J
- O:J 24 26 Z7 ZS Jo J1 J2 Ac:'!ON FUTUF>E EF=-ecT *SMUTOOWN f.:'.::\ ATTACMMENT Nl'RD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METMOD MOURS SU8MITTEO FORM SUB. SUPPLlcR MANUFACTUR~R W@W@.
JJ J*
W@
3~
LZ.J I 36 37 01 OI o Io I 40 lli.J@
llU@
42
- w@
4J I z ! 9 I 9 19 I@
"' 47 CAUSE DESCRIPTION ANO CORREC"rlVE ACTIONS @
[J))J I Wo-rdinll of T.:'. 1 1 1a was not snffjcient1y prerise Cnrrentlv. tank
):'*
IIJil I volume is being administratively controlled to maintain 250,000 gal above D:lJJ RAS setpojnt. SIRW tank Jqw ]<=>yel aJara setpqjpt wiJl be chang<=>cl r_o o::m reflect new limit. Need for T.S. Change will be further evaluated.
CTI!]
.7 a 9 so FAC:L..1~ ~ METMCC OF P.\
STATUS °'POWER *. OTMER ST... TUS \.::;:! DISCOVERY DISCOVERY DESCRIPTION ~
[ill] W@ I 01 g I s lL-1 La..J~~'--=T~*~S~.'--'B~a~s~i=*~s~R~e~v~i~e~w;_,___________.....
1 a 9 ACTIVITY
- CONTENT 10 1:. . 13
___;;,:N.o.t,A_ _ _---'
Q,_
45 co 80 RELEASED OF RELEASE . "'MvUNT OF ACTIVITY LOCAT10N OF RELEASE @':
~
7 . 8 W @ lz.J@ ...I ____,,1'....,IA..___ _ __.
9 10 11 45 so PERSONNEL EX~OSURES . Co, NUMBEP. r.;:;., TYPE OESCRll'TION ~
[!JI]
7 a 9.
I 0 I 0 I 011k~U.l@i....----::N.:.::A=---------------------.----.------'
12 13 , *.*
- ac --J PERSONNEL INJURIES Co\
NUMBER OESCRIPTION6 mJa I9 0 .I 0 I 011I@) ~12~----,;;,;;,;...,
NA ______________________________ ---:--e~c LOSS O< OR CAMAGE TO FACILITY r.;J'\
- TYPE DESCRIPTION '\:.:::,J.
C2TIJa W@ ~10~---~---o.i.a."---------------------------------~s~o 9
PUBLICITY C\ NRC USE ONLY ISSUED(:".:;\ DESCR1irr10N ~
[1TIJ Lli.Jo .
a 9 ~10--------~-~-------------------~sa N!\ I I I I I I I I 6~9..;,,,..i....;._._,.;,,.,,_._._. . . . . _. .I_,aoI
' ~-,
General Offices: 212 West Michigan Avenue, Jackson, Mlchl911n 49201 * (517) 788-0650 Ju~y l, l.9ti0 Mr .James G Keppler Office of Inspection and Enforcement Region III U S Nuclear Regulatory CoI1JII1ission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - L~CENSE DPR PALISJ-\~ES ?LftJfT - LICENSEE EVENT REPORT 80-019 - SIRW T.AJ:IK LEV'EL On the reYerse sid.e is Licensee Event Report 80-019 'N"hich is reportable 1m.d.er Technical Specification 6.9.2.A.8.
Da*;id. ? Hoffman Nuclear Licensing A;ln;j nistrator ...
- 1 CC Director, Office of Nuclear Reactor Regulation Director, Office o:., Inspection and Enforcement Tu"RC Resident Inspector - Palisades FJUL 3 1980
NRC FOJ'!M~
- PALISADES PLANT U.S. NUCLEAR REGULATORY, COMMISSION
'7*771 LICENSEE EVENT REPORT CONTROL BLOCK: I~,~--.......~----~---~61...:..1 I(,"\ (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lTiiJs 7
IM I I I p I Al L I i 101 oI o1- Io I o I o I o I o I - I o I o 101 4 I 1 I 111 11 101 I I0 9 LICENSEE CODE 14 ~5 1*.ICENSE NUMBER 25 :26 LICENSE TYPE 30 57 CAT !OB CON'T
~~~~~ L.!JG)I 01 5 I o I 01 o I 21 5 I 5 GI o I 6 Io I 9 I 8 I o IG)I 01 T I o 1.L I 8 I o 10
- 0JJa 7 60 61 DOCKET NUMBER 68 69 EVENT DATE 7* 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES @
[ill] !Durjng rey;ew of basjs for T.S. 3 3 H was determined that the STRW tapk
[]JI] 1should contain enough borated water to provide 250,000 gal of injection CIT!J ldtir;ng safety ;n-iection. TS. 3.3 ri:><.jufres tank total eontent"' ro he
[§JI] 1250,000 gal; consequently when RAS occurs, less than 250,000 gal would be
[]JI] !injected. This condition adversely affects post accident containment
[TII) 1pressure analysis. Reportability determination made on 6-16-80.
cmJ 7 8 9 BO SYSTEM CAUSE CAUSE COMP. VAL.VE cooe cooe SUBCOOE COMPONENT CODE suacooE SU BC ODE
!IIIJ 7 B ls I Bl@ w@ w@ 1z1z1z1z1z1z1e 9 10 ,.. ,~ l:l 16 w w@
lS 20 SEQUENTIAL OCCURRENCE REPORT REVISION
- 0. LEi<'RO CVENTYEAR REPORT NO. COOE TYPE NO.
\:..:.,; REPORT I 8 I0I
~:l,....._...,.._~_
lol1191 I/I lol1I L1:J l=J l.QJ NUMBER.
2 24 2e: 27 28 :t9 . JO 31 32
.o.cr:oN FUTUPE EFFECT SHUTDOWN A ATTACHMENT NPRQ-4 PRIME COMP. COMPONENT TAKEN ACTION ON PL.ANT METHOO HOURS \:31 SUBMITTED FORM ~UB. SUPPLIER MANUFACTU~E~
l£J@W@
3J J*
W@
35 W
36 I oI 31 OI o I o I lllJ@>
40 41 lliJ@
42 W
43 I Z! 9 l 9 I 9 I@)
.... 47 CAUSE DESCRIPTION ANO CORRec*nve ACTIONS @
((((] I Wo..-dinji qf T.S. 1 3 la was DO'" s11fffrjently precjc::e. C1p*re:itl v tank ITJJJ volume is being administratively controlled to maintain 250,000 gal above RAS setpojnt. SIRW tapk Jaw l<=>y<>l alarm 5i:>tpoint wi11 be cbff'"'f;Pd t"Q reflect new limit. Need for T.S. Change will be further evaluat:ed.
c:ma 9 80 FACIL1~ . rjQ\ METHOD OF (.;:;\
STATUS % POWER OTHER STATUS '.::;:/ OISCOVERY OISCOVERY OESCRIPTION 'CJ UiiJ W@ I ol 9 I sl@L.____...N....,A_ _ _--' LAJ~~I~-~~~~*~S~*....;B~a~s~i~s=--R~e~v~i~e~w:....~~~~~~~-'
a s 10 n 13 45 46 80 ACTIVITY RELEASED OF RELEASE CONTENT AMOUNT OF .O.CTIVITY e
(.;;;\
LOCATION OF REL.EASE @)
G:TIJa 1
W@ lz.J@ ...
g 10 I ___t....M.___ _ __...
11 45 80 PERSONNEL. EXPOSURES Q-,
NUMBEP. (.;':;\TYPE DESCRIPTION 82] I o I o I ol~W@>._I--'N=A;;;,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___.
1 a s 11 12 13 so
. PERSONNEL. INJURIES ~
NUMBER DESCR1PT10N'!2J Lill I 0 I 0 I OI@
8 9 11 NA
~,2~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~8~0 LOSS O* OR 0.0.MAGE TO FACILITY t.;31 n'PE DESCRIPTION '.::.:;J
!2TIJ 8 9W@ ~10~~~~~~~~........__~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~BJO PUBLICITY C\ NRC USE ONLY ISSUED(;".;\ DESCRll"T10N ~
[ill]a IJij1~~------N:.:.A:.!------------------J s 10 68 I I 59 II I 11 II I I ao I