ML18045A326

From kanterella
Jump to navigation Jump to search
Updated LER 80-017/03X-1:on 800510,PS Testing Procedures Review Revealed Setpoint of PS-1801 Through 1804 to Be Lower than Permitted by Tech Specs.Caused by Faulty Procedure. Procedures Revised to Conform W/Tech Specs
ML18045A326
Person / Time
Site: Palisades Entergy icon.png
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)
v • d • e


Text

consumers

  • /)..S.8 Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
  • 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

Retrieved from "https://kanterella.com/w/index.php?title=ML18045A326&oldid=2619864"