05000255/LER-1980-019-01, /01T-0:on 800609,during Tech Spec Review,Tech Spec 3.3 Determined to Provide Too Little Borated Water for Safety Injection.Caused by Imprecise Wording of Tech Spec. Low Level Alarm Setpoint Changed,Tech Spec Under Evaluation

/01T-0:on 800609,during Tech Spec Review,Tech Spec 3.3 Determined to Provide Too Little Borated Water for Safety Injection.Caused by Imprecise Wording of Tech Spec. Low Level Alarm Setpoint Changed,Tech Spec Under Evaluation

ML18045A312
Person / Time
Site:	Palisades
Issue date:	07/01/1980
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML18045A314	List: 05000255/LER-1980-019, Forwards LER 80-019/01T-0 05000255/LER-1980-019-01, /01T-0:on 800609,during Tech Spec Review,Tech Spec 3.3 Determined to Provide Too Little Borated Water for Safety Injection.Caused by Imprecise Wording of Tech Spec. Low Level Alarm Setpoint Changed,Tech Spec Under Evaluation
References
LER-80-019-01T, LER-80-19-1T, NUDOCS 8007080199
Download: ML18045A312 (6)

LER-1980-019, /01T-0:on 800609,during Tech Spec Review,Tech Spec 3.3 Determined to Provide Too Little Borated Water for Safety Injection.Caused by Imprecise Wording of Tech Spec. Low Level Alarm Setpoint Changed,Tech Spec Under Evaluation

Event date:
Report date:
2551980019R01 - NRC Website

text

General Officell: 212 West Michigan Avenue, Jackson, Michigan 49201 * (517) '788*0650 July l, 191::10 Mr James G Keppler Office of Inspection and Enforcement Region III U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PL.llJ~T -

LICENSEE EVENT REPORT 80-019 - SIRW TANK LEVEL On the reverse side is Licensee Event Report 80-019 which is reportable lm.der Technical Specification 6.9.2.A.8.

David P Hoffman Nuclear Licensing Administrator CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement Tu"RC Resident Inspector - Palisades FJUL 3 19~

PALISADES PL.ANT NRC FOf:;!M36£ (7-771 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: ~'~..__._~.._........_~..__,!G) 1 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI

~

7 s IM I I I p I Al L L i 101 0 I 0 I - I 0 I 0 I 0 I 0 I 0 I - I 0 I 0 101 4 11 I 111 11 101 I I 0 9

LICENSEE CODE 14

,5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT SS CON'T CIT2J 7

8

. ~~~~! ~I o I s I o I 01 o I 2 I s I s K?)I o I 6 I o I 9 I B I o @I o I T I o 11 I 8 I o 10 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE SO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES @

[ill] !During revjew of basis for T.S. 3.3 it was determined that the SIRW tank

@II] 1should contain enough borated water to provide 250,000 gal of injection rIEJ I during safety ;njectfon.

T.:::;. 3. 3 reqni res tank total contents to be [QJ]J 1250,000 gal; consequently.when RAS occurs, less than 250,000 gal would be

((TI] !injected.

This condition adversely affects post acc1dent containment r:TI2J 1press.ure.;inalysis.

Reportability determination made on 6-16-80.

[ill]

1 a 9 so

[§JI) 7 8

SYSTEM CODE IS I Bl@

9 10 C::\\

LE R IRQ CV ENT YEAR v..y REPORT I 8 I 0 I NUMBER 21 22

CAUSE

CAUSE CODE SUSCODE COMPONEN1" CODE w@ w@ 1z1z1z1z1z1z1@

11 ii 13 Hi SEQUENTIAL OCCURRENCE REPORT NO.

CODE l::::J lol119l 1.....-1 lol1J 23 24 26 27 28 29.

COMP.

SUB CO OE w

19 REPORT TYPE l1.l Jq VALVE SUBCODE w@

20 l=J 31 PRIME COMP.

REVISION NO.

LQJ 32 COMPONENT ACTION FUTURE TAKEN ACTION EFFECT ON PLANT SHUTDOWN METHOD r.;::;..

ATTACHMENT HOURS ~ SUBMITTED NPRD-4 FORM SUB.

SUPPLIER MANUFACTUR~R W@W@ W@ Ll.l I o I OI o Io I lliJ@

33 34 35 36 37 40 41 LBJ W@

I z I 91919 l@

CAUSE DESCRIPTION AND CORREC"flVE ACTIONS @

42 43 47 I Wo,..djn~ of T.S. 3 3.Ja was not snff;cjently precise.

Cnrrent1v. tank volume is being administratively controlled to maintain 250,000 gal above [ill]

ITTIJ RAS setpoint.

SIRW tank low l<>yel a]arm setpoint will be changed to reflect new limit.

Need for T.S. Change will be further evaluated.

7 8

9 FAC1u;v

~

STATUS

% POWER OTHER STATUS ~

METHOD OF A

BO [QI] W@ I ol 9 I s l@._I _..N...,_A ___

--.a DISCOVERY DISCOVERY DESCRIPTION \\:31 LA.J~~'~~T~*~S~*~B~a~s~i~*s::_R~e~v..:;..;:;.i~ew""'-~~~~~~--'

B 9

10 12 13 ACTIVITY CONTENT Q.,

RELEASED OF RELEASE AMOUNT OF ACTIVITY e l2liJ W @ lzj@._I __

___.NM.lA.__ ___

B 9

10 11 45 46 80 LOCATION OF RELEASE @

44 45 80 PERSONNEL EXPOSURES Q,

NUMBEP.

r.;::;.. TYPE

DESCRIPTION

C2:EJ I o I o I o 1'5'U,J@...__ __ N=A;:.,_ _______________________

~

1 a s 11 12 13 PERSONNEL INJURIES Q

BO NUMBER DESCRIPTION~

~IOI OI Ol@)~ __

__;N~A.;;.,_ _____________________

~

B 9

11 12 80 LOSS D< OR DAMAGE TO FACILITY '4JI TYPE

DESCRIPTION

i,;:::;

~

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1 a s 10 so PUBLICITY G\\

ISSUEOQ DESCRIPTION~

I2I£J LNJ~..__,.._,.._,.._,.._,..~N~A::..__,.._,.._,.._,.._,.._,.._,.._,.._,.._,.._,.._,.._,.._,.._,..~

I I I I I a s 10 ca 69 NRC USE ONLY I I ao

f)..S.B It

.... ~~

General Offices: 212_ West Michigan Avenue, Jackson, Michigan 49201

• Area Code 517 788-0550 July 3, 1980 l*:Ir Ja.--r:es G Kep~ler Cff:.ce cf Ir.:..spectior... and. Enfo:-cem.e!'"J.t RegiJn III lj S Nuclear Reg1J.lator;r CQmm.issior1 799 ?.coseve::i..t Ro:;.d Glen Ellyn, I:;:.

6013':'

~OC?:ET 5~-255 -

LICEIJS~ I:,PR. ?_t,.LI2)23S ?LA1~::1 -

UPJ_~TZ O"i!' I_ICEI:J3EZ

~,i-Ef~T REPO::\\T ac-:::1 7

~icensee E>rer:t Report (LE~.) 80-01*r was subrrit--ceC.. to ti1e i':RC, ?.egion III ofr"':.ce

.:;r:._.. 1-'i.::-.:.~ l.3, 19t-G.

C~ t.iJ.e r-e~r:::rs-:: side is an upde.te of Licen=ee E-ver.;.t Fe port 8G-Gl7.

~:t~anges.~re i:id.icE.ted 1:-:v-a *rertical lirle in the ~igh-: har.d T!la~~gin.

~c~c!' ~~ Hu.star:

Senior :;:,icensing ~ngineer CC Dir-ector, Office of Nuclear-Reactor Regulation Jirector, Office of Inspec-tion ar.d Enforcer:.ent

rnc ~es ident Inspector - Pali sades

'JUL 7 1sao

LTPDATE REPORT'-

PR.Eil~OUS REPORT DATE - June 13, 1980 PALIS.ADES PIJ..lIT NRC FORM 366 (7-77)

U.S. NUCLEAR REGULATORY COMMISSION*

LICENSEE EVENT REPORT CONTROL BLOCK: ~' _.._.......__...__.._...._..... 1 Q I

6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

[!li]IMI IIPIAILlllG)lulol.-lulololol Ol-lolOIG)14 lllllllll01 I l© 7

8 9

LICENSEE COOE 14

,5 LICENSE NUMBER 2S 26 LICENSE TYPE JO 57 CAT 58 CON'T [ill]

7 8

~~~~~ UJ©I o I 51 u I o I 01 ~ I 5 I 5 101 o I 5 ll i o I 8 I o !@I o 17* I o 13 I 8 I o 10 60 61 DOCKET NUMBER OS 69 EVENT DATE 74 75 REPORT CATE 80 EVENT DESCRIPTION ANO PROBABLE CONSEOUENCes@

IRev:.ew of PS testing nrocedures revealed the setnoint of FS-1801 th!'u 1804

[]JI] ~o be lower than permitted by TS 3.16.

PS-ldOl-1804 sense containment [IE] press2*e and are used to initiate RPS trius (one switch contact) and. SIS/

[QJij pont. isol/cont spray (other contact).

The procedure (RI-04) required

[)))) @etting both switches to oner ate at less than. 5 psig \\RPS set-point IAW [2JI) ~S 2.3); whereas ESFAS required set~oint Der TS 3.16 is 5.0 to 5.75 nsig.

r;:;-T"01g jf"',.,~n*,-+;~-

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CAUSE

CAUSE CODE SUBCOOE COMPONENT CODE L.QJ@ lzl@ I I I N Is IT I RI u1@

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9 Jo J1 REVISION NO.

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80 ACTION FUTl..'FIE TAKEN ACTION EF*ECT SHUTDOWN

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ATTACHMENT NPR0-4

'?RIME COMP.

ON PLAliT METHOD HOURS \\.:;,I SUBMITTED FORM ~us..

SU?PLicA IGl@lzl@ W@ UJ 101010101 L.!J@

IN!§~@

COMPONENT MANUFACTURER

l:l 34 JS 36 37 40 41 42 43 CAUSE DESCRIPTION AND CORRec*nve ACTIONS @

jU p 17 15 i@

u 47 Q))J I Oris::.na2. urocedure author annarently did not recognize different setpoint o:J:]

rea_1J.irements of TS 2.3 and 3.16.

Procedure has been reYised s1J.ch tna-:: botly [JJJ]

r;ig ?. 3 and ~. 16 are satisfied.

{Each switch can be indeuendently set i.

ITIII Eeuortable u11d.er 'T'S 6. 9. 2. B.1.

EIEl 7

8 9

FACH.. liY

(.;Q\\

STATUS

'6 POWER OTHER STATUS °\\::;:i GTIJ IG !@ I 010 I 0 l@1!...._N_A ____ ___

90 METHOD OF DISCOVcRY D5SC<'IPTION DISCOVERY I ~§ iJA 8

9 10 12 13 ACTIVITY C::ONTENT

~

AELEAScD OF MELEASS:

AMOUNT OF ACTIVITY ~

[QI] IZ I@ LI@I._ _N_A ______

7 8

9 10 44 45 46 ao NA

~OCATION OF RELEASE @

44

• 5 so PERSONNEi. !:XPOSUP.ES Qo, NUMBEP A

TYPE

DESCRIPTION

[ill Io I o I olIZ l@_":-N""'

1 A~--------------------------J a 9 11 12 13 PERSONNEL INJURIES

(.";\\

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so [liJ I o ! o I ol@

~L~

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~12~-------------------------------------

3

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0 LOSS o< OR OAM.. GE TO FACI LITI Q.I TY?5 OCSCRIPTION v:::!:)

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9 10 0 t..19LICITV

(;";;\\

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GE Iv J~~I

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2.0 NAC ~SE ONLY

(

~ t.*:

'!*-:l.

'.. ~ :.,

~

r. *.

. ~

~. *;.

~ :; -

.~.. '-\\.

".I General Offices: 212 West Mic;hlgan A.venue, Jackson, Michigan 49201

• Area Code 517 788-0550.

. July 3, 1980 l~Ir Ja..L..es G Keppler r_Jff*2.ce c~* I;-.:.~pectior: and. E!lfc~ce.T.e:it Regi.Jri III

~J S Nuc~ea~r Regu.latcr~r C'Jrrlmis.sior1 J)..:S.B 199 ?.CoseV.elt RoG~d

. Glen Ellyn, E.,

6013':'

?_i;.LI3P.1):2S

?L.4.I~T -

l.JPJ.. !'.\\.TZ cr-i

._

c~It3EZ E'i.El'IT R;~p;JRT 8C-*Jl 7

~icensee ZYent Re}'ort 88-Gl'I" *was subr1i t--ceC t.,:J tiJ.e :'TrtC, ?.egion III off:..ce

.:a:,.Ju::1'= 13, i;.:-t.o.

C!! ti:J.e

-e~rerse side is an *u.na.s.~e ct L.2.censee Eve!.it F-e:port 80-Cl7.

Senior L~censing ~ngi~eer cc. Director,. Office of Nuclear nea:dor "2egU.lation

~*,.,._'=1 +

Off-.J.."ce

• I.... '~nc~-*,....~:-L*. 1.:"

1r-d "'!"'!"!.ii'

+

!.l~-~c.... or, ____

.o J............. ~... '::-u..... GJn,ar...

• .~r:...:..o.~cerG.e~...

we ~esident Inspector -

'?i~~~ade~.-

.. ~: '.. :

'.'1.*.*.,'

• 'JUL 7

• .,\\

-* -- ~--'-*-*

lSSO

... ~

~...

'UPDATE REPORT. - 'PREi/IOUS REPORT DATE -

JlL~e 13, 1980 PALIS.ADES PLAUT NRC FORM360 (7*77)

U.S. NUCLEAR REGULATORY COMMISSION*

LICENSEE EVENT REPORT CONTROL BLOCK: ~l~...__._~.___._~..._~IG) 1 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

[I:EJIMI IIPIAILlllG)lulol.-lulo!olol Ol-lulOIQ)14 lllllllll©I I I@

7 8

9 1.ICENSEE CODE 14

• ~5 J..ICENSE NUMBER 25 26 1.ICENSE TYPE JO

~7 CAT 58 CON'T [ill]

7 B

~~~~~ LJJ©I ol 5lu IOI Ol~I 515 K2)1o 15 ll lo 181 ol@I OIT IO 13 18 I olG) 60 61 DOCKET NUMBER OS 69 EVENT CATE 74

• 75 REPORT CATE 80 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES@

IRev:'..ew of PS testing procedures revealed the setuoint of FS-1801 thru 1804

((II] rto be lower than permitted by TS 3.16.

PS-ldOl-1804 sense contair.ment CQJI] !presst.Lre and are used to initiate RPS tri us lone switch co~tact) and SIS/

[)))) sont. isol/cont ~pray (other contact).

The procedure (RI-04) required

[)))) ~etting both switches to ouerate at less than 5 psig \\RPS setpoint IAW

((II) ~S 2.3); whereas ESFAS required set~oint per TS 3.16 is 5.0 to 5.75 psig.

[§))] lrondjt~on did :rnt prPy,.nt ES"' systems f',..om f'1mctionjn~ pro;perl-r.

B 9 [ill]

1 a

SYSTEM CODE Is I HI@

9 10

{.:;'\\

l.E R 'AO CVENT YEAR

\\:.:.I REPORT

!8 I 0 I NUMBER

~l z2

CAUSE

CAUSE COMP.

CODE suscooi.

COMPONENT CODE SUSCOOE lliJ@ I z I@) I I I N Is I T I R I UI@ L§J@

11 12 13

• 16 15 SEQUENTIAi.

OCCUR A ENCE REPORT REPORT NO.

CODE TYPE VAi.VE suecODE l.!J@

20 I I I o I 117 I l:"' I I o I 3 I W.

l=l 23 24 26

a 29 30 J 1 REVISION r~o.

ll..J 32 I

. 80 ACTION FUTURE EFFECT SHUTDOWN

(.;::\\

ATTACHMENT NPRD-4 "RIME COMP.

TAKEN

.>.CTION ON Pl.ANT METHOD HOURS *~

SUBMITTED FORM ~us, SUPPl.leR COMPONENT MANUFACTURER l Gl@IZ I@ W@

~ I 010 I 01 01 I NI@

IN!<§

~@)

~J J4 JS J6 37 40 41 42 43 JU p 17 15 I@

CAUSE DESCRIPTION ANO CORREC"rlVE ACTIONS @

Ori,.:.na.1. urocedure author anparently did not recognize diffe:!'."ent setpoint 1II3J requirements of TS 2. 3 and 3.16.

Procedure has been revised such t!J.a"t. botq CIJJ]

ms ?.3 and ~.16 are satisfied.

iEach switch can be indenendently set).

GJ]J Ewo"'table u.rder rrs 6. 9. 2. B.1.

!.1EI 7

8 9

FAC:i..1~

~JO STATUS

!(,POWER OTHER STATUS \\;:::/

. GJI] IG !@ I 010 I 0 l@1._IN_A _______.....

90 METHOD OF DISCOVERY DESCRIPTION @

DISCOVERY I I Z!@

iJA 1

a g

10 12 iJ

~TI~n

~TIITT

~

REl.EASEC OF REL.EASE AMOUNT OF ACTIVITY 8TI IZ I@ LI@I NA 7

8 g

10 11 44 45 40 so I

NA l.OCATION OF RELEASE @

44

• 5 so PERSONNE'- EXPOSURES Q..

0 NUMBEF'

~TYPE~

OESCl'llPTION ITI2] lo I ol olIZ l~N"""~A

.... *.---'-*-------.,...----------------....1 a

g 11 12 13 PERSONNEi. INJURIES (7,'\\

.~UMBER DESCRIPTION~.

50 [ill] I 0 l 0 I 01@ NA 7

R 9

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OCSCRIPTION

~

[Ej lzJ@

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• 1 a

9

~,o~~--~~~~~~~~~~~~~~~....;..~~~~~~~~~~~~~~--~~~--~..Jao.

0 1..1!31..ICITY

~

ISSUED(;:;\\ DESCRIPTION~

rII2J I >r lo._._..cr..,~.__ _____________________________ _..

I 1 I 1 I,

NAC L:SE ONLY r

I I

~ 0 66

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