ML18045A326

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
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: ML18045A326 ML19320B107
References
LER-80-017-03X, LER-80-17-3X, NUDOCS 8007090319
Download: ML18045A326 (6)

Text

{{#Wiki_filter: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}}