ML18018B264

LER 78-007-00, LER 78-008-00, LER 78-009-00 and LER 78-010-00 for Nine Mile Point, Unit 1 Re Technical Specification Violations of Listed Sections

ML18018B264
Person / Time
Site:	Nine Mile Point
Issue date:	03/01/1978
From:	Schneider R Niagara Mohawk Power Corp
To:	Grier B Office of Nuclear Reactor Regulation, NRC Region 1
References
NMP-0130 LER 78-007-00, LER 78-008-00, LER 78-009-00, LER 78-010-00
Download: ML18018B264 (14)

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0 REGULATORY INFORMATION DISTRIBUTION SYSTEM (BIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-220 REC: GRIER B H ORG: SCHNEIDER R R DOCDATE: 03/0 i/78 NRC NIAGARA MOHAWK PWR DATE RCVD: 03/07/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 0 ENCL i LICENSEE EVENT REPT (RO 50-220/78-07> ON 02/06/78 CONCERNING DURING STEADY STATE OPERATAION, AN INSPEC OF THE LIQUID WASTE SURGE TANK FOUND SEVERAL PINHOLE LEAKS... W/ATT LERS78-008'8-009 AND 78-0i0.

PLANT NAME: NINE MILE PT UNIT i REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:D4 4+++++++++++++++> DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS +4+4+++>>>>>w>>+>>

INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION: BR HXEF hEA 4 W/4 ENCL I

INTERNAL: REG FILE44W/ENCL NRC PDR++W/ENCL I 5 E44~W/2 ENCL MIPC++W/3 ENCL S DEREK'044W/ENCL HOUSTON++W/ENCL NOVAK/CHECK+~W/ENCL GRIMES++W/ENCL KNIGHT4 +W/ENCL BUTLER+4W/ENCL HANAUER++W/ENCL TEDESCO++W/ENCL EI SENHUT44 W/ENCL BAER~~W/ENCL SHAO+~lW/ENCL VOLLMER/BUNCH++W/ENCL KREGER/ J. COLLINS4+W/ENCL ROSA%%W/ENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR'S OSWEGO> NY++W/ENCL TIC++W/ENCL

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NWP-0130 NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE. N.Y. 13202/TELEPHONE (315) 474.1511 M~ch 1, 1978 2

ISA. Boyce H. G/u'.e/L NJzmtoh. ECQyQ Unkted State5 Nucleo/1. ReguLatotu/ Coming a~on Regin I >.S,A1~ Vg 1gi 631 Pmk Avenue, King o) Prism, PA. 19406 Ay~>iP RE: Bock& No. 50-220 Pem tl(/L. Gtu'.e/L:

In accordance Tecktu,cat!

~ one lNZe Po~ NueLea/1.

Speci.pcatiow, uIe he/Lebg sub~ She )oLEoeing Licensee S~n U~ Ill Eve< Repo~:

LER 78-07, uIhich ~ ~n vs~on o) Section S.9.2b(4) o(

Xhe Tech'.caL S peci.pcatLow LER 78-08, Iolu.chke ~n vLaZatiun o) Se~n 3.6.2 o( Eke Techtu'.cat'. Speci, pcatLoe6 LER 78-09, in acco/I,dance I0Mk Eke S peci.p.catLons urn~on Tech',cat'ER 78-10, uIfu'.ck m an o( Section 3.6.2 o( Xhe TechmeaL Speci, pcatLorv Thee /Lepo~ uIe/Ie completed ~n Cke )o/uIat de5~gnated ~n NUREG-Olbl, dated July 1977.

Ve/I.y ~y pouts, R.R. Schneide/L V~ce P/I.e54'.dent-Electtu'.c P/I.oduct4.on Attachments (3 cop~e6) xc: Mcecto/L, 0)pce o$ ISE (30 copie5)

Mtcecto/L, 0(pce of WIPC (3 copk e5)

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LICENSE NUMBER

' ' 25 26 LICENSE TYPE 30 57 CAT 58 CON'T KZ 3~178E~CQR 50 61 0 5 0 0 0 DOCKET NUMBER 2 2 OQ70 68 69 2 0 EVENT DATE 6 7 QQs0 74 75 2

REPORT DATE 80 QB EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO

~o~ Qurin stead state o eration an i s e

~0 3 tank found several inhole leaks. There were no measurable losses of

~o ~ li uid but leaks could be identified b dried de osit tracks o h

~o B side of the tank. This is re ortable er T.S. 6.9.2b 4 . This

~o G condition resulted in minimal safet im lications.

~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE SUBCODE COMPONENTCODE SUBCODE SUBCODE 8

CODE CODE 7 8 9 10 Q11 11 0 Q12 ~CQP3 12 13 A C C U M U 18 WZQ 19 ul Q SEOUENTIAI. OCCURRENCE REPORT REVISION OT LERIRO REP0RT EVENT YEAR

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HOURS Q22 0 0 0 40 SUBMITTED 41 N Q23 FORM SUB.

~NQ24 42 SUPPLIER

~N 43 Q 44 MANUFACTURER P 2 7 0 47 Q

o A 50 000 al.aluminum B-209 tank built b Pittsbu -D was constructed with walls 0.1875 inches thick. During assembly, weld-ing and grinding reduced the thickness in spots to half of this value apparently leaving pinhole leaks. A tank liner is being considered as a permanent solution, currently usage is strictly controlled.

7 8 9 80 FACILITY METHOD OF STATUS EMPOWER OTHER STATUS QSO DISCOVERY DISCOVERY DESCRIPTION Q2

~l" E Q28 ~09 9 Q28 NA 44

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ISSUED LgQ44 P U 8 L I C I TY DESCRIPTION NA

~ NRC USE ONLY 7 8 9 10 68 69 80 o PHDNE 31 5-343-21 1 0 ext. 1 558 NAME OF PREPARER

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NRC FORM 3GG U. S. NUCLEAR HEQULA I OR Y CO/slMibbiLIN (7 77)

LICENSEE EV ENT R EPORT

> CONTROL BLOCK: Qi tPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6 KOT 7 8 9 N > N N LICENSEE CODE P 1 14 Q2 15 0 0 0 0 0 LICENSE NUMBER 0 0 - 0 OQE 25 26 4 1 1 LICENSE TYPE 1

30 QE~QE57 CAT 58 2

CON'T sou~~RE MQ8 60 0 5 0 0 D 2 2 DQ 68 69 02 EVENT DATE 7 8Qs 74 75 0 2 2 REPORT DATE 8 7 8 80 Q

61 DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q1P

~o 2 Durin stead state o aration erformance of sur11eillance test Nl-ISP-

~os RE22, foun'd RE220 wi th a set oint of 103. 5 PS I 0, RE22E at 1 03. 0 PS ID, 8] and RE22F at 103.5 PSID. Re uired set oint for these main steasi line

~OS high flow indicating switches is 105 PSID +/- 1 PSID. This condition

~p G resulted in minimal safet im lications. The three instruments drifted

~o 7 in a more conservative direction.

~OS 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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~EQ18 ~ZQER ~ZQ20 ~>Q>> 0 0 0 > N Qs ~~Q4 ~~Q28 8 o 8 o Q28 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o The deviation in set oints ex erienced on the Barton Model 278 Differen-tial Pressure Indicatin Switches was due to instrument drift. RE22C 2 was reset at 1 05 . 5 PS ID, RE22E at 1 05. 0 PS ID, and RE22F at 1 04. 7 PS ID.

3 Current surveillance testin schedules are adequate to insure early 4 detection of future instrument drifts.

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7 FACILITY ~3P METHOD OF DISCOVERY DESCRIPTION

[ii) STATUS  % POWER OTHER STATUS DISCOVERY Q32

~EQ28 ~os 10 8 Qs 12 NA 44

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315-343-2110 ext 1558

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NRC FOIIM 3GG U. S. NUCLEAR IIEGULATORY COMMISSION (7.77)

L[CENSEE EVENT REPORT x ~ v- CONT'ROL BLOCK: {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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~os Ouring routine station operation with the TIP detectors withdrawn, ex-plosive charges in the TIP shear valves were replaced with new charges.

Following replacement. it was found that the ohmmeter continuity test for acceptable electric contact was unsatisfactory. The normal TIP tube i so ati on 1 system was operabl e at thi s time . An eval uati on of the sa fety implications is being conducted.

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~01 28 ATI'ACHMENT CODE 29 NPRD 4 TYPE

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COMPONENT TAKEN ACTION ON PLANT METHOD HOURS &22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~FI@~Z QIB ~ZQ20 ~Z Q21 0 0 0 7 Y Q23 ~N Q24 ~N Q25 G 0 8 0 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 D It was found that the actual electrical connections as ori inall wired were not as described in the Maintenance Procedure or in a re-vised GE drawing. The wiring was changed to a ree with the revised GE 3 dwg and al 1 four of the ol d squi b devi ces were detonated successful 1 8 9 80 FACILITY STATUS gg POIVER OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 Surveillance Testing 5 Qss ~Og g Qss NA MQ" 7 8 9 10 12 13 44 45 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITY LOCATION OF RELEASE QG EK LQQ33 7 8 9 10 z Q34 NA 45 NA 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~00 0 Qs z Qss 80 7 8 9 11 12 13 PERSONNEL INJURIES s ~00 NUMBER 0 Q4o DESCRIPTION NA Q

7 8 9 11 12 80 OSS OF OR DAMAGE TO TYPE Z

DESCRIPTION NA FACILITY Q

Q42 7 8 9 10 80 PUBLICITY O

ISSUED

~NQ44 DESCRIPTION NA Q NRC USC ONLY 7 8 9 10 68 69 80 o NAME OF PREPARER D.K. HacVittie 315-343-2110 x 1558

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NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARO WEST. SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 Feb/cuaIcy 28, 1978 hK. Bogce H. G/cie/c

'OMeeto/c United &ates Nuelea/c Regulato/cy CoInm@ sion Regi.on I 631 Parck Avenue King o) Ptuua~, PA. 19406 RE: Socket No. 50-220 LER 78-09/01T-0 hilne hKEe Pokery Nuclea/c S~n Unky ill Vea/c hh.. Gru.e/c:

'Outung /co~e a~on ope/cation wMk Che TIP dete&o/cs eithdrcawn, explosive eha/cges in She TIP System ahea/c valves wE/ce /cepLaeed at'h necks cha/cges. The, explosive opere+ted TIP ahea/c molafion valves a/ce a, back-up sgkem Co be ccsed (o/ckeolation of Che TIP Wbes in Che event MLe noC possible Co unit'hd/caw Che dMeMo/c so Che norunal acctomatie isolation acJ64em may (un~on.

Following /ceplaeeme&, pe/ctIoenance o) hfau<enance P/coeedu/ce, Nl-Ih(P-TIP-3 )ound Chat She ohmm&e/c eontinccity desk (o/c acceptable eleefru'.e eontaM was unsated (a&o/cy. The. no/cmal TIP Wbe ~option agtem was ope/cable at thks ~e.

IC was found Chat Nce anal elect/cical conne~ns Co Che explosive eha/cges we/ce nok as dese/u'.bed in Xhe Waintenance P/cocedu/ce. Gene/cal Electric NEO P/codu& Se/cvice was in(o/cmed of Che p/coblem and given Che nombetcs otI Che drcauccnga ccsed Co wi/ce She ac/stern. A /cession Co Xhe d/caceing, which had o/ciginaLLy beenksaued in Feb/cua/cy 1968, was Located.

The configu/cation shown in ChQ /cevmion would eaccse 4he efia/cger W $ ~e.

The, wi/cing )o/c +Ring She cluvcgesin Che TIP Sy/tern was changed Co match Chat shown in 4he /ceded Chawing. ALL o( Che old eha/cges cue/ce CesC PAed ccsing Xhe wrung achene, shown in .the. /ceded drawing. Thecal all

$ i/ced success (ulled.

A /ceview o) Xke P/ce-Ope/cMional Test o( ou/c Liquid Peon Sgakem showed Chat She explosive ahea/c valves in Chat system had been ope/cationaLLg Nested p/cio/c W a~p.

In ad~on Co Che wuu.ng p/coblems uncove/ced, Lt was )ound Chat Eke 2 AMP (ccses /ceqcurced in She squib circeccits we/ce instr< blow devices iIuskead otI Che slow blow 4ype speci.p.ed bg She vendo/c. ALL o) Ae (ccses in She mo>~o/c/co~oL units we/ce jceplaeed with new devices.

An evaluation o( She sate+ inIplicatiom is being conducted.

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NHCFOHhl 366 U.S,NUCLEAR HLUULAFOHYCOMMI543IUN (7 77 )

LICENSEE EVENT REPORT es 8 P~ CONTROL BLOCK {PLEASE PRINT OR TYPE ALLREQUIRED INFORMATIONI I 6 789LICENSEECODE1415 li P I Q2 0 0 0 0 0 LICENSE NUMBER 0 0 - 0 0 25 Qs 26 4 I I LICENSE TYPE I I 30 Q4~ 57 CAT 58 Qs CON 'T

~RT 488848 ~LQE 0 5 0 0 0 2 2 0 QT 0 2 0 4 7 8 Qs 0 2 2 8 Qs 8 60 6I DOCKET NUMBER 68 69 EVENT DATE 7475REPORT DATE E VE N T DESCRIPTION A N D PROBABLE CONSEQUENCES Q10 I

~02 Dui in stead state oaration erformanceof surveillance test Nl-ISP-

~os RE04, foun'dRE04D with asetpoint of 3.65PSI.T.S.3.6.2 reuires the drywall high pressure switches to have asst oint of 3.50PSI +-0.053

~06 PS I. Th i s c o n d i t i o n resulted i n m i n i m a safety 'plications.

1 Re d u n-

~06dant instrumentation was ava i abl e 1

~08 80 7 8 9 SYSTEM CODE CAUSE CODE CAUSE SUBCODE COMPONENT CODE C0M PVA SUBCODESUBCODE LVE 7 ' 9

~18 I0 Q>>

II E QE2 ~E I2 QE3 I3 I N S T R U I8 Qi ~S I9 QEE ~Z 20 Qis, SEQUENTIAL OCCURRENCE REPORT REVISION 212223+

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QTT REPoRT ~78 ~01 24 0

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~03 28 29

+L 30 3I 32 ACTION.FUTURE EFFECT SHUTDOWN ATTACHhiENTNPRDPPRIh'IECOhiP. COh'IPONENT TAKEN ACTION ON PLANTRIETHOD HOURS Q22 SUBMITTED FORMSUB.SUPPLIER MANUFACTURER LIQERQERLIQERQTooooQ227Q24NQoDDQ.

33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION ANDCORRECTIVE ACTIONS Q27 0RE04Da Barton Model 289res sure i ndi cat i n switch dri fted from a se t o i n t of 3 5 5 P S I It wa s reset t o 3 5 0 I

~ ~ ~ PS . Current surveillance tes ti nschedul es arcade uate to i nsure earl detection of future 3 instrument dri fts 7

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7 8

8 8

9 9

FACILITY STATUS E

ACTIVITY

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CONTENT RELEASED OF RELEASE I0 Z

%%d PERSONNEL EXPOSURES POWER Q34 9 3 Qs I2 NA I3 OTHER STATUS NA AhiQUNTQF ACTIVITYQB Q

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~B 45 Q31 45 46 NA Survei 1 1 DISCOVERY DESCRIPTION Q32 ance Testing LOCATION OF RELEASE Q36 80 80 80 NUMBER TYPE DESCAIPTIONQ39

~l7 ~00 0 QET ~ZQ28 NA 7 8 9 II I2 I3 80 PERSONNEL INJURIES NUMBER 0E SC B I P 7 I 0 N Q41

] ~00 0 Q4o NA 7 8 9 II I2 80 LOSS OF OR DAhiAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q42 NA 7 8 9 I0 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION 0 ~NQ<<NA 2 7 8 9 I0 80 NAME DF PREPARER D~ K.MacVi ttie PHoNE 3 1 5 -34 3 -2 1 1 0 x 1 558 0 O

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