ML18018B263

LER 78-011-00, LER 78-012-00 and LER 78-013-00 for Nine Mile Point, Unit 1 Re Technical Specification Violations of Section 3.6.2

ML18018B263
Person / Time
Site:	Nine Mile Point
Issue date:	03/16/1978
From:	Schneider R Niagara Mohawk Power Corp
To:	Grier B Office of Nuclear Reactor Regulation, NRC Region 1
References
NMP-0139 LER 78-011-00, LER 78-012-00, LER 78-013-00
Download: ML18018B263 (10)

Text

REGULATORY INFORI'fATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-220 REC: GRIER B H ORG: SCHNEIDER R R DOCDATE; 03/i6/78 NRC NIAGARA MOHAWK PWR DATE RCVD: 03/22/78 DOCTYPE: LFTTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR i ENCL LICENSEE EVENT REPT (RO 50-220/78-0ii) ON 02/26/78 CONCERNING LOW LEVEL ALARM ON ONE CHANNEL OF THE RX BLDG VENTILATION RADIATION MONITOR INDICATED EQUIPMENT FAILURE. CAUSED BY FAILURE OF A GEN ELEC RN04B-5 SENSOR... W/ATT LERS 78-i2 8. 78-i3.

Pl AINT NAME: NINE MILE PT UNIT i REVIEI JER INITIAL: X JM DISTRIBUTOR INITIAL: ~

ssWn<H>+cHH>cs+clw+wes+ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION: BR CHIEF AR++W/4 ENCL I NTERI4AL: . C" NRC PDR44W/ENCL I 8. E~H~W/2 ENCL MIPC+4W/3 ENCL SCHROEDER/IPPOL ITO+4 W/ENCL HOUSTON4+W/ENCL NOVAK/CHECK+4lW/ENCL GR IMES++W/ENCL KNIGHT~AHJ/ENCL BUTLER4+W/ENCL HANAUER~~~W/ENCL TEDESCO++W/ENCL E I SENHUT<<~W/ENCL BAER~~~W/ENCL SHAO~~~~W/ENCL VOLLMER/BUNCH++W/EI4CL KREGER/ J. COLL INST< l J/ENCL ROSA~~~W/ENCL K SEYFRI 7/IE'H~W/ENCL EXTERNAL: LPDR S OSWEGO'Y++W/ENCL TI C~4iW/ENCL I

NS C+4f W/ENCL ACRS CAT B++W/i6 ENCL COPIES ilOT SUB'.JITTED PER REGULATORY GUIDE 10. 1 DISTRIBUTION: LTR 45 ENCL 45 CON OL NBR: 780830073 SIZE: iP+iP+2P

%%%4%%%%4M%%%%4%%%%%%%%%%%%0HH8%0&%%% THF END

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Mh(P-0139 NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST. SYRACUSE, N,Y, 13202/TELEPHONE (315) 474-1511 Wa/I.ch 16, 1978 ilia. g )ig IP

~A 5 1lf'~~1 I'I h(tL. Bogce H. Gtu'.e/L Nlte&otL United Statm Mulct'eats ReguZatotI.y Commission Region 7

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631 Pa/Lk Avenue

~g o$ PtuL5aka, PA. 19406 i>

RE: Socket Mo. 50-220 VeatL &L. Gtu'.etc:

7n accotIdance Ioith Mine NXe Point MucZeatL S~on UILt <1 TechIu.e+E Speci.pcatioru, IIIe herceby submit LiceIIt ee Evert RepotLt5, LER 78-11, LER 78-12, and LER 78-13, IIIhich atI.ein vioLation o(

Section, 3.6.2 o( Xhe Technical Speci+cat'ioIm.

The5e tLepo~ uIette completed in Che (otImat de5ignatedin MUREG-0161, dated JulI/ 1977.

Vetch Wut'y poult, ORIGIMAL SIGMEO BY R.R. SCHMEIVER R.R. SchneidetL Vice Pri.widen.t-Et'.ecttu'.c PtIodu~on Attachments (3 copie5) xc: Pmecto/L, 0)pce o) 78E (30 copie5)

NrcectotL, 0)pce o( WIPC (3 copiet) 780830073 4

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N AC I'ORM 3GG U. S. NUCLEAR REGULATORY COMMISSION I7 77)

LICENSEE EVENT REPORT CONTROL BLOCK:

I ,Q {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~o 7 8 9 N Y N LICENSEE CODE M P 1Q2 14 15 0 0 - 0 0 0 LICENSE NUMBER 0 0 0 0 25 Q3 26 4 1 1 LICENSE TYPE 30 Q4~Q5 57 CAT 58 CON'T

~01 7 8

'o"'~LQG 60 61 0 5 0 0 0 DOCKET NUMBER 2 2 OQ 68 69 2 2 EVENT DATE 6 7 SQBO I4 75 3

REPORT DATE 80 Q

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO During steady state o eration a low level alarm on one

~53 Rx . Bldg Venti 1 ation Radiation Noni tor indicated e ui ment'ai 1 ure .T. S .

3.6.2J requires both channels of this s stem to be o erational. This condition resulted in minimal safety implications. The redundant monitor was functionin .

~OB 80 7 8 9 SYSTEBI CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~OB ~BB Qii E Q12 ~EQ13 I N S T R U Q ~EQ ~2Cml 7 8 9 10 ll 12 13 18 19 20 REVISION SEQUENTIAL OCCURRENCE REPORT Q'2 LFRIAO

<<2<<2 ACTION . FUTURE EVENT YEAR

~78 21 22 EFFECT

+

23 SHUTDOWN

~01 24 REPORT NO.

1 26

+a 27

~03 28 ATTACHMENT CODE 29 NPRDA TYPE

+t 30 PRIME CohlP.

31 QO 32 NO.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBhllTTED FOAM SUB. SUPPLIER MANUFACTURER L~JQ15 ~~Q15 ~~Q25 ~~Q21 0 0 0 0 ~~Q23 ~YQ4 ~NQ25 8 0 8 0 Qss 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o A General El ectri c RN048-5 sensor fai 1 ed and was repl aced. The new sensor was tested per N-RTP-23 to verify calibration and insure ro er 4

response.

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~l4 80 7 8 9 FACILITY hiETHOD OF STATUS '4 POWER OTHER STATUS QBO D I S COY E AY DISCOVERY DESCRIPTION Q32 5 E Q2s ~0099 9 9Q so N ~AQ3) Alarm in Control Room 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE NA AMOUNT OF ACTIVITYQ35 LOCATION OF RELEASE Q G ~Z Q33 Z Q34 NA 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~00 0 Q32 ~ZQ35 NA 80 7 8 9 II 12 13 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 B Z Q42 NA 8 9 10 80 PUBLICITY

~2o ISSUED

~NQ44 DESCRIPTION NA Q NRC USE ONLY 7 8 9 10 68 69 80 o D.K. MacVittie 315-343-2110 x 1558 0 NAME OF PREPARER PHONE:

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NRCscORM 3GG U. S. NUCLEAR IIEGULATORY COiYIMISSION (7.77)

I LICENSEE EVENT REPORT sv CONTROL BLOCK: Qi (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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~01 N Y N M P IQ20 0 - 0 0 0 0 0 - 0 OQ34 1 1 1 I QR~Q5 7 8 9 LICENSEE CODE 14 15 LICENSE NUhIBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T

~01 "o,~LQ8 0 5 0 0 0 2 2 OQ2 0 3 0 3 7 8Qs.

'75 0 3 1 5 80 Qg 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO During steady state operation, performance of surveillance test Nl-ISP-RE18, found RE180 with 8 setpoint of 129 inches WC. Required setpoint of the Rx Lo-Lo-Lo water level switch is 125 inches WC +2.0/-2.'6. This instrumentation was avail. able.

~OB

~OB 80 7 8 9 SYSTEM CAUSE CAUSE CORI P. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~og 7 8 9

~IB 10 Q1, 11 E ~5Q13 12 13 I N S T R 0 18 Q14 ~SQ15 19

~Z 20 Qs SEOUEN TIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT NO. CODE TYPE No.

Q2 LERIRO RRRRR2 ~78 21 22 Q

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~01 24 2

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~03 28 29

~L 30 31 32 ACTION . FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDA PRlh'IE COMP. COAIPONENT TAKEN ACTION ON PLANT METHOD HOURS 22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~ZQI 0 0 0 0 B 0 8 0 QJQIB 33

~QIg 34 QJQ2O 35 36 37 40 41 N

Q23 ~YQ24 42

~N 43 Q25 44 47 Q2G CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 RE18D, a Barton model 288 level indicating switch drifted from a set-point of 126.0 inches WC. It was reset to 124.5 inches WC. Current surveillance testing schedules are adequate to insure early detection 3

o f future i nstrument dri fts 4

7 8 9 80 FACILITY METHOD OF STATUS 98 POWER OTHER STATUS QBO DISCOVERY DISCOVERY DESCRIPTION Q32 5 E Q28 ~09 9 Q28 NA ~BQ3I Surveillance Testing 80 7 8 9 10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITYQ3G LOCATION OF RELEASE QG G ~Z Q33 ~ZQ34 NA NA 7 8 9 10 11 44 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q3g 2 ~00 0 JQ32 ~ZQ38 NA 7 8 9 11 12 13 80 PERSONNEL INJURIES 7

8 8

~00 9

0 Qso 11 12 NA 80 LOSS OF OR DAMAGE TO FACILITY Q43 7 8 9 10 80 O

ISSUED PUBLICITY DESCRIPTION ~ NRC USE ONLY 7 8 D.K. HacVittie 315-343-2110 ext 155&

NAME OF PREPARER PHONE:

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NRCRFORM 366 U. S. NUCLEAR REGULATORY COI'1MISSION (7 77)

LICENSEE EVENT REPORT

,Q

>> 0~I CONTROL BLOCK: (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

Y MP 1Q2 0 0 0 0 0 0 0 7 8 9 N N LICENSEE CODE 14 15 LICENSE NUMBER '5 Q3 26 LICENSE TYPE 30 57 CAT 58 CON'T

~o soURcE ~LQB 0 5 0 0 0 2 2 0 Q7 0 3 0 4 7 8QBO 3 1 5 80 QB 7 8 60 61 DOCKET NUMBER GB 69 EVENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO Durin stead state o eration erformance of surveil an

~0 3 RE04, found RE04A with a set oint of 3.37 si and RE04D at 3.40 si.

~0 4 Re uired set oint of these dr well hi h ressure switches is 3.50 si

~0 6 +/- 0.053 pis. This condition resulted in minimal safet im lications.

~0 6 All switches drifted in a more conservative direction,

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~OB 80 7 8 9 SYSTEM CAUSE CAUSE COSIP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8

~IB 9 10 QT7 11 E Q72 ~EQ72 12 13 I N s T R U 18 04 ~SQR 19

~E 20 O75.

SEQUENTIAL OCCURRENCE REPORT REVISION Q77 LF AIAO R 5PO R 7 ACTION . FUTURE EVENT YEAR

~78 21 22 EFFECT

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23 SHUTDOWN

~01 24 REPORT NO.

3 26

+~

27

~03 28 ATTACHhIENT CODE 29 NPRDR TYPE

+L 30 31 PRIh'IE COhIP.

+0 NO.

32 COMPONENT TAKEN ACTION gjigJQ19 33 34 ON PLANT gf 35 Q20 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 METHOD gJQ2 36 37 HOUAS &22 0

40

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SUBMITTED 41 Q23 FORM SUB.

~Q2 42 SUPPLIER

~N 43 Q26 44 MANUFACTURER 47 Q26 These changes in setpoints ex erienced on Barton Model 289 ressure indicating switches were due to instrument drift. RE04A was reset at 3.50 psi, and RE04D was reset to 3.50 psi. Current surveillance testing schedules are adequate to insure early detection of future instrument drifts.

7 8 9 80 FACILITY METHOD OF STATUS So POWER OTHER STATUS Q30 D I 5 6 OV E AY DISCOVERY DESCRIPTION Q32 5 E Q25 ~09 9 Qoo NA ~BQ31 Survei 1 1 ance Testing 7 8 9 10 12 13 44 45 4G 80 ACTIVITY 'ONTENT 6

RELEASED OF RELEASE Z NA AMOUNT OF ACTIVITY Q LOG AT I ON OF A E L 5 AS 5 Q

~Z Q33 Q34 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER 0 E SCRIPTION Q41 5 ~00 0 Qoo NA 80 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 0 Z Q42 NA 7 8 9 10 80 PUBLICITY

~20 ISSUED

~NQ44 DESCRIPTION NA Q NRC USE ONLY 8 9 10 68 69 80 D.K. MacVittie 315-343-2110 ext 15580 NAME OF PREPARER PHONE:

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