ML20009E719

Revised LER 81-008/03X-1:on 810120,during Shutdown Maint & Primary Coolant Pressure Scram Calibr,Voltage Outputs of Pressure Transmitter Discovered High.Caused by Instrument Drift.Transmitter Calibr.Surveillance Test Completed

ML20009E719
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/18/1981
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20009E712	List: ML20009E711 ML20009E719
References
LER-81-008-03X, LER-81-8-3X, NUDOCS 8107280387
Download: ML20009E719 (1)

Text

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• NRC.#07M'56 U.S. NUCLEAR REGULATORY COMMISSION (7 77)

LICENSEE EVENT REPORT CONTROL BLOCK: l 1

l l l l l lh 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

Io IiI8 IC 10UCENSEE Iv isCODE Iv ii l@l0 10 l- 10 10uCENSE 10 NUMBER 10 to l in in l25@ l4 26 11LICENSE 11 12TYPE 10JOl@l57 CAT 58I@

7 9 14 15 CON'T loIil 7 8 SObRC 60 lL @l0 l DOCKET 61 5 l010 10 12 l6 NUMBER 68 l769hl0 EVENT 11 12 DATE lo l8 l1 hl0 l6 74 75 Il l DATE REPCRT 8 i8 l180l@

EVENT OESCRIPTION ANO PROBABLE CONSEQUENCES h I o 12 l l During a shutdown maintenance period, instrument personnel nerformed the orimarv I l o t a l l coolant pressure scram calibration and found that the voltage outputs of the three - _]

l o 141 l pressure transmitters were high and could have caused the primarv coolant low pressurel This is being reported l g g ] switches to trip below the limits of LCO 4.4.1, Table 4.4-1.

lo is l l per Fort S t. Vrain Technical Specification AC 7.'5.2(b)1 and AC 7.5.2(b)2. ~ No effect l 1017 l l on public health or safety. No affect on plant operatio'n. Similar occurrences RO l

,o,g, ; 79-57 and RO 77-46. [

7 8 9 C DE CODE SUSC E COMPONENT CODE SU8 CODE SU E lo19l l Il Bl@ W@ l E l@ l1 lN lS lT lR lU [@ lE l@ g @ 13 i8 19 20 7 8 9 10 11 12 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT No. CODE TYPE No.

@ aEg LER Ro l-l l0 l0 l8J26 y [0 l3 29l l X[ g y u

_ l2i8 l1J 22 23 24 27 28 30 31 32 KN AC N ON PL NT ME HOURS S8 I FORi 8. SUP l MANUF C RER LsJ@LvJ@ L7J@ Izl@ 101010101 IY l@ l42N l@ lNl@ l44G l 0 l 6 l 347 l@

33 34 J5 36 31 40 41 43 CAUSE OESCRIPTION AND CORRECTIVE ACTIONS 11 101 l The hieh outout vo le ne s from th e n ra s s ura *r,"amitrare Jere d"a *m i n e rn an" d ** #

• I The c res sure ernnamierare 2 ara c,14k- e d and eka enr- I

, W [,of - the cressure t ran smit te r.

l 1, i , i l veillance tes t successfully como le te d. Once a month (when the reactor is nressurized .

l,l3l l above 400 psia), on a temporarv basis, the oressure transmitters v.oltage outputs will l

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I i I 41 l_be chec_k_ed against reactor oressure to dety.dne if further instrumen t drif t is oc-  !

7 8 9 curring.

This will continue unti the next "calibration or it is determined no cali 80 30 $iSEoNRY" oiSCOvERY oESCRiPTioN @bration drif t

2NIS ST

• POWER oTHER STArVS l l B l@l Scheduled Surveillance Test is occurTling.

l l1 l 5 l lG l@ l 0 l 0 l 0 l@l N/A A TIVITY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Ii Ie l lz l @ Lzj@l N/A I l N/A l 7 8 9 10 tt 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION l

l i 171 10 10 lo l@lz l@l N/A 80

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• PERSONNEL iNau'R,,, 2 i3 NUMBER oESCRiPTiON@

l li la 8l 9lo lo lo l@l N/A 7 11 12 80 l

l LOSS OP OR DAMAGE TO FACILtTY I TYPE DESCRIPTION l t 9 l 7 8 9 I z l@l N/Ato '

80 l

PuBUCITY c 8107280387 810618 NRC USE ONLY

• iSSuEo cESCRiPTioN U PDR ADOCK 05000267 i

12 i ol l N l@l N/A S PDR l llllIlllll11II 7 8 3 to 68 69 80 ;;

NAME OF PREPARER b PHONE:

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