ML17285A578

LER 89-005-00:on 890311,of 185 Control rods,34 Drifted Inward from One to Seven Notches Due to Momentary Low Scram Air Header Pressure.Caused by Main Steam Radiation Monitor Design deficiency.W/890616 Ltr

ML17285A578
Person / Time
Site:	Columbia
Issue date:	06/16/1989
From:	FULLER R E, POWERS C M WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-005-01, LER-89-5-1, NUDOCS 8906290239
Download: ML17285A578 (12)

Text

REGULATORY INFORMATXON DISTRIBUTXON SYSTEM (RIDS)ACCESSION NBR:8906290239 DOC.DATE: 89/06/16 NOTARIZED:

NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION FULLER,R.E.

Washington Public Power Supply System.POWERS,C.M.

Washington Public Power Supply System R RECI P.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 89-005-00:on 890311,multiple control rod drifts caused by momentary low scram air header pressure.W/8 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR i ENCL (SIZE:/TITLE 50.73/50..9 Licensee Event Report (LER), Incident Rpt, etc., NOTES D S RECIPIENT ID CODE/NAME PD5 LA SAMWORTH,R INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DS P/TPAB DEDRO NRR/DEST/ADE 8H NRR/DEST/CEB 8H NRR/DEST/ICSB 7 NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NUDOCS-ABSTRACT RES/DSIR/EIB RGN5 FILE 01 EXTERNAL: EG&G WILLIAMS,S L ST LOBBY WARD NRC PDR NSIC MURPHY,G.A COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 4 4 1 1 1 1 1 1'RECIPIENT ID CODE/NAME PD5 PD ACRS MOELLER AEOD/DOA AEOD/ROAB/DSP IRM/DCTS/DAB NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/PEB 10 RPB 10 RE FILE 02 S/DS PRAB FORD BLDG HOY g A LPDR NSIC MAYS,G COPIES LTTR ENCL 1 1 2 2 1 1 2 2 1 1 1 0 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 NOZE XQ ALL'RING" RECIPES: PURSE HELP US'Io REDUCE%ASTE!(EPZACZ'QK DXUNEÃZ CONZBOL DESK, RXH P1-37 (EXT.20079)TO ELIKBQXB YMR NAME PKH DIPZRIBVXXCH LISTS PER DOCUMENXS VXJ IXRPT NEEDf FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUXRED: LTTR 43 ENCL 42

~A~WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George 11'ashinglon Way~Richland, 1l'ashington 99352 Docket No.50-397 June 16, 1989 Document Control Desk U.S.Nuclear Regulatory Comission Washington, D.C.20555

Subject:

NUCLEAR PLANT NO.2 LICENSEE EVENT REPORT NO.89-005

Dear Sir:

Transmitted herewith is Licensee Event Report No.89-005 for the WNP-2 Plant.This report is submitted as an informational LER and discusses the corrective actions taken, and actions taken to preclude recurrence.

Very truly yours, C..owers (M/D 927M)WN Plant Manager CMP:lg

Enclosure:

Licensee Event Report No.89-005 cc: Mr.John B.Hartin, NRC-Region V Mr.C.J.Bosted, NRC Site (M/D 901A)INPO Records Center-Atlanta, GA Ms.Dottie Sherman, ANI Mr.D.L.Williams, BPA (M/D 399)8~0625'0235'<7+<>

g 6 F'DR ADOCK 05gc~i03yy PDC NRC Fnm 355 (9 53)'ICENSEE EVENT REPORT ILER)r~UPI NUCLEAR AE COLA'TO AY COMMISSIONLN APPAOVED OMS NO.31500104 EXPIRESI SI3)ISS FACILITY NAME (II DOCKET NVMSER (1(rACE I3l Washin ton Nuclear Plant-Unit 2 0 5 0 0 0 3 97 1 OF]0"'""'Multiple Control Rod Drifts Caused by Momentary Low Scram Air Header Pressure Due to Multi le Ra id Half-Scram Tri s and Resets EVENT DATE ISI YEAR OAY MONTH YF.AA LEA NUMBER IS)AEPOAT DATE (7I iC<<<<5ECVENTIAL i%'or HVMSEIa OAY YEAA REvrlrotr MONTH CiQ: IIVreEER DOCKET NVMSERISI 0 5 0 0 0 FACILITY IIAse55 OTHER FACILITIES INVOI.VEO (SI 0 3 8 9 005 0 006 1 6 8 9 0 5 0 0 0 OP E R AT IN 0 MODE lol]POWER LEYEL 0 7 8+4'...-'<<5<'

4v.I%6<<., c<<6<<I+gyp THIS REPORT IS SUSMITTED PURSUANT TO THE AEOVIREMENTS OF 10 CFA ('I: ICntra Ont Ol mete Ol rnt IOIIOtnnI)

IIII 20.405(cl 50.35(clll) 50.35(cl Ill 50.73(~I(2 IIII 50.73(el(2)(E) 50.73(el(1)(llrl LICENSEE CONTACT FOR THIS LEA 112)20.l02(bl 20.405(~Ill)Ill 20.405 (e l(1 I (E I 20.40S I~I ll I (ill I 20.405 le I ll I lit)20.405 (e l(1)H)50,73(~I)2)lie)50.73I~I(2)(rl 50.73(~I (1)(alii S0.73(~I(2 IN)Ill(A)50.73(el l1)It)(I)ISI 50.73(el(1(la) 73.71(II)73.71(c)CTHE R Isptciiy in Aoro'ect otlow end in Teel.IYRc ferne 366AI X Informational NAME R.E.Fuller Com liance En ineer TEI,EPHONE NUMSEA AREA CODE 50 937 7-2 79 7 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCAISED IN THIS REPORT (13)CAUSE B SYSTEM S B COMPOsrENT 0 N MANVFAC TVREA G 0 0 EPOATASLE TO IIPADS 4Ãj$33 COMPONENT MANVFAC.TUREA EPORTASLE TO NPADS:~g$SUPPLEMENTAL REPORT EXPECTED (lll MONTH DAY YEAR YF5 III yn.comprert EXPfCTED SVSMISSION OATfl NO EXPECTED SVSMISSION DATE (151 ASSTAAcT (Limit to teoo rotter.I.e., epproeimertly liltnn rintlt Iptct rypttnitrtn linnl 115)Thi s i s an informational LER.On March ll, 1989, at 21:02 hours, 34 of-the 185 control rods drifted inward from one to seven notches due to momentary low scram air header pressure.The low air header pressure occurred subsequent to a very rapid series of Reactor Protection System (RPS)half-scram trips and resets which occurred over a period of approximately 1 to 2 seconds.The cause was a cyclic failure in the Channel HBH Main Steam Line (MSL)radiation monitor (MS-RIS-610B) high-voltage low inoperable sensing circuit which occurred coincident with resetting (one operator action),the RPS half-scram condition.

The root causes of the rod drift event include: 1)a MSL radiation monitor design deficiency which failed to anticipate the effects of a cyclic failure, and 2)'rocedure direction was less than adequate in defining the actions required when the underlying cause of abnormal operation of a safety related device is indeterminate.

The immediate.corrective actions to recover from the rod drift event included: 1)determine status of all control rods and verify no further drifting;2)verify no thermal limit was being exceeded;3)reduce fuel power below recommended fuel preconditioning limits;4)reestablish the desired rod pattern;5)trouble-shoot, rework, and test the MSL radiation monitor;and 6)restore reactor power to 78K.NRC Form 355 ro Ral NRC FEDm ESSA)843)~k<US.NUCLEAR REOULATORY COMMISSION LICENSEE IONT REPORT (LER)TEXT CONTINUA'Q4

'PPDDDDDDkkkD.DIDDkkkk EXPIRES: 8/3)/88~FACILITY NAME)))COCKET NUMBER)ll LER NUMSER Id)SEOVENTIAL:+DD REVISION NVMEER'NVMSER PACE (3)Mashin ton Nuclear Plant-Unit 2 TEXT///mace E/D/ce//mdv/DPd, II/E////PRE/HRC Fom/3ESAS)l)TI 0 s 0 0 o 97 89-0 0 0 0 o"1 0 Abstract (continued)

The corrective action to prevent recurrence is to perform a design review of the HSL radiation monitor drawer.Other corrective actions inclvde: 1)Abnormal Response procedures will be evaluated for consistency during periodic reviews;2)management policy relative to half-scram resets will be clarified and appropriate procedures revised;3)multiple rod drift related procedures will be modified to provide consistent direction, and 4)multiple rod drift scenarios will be included in the operator training program.There was no safety significance associated with this event.Calculations indicate that no thermal limit was exceeded.All safety systems were functional if necessary.

Plant Conditions a)Power Level-78K b)Plant Mode-1 (Power Operation)

Event Oescri tion On Harch ll, 1989, at 21:02 hours 34 of the 185 control rods drifted inward from one to seven notches due to low scram air header pressure.The low air header pressure occurred subsequent to a very rapid series of Reactor Protection System (RPS)half-scram trips and resets which occurred over a period of approximately 1 to 2 seconds.The driving signal for the rapid RPS trips and resets was the Channel"B" Main Steam Line (MSL)Radiation Monitor (HS-RIS-610B) rapidly cycling in and out of the trip and reset-to-normal condition coincident with a single RPS reset action.The HSL radiation monitor HS-RIS-610B is a Radiation Indicating Switch (RIS).An inoperable trip of.this switch causes: 1)a Hain Steam Isolation Valve (MSIV)half isolation trip on Channel"B";2)trip of the UB" Gland Steam Exhauster; and 3)a RPS Trip System"BU half-scram.

This switch has automatic reset-to-normal capability when the incoming signal that causes the switch to trip returns to within the trip setpoints.

However, the MSIV half isolation trip and RPS half-scram each require a manual reset.The UB" Gland Steam Exhauster trip is cleared with reset of the HSIV half isolation trip.The same MSL radiation monitor had undergone a similar trip/reset-to-normal cycling a few hours earlier at 1813 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.898465e-4 months <br />.The Reactor Operator, within a few seconds of the RPS Trip System"B" half-scram trip, attempted to reset the half-scram.

Operators subsequently heard the RPS relays (K14)cycle rapidly between the energized and deenergized state before the half-scram was reset-to-normal.

The HSL radiation monitor stabilized and Maintenance Technicians were requested to trouble-shoot the MSL radiation monitor drawer.Trouble-shooting activities were delayed since Technicians more knowledgeable on the radiation monitor instrumentation were due in at shift turnover, at approximately 22:30 hours.NRC FORM SESA l9 R)t l DURST CTOD)9dd~)CE)))DIEI)90 NRC Form 3SSA l043l LICENSEE T REPORT tLER)TEXT CONTINUA U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OM8 NO.3IS0-0104 EXPIRES: 8i31(88~FACILITY NAME III Washin ton Nuclear Plant-Unit 2 TEXT N more spsseis required, oss sddio'oosl irRC'Form JMA'sl IITI OOCKET NUMSER 13l 05000397 YEAR 8 9 LER NUMBER Idl SEQUENTIAL NUMSEA 0 0 5 AEVISION NVMSEA 0 0 PAGE ISI 0 3oF At 21:01:47 a rapid series of tri p/reset-to-normal cycles occurred, initiating another ov eral 1 period of HSL radiation monitor inoperable ins tabi 1 i ty.Th js overall period of instability lasted approximately 125 seconds until it was placed in"STANDBY", thus sealing in the inoperable trip.There were six distinct periods within the event in which the NSL radiation monitor experienced rapid cycling and/or was stabilized in the tripped condition.

It was during the first period of cycling that multiple control rod drift indications were observed.The control rod drift event is described as follows.21:01:47.3 A RPS Trip System NBN half-scram occurred due to an inoperable trip on MS-RIS-610B; As a result;the 185 Control Rod Drive (CRD)scram air pilot valves (CRD-SPV-118), one'n each Hydraulic Control Unit (HCU), moved to their scram position.This was the beginning the first period of the NS-RIS-610B instability.

The RPS scram contactor (K14 relay)de-energizes when the radiation monitor trips.The RPS reset pushbutton re-energizes the scram contactor when no trip signal exists.While the reset pushbutton is depressed, the tripping and resetting of the radiation monitor also cycles the scram contactor.

Cycling of the scram contactor cycles the CRD scram air pilot valve (CRD-SPV-118) on each HCU.See Figure'-for piping schematic of the scram pilot valves and the scram valves for one HCU in the normal operation configuration and Figure.2 for the RPS Trip System"BN half-scram configuration.

Energizing the CRD SPV 118 to the vent position vents a small portion of the instrument air piping between the scram air pilot valves (CRD-SPV-117 and CRD-SPV-118) to atmosphere.

While the solenoid valve is rapidly changing position, a scram air header vent path is also established for a short time.21:01:54 A scram air header high pressure alarm occurred.NOTE: Historically, a high pressure alarm has occurred on the scram a>r header following a RPS Trip System NBN half-scram actuation.

The high pressure response of the scram air header was attributed to air leaks in the HCUs, and regulator overshoot on a half-scram trip.This was concluded to have no effect on the rod drift event.21:01:57.5, RPS Trip System NBN half-scram reset-to-normal was recorded.While the RPS reset pushbuttons were depressed for 1 to 2 seconds, the scram.pilot valves=cycled due to the radiation monitor drawer repeated trip and reset.21:01:58.3 The high pressure scram air header alarm cleared and a low pressure alarm occurred.Between 21:01:57.5 and this point in time, a total of 13 trip/reset-to-normal cycles were recorded for/IS-RIS-6108.

NAC soAM 344*ro 441~II.S~CSOr leds STC de NRC Form 866A e., UA.NUCLEAR REGULATORY COMMISSIONr LICENSEE IjltIT REPORT (LERI TEXT CONTINUA4 APPROVEOOMB N0,3INMIDl EXPIRES: 8/31/88 FACILITY t/AME)ll Washington Nuclear Plant-Unit 2 TEXT///moIO/Oooo/o Iud/rud, uoo odd/dorN//VRO fonII 368A 8/117)OOCKET NVMSER)1)0 s o 0 03 97 89 LER NUMBER)6)+~SEQUEN'TIAL KN NUMSEII-0 0 5 j..66 REVISION.rrXC NUMSER 0 0 PAGE)3)0 4oF1 0 21:02:00.2 MS-RIS-610B reset-to-normal whichwas the end of the first period of rapid cycling.A total of 15 trip/reset-to-normal cycles were recorded since 21:Ol:57.5.

21:02:00.3 A rod drift alarm occurred at this time.The operator was aware that a rod drift alarm had occurred and saw several rod drift indications.

• The MSL radiation monitor had five more periods of rapid cycling.The RPS Trip System"B" half-scram was reset-to-normal following each of the four periods.These later events did not affect the rod drift event or result in any additional rod drift events because the scram-reset pushbuttons were not in the reset position during the MS-RIS-610B cycling.21:02:04.3 The scram air header low pressure alarm cleared.21:03:53.7 The MS-RIS-610B switch was placed in"standby", thus sealing in the inoperable trip.Immediate Corrective Action The following is a chronological description of the events and corrective actions immediately after placing the MS-RIS-610B switch in"STANDBY".21:05 The Plant Operators reviewed the applicable procedures.

Assessment of control rod status was begun by the Shift Technical Advisor.21:08 The Shift Manager ordered a reduction in power from 78K to 75K.The Reactor Operator confirmed that a large number of rods were at incorrect positions.

21:15 Based on input from a Plant Nuclear Engineer, the Shift Manager ordered Plant power reduced 10K.21'21 Reactor power was at 72.1%.A core performance monitor calculation was initiated at this point.21:25 Reactor power was at 65.6%.A second core performance monitor calculation was initiated at this point.21:30 21:35 The core performance calculation at the 72.1%power conditions was completed.

Review of core performance edits indicated a wide margin to all thermal limits existed.Review of fuel preconditioning edits indicated 63 nodes had exceeded the fuel preconditioning envelope, up to a peak of 1.5 kw/ft.The core performance calculation at the 65%power conditions was completed.

Review of edits indicated there were only four nodes still over the preconditioning envelope, up to a peak of 0.67 kw/ft.Based upon further input from a Plant Nuclear Engineer, the Shift Manager ordered core power reduced to 35%to reestablish the rod pattern.NRC POIIM SESA I9 8))~V.S.CPOi)966 AS)C SSF EOOTO NRC Form 3)ISA IS@3)'I/A.NUCLEAR REGULATORY COMMISSION/

LICENSEE tIIT REPORT (LER)TEXT CONTINUA~APPAOVEOOMBN0.3ISD-OIDI EXPIRES: S/31/ES I FACILITY NAME II)DOCKET NUMSER)3)LER NUMBER IE)Fqg<SEOUENTIAL dgj.REvrSION NVMEE/l 4 NUMSErl rAGE)3)Washin ton Nuclear Plant-Unit 2 TEXT I/I//lore s/lese Is rsr/o/red, os@edd I/orrs/HR forrrr 3//rr)A'sl

)1)l 0 5 0 0 0 3 9 7 005 0 0 0 5 OF 22:30 22:45 22:54 23:47 3-12-89 Reactor power was at 47.3%.A core monitor performance analysi s determined a wide margin (at least 16K)to all thermal limits existed throughout the event, and that the highest power node was 2.1 kw/ft above the fuel preconditioning envelope.There were no signs of fuel clad damage.Work had begun to recalibrate the high-voltage low inoperative setpoint of MS-RIS-610B.

Reactor power was at 36.5%.Plant Operators initiated restoration of the rod pattern.MS-RIS-610B was returned to normal operation following recalibration.

Reactor power was at 36K.The appropriate control rod pattern for return to rated power was reestablished.

Reactor power increase was started.02:14 Reactor power was at 78%.Further Evaluation and Corrective Actions A.Further Evaluation 1.This event was determined to be nonreportable for the following reasons.a.There were no Technical Specification limits exceeded during or following the rod drift event.b.The rod drift event did not result in conditions that fell outside of the design basis or safety analysis envelope of the plant.The integrity of the plant safety barriers were not compromised or degraded.c.All safety systems were functional to perform their intended function in the event any would have been needed.2.The cause of the Channel"B" MSL high radiation monitor indicating switch (MS-RIS-6108) was the"High Voltage LowU trip setpoint had drifted upward to equal the normal high voltage operating value.Since the logic circuit is a reset/set flip-flop, the condition"equal to" is indeterminate.

Therefore, a high voltage just equal to the trip setpoint,causes the rapid trip/reset-to-normal cycling to occur.A detailed review of other RPS trip inputs determined the possibility of this type of failure is less likely to happen from other similar input trips due to the design hysteresis of the trip logic, i.e., the dead band or the difference.between the tri p/reset-to-normal values is not zero.NnC rOrlM Sr)EA~U.S.Crcr IEEE 33F)ES OEOTO NRC ForrR 358AIS 83l.UA.NUCLEAR REGULATORY COMMISSION LICENSEE T REPORT (LER)TEXT CONTINUAT=APPRovfooMB No.3IEO&I04

'""'XPIRES: 8/31/88 FACILITY NAME (II OOCKET NUMBER ISI LER NVMSER ISI (gI SEQUENTIAL I~sl REvlsloN NUMSSA N%NUMSSR~AGE IS)Washington Nuclear Plant-Unit 2 TEXT Ld mrsrs s/ssss/s rssrr/ItN/

v>>sdd/drms/H/IC forrlr 3884's/IITI o s o o o3 97 8 9-0 0 0 0 0 6 OF The cause of the rod.dri ft event was the rapid cycling of the RPS relays/solenoids during the period of time the RPS reset pushbuttons were depressed, thus allowing the scram air header (local effect only)to vent to atmosphere.

3.The root causes of'the rod drift event include: 1)a design deficiency in that the MSL radiation monitor inoperable trip circuitry did not anticipate the trip/reset-to-normal cycling problem associated with voltages equal to the trip setpoints and 2)the Plant procedure lacked specific guidance regarding necessary actions to be taken when the underlying cause of abnormal operation of a safety related device is indeterminate.

a.The problem was not anticipated in that the MSL radiation monitor inoperable trip is the only RPS trip signal in which the design values for trip and automatic reset are equal.Had the monitor been designed such that the trip/reset values were different, as is the case with the other monitors, e.g., intermediate range monitors, the rapid tri p/reset-to-normal cycles would have been avoided.b.The Reactor Operator assessment and immediate response to the first inoperable trip of the radiation monitor was appropriate.

Specifically, the cause or source of the trip was identified to be the MS-RIS-6108, the inoperable trip condition had cleared, the process variable indications were normal compared to redundant equipment, the trip circuitry was functional, and the RPS half-scram was able to be reset.Appropriate subsequent actions were taken by the Shift Manager which included initiating.a Problem Evaluation Request (PER)per Plant procedures and requesting trouble-shooting for the underlying cause of the radiation monitor inoperable trip.When the second radiation monitor inoperable trip occurred, the underlying cause of the first trip'ad not been identified and corrected.

The Reactor Operator r'esponse to the second trip was similar to the first and appropriate per the existing procedures.

However, the Plant Abnormal Response procedures lacked specific guidance regarding appropriate response to subsequent abnormal operation of an inservice safety related device that has previously undergone abnormal operation and the underlying cause of the abnormality remains indeterminate.

The operational event was reviewed and analyzed to determine the best operational response to the event.It was determined that upon receipt of initial indication of any rod drift, the direction is to immediately reduce total core flow to 45K of rated within 30 seconds.This core flow represents a condition where even for extremely limiting control rod patterns, the power distribution would not violate either fuel thermal'limits'r fuel preconditioning guidelines.

This was determined to provide acceptable compensation for the worst case event.If a complete loss of scram air header pressure is indicated, or if more than one control rod continues to drift in, direction is given to manually, scram the reactor.NRC FOAM SSSA A r'r'0.5~CPOr I955 5;959 NRC Fo/m 3664 IQ43l LICENSEE E T REPORT (LER)TEXT CONTINUA U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMS NO.3IEO&104 EXPIRES: 6/31/88 FACILI'TY NAME ill DOCKET NUMSER (1l LER NUMSER l6)SEOVENTIAL NVM ER Re.y.ix'6 REVISION NVMSER PACE l3)Mashington Nuclear Plant-Unit 2 0 s o o 0 3 9 7 9 TEXT///more Z>>ce/e requ/red.uee edd/o'or>>/HRC

%%dmI 3SSI'e/I ITl 0 0 5 000 7 0F 1 5.The previous training on rod-drift events involved only the inward drift of a single rod during simulated startups.B.Further Corrective Action 1.Evaluate a design change of the MSL radiation monitor drawer which would preclude rapid trip/reset output signals from being generated.

2.Management has evaluated the current practice related to half-scram resets.Their expectations will be comunicated to the Licensed Operators and appropriate procedures revised.3.All.Abnormal Response procedures will be evaluated during periodic reviews to minimize ambiguity and ensure consistency of direction.

4.All procedures related to multiple rod drifts have been identified and modified to provide consistent direction.

5.Multiple rod drift scenarios will be included in the licensed Operator simulator training program.Safety Si nificance There is no safety significance associated with this event.Calculations indicate that thermal limits were not exceeded.Calculations, performed for a reactor power of lOOX at less than a half cycle core burnup with a worst case rod configuration, indicated that fuel power conditions might have reached or slightly exceeded Technical Specification thermal limits;Slightly exceeding thermal limits is not safety significant provided timely action is taken'o restore the Plant to acceptable conditions.

Technical Specification Safety Limits would not have been exceeded.'or greater than half cycle burnups, no thermal limits would be exceeded.This event occurred near the end of the fuel cycle.All safety'ystems were functional in the event cladding damage occurred.Had either immediate or latent cladding damage occurred, the Division I MSL radiation monitors were available to complete the RPS scram signal input if radiation levels exceeded trip setpoints.

The MS-RIS-610B had been placed in"STANDBY", which sealed in a Division II half-scram.

Also, Offgas System isolation capability was available to ensure against excessive radionuclide release to the environment in the unlikely event radiation levels exceeded preestablished setpoints from fuel failure.The administrative limits imposed by the WNP-2 Technical Specifications would also have prevented sustained plant operation at elevated radionuclide release rates.Therefore, this event posed no threat to the health and safety of the public or plant personnel.

Similar Events None":~S~CPP~It!.S C S!)OOO NRC For/n dddA (843)LICENSEE EIT REPORT (LER)TEXT CONTINUATN UA.NUCLEAR REOULATORY COMMISSION APPROVEO OMB NO.3(50-OIOd EX PIR ES: 8/3//88 FACILITY NAME (Il OOCKET NUMBER (El YEAR LER NVMBER (dl 5EOVENTIAL NVM ER.ib REVISION NUMBER PACE Ldl Washin ton Nuclear Plant-Unit 2<<<<o 3 9 7 TEXT////nord dpddd l/reqv/red, II/d dddWonN HRC'Fern 3BBA8/(lll 8 9 0 0 0 0 8 OF EI IS Information Text Reference EI IS Reference System Component Instrument Air Supply (Control/Service Air System)Instrument Air Supply (Pressure Control Valve, CAS-PCY-2)

Instrument Air Supply (Air Filter)Control Rod Drive System Control Rod Drive System (Scram Solenoid Pilot Yalve, 185 each CRD-SPY-117)

Control Rod Drive System (Scram Solenoid Pilot Yalve, 185 each CRD-SPV-118)

Control Rod Dt ive System (Scram Valve, 185 each CRD-Y-126)

Control Rod Drive System (Scram Yalve, 185 each CRD-V-'l27)

Main Steam System (Radiation monitor, NSL-RIS-610B)

Offgas System Reactor Protection System Annunciator System.Reactor Protection System LD LD LD AA AA AA AA SB WF, JC IB JC PCY FLT VTV VTV LOV LOV NnC FOnM SEEA U.S.Cl'0<Iddd 5/d Sdd 400/II I g II 1t~t il'~tl 4I Q2 Ek n 0 a 3 CI CONTROL/SERVICE AIR SYSTEM CAS-PCV-2~l C J M 4 INSTUMENT'IR HEADER a.'e M Mo ECI O n I C z III 2 IO"5n O m Z Ul m m CRD-SPV" 117 CRD-V"116 EXHAUST: CRD",SPY-118

~~.RPS CHANNEL'B'PI Z C 3 D QÃm 0 O.lTl m X, 0 0 z a n O E8~P~I~0 o hCCUMULhTQR AND CHARGIN VhTER CRD-V-126 RPS CHANNEL:h DRIVE VATER DRIVE MATER (INSERT CONTROL'VITHDRAV ROD DRIVE)FROM CONTROL ROD DRIVE)CRD-V-127 tD CD Vl O II Dn CC 3 III aa l%K Dy I-ZD c~3a (III j5 I D D n C iII Pre 0 g III (Zo-D~Ola 3le me 0 0 Q D'S~n L;3 o i3 ,L (o)