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Insp Rept 50-440/85-85 on 851202-06 & 09-13.No Violations Noted.Major Areas Inspected:Alarm Response Instructions. Errors Found,Including Setpoint Values Indicating Lack of Adequate Procedure Review
	ML20138N836
Person / Time
Site:	Perry
Issue date:	12/18/1985
From:	Knop R; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20138N815	List: IR 05000440/1985085; ML20138N813;
References
	50-440-85-85, NUDOCS 8512240176
	Download: ML20138N836 (7)
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REGION III

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' Report.No.150-440/85085'-

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WDocketTNoi50440i

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(LicenseNo.CPPR-148'

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' Licensee:LCleveland' Electric.Iiluminaf.ingCompany s

Post Office Box 5000~

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Cleveland,' OH 44101 s

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iFacility Name:

Pe'rry Nuclear Power Plant,' Unit 1

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Inspection Ati _ Perry Site, Parry,. OH

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y InspUction' Conducted: : December 2-6 and 9-13i 19852 s

'Inspectorsi JJ McCormick-Barger

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D Jones:

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N. Spang7

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Approved.Byi 1,0.' Knop,.C_ hie

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. Reactor Projects Date-2D FSection.1C':

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Inspection ~ Summary 3

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(Inspection o'n DecembAr 2-6 andi9-13, 1985 (Report No.- 50-440/85085(DRP)) ~

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p Areas = Inspected: _ Announced safety inspection 1to. ascertain whether plant Alarm?

.e iResponse-Instructions (ARI's)'are prepared to adequately control ~ safety-related

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~:functionsiin,the event of-system or component malfunction indications. ?The

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inspection involved a total of 90 inspector-hours onsite by.:one NRC inspector-

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tand two; consultants including six. inspector-hours'.onsite during offshifts.

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LResults:

No diolationsJof NRC-requirements ~were identified-during the

. Gi_nspection. iThe ARI's reviewed where generally found to be technically ~

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' adequate! EHowever,'nunerous errors:were found' including referenced

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'; documentation =and._setpoint values.which indicated a lack of. adequate procedure'

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se 1 review and a program.to assure that changes:to; alarm setpoints.andLTechnical

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' Specifications are reficcted inl plant procedures.

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i-DETAILS-

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- cic hersonsContacted

Cleveland Electric Illuminatina. Company

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LM.MLyster, Manager, Perry Plant Operations Department (PP00)

,C; Shuster, Manager, Nuclear-Quality Assurance Department-R. Tadych, GeneraleSupervising Engineer, PP00 B. Walrath," General. Supervising Engineer, 0QS:

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~B.:Liddell,10peration Engineer-

~ B. Ferrell,; Licensing - Engineer?

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.LT.?Heatherly, Compliance Engine'er.

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V2 Concel, Unit Lead,iSPE

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,P. Russ',::Complience' Engineer

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D. Myers, CEI Consultant t W.;Colvin, Operation Engineer R

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D._Cobbi Shift Supervisor J. Meyer,: Engineer

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O.~S.JNuclear Regulatory Commission-

J. McCormick-Barger, Project Inspector, Perry

N.DSpang, EG&G (NRC Consultant)

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L.1 Jones,:EG&G (NRC Consultant).

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1J.:Grobe,! Senior Resident Inspector,. Perry TK.iConnaughto'n, Resident-Inspector, Perry y

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.C.jscheibelhut,;Argonne (NRC Consultant)

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'All the ab"ove persons' attended the exit meeting.

Otherilicensee

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.. personnel were routinely contacted during, the course of the. inspection.

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. Review of Perry Unit 1' Alarm Response Instructions'(ARI's)-(42452)"

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The inspectioniwasl conducted lto-assure.that" Perry ARI's were. prepared in

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.accordance'with their:' administrative procedures,Jinformation contained in theLinstructions were correct,-and the instructions:were. technically g-adequate.

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-A review'of Operation Administrative Procedure:0AP-0506 " Preparation off N.? ) 4

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iAlara Response' Instructions" was~ conducted to determine procedure-

~ dequacy.and method byLwhich ARI's were' prepared.

-A detailed review-a

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.of-selected ARI's for annunciator alarms. located.at-the operators console-

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l twas: conducted to; assure compliance with 0AP-0506. ' Technical adequacy was

. Jdetermined by. comparing the ARI's to the applicable electrical: drawings,.

Perry Final; Safety Analyses Report (FSAR), Piping and Instrument Diagrams

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(P&ID's), and fina1Ldraft copy of Perry's Technical Specifications.

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Nhe'fo11mingisallist:of[ARI's,in.whidhajdetailed' review:was.

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Econducted by;the inspectors, including the specific. alarms reviewedJ m~ -

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for each:ARI:

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-(1)' ARI-H13-601-16,' Revision 0,~"ARI-H13-P601 16:

High Presse e

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.CoreSprayj(Unit 1)"

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l(a) HPCS. Pump Auto Start Receive'd (A5)~

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.(b)1 HPCS'RX+ Level.LO L2 (CS)

_(c)~ HPCS.Out:of-Service (D4).

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t (d)f-DG -Trip Lockout. Relay. (E1) E

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(2)'f RI-H13-P601-17,; Revision 0, "NRI-H13-P601-17

RHR B&C'(Unit 1)"

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ALARMS

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(a)CNTMT Spray B Auto StartIReceivedf(A3)

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(c) DW to CNTMT Diff Press B High (ES)..

T(d)-RHR Pump B Discharge Pressure HI/LO (F3)

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(3)]ARI-H13-P601-18, Revision 0,"ARI-H13-P601-18: ' Leak Detection"

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(a)- Drywell' Identified Leak.RateLHigh (A1)

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('4hNRI-H13-P601-19, Revision.0,"ARI-H13-PE01-19

SRV's, OTBD:

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ISOL. Valves' &' Main -Steem"--

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l(d);: Safety-Related' Air' Header B Pressure Low (H10)

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LA f(5)j i ARI-H13-P601-20, Revision 0, ARI-H13-P601-20i RHR A (Unit-1)"'

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O (b); CNTMTLSpray A CNTMT Pressure High (84)

l(c) iSUPR Pool Level-A HI HI.(D2)~

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Reactor Core 7;

' Isolation Cooling"'

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_ L(8) iARI-H13-P680-2,iRevision 0,:"ARI-H13-P680-2: - Condensate" c'"

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Feedwater

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RECIRC Flow i

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. c) iRCIRC B Motor _CLR Flow'Lo (D11):

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Reactor Control-

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('a)' RRCS.RX: Press HIL(A2)

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b " ROD Block?IRM Downscale (D2).

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Steam Control

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l(14) ARI-H13-P680-8, Revision 0, "ARI-H13-P680-8:

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m a-1(a):LoadLMTSetbackVAC'LO[(C6)

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?The"detaiNdIreviewlid'ntifiedthreealarmresponseLinstructidns.with

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uSection:1.11'of-ARI-H13-P601-16Lalars'(D4) "HPCS.out of service"'

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. breaker EH1301,7 auto trip.

This-alarm source could not be sidentified.

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tSection 1;0.1 of/ARI-H13-P680-4l alarm -(D7) '.' Steam Dome to Drain

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-:*1 S'ection 2.0.1~. of ARI-H13-P6'80-5 :al' arm (C5) '.'RPS B&D Out of

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EServic'e": listed five trip' sources that would activate the

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iannunciator. The'electricalidrawings'. indicated six: sources.

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The missing source on the ARI was "1st Stage Turbin~DPressure e

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', :In addition to the.three' logic l errors,13 other individual alarm

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instruction sheets..were found to contain errors such as incorrectly e

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specifying relays; identified to.be'.~the cause of the al. arm, missing

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[or' incorrectly _identifiedireferenced drawings.and~ technical

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. specifications!and incorrectly identified trip-setpoints..

In

- generaliwith.the exception of the logic errors-listed above, the'

tinspectors found'the" technical aspects of the' instructions, that is-the. cause of the' alars :and-auto action listed, to be in. accordance

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lwith controlled drawings.

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b.- CAfter.perfbraing'the ' detailed. review of the ARI's listed above,? the.

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~Tinspectors1 performed a nondetailed review of 63 different specific

' alarm response'. sheets: chosen from the'ARI's listed.above.

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N Lnondetailed review wasnsimilar to the~ detail. review, except1that'-

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Lreviews of electrical logic' drawings and P&ID's.were not included.

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lTheTnondetailed review identified 17-instructions-with<various

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J Lerrors:and: omissions Lsuch asfreferences to drawings, Technical

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? Specifications, relays, and initiation -setpoints.

The operator

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1responsestidentified:inLthe~ARI s were generally found1to be. adequate.

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iHowever,: severa1' responses were found to ;1ack information1that could.

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Taid;theioperator' in. responding to.the alarm condition. l Examples of

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lalare Lresponses: that <were. found to need_ additional operator ' response cinformation are as'follows:

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i.Section 3.'0 "Immediate Operator" Action"Lof ARI-H13-P601-21.

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alarm ~(D2) "RCIC ISOL?RCIRC ROOMiTEMP:HIGH" states that "IfI thereDare: indications of a steam' leak in the RCIC: Pump Room,.

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implement ONI-N115 ;The alarm response gave'no instruction:

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.to,the operator as-to.how the determination'of a steam leak

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~Section 3.1$" Subsequent Operator Action" ofJARI-H13-P601-20

alarmi(B2)(" SEPARATOR =STRG-P00L LEVEL A HI/LO" provided

-instructions;to fill the separator. storage: pool that did not

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provide for opening a valve necessary to perform the fill.

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It shodid:be-noted t' hat the errors and omissions foundfin'the

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f operator: action:section of~ the ARI's were.few-and easily overcome by W

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.a knowledgeable operator.

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Inspectioniummary?

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The inspectors reviewfof theLARI's revealed th'at the current' program m-

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identified by theflicensee to update:ARI's when alarm setpointslare

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changed appears to be. inadequate. ;Approximately 25 to.30 percent of.

y the setpoint'value's verif.ied by the inspectors where~found to be in

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l error. 1The inspectors.are concerned that this finding may also be a

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- problenlin other procedure, such as: surveillance-and system m'

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operating instructions.'

Errors 1n the referencing of. Technical'

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-Specifications'were also' found to-be~ numerous and reflect an

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iinadeq'uate' program to assure that changes (in Technical'

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' Specifications areireflected in the applicable procedures. -In

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Laddition to :th'e' two generic concerns -identified above, the.

? inspectors-found. numerous _minorerrors'thatinithemselves,Jaaynot

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'cause serious. operator: errors, but reflect on-the licensee's-

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c; LdetailedEreview offthe' procedures. : During the. exit meeting, the

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m l inspectors" informed the: licensee-that'a re-review'of the ARI'.s would

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be nece'ssary:to' assure _thati.information identified in'the ARI's is

correct ~and reflectithe plant drawings,-setpoints and Technical

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Specifications. jThe licensee was also instructed to review their

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program,for. revising plant procedures when. changes.to plant

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Tsetpoints and Technical Specifications'are'made. This is considered

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'?tojbe;an-Open; Item (50-440/85085-01).

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TOpen' Items ~

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Open Items:are matters which have been discussed!with the licensee ~, which~

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will be reviewed further byithe. inspector, and which involve some action

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ion theipart of-the NRC or licensee or both. LAn open; item disclosed.

'during the : inspection Lis ~ discussed in Paragraph 2ic.

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' Exit Interview

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JTheiinspectors met'with licensee.. representatives (denote'd in Paragraph 1)_

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-,the scope-'and findingsfof; the= inspection ~ activities.

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Afterfdiscuss^ionsiwith'the' licensee,Sthe inspectors ~have determined there.

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is~no proprietary' data contained in thisL. inspection report.

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IR 05000440/1985085

Text

REGION III

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