ML20138P000

Responds to NRC Re Violations Noted in Insp Repts 50-282/85-16 & 50-306/85-13.Corrective Actions:Program Underway to Upgrade Alarm Response Procedures

ML20138P000
Person / Time
Site:	Prairie Island
Issue date:	11/25/1985
From:	Larson C NORTHERN STATES POWER CO.
To:	Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20138N948	List: IR 05000282/1985014 ML20138N971 ML20138P000
References
NUDOCS 8512240244
Download: ML20138P000 (7)

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' Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401 Telephone (612) 330-5500 November 25, 1985 C E Norelius, Director

. Division of. Reactor . Projects US Nuclear Regulatory Commission

. Region III

. 799 Roosevelt Road Glen Ellyn, IL, 60137 PRAIRIE ISLAND NUCLEAR GENERATING PIANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 This letter is'in response to your letter of October 24, 1985, which transmitted-Inspection Reports 50-282/85016 and 50-306/85013. This letter also restates the responses given in our letter of September 30, 1985, and' includes minor revisions to those responses to answer comments by the Senior Resident Inspector. New and changed material is sidelined.

Violation Technical. Specification 6.5.A.3 required, in part, that detailed written procedures shall be prepared and followed covering actions to be taken to correct' specific and foreseen. potential or actual malfunction of systems or components including responses to alarms.

Contrary to the above, a complete alarm response procedure for annunciator location 47501-501 was not available in the control room from August 23, 1984

- to June 24, 1985.

This is a Severity. Lev'el V violation (Supplement 1).

Response

- The alarm responte procedure in question pertains to the new intake screenhouse. When the new screenhouse was turned over to the operations

-department in early 1984, temporary operating instructions were issued. The alarm response procedure was part of Temporary Memo (TM) 84-10. The

" permanent" alarm response procedure C47.26 issued in June 1984 made reference to TM 84-10. On August 23,_1984 the temporary operating instructions were reissued as TM 84-42 and TM 84-10 was cancelled; however, the u i..lL - . K:- -

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'I^ :C47.26 procedure-still referenced TM 84-10. On January 25, 1985, the~ _

temporary operating instructions were again reissued,(this~ time as TM.85-04.

TM.84-42.was" cancelled, but the old reference to TM 84-10 remained.in C47.26.

It now appearedtthat.no procedure was available, since TM'84-10 had been .

j (cancelled,iwhen in fact the procedure was in effect under another TM number.

In' June l1985 the~C47.26 procedure wasl corrected to provide a proper ~

^ reference. 'Fullicompliance had been achieved. There is a program now under

.way to upgrade..the: alarm response procedures.

. Items of' Safety Concernt 1TheLfive concerns listed below all relate to modifications. to the facility. .

'Sp.cific. corrective _ actions are listed'for each concern noted. Corrective '!

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' action for the broader area of modifications includes lthe following management 0 -actions:

1) 'More detailed review:of modification work packages by members.of

~ plant staff. knowledgeable in integrated plant operations and engineering criteria.-

'2)- Use of-the " team" concept in the modification process to. identify interfaces and interferences early.

3) ~ Strengthening-the ties between the plant and construction QC organizations.to-ensure timely resolution of problems.

i4) Strengthening NSP, supervision of-construction crafts to ensure-that

' craft supervision is aware of the special concerns required for work

~in an' operating facility..

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-It isibelieved that these actions support the specific corrective actions

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listed below and. address the broader concern of physical control of plant

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-a. Concern:

~NSP Corporate"QA Audit No. AG 85-16-Outage resulted'in'a Finding (No'.

i FG-85--5) that - Commonwealth Electric, Co. , a contractor - to NSP at Prairie

--Island,'had conducted work ar.ivities which were ineffective in complying with'NSP QA program requirements,as delineated in Corporate-Administrative Work Instruction.NIAWI 5.1.15, Revision O. This instruction' specifies in Sections 6.5.2 and 6.5.3, among other things, that an Engineering Change Request-(ECR) is'to be released-for

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implementation only after, resolution of.the ECR. Specifically, the

. Corporate.QA Auditorifound that conduit support hangers and other-

-electrical. components'were installed without prior engineering approval

'and=not in accordance with' existing design' documents.

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' LIn-p,lant-corrective actions have included review'of the existing; ,

7 s - finstallationsEof1 conduit l support hangers.; To_.date, two safety related 9

Kelectrical cabletsupports have'been found which will require special u Eb ? seismic; analysis'.EiThis'. analysis is to be_ completed by Augusti30, 1985. -

L, yn- lCorrectiveiactions-by the construction' forces have. included management.

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'reviewtof[the Findingp review and updating of constructionistandards,-

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f  ; personnel additions to,the;NSP. Nuclear 1 Engineering and. Construction field W ' - staffijand} personnel changes;intCommonwealth-Electric Company. ,

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N f rN N actions outlindd:inIthe above' concern have been effective-in jresolving;-thiefproblem.;: Theasp.ecial seismictanalysis'of_eight supports'for.

%"., Q , Jtwoisafety-related conduits has.been completed. =Some minor upgrades.are._ u

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. .  ?? :necessary; materials for;.thos'e upgrades'hav'e.been ordered. .Capabilievf t_o :do .

9 suchl analyses in-house.is_also being~ developed. A school ontsupport analysis '

q Twas-held 10-31-85h:The program:on; structures' analysis'h'as been 3 G red. -

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j - . m [NSP[ Corporate'QhAuditlNo.?AG 85-17-Outage resulted in Finding's that'the i PrairieLIsland.plantjstaff[the'NuclearTechnicalSdrvices' staff.andthe'

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7NuclearaEngineering~and Construction-staff lall failed to-properly-KimplementLthejNSP< uniform modification: processes described in Corporate

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" Nuclear Administrative Work Instruction-N1AWI15.0,' Modification and:

iMaintenance, Revision.-1, which contains anfoverall description and-

" igeneraljinstructions.for'the'us'e.oflthe:prosess.x The' Corporate.QA; YAuditor:found;inihis'reportcforitheiperiod" January 14 .' March.18, 1985 ~

cm ;thatithe~PrairieTIsland plant staff, the5 Nuclear Technical Services-

,. fataffifand the.-Nuclear Engineerin'g and Construction staff alll failed to .

A 1 properly Jimplement the uniform modification process'.1 These failures!were xy ' finsthefareasiof-planningland coordination 6 design,Llogging/ tracking,

- idocument control,iproject control, andLturnover.

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' Corrective' actions; implemented b'y)the.. licensee have.includediretraining; foffthe: users.'of.the modification process. . In-addition,'further audits of'

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rtheiuse of the process are tolbe con' ducted by:CorporateiQA4during the' j.; _ _ 2 Unit 2 10-year ' outage scheduled to;begin in September 1985. : The . resident;

~ iinspectorlwill review the1results of these-audits.

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$ I Affoll(ow-upjaudit was'_ completed just before th'e refueling outage.

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audit:were that:

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,#1.- ATraining was conductedias required for correction of the previous j audit'findingsL NE ~

d. [Thereiwasg'eneral< improvement-inmodificationprocessing.

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Another:ifollow-up'udit1was a auditLwere that'there;were-some minor administrative ~ problems, but that the conducted.during'the' outage. -Conclusions of,that 1 program'is beingD effectively implemented.

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During:the: conduct of fand 'in thdilocation of Append'ix R work:in: the:

" , 1AuxiliarylBuildingion May.8,--1985,.the:two-inch instrument: air supply. >

lineYfor; Unit?1. failed. One. result of thisifailure was.a trip of Unit 3

Tv il. a(See?InspectioniReport :50-282/85010(DRP); 50-306/85008(DRP)).

~$" ;Possible causes 'of =.the: break! include ac'cidental bumping of' the line and irelocation-ofithe linefto: accommodate Appendix R work.

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1 LCorrectivelactions have lneluded1 inspection of'the.line and. reinforcement W " h of fleaking'~ solder joints. - The . licensee's final Investigative Report will J W [he. reviewed by the Resident inspector.-

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+ 'ThisLevent'wa's" reported;as Unit-1 LER 85-009.

6 0n1Mayf8,7198'5, Unit-13was.at_100% power. iAt about 1323, a 2-inch copper;.

(instrument ' air :line separated at 'a soldered elbow joint.' As a- result, .the

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, sUnit-IJsideLofiche instrument' air system depressurized enough~to-cause'the ~

feedwater regulating valve to No.

12 steam generator to close. At 1326, Unit 1 tripped.on;-low' steam generator level;plus feedwater flow / steam flow mismatch.

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&  ; Cable. tray; wrapping for-Appendix R compliance was.in progress in the vicinity

' - .ofJthe break,"and;therair.line was moved somewhat'to' accomplish'the wrap.

>- 1ThisLcould have_placed enough stress.on:the' elbow to cause it to separate.-

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iTheJunit.was maintained in hot shutdown-while repairs were made. While:

~ frepairs were.in progress,"another leak was discovered nearby:in~a 2-inch

- soldered' coupling. 1The:: leakage had been patched before;: clamps were added to ~

tie-- the coupling together.. 'A walkdown' insp'ection'. of the instrument . air system -

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.was. ~: performed:in areas of the plant wherelcable tray wrapping had taken place

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lor _.wasTin progress;'no. additional; problem' areas were identified. The unit,was 3

returned to service at 1847..on'May 9.-

- iPlans#are.being made*to upgrade the:compre'ssed air piping syst' ems over the

next.few; years,with higher 1 strength materials.-

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[Asinoted earlist. steps-are being'taken to strengthen supervision of e [ construction (craft personnel which will reduce the probability of future.

~r ;incidentsiof thisinature.-

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4 n j.y r t 30niJulyf2'6,1f198'S',fa" temporary;c'able spliceLin1the power supply,to MCC,

'n 49, ]1TA1(failed by; shorting to ground. cThis fault; disabled many.of'the.D-1 .

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? diesel generator auxiliaries;.1.The fault occurred in' allocation where:

pGp% N TAppindix!R work (had been done'and-might be related to that activity..

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(An. investigation?by.the"licensie'is underway.

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A ," ~- non+ July l26th,l Unit <1Lwas; increasing power following a routineiload follow

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t g . Y [ operat_ ion, and Unit 2lwasfat 90%jpower coastin'g down- tio refueling.

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s JAtt0800E an operator making rounds discovered thatjthe-auxiliaries to D1-

?DieseljGenerator were not in operation.- Investigationcreveale'd'the' supply;.

_ Qbreaker? to'MCC)1TA1 l(which1 powers t i he auxiliaries' for D1 Diesel Generator) was--

. . . itrippedh3A'fasitihadLoccurred-in a_ splice _in a-temporary power-supply-to.MCC ~

WP " i1 TAI from MCC t1Kl. :;The temporary power: supply had been made 18 months earlier n e h asLpartiefLa p1' ant;modificationb tCompletion of.the modification was delayed

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other, modifications ~and: Tech Spec' operability

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q .  : Power _ing oflMCC11TA1(from a~ permanent source had,.been planned <for the

'ifollowingtweek,isoiinstead!of-repairing the temporary. feed;the permanent

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m wJw ;TThe% temporary power suppljitoIMCC11TA1 had bAen~ spliced to a temporary: cable

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.fedTfrom MCC?lK1;1the'splic'es.were located on; top of-the,MCC.. The fault

' ?odcurred"where;the? splice rested on a switchgear.. bolt. <1t is surmised that m ' e [during cableitray1 wrapping! work'the' splice:wasistepped on, causing an

- M S ,lindentationfand? loss;of protectiveJinsulation,t eventually resulting in'a fault.

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-The' cable fault! result'edlid loss of'D2 Diesel Generator' auxiliaries. The-

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%$ eEsignificant5 auxiliaries;affected were generator. ventilation . room ventilation 1 f andithe Ec1'ean fuelioil; pump; the Lothers were minor . keep ~-warm: systems,1 etc.

' }.Diesekgeneratorfoperabilityfdepends on-noneiof

these' auxiliaries.in the short ~

yMB Jters;{thejdie'sel generator.would have,startedrand loaded'as required. .In;the

"  : longitera,fwithout operator action fgenerator insulation may_have degraded, g

W Tsince1 generator ventilation;was unavailable.: Itlis' felt that reasonable Cc -[ operator actionsin restoring powerLto the auxiliaries'would have~ prevented any t

?'~ . adver'se.ieffectToniD1'1 Diesel'_ Generator.and operability would have been

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] incidents Lof / thisl nature.:

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.' .OntAugust11,fl985, breakeri2281 tripped .thus _ disabling certain safeguards ~

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equipment l momentarily.. The tripping might.accidentaliy_have been: caused.- '.

ibyl construction' activity;near theibreaker. Subsequent electrical' testing:

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ioffthe'bre'aker showedlno faulticonditlons in-the' breaker itself.

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f >J This.was reported.as;a Unit 1"LER 85-011..

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g~ - 50rijAugust 71 , 'I1985/ Unit"liwas'at~ 100%l power," add. Unit"2'wasat;83% power.in

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coastdown

forl refueling; JD1 Diesel Generator _was out'of service for'

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1 -AtD1030,?No.f22; control' room chiller trippe'd.- . Investigation.showed that.480

<  ? 1. volt : Busu220rBreaker'228 had'trippedf deenergizing motor control centers IT2.

f, . d (which powers the' control room _ chiller) and 11TA2 (which powers J the auxiliaries ' .

, ~ ?for D2 Diesel! Generator).s sat 1056,fBreaker 228 was reclosed, restoring power m.

ito"MCC'1T2.andl1TA2.2 u r ..l~- .

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fBreaker}228..wasjapp'arently; accidentally. tripped by. construction electricians Lworking'in'the; area. xBreakers_offthis-type usually have a manual trip;

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iblockingidevice finstalled- to prevent accidental trips 3 such as :this, but-.in -

Lthisfcasel.the'devicetwa's missing. ?(The devices.themselves,are quite. easily 3.' .

removed so.that manualitrip of the breakers;can be accomplished quickly, iff

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,. Thefs'ignificant auxiliaries affected were generator. ventilation, room

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sventilation'and the clean fuel-oil: pump; the-others were minor keep-warm e ' systems .etc.1-Dieseligeneratorloperability depends on.none of these auxiliaries intthe~short: term;Lthe diesel generator,would have started and-iloaded"as:requiredJ xIn theilong term,Lwithout operator; action, generator

. >(insulation.may have' degraded since generator ventilation.was unavailable. It-

< j u isLfeltichat? reasonable (operator action.in restoring power to theLauxiliaries W ~

fwould have prevented?any adverse ~effection'D2. Diesel: Generator and operability

.:would;have been. maintained.

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t'As~n'oted. earlier,' steps are being:taken'to~ strengthen supervision'of~

E N1 __ - (construction = craft [ personnel which will reduce the probability.of futute- .

% jy incident?of-this' nature.,

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~[ h1 volved. workmen were counseled.concerning their~ activities. An additional

' physical barrier was erected in the work area to minimize the chance'of-F- . recurrence. A search-for a more' effective manual trip blocking device is underway.

lRdcent} Event On' October 1,.1985, the 480; volt breaker 12M,' which supplies one. train of Unit 1 safeguards 480V;1oads was.' accidentally tripped b'y a' workman working in the

-area. -This.was reported,as LER 1-85-14.

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Corrective actions taken include.the following:

1. ' Yell 7w caution ribbon was placed around breakers in all bus rooms where construction activities were taking place.

2. 'A more effective manual trip blocking device has been designed.and built for.this type of breaker. The devices have been installed on. Unit 2 breakers since-it was shutdown for refueling at the time of the event.

The devices will be installed on. Unit 1 breakers at the-lfirst opportunity.

, ;3. - Administrative controls were tightened. Involved' supervisors and engineers have discussed the event in .a detail and the need for continued supervision presence-

.was emphasized.

Furtherrrecommendations'for prevention of-similar events are being evaluated.-

C E Lars '

-Vice President ~ Nuclear Generation-X cc: G.Charnoff Regional Administrator --III, NRC~

NRC_ Resident Inspector w

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