ML20031C528

To Requalification Action Plan,Qualification by Test of Class IE Equipment Per NUREG-0588

ML20031C528
Person / Time
Site:	LaSalle
Issue date:	09/01/1981
From:	COMMONWEALTH EDISON CO., WYLE LABORATORIES
To:
Shared Package
ML20031C526	List: ML20031C525 ML20031C528 ML20031C531
References
RTR-NUREG-0588, RTR-NUREG-588 NUDOCS 8110070243
Download: ML20031C528 (18)

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LaSalle County Station, Units 1 & 2 n

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Requalification Action Plan Qualification by Test of Class IE Equipment In I.ccordance with NUREG 0588 4

Prepared by:

Wylt Laboratories and Comonwealth Edison Co.T.pany

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I Revision 1 September 1, 1981 6

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l REQUALIFICATION ACTION PLAN

1.0 INTRODUCTION

1.1 Introduction NRC Memorandum an i Order CLI-80-21, dated May 23, 1980, to the industry regard..; the enviimmental qualification of safety-related electrital equip-ment requires that Class 1C ele-trical equipment for operating nuclear power plants must meet tbc requirements of NUREG-0583, " Interim Staff Position ca Environmental Qualificatien of Safety-Related Electrical Equipment."

Class IE equipment for Cmcanwaalth Edison Company's (CECO) La Salle County Station is required to cor. form to NUREG 0588, Category II.

Comonwealth Edison has identified the electrical equipment at LSCS which may experience harsh envi-ronments due to Less-of-Coolant Accicents (LOCA) inside primary containment, Instrument Lina Ersaks outside priraary containment, and High Energy Line Break (HELB) accidents outside primary containment.

Equips.nt identified by Commonwealth Edison includes the follo,eing:

Equipment needed to bring the reactor to a cold shutdown condition folicwing tha defined accidents.

(This includes reactivity extrol and initial cooling of the core and its depressurizat.on tc am'ient pressure.)

a b.

Equipment needed to remove core decay heat to maintain fission product barrurs.

Equipment needed to isolate :.nd assure containment integrity.

c.

d.

Other equipment designated by NRC.

Additionally, Comonwealth Edison has identified equipment which is safety related,' as described in a, b, and' c, above', but which will not experience

1arth environments.

That equipment is not a part of this requalification action plan.

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2-This equipment has been evaluated by Wyle Laborateries' Qualification Assess-J.2 That record was ment Department based upon its initial qualification record.

quite variable with respect to Environmental Qualification Standards because ruch of it pre-dated the IEEE 123-1971 criteria and most of it pre-dated the implementation in industry of the IEEE 323-1974 criterie. A first evaluation to the NRC's DOR Guidelinet wal submitted on Oct%cr 31, 1980; howcycr, this cas judged an inadequate basis during ut flity di,5 cessions with the NRC staff in February, 1981.

A second evaluation to NURES OE'G Categery Il standards was initiated and a status report was submitted as an informational package on This second June 1,1981 to encourage a field audit by tu NRC-Staff..

evaluation has continued since the field audit with particular emphasis on the NSSS equipment which previously had no aging assessment.

f.s a result of the field audit where new deiinitions were g.iven for the radiation threshold and the temperature thresteld,Nich determine a HARSH cnvironment, all the HARSH zones in the plant were redefined with respect to the radiation parameter and several HARSH zones were added basad.cpe1 temper-ature effects of the four accidents of concern to cquip,nent oyalification.

At this juncture it was also prudent to reevaluate the. r.dcup of the EQ equipment list which had grown to an extensin enemvatico bned upon the That safety - non safety categorization scheme usef by tne NSS5 var. car.

scheme essentially overlaid the entire plant with all accident scenarios and then assumed that all equipment under that composite accident overlay must perform its limiting safety functions as if al'. accidents were simaitaneous.

Such a scheme overlooked the basic criteria used for equipr.ent placement at E

LSCS wherein control and instrumentation equipmsnts were purposefully removed l

f from the primary containment to avoid LOCA, designed away frcm the main steam l

tunnel and other steam line chaises, and not located near high energy lines except as required within physically separated ECCS cubicles where system I

redundancy or diversity could be relied upon to perform the safety function.

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3-A revised list of EQ sensitive equipment was developed on the basis of assessing the effects of all LSCS Chapter 15 accidents and all LOCA Chapter 6 accidents at La Salle. (See the accompanying LSCS report, " Justification for Interim Operation").

The equipment on the revised EQ list must perform a safety function in the appropriate time interval for the specific accident under which it is axposed to c-HtRSH environment.

For other limiting acci-dents - one of the fcur which causes a HARSH environment, its performance may or raay I.ot be required, but if re.;uired it is performed in the environment and with the function time associeted with this other limiting accident. In cases where the equipmer.1 performs safety functions in more than one limiting acci-dent, its EQ requirements are Mittated by the most severe limiting accident.

This revised EQ list is the t.asic equipment list for the EQ program at La Salle; it also includes other equipment mandated for inclusion in the La Salle EQ Program by NRC Staff.

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1.2 Equipment on this revised. list. hc3 been evaluated by the Wyie Laboratories Qualification Assessment Department for conformance with NUF.EG 0588 Cate, gory 11 requirements. LSCS aging ana'rysic was a part of that evaluaticn; it is a continuing procest. (The NSSS equipment was also evaluated by the NSSS vendor und the BOP equip =cnt w:s clso evaluated by the Architect Engineer for La Salle).

Equipmer:t for which' adequate evidence of cualification does not currently exist o' ~or which tnere are no EQ test reports were cesignated for rcqualification ty testino.

See FSAR Section M.7 for detailed equipment lists.

The Requalificatiar. Test Program presented herein is designed to develop the Test Plan, Test Procedurcs, and Schedule via the technical approach described in the following sections.

20 TECHNICAL ADpROACH I

2.1 Wyle's technical approach for the overall qualification program for la Salle Class lE equipment included the following major tasks:

1.

Preparation of the Qualification Program Plan (overview)

II. Data Collection and Evaluat.fon of Equipment against NUREG 0588 Category o

II Requirements.

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l 2.0 TECHNICAL ADPROACH '(CONTIN'JED)

III. Agir.g Analysis IV. Review of Qualification Alternatives V.

R' qualification Testing VI. Final Report Preparation 2.2 Data Col httion. Evaluation and Analysis n

Search -fer applicable test documentation has involved vendor tests for both "he CfS and NSSS equipment, the Wyle test files, EPRI library, and other

,r.du tr ial sources.

Applicable data'to support the environmental qualifi-cction of La Salle equipment has been entered into the assessment report for-carh couipment type (Manufacturer, and Model Number).

If comprehensive test data was not located, analysis of existing test data was attempted to estab-lish adequate coverage cf the environmental parameters for that particular piece of equipment. Where these two assessment techniques f ailed to establish i.he necessary qualificaticq basis, a revalidation of functional safety rceirements wcs made (functional time); also the applicable environmental parameters were authenticated; then one or more of the following techniques were employed.

Demonstrate via a heat transfer a.

Thermal Lac Analysis analysis that the critical ir ternal components of a device could never attain a temperature higher than the test temper-ature.

Demonstrate that the b.

Deoradation Eauivalency Analysis mea'sured degradation shown by a timed test is equal to or more severe than that which would result from the postulated accident conditions.

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5-2.2 Data Collection, Evaluation and Analysis Continued c.

Thermal Test Duration - Demonstrate that the thermal effects measured by short-term high-temperature testing were as severe or worse than those expected from lower temperatures associated with longer periods of post-ulated accident conditions.

Where adequate qniification records exist except for equipment aging effects, an apprisal is made of all nonmetallic materials in the Class lE equipment via vendor contratts. materials analysis, or testing.

After identification is completed, a time / temperature and radiation effects analysis of each netcrial is made through use of the Arrhenius cata and fundamental radiat ion data.

An estimate of material life, hence equipment maintenance intervals is established whenever the Arrhenius prediction indicates lifetim u less than 40-year plant design life.

These. data collection, evaluation, and analysis techniques are continuo'usly applied to equipment items unti.1 it becomes evident that either qualification testing or replacement / modification is the practical and timely resolution for the unqualified device.

2.3 Qualification Testjne When qualificatier testing of new or existing Class lE equipment is required, a detailed test plcn (precedure) is developed (exempting aging whenever justified because that car. be analytically pr6vided for many materials). This test plan acknowledges the service conditions and the accident profiles of the environmental paramaters.

It also establishes sequence functional checks to bring the Class lE equipment into compliance with IEEE 323-1974 and NUREG 05SS Category I.

An tuditable qualification test raport is the output of this effort.

Schedule-wise, unqualified equipments are assembled into generic groups (baskets) where practical,- to reduce test costs and to preserve -

schedule, provided of course that the test conditions meet or exceed the generic service conditions.

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6-s 2.3 Qualification Testino (Continued)

Qualification test plans may Le refined as dictated by the following practical considerations.

2 a.

Subgroups based upon radiation levels may to necessary.

b.

Time / temperature aging and cyclic tests nsy be arranged to accomodate uniquely susceptible equipment to enable enroute completion of less severe test objectivts for that type of equipment.

c.

Where separate seismic qualification results have estcblished acceptability via the SQRT program, components will not be retested unless evidence exists to ind cate dependence on mechanical behavio-to time / temperature or radiatien agina effects.

d.

Finally, the safety function operability ~equirement, if any, must be defined in terms of functional tim? before, during, or following the accident (event) to require a specifir.

verification test.

A typical qualification test sequence will con';1 der the following:

1.

Test Plan Review and Approval by CECO 2.

Test Article Procurement and Preparation 3.

Baseline Functional Tests 4.

Radiation Exposure 5.

Functional Tests 6.

Time-Temperature Aging and Cycle Aging l

7.

Functional Tests 8.

Extreme Operating Conditions Tests l

9.

Functional Tests 10.

Seismic Qualification 11.

Functional Tests 12.

Harsh Environments (LOCA, HELB, or Abnormal Environment) l 13.

Functional Tests l

14.

Preparation of Final Qualification Test Report s

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2.3 Qualification Testino (Continued)

D(finitive test acceptance criteria will be established in the Test Procedures on which an unambiguous judgment of test success or failure can be

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based.

Detail;d component qualification Test Procedures, written by Wyle, typically include the following provisions:

e.

Functional test data is recorded on component measurements like:

1)

Insulation resistance 2)

Voltage ratir, on transformers and coils 3)

Contact resistance on relays, switches, and breakers 4)

Pull-in and drop-out voltage on devices in 3) above 5)

Capacitance, imoedence and rated voltage on Capacitors 6)

Insulation, resistance and continuity of cables, buses, terminal blocks 7)

Input / Output ratios for operational measurements on tran-sistors, integrated circuits, and control boards 8)

Setpoints and time intervals on pertinent devices b.

Padiation exposures used in testing will include a 10% margin on normal and accident doses.

Aging procedures will acknowledge such potential aging para-c.

meters as the number of electrical and mechanical operational cycles, time-temperature, and humidity.

d.

Electrical test parameters include continuity, current and voltage, spurious operation (contact chatter, pressure and temperature where pertinent), and specific tolerances on the measurement instrumentation.

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g 3.0 SCHEDULE s

The preliminary schedule for La Salle requalification efforts is indicated on pages eleven through eighteen.

?.djustment to this schedule will be made as now information develops.

Test group sevan, for which no schedule is pre-sented, is available as a contingency for replacement items or retest as necessary.

In acdition to the comments shown on each Test Group (Basket)

Schedule, the folleaing assumptions have been made:

1.

Arrhenius techniques will be used to shorten the 100-day duration test requirement to 30 days.

2.

Time-tempera:.ure testing (aging) will be accelercted to enable achievement in 12 weeks er less.

3.

Procurement of test items is assumed to occur in parallel with test and analytical activities and will, therefore, no affect schedule.

4.0 FACILITIES A"D CADABILITIES Since 1970, Ryle has performad over 1,000 seismic qualification programs; since 1974, Kyle I.as performed over 100 complete environmental qualification

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programs in accordance with IEE 323-1974. Wyle originally developed the most practical approaches to nuclear qualification and has consistently improved these engineering approaches as requirements changed.

In 1975 Ryle recognized the need for an Aging Library of material and compo-nent aging characteristics and has developed an Aging Library from a search over 2,000 applicable documents.

This library is continually updated as new materials and data become available. While most of this material is propri-etary to the organizations for whom the tes,ts were performed, Kyle has had good ' success in obtaining releases from the test report owners for use by utilities.

Finally, Wyle also uses a terminal for the computer accessed Environmental Qualification Data Bank (EQDB) of the Electric Power Research Institute (EPRI).

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-9 4.0 FACILITIES AND CADABILITIES (CONTIhUED)

Recent expansion of Wyle's Huntsville facility has created the following capability in laboratory' space, test chambers, and seismic' tables:

o Laboratory Space 152,000 square feet o Aging Chambers 34 (-1000F to 6000F) o Temperature-Humidity Chambers 8

o L'OCA Chambers 11 (pressures to 400 psig; tempersture to 40:0F with saturated steam and 6000F

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with superheated stec.m;

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temperature rise rate as requirad; chemical spray injecti0n independent of steam flow; volume 1.8 -

385cubicfeet) o Seismic Machines 3

The data acquisition systems for the LOCA sinoiators 'have up to 32 analog inputs and 32 digital outputs at a data rate of 22 channels per second interfaced with a high-speed printer.

Wyle subcuntracts fe'r. radiation services and will select from two alternative' approved radiation facilities on the basis of ability to meet test requirements with optimized scheduling and competitive bidding.

In addition to our Huntsville capabilities, Wyle operates other major testing facilities at El Segundo and Norco, California.

These laboratories have the following number of chambers for nuclear qualifi-cation testing.

o Aging 29 o Temperature-Humidity 11 o Seismic Machines 4

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4.0 FACILITIES AND CAPABILITIES (CONTINUED)

In case of heavy testing schedules our California facilities can be used. On each test chamber at all Wyle facilities continuous recorders are used so that

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a permanent continuous record is maintained of all test conditions.

5.0 QJALI Y ASSURANCE It is the policy of the management of Wyle Laboratories to maintain the highest standards of quality throughout all its operations in accordance will.

ell recognized industry quality assurance standards.

Wyle has prepared.

detailed procedures for assuring the highest quality of work.

Theie proce-

'eres are designed to ensure compliance with 10 CFR 21,10 CFR 50/ Appendix E, ANSI Standards N-45.2, cnd other government and customer specifications. The manual sections correlate directly with the paragraphs of 10 CFR 50/ Appendix B.

Th2 final qualification test plan will be prepared and the subsequent test program will be in accordance with Wyle Laboratories' (Eastern Operations)

Quality Assurance Policies and Precedures Manual.

All test equipment and instrumentation to be used in the performance of this test program will be ralibrated in accordance with the Manual, which conforms to the applicable portions of ANSI N-45.2,10 CFR 50/ Appendix B, and Military Specification MIL-C-15652A. Standards used in performing all calibrations are traceable to the National Bureau of Standards.

Wyle 's Q. A.

System has been audited anc approved by Commonwealth Edison Company.

A high quality of work on this project will be assured by the use of technically competent personnel workine in a controlled environment.

The primary Q. A. emphasis on this project will be placed on document control, preparation of qualification plans, review of reports, and performance of tests.

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OUALIFICATION PROGRAM SCHEDULE COMMONWEALTH EDISON COMPANY TEST GROUP NO. 2 (BOP)

ITEM 1981 1982 1983 MANUFACTURER JUN JUL AUG SEP OCT NOV DEC JAN IEli MAR APH fAAY JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY GE pe S S;"glm Faer nm amm I,= =,,$ ~""

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CUAL TEST PL AN 1EST ARTICLE TT&

t itNAL TEST REVISION PRIP AND CYCLE ADNORMAL (wittu nroutliio)

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• Schedulo advanced froin previous action plan.

QUAllFICATION PROGR,%M SCHEDULE COMMONWEALTH EDISON COMPA!JY TEST GROUP NO. 3 (NSSS)

(Start Dains Est! mated) 1982 1983 1981 i

ITEM MANUFACTURER JUN JUL AUG SEP OCT h0V I;t C JAH ItB Man f.PR MAY JUN JtA AUG SEP OCT NOV' DE:

JAN FEB MAR APR MAY I

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Main Steam Line 7/////[/2d3$l lll((l$$h,,, PX y Hadiation Detector GE ///// / !//////// U 1llllll llllll'lllllll l 1X D ector E i l bI i ut on e for GE l Intermediata Rangel Source Range Preamplifier _ /#////////////7Nhh Ul ll[}l[lhlh h[kEk GE I j j l 4. FINAL QUAL TEST PLAN ' TEST ARTICtE T T &* 'EST REVISION PlilP ANil CYCLE ABNORMAL (wtitM flE0tMID) HARSH REPORT Pt AN &.* PI'l10V AL . '"HC 110H al f1 An14 TION. Ar.ING INVilitiNMI NT SilSMIC INVlfinNMr N T P AI P. ...__ j NiUl[ihlilit kkf d d 'd#### # w. g O

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3 i OUALIFIC ATION PROGRAM SCHEDULE { COMMONWEALTH EDISON ' COMPANY TEST GROUP NO. 4 (NSSS) 1981 1982 1983 ITEM I IWANUFACTURER JUN Jut Auc str CCT NOV ott JAN FEB MAR APR MAY JUN JUL AUG SEP CCT MaV DEC JAN TES MAR APR MAY Pmsure Transmitter yj77g g g g g gg ] dai. y 556 y ' j '- jp ',g{ l y .ssure Switcle j esarksdale B1T FfRE] Iis@lE I@!!t? $',","s"la*o $" 8 i i ~ O ^g.j - 77, %. ' ' t 'gd}' 'I 'q"' l m Pressure Switch ^ t-uarksdalo PlH i 1 e i $',','ioh' 288 . V/AINEl Ei EIIEE-h i l $',, o'n58 b3AD I EI lEIIIEE3X P two Switch [ gg g g ,x r-f narion 289 f/82EE1 EI II5IIIE[IEM ua i n o riag et I751 Temperatiire Element 777 g] gg g g} l l l II l F1NAL QUAL TEST PL AN 1[ST ARTICLE TT& il5 T Bt Vist0N PltlP AND CYCLE ABNORMAL (WHIN RIQtliRID) IIARSH RfPORT Pt AN & AltitHV AL IUNCIt0HAL RAD!Alf0N AG!NG INViitDNMI NT SilSMIC lhVmHNMINT Fill P. b......... ) b'#^" A! M*

QUALIFICATION PROGRAM SCHEDULE COMMON'NEALTH EDISON COMPANY TEST GROUP NO. 4 (NSSS) (Continued) l ITEM 981 1982 1983 MANUFACTURER JUN JUL AliG SEP OCT NOV DEC JAN flB f.fAa APH MAY Jt *f. JtfL l AUG$[P 'OCT NOV DEC JAN FEB MAR APn MAY Pressure Transmitter ) Rosemount 1152 [ / [ / 2 h /[/] {}(([llIllll lllllll k,1. i WlOutput Code E Only a Pressure Switch l 1 Static O Rind 12N 777geg g g'gg g a ic II SN(6N) s l Anx. Turbine Controls e city Corp. GS 2 yfjfpfffff ;7pg [ ggg{gg m[ Radiation Sensor Converter m yg7pf,yfg g llljjjj jjjjjjj ggy I i 1 I i ' l ? I i l 4 f I g I l l 1 l l l l' i I i l i i i I I l i i l i OUAL TEST PLAN TEST ARTICLE TT& fMAL TEST REVISTON Pfl[P AND CYCtE ADNORMAL (Wilf N R(O',FlfttD) HARSM RIPORT 4 Pt AN & APPilDVAL IUNCIl0N AL RADtAil0N Af;fftG INV ftDNttf NT SitSMIC [NVill0NMI NT FHI P. F#M23 B.? f i'A 3 I I L1 1 ililil!imiliti!M IIRITA 1 - " *1 C___ZJ Ed < 1

e QUAL.fFICATION PROGRAM SC;tEDULE COMMOMWEALTH EDISO'J COMPAN / TEST GROUP NO. 5 l 1981 1982 1983 MAR APR MAY JUN JUL AUG SEP DCT NOV DEC JAN FEB MAR APR MAY JUN JUL JANlItB AUG SEP OCT NOV DEC 22 Analyzer '/////4(2: ~ff} hh [ddyOdl,II2-M ] Delphl H 0 PanelKIV l 8 l i Canler Control Panel Y////// 3 l[hh[}hl h{ff[' T Careler Power Panel k 7 / /] hl) ((((ll}}{}l((C MCC Power Control Panel { g {." ( 3 j ]ll lll}lllllhl { I Limitorque MOV's //[/ /h,hg l']Il0l lI}lllE$$ M O Weed E4B and 611 W///$sl ()ll l[}ll ((}$ { ,,,j 7///////////Msd l' 00((l[lO((ll(([N[lk2IM. j G.E. Refrigeration Motor 1 IMAL QUAL TEST PLAN TEST ARitttE T.T & itST Rt Vtst0N TrJ;' .r. Sure r. anunnMAI swHtu ntmnniD) HARSH REPORT ec !'".*"'"* MTWT PH1P. Pt AN & APP 110 VAL tn:C1*0'8 ' t EAinAlt0rl f.t ?:f. 5 M'. tc."* C.iT L. .1 (.k k k )

? QUALIFICATIOitPROGRAM SCHEDULE COMMONWEALTH EDISON COMPANY TEST GROUP NO.~6 1981 1982 1983 AUG SEP OCT NOV DEC JAN IED MAR t.I'll MAY JUN Jt!L AUG SEP OCT NOV DEC JAM FEB MAR APR MAY JUN JUL _ L Siemens/GE Blower Motor F///////////////)M3_jl!INIl b(Ol(l0N.l00N' M Gould Level Transmitter I l ,bh / -kd [!}f[1l! ff}!!ll}ff!!h' b Al itydrogen Recombiner I N' .k')M j!!h!![3!!l [{$},h 3 Crosby SRV 1 1 l /jk [ !,flh !!Sf! f[pC1M Barksdale Pressure Switch I [d [$ }!((NN!!N{}b!, f!!h,[b h TC9622 l I Barksdale Vacuum Switch

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