ML20010D225

Forwards Response to Deficiencies Noted in NRC 810417 Suppl to Facility SER Which Contained Evaluation of Util NUREG-0588 Submittal.Encl Provides Addl Info Necessary to Resolve NRC Identified Items

ML20010D225
Person / Time
Site:	McGuire, Mcguire
Issue date:	08/17/1981
From:	Parker W DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0588, RTR-NUREG-588 IEB-79-01B, IEB-79-1B, NUDOCS 8108240109
Download: ML20010D225 (114)

Text

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1 DUKL POWEH CO>mMY Powzu lhnt.o No 422 SouTu Cnuncu STur.zT, CnAHIDTTE, N. C. 28242 3

WILLI AM O. PA R l( E P,28 R.

V<r Peggen *NT TELtPMONE: Aata 704 S t w PnoovcTioN 373-4083 Mr. Harold R. D(.. ton, Director e rf)

Office of Nuclear Reactor Regulation . V U. S. Nucleir Regulatory Commission ,

/? J' Washington, D. C. 20555 [j 2

s Atcention: Ms. E. G. Adensam, Chief -3

• • • 1 75 i

h *1 3 8,J 7g Licensing Branch No. 4 '{

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Re: McGuire Nuclear Station Docket Nos. 50-369, 50-370  % .

i l Environmental Qualificatitn of Equipment ]

Dea: Mr. Deaton:

i The attached information is Duke Power Company's response to the " deficiencies"

noted in the NRC Scaff " Safety Evaluation - Environmental Qualification of Safety-Related Electrical Equipment" as transmitted in SSER No. 5, Appen*tx D. This response addresses each of the items in the Safety Evalu-ation in a format similar to our NUREG-0588 response. This response includes the following tables

1) Summary of Environmental Qualification of Class 15 Equipment Located inside Containment.

2) Summary of Environmental Qualification of Class lE Equipment Located outside Codtainment and Exposed to the Post-LOCA Recircu-lation Radiation Environment.

3) Summary of Environmental Qualification cf Class lE Equipment Located outsi&. Containment and Exposed to HELE Environment.

n It should be noted that the "Inside Containment" table was previously submitted on July 15, 1981. This table is included in this submittel to add specific referencun on aging for each piece of equipment.

If you have any questions regarding this submittal or any previous sub .ittal ot -cav i ronmental qualification of Class lE equipment, we would be happy to meet with you.

i Very truly yours, f W ,

William O. Parker, Jr. p GAC/php Aetachment 0108240109 B10815 PDR t'. DOCK 05000369 8'fI/

E _ _ _ _ _ _ _ pp L

1 Mr. Ilarold R. Denton, Director August 17, 1981 Page 2 t

cc: Ms. M. J. Graham Mr. James P. O'Reilly, Director Resident Inspector . S. Nucicar Regulatory Commission l McGuire Nuclear Stati v. Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 1

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McGuire Nuclear Station - Unit 1 Environmental qualification of Class lE Equipment NRC letters coced October 15, 1979 and Februury 15, 1980 concerning the i environmental qualification of Class IE equipment defined the NRC Staf"'

I requirements with respect to NUREG 0588, interim Staff Position on  !

Environmental qualification of Safety-Related Electrical Equipment. ,

Basically, the Staff's requirements were as f;11ows:

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! I) Provide a table listing by generic type all Class IE  ;

i equipment including the appropriate qualific dion data for '

! the equipment. The format for this table wa= provided in

] the Staff's October 15, 1979 letter.

l 2) Review the adequacy of the environmental cualification for the equipment identified in item I abc a- with respect to the l Staff's position d$ scribed in NUREG 05c8, document the degree j of conformance, and Justify any deviations.

Further, the NRC issued a Memorandum and Order on May 23, 1980 establishing l NUREG 0588 as the requirement which applicants must neet in order to satisfy General Design Criterion 4 relating to the environmental qualification of

Class IE equipment.

I In response to the NRC Staff's requests for Information in this matter, Duke Power Company has conducted a thorough review of the environmental qualifica-ti?r -f Class 16 equipment located in a potentially harsh environment. A l suanery of the findings of this review was prodded to the NRC Staff in i submittals dated Janua?/ 18, 1980, August 13, 1980, and October 14, 1960.

4 On April 17, 1981 the NRC Staff Issued Supplement 5 to the McGuire Nuclear Station Jnit i SER which contained the Staff's evaluacion of the McGuire Unit 1 NUREG 0588 submittal. It is the purpose of thi? doctment to provide the additional l Informatic, necessary to resolve the itet s identified by the Staff in both the

SER text and in the t ompanying tables.

i SER Text ,Pt'agraph 3.1 l This paragraph of the SER addresses the completeness of the Class IE equipment qual!fication review from a systems standpoint, in this paragraph the Staff requested that the main steam isolation system be addressed or that proper i justification be provided Ter not addressing the system. We have concluded

! t.1at the Class IE componer.t> of the main steam isolation system were erroneously omitted f rc9 our NUREG 0588 submittal and that the qualification of these components will be addressed in the next revision to the submittal. The revision is scheduled for September 1;, 1981. _

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Page 2 SER Text - Para _ aph 3.2 This paragraph of the SER addresses the basis ' the service conditions identiffed in the NUREG 0588 submittal. In this paragr pn the Scaff requested verificativ.-

that the containment spray system is not subjecc to a disabling single - component failure. It has been verified that the McGuire Unit I containment spray system as described in the McGuire FSAR, Section 6.5 is not subject to a disabling single component failure.

SER Text - Paracraoh 3.3 This caragraph of the SER addresses the temperature, pressure, and humi 'Ity conditions inside the containe nc resulting f rom a LOCA or MSLS. In this paragraph theSgsffrequestedthat the profile in a review of theforMSLB the MSLB be extended scenario, from 1000that it was determined seconds within to .0 seconds, 10 minutes into a MSLB event, all feedwater flow to the affected steam generator will be terminated. Following the blowdown and subsecuent dryout of the affected steam generator, the containment temperature decreases rapidly due to the termina-tion of steam release. Af ter 20 minutes following a main steamline rupture, the containment temperature is less limiting than the temperature exhibited following a postulateJ rupture of the reactor coolant system. Therefore, it is not necessary to extend the MSLB profile to 105 seconds, in tFis paragraph the Staff also questioned the use of the LOCA temperature in the upper containment as the Ilmiting temperature. The question is based on the f act that the hydrogen ski nmer f ans take suction f rom !.he lower containment and discharge in the upper containment followlog either a LOCA or MSi s. In a review of this concern it was determined that the discharge of the hydrogen skimmer f ans into the upper containment will have no adverse effect on any Class 1E equipment also located in the upper conta i. ment for the following reasons:

1. The actuation of both the hydrogen skimmer fans and the containment air return fans is delayed 10 minutes f rom receipt of a containment high pressure signal. This means that the low cr containment temperature w:ll have already begun to decrease prior to initiation of these fans.

2. The actuation of the hydrogen skimmer fans is concurrent with the actuation of the containment at return f ans; thereforn, mixing provided by the containment air return fans wil' negate any p>tential temperature in the upper containment due to hydrogen skimmer fan d!* charge increase. This is evident f rom the capacities of the fans:

hyJrogen skimmer f ans - 3,200 cfm; containment air return f ans -

30,000 cfm.

3. The hydrogen skimmer f ans are .oco.ed at elevation 820 which is approxi-mately 50 feet above the coerating check. There is no Class IE equip-ment located in the direct sischarge path of these fans.

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l I SER Text - Paragraph 3.5 This paragraph of the SER addresses submergence. In this paragraph the Staff noted that the NUREG 0588 submittal Identified certain saf ety-related motor operated valves includir; associ.ated cables that are located below the maximum 1

post-LOCA water level. The Staff requested that an assessment of the failure j modes of these corronents be provided with consideration of the effects of their potential submergence on any other safety function including the potential of misleading information being supplied to the operator. The Staff further

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recuested that this review consider operating time, across the spectrum of events, in relation to the time of submergence.

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in a review of the safety-related motor operated valves located below the nortmum post-LOCA water level, it was determined that for all defined events the vaive 4 motor operators util perform their safety function prior to becoming submerged.

The flood level will reach the lower most safety-related valves at approximately 5 minutes into an accident situation. These valves, however will have moved to their safety position at apprcximately 15 seconds into an accident situatine j and are not required to rcposition subsequent to submergence. This time in04tsal l provides adequate margin to assure the completion of the required safety function.

1 Additional information concerning these valves is found in the McGuire FSAR,

Section 15.4.1.3 .

j The aspect of misleading information being supplied to the operator is under

review. Further information on this matter will be provided in an update to i

this report.

! SER Text - Paragraph 3.6 i

This paragraph of the SER addresses chemical spray. In this paragraph the Staff requested additional information regarding the concentrations of the chemical sprays used in the various qualification programs. We hnve reviewed the qualification programs for the Class IE equipment located inside the containment and have provided the requested Information as appropriate or the attached table.

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,SER Text f Paragraph 3.7 t

This parag aph of the SER addre;ses the aging of safety-related equipmenc. In this paragraph the Or3ff discusses the aging requirements for valve operators l

aualified in accordaece with IEEE 382-1972 and continuous duty motors located

' inside containment qualified in accordance with IEEE 334-1971. The Staff also

discusses the aging program for other safety-related equipment.

For the sa'?ty-related valve operators (motor and solenoid) located inside

, containment, a review of the qualification documentation shows thdt *.h se '

} operators were mec' anica11y, thermally, and radiation aged to an equ; valent 40 year service life in accordance with IEEE 382-1972. prior to DBE testing.

' Additiona' ty a review of the qualification documentation for safety-related .,

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continuous duty motors installed inside the containment shows that these motors were mechanically, thermally, and radiation aged to an equivalent 40 year service life in accordance with IEEE 334-1971 prior to DBE testing.

Maintenance schedules have been established for these valve operators and

, continuous duty motors that will assure that the 40 year life of the equipment

. Is maintained.

1 For other equipment, addressment of aging was no; a requirement in qualification programs committed to IEEE 323-1971 (i.e., Category II equipment). However, with the wealth of in-service experience covering a variety of equipment

! types, no significant in-service aging mechanisms have been identified which

could prejudice the qualification tests performed on new equipment within a I few years f rom start-up.

Duke Power Company is evaluating the In-containment Class IE equipment and will report at the time of discovery any equipment for which significant aging mechanisms are identified including the justification for condnued use and/or reasonable alternative action. This on-going investigation will necessarily be very time consuming and wil' ely heavily on EPRI research, NRC studies, NPRDS Information, IE Bulletins and Circulars, and Industry research and testing. Duke is an active member of the EPRl/ Utility Advisory Group on

Iquipment qualification and the AIF Subcommittee on Equipment qualification and is participating in the current efforts to develop an industry position

In regard to the aging issue.

in addition to the program described above, there are several on-going programs within Duke Power Company which address the surveillance, maintenance, and j replacement aspects of SER Text - Paragraph 3.7 These programs are described below.

The incident Investigation Program provides for the evaluation of equipment failures. As part of this program any components that may have degraded and i caused equipment failure would be Identified and appropriate corrective action taken. Identification of a component which degrades unacceptably over a period I

of time would result in either (1) replacement of the c 4.ponent with a better comp (4 ant or (2) establishment of a periodic replacement schedule for the com-ponent based on the length of time the original component functioned, in either of these two cases, the poter;tial for future failures is diminished with a re-sultant increase in rellaellity and .iafety. Failures are also evaluated to determine whether any entematic trends exist. Additionally, the Maintenance Management Program presently under development will provide trend information on a wide variety of equipment problems. This is a computer based system with the capability to identify recurring equipment problems. As problems

! related to aging or degradation are identified similar corrective action to that metioned above can be taken.

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l SER Text - Paracraoh 3.8 This paragraph of the SER addresses the basis for the calculated radiation doses both inside and outside the containment. In this paragraph the Staff questioned the radiation dose value range identified for inside the contain-ment since certain values were below the Staff's screening criterla. A rev!sw of this situation indicates that the equipment which has a 40 year plus accident T10 that is less than the Staff's screening criteria is only required for a shatterm function and is, therefore, not exposed to a high radiation dose prior to performing its safety function.

SER Text - Paracraoh 3.9 This paragraph of the SEA addresses margin. It should be noted that where margin has been identified as a potential deficiency for a given piece of equipment, it has been addressed on the attached tables.

SER Text - Paraaraoh 4 This paragraph of the SER addresses the Staff's assessment of the individual equipment items identified in Duke Power Company's NUREG 0588 submittal. The potential deficiencies identified by the Staff on a per equipment basis are addressed on the attached tables.

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McGUIRE NUCLEAR STATION - UNIT 1

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT LOCATED INSIDE CONTAINMENT

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I McCul8E NUCLEAA 11 Ail 0N - tJNii 1 Pap 2 SLMMAAf 0F ENVIRGNMENIAL QUAllFICAil0N 0F CLA51 $E EQUlPMENT Devision 1 LOCAIED INSIDE CONTAINMENT

!QUIPME NT M00EL OR ACCIDENT INVIADNntNT OPIAA84tlif CPlaAsillif ACCuaACT AC(URACV QUALIFICAllell IDf1TiflCAll(al MANUFACTuata 50ENilFICAT4Get ENvlRONhENT TO %AtlCN REQUIRED IN 84 MON 51AA1(9 DEQUlRES Dut(dellAAitt SIPO41 ANG (1) INHeta (2) QuALIFit0 ACCIDENT M&inOS INvinowirNT (H (t et sp nl (t et sp nl 6)

Trossaltter - Barton 764 Temp: 327 F Teep: 380 F 2 e.eeks 4 months t til nom.terer 857 WCAP 9585 Fressua lser Le <a n (tot 2) Press: 14.0 psig Peess: 75 psig post t,st post est nethod: 1,st (Lo er cotital u all RH; 1001 RH: 1001

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i 3.4=80 n a.d: 5 luia

'C.ier Spray: Soric Chee isray: Boris acid anJ sodlue C d and sodlas tetreborate soln. lqaromide soln.

SER ITEM CS: Initial Spray: 2000-2100 ppm Boron Reci rculated Spray: 1800-2200 ppm Boron 4.0 - 4.7 pH 6.0 - 10.0 pH Test Spray: As documented in _WCAP-9885, the chemical spray consisted of 2750 ppm boric acid dissolved in water and adjusted to a pit of 8.5 by sodium hydroxide, which is representative of the range of pil values permi tted in the long term. ,

A: Aging was not a requirement in the qualification propam for the Barton (LOT 2) transmi t ters, which was developed to address IEEE-323-1971 Radiation aging, however, has been adequately addressed by the LOT 2 testing program.

The materials and cunponents used do not have a known thermal aging mechanism (as canpared to Appendix C of IE Bulletin 79-010) that could af fect the performance of the transmi tters during the* first two fuel cycles of reactor operation. Upon the coupletion of ?.arton LOT h tests, which include aging, our intent is to demonstrate the similari ty ot' the earton t0T 4 and t03 2 transmi tters and thus obtain e proven queiified ii re. Aaditionaiiy, refer to the generic discussion of SER Text Par.agraph 3.7, Aging.

H: This deficiency was deleted per discussions with H. Slosson, NRC-EQB, 7-8-81.

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McCutRE Nutt!AR STAilcol - UNIT I Peve 3 StewSAf 0F E48vipONhtNTAL QUAtlFICAT10es CF CLA55 It EQulPMilei Realelon 1 LOCAlt0 IN51M CoeilAINHtNT EQulPntNT M00tL OR ACCtW NT EldVIR00MlNT OPEAAelLITY OPERA 81LITY ACCuaAs;V ACCT 4 LACY quAttflCAlless IDCTiflCAll006 MAfteFACTUMA INNilF ICATIoli toevikosentNT IJ446tCH MQulus las Mst0se5TnAite Meulus etse0N1TaAige u PCai ANG (I) minista (2) quatiftts ACClw NT Mt Noe ENvlacNntNT (3) (t et spen) (1 .t spen) (4)

Treaseis tsr - Bertoa 764 Temp: 327 F Temp: 380 F p actor trip 4 aunths Trip funcelon: <a 51 (5 maal W AP apets 5/G towel (8686) (tot 2) Press; 44.8 psig Press: 75 pals K5 min.) Post Det e 51 (5 mia) twthod. Test (Lc,-er contalaw.at) pH: 1001 aN: 10C1 Plus 4 months Sad 2.)ml0 7R Aed: 5=l0i# poet Def PAM functica: Maa irror 15%

Chem Spray: Soric Chem 5 pray: seric t 25% (4 mo) (4 au) acid end soJitse acid and sodlise tetrettorate sola, hydroalde sein. (Note 5)

SER ltem CS: Initial Spray: 2000-2100 ppm Boron Recirculated Spray: 1800-2200 ppm Boron 4 .0 - 4 . 7 pli 6.0 - 10.0 pil Test Spray: As documented in UCAP-9885, the chemical spray consisted of 2750 ppm boric acid dissolved in water and adjusted to a pil of 8.5 by sodium hydroxide, which is representative of the range of pH values permitted in the long term.

A: Aging was not a requirement in the qualification program for the Barton (LOT 2) transmitters, which was developed to address IEEE-323-1971. Radiation aging, however, has been adequately addressed by the LOT 2 testing program. The materials and components used do not have a known thermal aging mechanism (as compared to Appendix C of IE Bulletin 79-010) that could affect the performance of the transmitters during the first two fuel cycles of reactor operation. Upon the completion of Barton LOT 4 tests, which include aging, our intent is to demonstrate the similarity of the Barton LOT 4 and LOT 2 transmitters and thus obtain a proven qualified life. Additionally, refer to the generic discussion of SER Text Paragraph 3.7, Aging.

M: The qualification tests demonstrate that the trip accuracy requirement is maintained for up to five (5) minutes and probably much longer although that was not the intent of the program. Once the protection signal is generated, it is " locked-in" by the protective system and will not reset regardless of the transmitter's subsequent performance. The qualification program also verifies that the transmitters will continue to operate for at least four (4) months post-accident witisin a relaxed accuracy requirement which provides additional margin for the five-minute trip requirement.

The qualification program utilized a IS-day test period simulating a four-month post-DBE unvironment based on conservative aging proceduren referenced in MCAP-9885. This conservative basis (0.5 ev in the Arrher as equation) ensures that ad 'uate margin exists.

tecCulRE NutttAR SIATION - UNii l rey. I StewtAAf Or EWlp0NMINTAL QUALIFICAll0N OF CLA55 IE EQUIPMENT Devlslon I LOCATED ON58DE CONIAINMENT I

(QUIPttENT ft00EL OR ACCIDENT ENVIRONMENT OPE RAtiLITY OrtRAtiLITY ACCumACY ACCURACT QuALIFICA110sl

( WlR0hMENT TO WHICH FEQUISED 2N DEMONSTAATED SEQUlk(B sinese51pAltp p(P6Al AND ID(ITIFICA11011 ftANufACTuaEA 10(NilFICAT1000 leunt(R (2) QUAllFl(9 ACCib(NT #4TH00 (1)

LWlA069dNT (3) (l ef Spen) (S of Span) (4)

Rio - Aosemount 176 EF Temp: 327 F Temp- ll2 F Reactor Trip bN 1 0.2% 1 0.2% WGP Siti eaJ Ode AC$ Tawerature (km) Press: 14.8 psig Press:  % psi 9 (< 5 ein) PaST S'd 8etier t.ner to RN: RN: 1001 ter ton dated Decepeer (towe r cont airment) 100%g RaJ: IX10 A Red: lal00d 19, 1973 them Spray: N/A ClemsSpray: Beric acid anJ sodlum Me t t.oit Test /4nalysis hydromide soin, - _-

SKR STEM CS: These RTD's are not exposed to any degradation f rom the effects of chemical spray prior to performing thei r safety function.

A: Addressnent of aging was not a requirement in quali fication program for these RTO's which was developed to meet the requi rements of I EEE-323-1971. Futhermore, in-service experience wi th the type of equipment supplied by Wostinghouse shows that it is hignly unlikely that a significant in-service mechanism exists which could prcJudice the quali fication tests perforned by Westinghouse on new equipment. I n addi ti on, radiation aging has been adequately addressed by the Westinghouse test program. A marginal application of one material (ethylene propolene rubber) has been identi fied in Appendix C of IE Bulletin 79-018. The RTD's will be replaced within 10 years unless it can be shown that the EPR i s a non-cri tical inaterial . Addi t i onal l y ,

re fe r t o the generic discussion of SER Text Paragraph 3.7, Aging.

based on the radiation test of I X 10 ganrna 0 , the RTD's quali fied li fe would be in excess of 10 years plus 4

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fi ve mi nutes pos t-SLB. I f the EPR is Judged to be a cri tical material, the life would be limited to 10 years.

The Rosemont RTD quali fication test program utilized a 6-day test period simulating a 52-day post-DBE environment based on conservation aging procedures. This test documented by _WCAP-9157 ensures that adequate margin exists.

P. ,e 5 IncCUIRE hutitAR STAitose - Balli i 9evision l StoutARY OF HewlSesetLNTAL QUALIFICAi40se OF (LA15 It EQultetENI LOLATED Im51DE C006IAlletENT ActuaACY QuAlsi scala Get ACCIDENT ENvisosettici ortEAalLITY crthAtlLITV AttunACT 4QUIPMtNT MODEL OA REQuipfD $N F*H0el51AATie A&quisit gueGee51 AA148 Streat Ane IM ullflCATielt Laevincestini ToneutH ediscos 8 CilFICAileu MAleufACTuata litete(A (2) Qu4tif t(8 ACCIM WT (1) Envl A0sedNI ()) (% of Spen) (1 ef Spen) (4) 1 0.21 1 0.21 hette 9161 .nd Dune Temp: 377 F Temp: 352 f 2 weeks 8eIIe' Pasker to Susemuunt 176 K5 sip -

Press: 18. 8 psig Psess: 66 psig post Det 6u t L L')L DesvLgn dele t Lecember

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1110 A peJ:

1 Iml0 A

1. 9. 09/9 (hem Spray: seric Clem Spray: Suric .sshoe C aw.r es to aclJ and sodlum acid and sodium noJa e n nr toer.>or se sola. hvero lde s.In. Tess/An. lysis SER l tem '

l l CS: Initial Spray: 2000-2100 ppm Boron Recirculated Spray: 1800-2200 ppm Boron is,o _1.7 4 pli 6.0 - 10.0 pil Test Spray: The chemical spray solution consisted of 1.116 wt. % boric acid and 0.17 wt. % Na0li dissolved in H O 4 2 which l corresponds to a pH of 8.5 and is representative of the range of pH values permitted in the long term. ,

1 A,M: Addressment of aging was not a requirement in qualification program for these RTD's which was developed to meet the require- I ments of IEEE 323-1971. Furthe rmore, in-service experience with the type of equipment supplied by Westinghouse shows that it is highly unlikely that a significant in-service mechanism exists which could prejudice the qualification tests perforn:ed by Westinghouse on new equipment within a few years from startup.

The materials used in this component have been compared with the list of components In' Appendix C of IE Bullet in 70-010 and, based on this comparision, no significant degradation would occur during this time. Basedonthenewrequirementgoaddress source terms associated with contained ac.cidents in the reactor coolant system and the test program dose of I x 10 rads gamma, radiation aging effects have been adequately addressed for 13 effective full power months (1st fuel cycle), and 2 weeks post-DBE. These RTD's will be replaced during the first refueling outage. The qualification progran utilized a 6-day test period simulating a 52-day post-DBE environment based on conservative aging procedures documented in WCAP-9157. 1his l provides adequate margin for the time period discussed above. Addi tionally, refer to the generic discussion of SER Text l Paragraph 3.7, Aging.

. l

McCulM IsuCttAR STA180N

• IMlT I P.go b

a. isie. I Stavaar er sNVia0witNIAt QuAtirtCA180N Of ttASS et EQUlentNT toCAnto INSIM C0h1AINedNI M00tL OR MCIDENI (NVIROhNINT OPERA 81Ll V OPEAA41LITV MCURACT M CURACY QUAlliICAllesi tQUlPMfMT MPOAf Amt letNilflCATIGII INVIRohhENT 10 taitCN REQUtM9 IN M nGIISTAATES MQUIMD MM01851AATES 190TiflCATICII ftAHufACTUMA ninhop INetMR (2) QUALIFIES ACCIM NT (1) ENvinose<NT (3) (s er Sp.nl (s et 5, ) (4)

E lsct ric etydrag.. g Sturt.w t A ve.p: ISO F Te.p: 309 f 3 .s.nths 8 y..r N/A es/A KnP 7820 .n4 Fr.ss: 14.8 esig Pr.ss; 62 psig post LOCA post LOCA supplenents 1-4 4tumbine r t (Upper cont.inment) pH: 1001 8H: 1001 R.d; 8.IIl0 A I

n.J: 2alo0a k(AP JJo9.L .ad Chee Spr.y: Boric nee Spr.y: Doric 5.pplement s I-4

.c14 .nd so45 4.t,.i ,.t. soi.. .c.la iv , .no sodio.

soi.. ne n.om 1.st SER Item CS: Initial Spray: 2000-2100 ppm boron Recirculated Spray: 1800-2200 ppm Boron 4.0 - 4.7 pil 6.0 - 10.0 pli Test Spray: PCAP 7709-L, Supplement 2 describes chemical spruy testing conducted on the 112 Recombiner. Several types of spray tests were conducted including one using 2500 ppm boron (boric acid) with haOH added to give a p!! of 10.0.

To this spray, sodium tet.aborate was also injected.

A: The metallic materials used in the H2 Recombiner are not known to be susceptible to significant degradation due to aging.

All electrical components furnished with the y electric recombiner which may be exposed to post-LOCA environments and which use electrical insulation were tested. The power cable, heater connector wi re, heater elements, thermocouples and extension wire were subjected to thennal preaging of 80 heatup and cooldown cycles followed by si.x. LOCA steam pressure 8 and spray cycles. All of the above items plus the terminal blocks were subjected to a radiation exposure of 2 x 10 rads ganuna followed by another LOCA test as described in ECAP 7709-L, Supplement 2.

Due to the fact that no significant degradation was observed following the thermal cycling, radiation exposure and LOCA cycle described in yCAP 7709-1 and Supplements 1-4, it is felt that the H2 recombiner will provide adequate service for 40 years of normal operation plus 1 year post-LOCA. Additionally, refer to the generic discussion of SER Text Paragraph 3.7, Aging.

M: lhis deficiency was deleted per discussions with M. Slosson, NRC-CQB, 7-8-81.

l -

\

etcCulkt htXLEAR 51AllON = UNII l 5MAf 0F INvl AotettNIAL QUALIFICATause OF (LA55 18 EQUIPMINT Page 7 LOCATED IN51DE CONTAINittNI Aevision !

EQLI)PtstNT IDCilFICAllosi tt0DIL Oft ACClotNT inANUFACTUAIR FNVI ACNMENT OPE RA88 tiTV SCENTIFICATices GPEAA88teTV (4) (NVI RON#t(MT 10 natit:1 AtQuaAfD IN ACCunACT ACCU 4ACY leutteth (2) ctM0N5IAAIL. QtMllFICAllous QUAltfl10 ACCIDENT AtQUSA10 DORON51AAlle AireRI AND tNvlAONntNT (3) (1 of 5 ,en) MiiH00 (s .F sm) (4)

Centslewunt Air .loy/Rellence 2XF-3)o081 Temp: 380 F Art sn t an Neurs Ice ,: 110 F 2 sonths (e;,per coccalaient) Press: 14.8 psig Press: 85 pal 9 8 year N/A N/A AN: 1001 Aet post 08I post IP lest ar pse PF-64182 AaJ: 7.6180 74 Add: 100<3 IX30 M ard he,,,le.e ne e t Chem Spray: Boric Chee Spray: Aoric i o,n;u l reg,, 14 403 acid and sodlue acid and sodiwa 0 less Accart Il kW tetrateorate sein. hyJroalde soin, I lest 4 Wet but-9 ar.1 byp lace at 4/84/oO

_ g heitoJ: test SER l if M. _.

CS: Initial Spray: 2000-2100 ppm Boron 4.0 - 4. 7 pH Reci rculated Spray: 1800-2200 ppiii Boron 6.0 - 10.0 pil Test Spray: 3000 ppm Boron, 10.5 pfl A: Safety-related continuous duty motors aged to an equivalent of 40 years of servicelocated inside containment have been mechanically, thermally, and radiation discussion of SER Text P.ragraph 3.7, Aging. in accordance wi th IEEE 334-1971. Addi t i ona l l y , re fe . to the ge ne r i c M:

This deficiency was deleted per discussions wi th H. S losson, NRC-EQB , 7-8-81.

etcCutRE huCIEAR STATION

• UNii l Pege 8 St#utMV Or Elfv1R0hnlNIAL QUAteFICAll0N OF CLA55 It (QulPMENT nevision LOCA1ED IN5tM CONTABMINI (QulPMENT et00(L OR ACClDINT ENvlPONntNT OPE AABILITV ettAAstllTV ACCunACV ACCunACY QUAllflCAI10Il I MITIFICATIGIt itANuTACiunfA INNilFICAT1011 Elevl AONMNT TO WHICH AlQulAfD IN M M000$iAAIES REQulMD MMuM51aAlte stP0al ANe (1) leuM44A (2) QUALIFICS ACCIDENT Mince aNvlnolenni (3) a et Span) (s .t 5,en) (n)

• yJrov en Skla er Joy /Rellence 1 VF-882)l5 Ter p: 180 F , p: 330 F 2 .nths 1 year N/A N/A 1.s t e. gor e # 5 - 64231 Fan Maeors Pr.ss' 14.8 psig Press: 85 psig gast Dtt post Ost end S.pp te n . ,e (upp,' :ent elnns nt ) RH; 100% RN: IW recknic as p.,e ,- i A-koit mea: 7.6 307a nea, voa 9 test e, poet e-604 Chem Spray: Soric Chem 5- - , soric te s t R s oe t muc-9 and acta e.nl season ecle e soolo. 5-p i. ni 4/I*/80 tetraborate soln. hydroside soln. nettoa: Te s t SER ITEM CS: Ini tial Spray: 2000-2100 ppm Boron Recirculated Spray: 1800-2200 ppm Boron 4.0 - 4.7 pli 6.0 - 10.0 pil Test Spray; 3000 ppm floron, 10 .5 pil A: Safety-related continuous duty motors located inside containment have been snechanically. thermally, and radiation aged to an equivz. Vent of 40 yeals of service in accordance with 334-1971. Addi tionally, refer to the generic discussion of SER Text Paragraph 3.7, Aging.

M; Thi s de ficiency was dele ted per discussions w8 ?S M. Slosson, NRC-EQB, 7-8-81.

McGulRE hutitAA STATION - IMli l Page 9 SteetAmf 0F ENWISONMENTAL QuAtlFICAll0N OF CLA55 IE (QUIPMENT Aevlslon !

LOCAlt0 Sh51DE CONIAiletini EQUIPHINT M00fL 0A ACCIDENT E NWlR0hMENT OPEAAsiLITY OPEAA81LITY ACCUAACT ACCURACV QuatlF ICATION IDCilFICAil A MJ4WACTUREA IDENilFICM10ll thW4 RONMiki 1C mlCN a(Qulpts IN Mn0N51AAfts atQuinte sin 0N5Imitt stroni Aho 62enMR (2) QuhLIFIE D ACClothi MilHOS (1) (1 of Span) (% of Span)

• thvinosetthi ()) (le) temp: 327 F 38.0 F 5 min ju days h/A N/A test 8ePo'*8 Volve Ntor motork 7 hAl, il NAI, T ems.: N 41/3g , Ceten er $9I0 Cperators 14 hAl, 16 NAl, Press; 14.8 psis Press: 15 psis (Notes 8 nd 9) pcs cet fu lit, k tol.ee 491) ite.er contalement) 30 NAl, 40 hAI, Ast: 400% P.se: 8001 in 222, has 19/5

. 70 h41, 90 esAl P ed: 6.728072 24J: 2ml08a Chen Spray: sorIc slee Spray: Soric Wh ed 1881 acid awl sodime r id and sadlma te trat, orate soln. hyJromide soln. , l

~

~ '

SER ITEM QT, H: The actual qualification test duration is 30 days post-DBE whic;i adequately exceeds the required operating time.

A: Safety-related valve operators located inside containment have been mechanically, thermally, and radiation aged to an i equivalent of 40 years of service i n accordance with IEEE 3P. '972. Addi tionally, refer to the generic discussion of SER Text Paragraph 3.7, Aging.

CS: ini tial Spray: 2000-2100 ppm Boron Recirculated Spray: 1800-2200 ppm Boron 4.0 - 4.7 pH 6.0 - 10.0 pil Test Spray: 10,000 ppm Boric Acid, 7-9 pfl .

, l e

e W

l

pe ,. 10 Sevisionl InGutRE lauttEA8 STAllose = UH8T I 54WIARY OF EmWlh0NHINIAL QtaAllFICAlsost 1 (LA55 lE EQUlfvtLMT LOCATLD IN580( CONIAINrt1NI QuAllflCAllagt ACCURACT ACCunA(f McGai Amt OttaA84tlTT GetaA88LITY MmouslaAlte ENVISOhnthT M noss518ATES i Alftusals MiiNos ACCIDE NT atQUHD Im (4)

M00(L 04 tuviachntari To naus.)

ACCIDENT is of speal (s of spen)

(QueenthT INNisFICATleal 44MLif etD ENvin0mntui 0)

ItAlluf ACiuhEA lelmi4&A (1)

IDCilFICAT1016 t is>I sor que test (4) N/A N/A Sepoes; 4G058 10 days

- Temp: 340 I $ min post Cat Jeauery ll, 490 SMS Temp 180 F Press; IOS p>lg (Notes 8 and 9) valve r or Llelteeque Passs: 14.8 psig 8004 nested. Test AN:

0.>e ret o. , Ast: 100% 0 ped: 1ste d meJ: 8.2ml0 4 (Upper contalmeent) Chee $ prey; Boric them 5 prey: Boris acid and sodium acid and sodium tetretorate sola, hydroalde sola.

w SFP l TEM required operating duration is 30 days post-DBE which adequately exceeds the QT, M: The actual qualification test time, have been mechanically, therioally, and radiation e

located inside containment Addi ti onally, refer to the Safety-related valve operators ith IEEE 382-1972.

A:

aged to an equivalent ofl f 0 years of service in accordance w yeaeric discussion of SER Text Paragrapli 3.7, Aginj. 1800-2200 ppm Boron Recirculated Spray:

Ini tial Spray:

2000-2100 ppn Baron 6.0 - 10.0 pil CS: 1 .7 pil

', 1 .0 6 6 Test Spraf: 3,000 ppm Boron, 10 .5 pli

l locGutRE NUCifAA STATION = UNil 1 Page i

$sDWSAY er ENVIR0eettMTAL Q.aAs tFICAf ton of (tAs1 BC (qulMitNT neelston 1 LOCA110 IN51DC CON 1%IMntNT (QuirntNT MODEL 04 ACCIDENT (NVISDNn!NT OPEPAtiLilf OP(AAtiLITT ACCunACT ACCURACY QuAllFICA100N BDCTIFICAllell MANUFACTuhtm INNilFICATielt ENvlachntNT 10 WMi t ** RiqutRED IN Mn0NSTRAfte MQulMe M nonstaAlto atPcal ANs (t) lasteER (3) QuALIFl!8 ACCID (NI (t et spen)

MLTH0s (NVlaceewNr (3) (s r 1,en) (4)

Votes Solenoid Welsor V526 leg: 327 F Temp: 3% F Operate upon 31 days N/A N/A Iett bePosts operctors V$7) Press: 14.8 palg Press: II) pst. receipt of a post ett Gh-5;t4>515 a..J (tower containment) AN: 100% AM: 10G1 safety signal CA-57300-5Mb-i-1 Red: 7.5=IO?n mad: 2alc8a October II. 1977 Chem Spray: Boric Clee Spray: soric n., 15. 1973 acid and soJI.un acid ens soJium tetreborate soln. hydroalde sola. Ne llud lest SER I TEM _

QT, M: The actual quali fication test dui tion is 31 days post-DBE tvhich adequately exceeds the requi red operating time.

A: Safety-related valve operators loc'ated inside containment have been mechani ally, thermally, and radiation aged to an equivalent of 40 years of service in accardance with IEEE 382-1972. Addi tionally, refer to the generic discussion cf SER Text Paragraph 3.7, Aging.

C5: Ini tial Spray: 2000-2100 ppm Baron Reci rculated Sr.n y: 1800-2200 ppm Horon 4.0 - 4 . 7 oil 6.0 - 10.0 pil Test Spray: 1720 - 2200 ppm Boric Acid, 9.5 - 10.5 pit .

f McCulpE NUCLEAR SIATION = U14I I rage 12 SUHttAAf SF ENWlRJNn1NIAL Q' J ALIFICATION OF (LA55 f t EQulPMENT movision I LOCAlto INSIDE CONTA10eNINI (QUSPMENT MODEL OR ACCIDENT ENVIRONM[NT OP AABILITV OP(AAstLITY ACCumACV .sCCuaACV QuAthFICAT10sl IMITIFICAll0ll E UFACTumEA ID8MilFICA140ll ENWi&ONMENT TO WNBCN MQulMD IN MMosl5TRAlle mEQulMe NMEss51AAits p(Pont ANe (1) 18uHeta (2) QuAliftfe ACCIDENT Mt1Noe (NvlaOsedNT (3) (1ofspen) (% of spen) (4)

Rotork temp: the F Temp: 340 F 5 min (maa) 30 days N/A N/A test repoet Mil /4 '

Containmnt Air flNAll *

1. eturn Isolation Press: lle.8 psig Press: 75 psis post beg post Oer Cece.Aer Isla Lt y r notor ein: 1004 AH; 10G7 Red: 8.1380 A sed: 2ml08A le ss ste pos t Tall 6 (Upper containment) them Spray: toric them Spray: DerIc Oc tua es 1973 acid and sudium '

acid anJ sodismo tetral. orate sola. bydronide sula. Method: f e st

~

SER1[EM CS: Initial Spray: 2000-2100 pgNn Boron Reci rculated Spray: 1800-2200 ppm Boron 4.0 - 4.7 pit 6.0 - 10.0 pit Test Spray: 10,000 ppm Boric Acid, 7-9 pit A: Safety-related valve operators located inside containm<.nt have been mechanically, thermally, and radiation aged to an equivalent of 40 years of service in accordance wi th IEEE 382-1972. Addi tionally, refer to the generic discussior of SER Text Paragraph 3.7, Aging.

M: This deficiency was deleted per discussions wi th M. Slosson, NRC-EQB , 7-8-81.

-+

em

W.JIME huCLE AR $1AT1000

• UNIT I rage l3 568WtAAV 0F ElevepoemtNIAL QuAtlFICAllose CF (LA55 If LOMf.Ni Sovision l LOCAlte inMet C0hlAltedNT l

EquippetNT lt00CL OR ACL10ENT ENWlAUNMENT OrfaAsstl1Y cetaAstLITY ACCunACT ACCunACV quAtlFICAllen it( TlFICA110N leMeufACTse;4 r 19&milFICAll0Il thvit.ONMENT 10 ndH4CN REQUlkt0 IN Duten5TAAlte StQUIRES theonS1h4Its B(Pont Amt i lensetEA (2) quhttfits ACCID (hl set tosos (1) (s of spea) tuvimosetmi 0) (s et see ) (6)

Welwe 548englJ /sco NP8)l6t34f leap: 327 F leap: 3% F operate upun 30 Jays m/A m/A Tesi m. port kr8)l6( 34.1 Press: 14.8 psig Press: ele pelg sesalpt of safety post 14t AQ528678/IA Gr retors RH; RH; O twr consa3auxet) 8005 d00s. s I egenel SaJ: T.5ml07s R4J: c. l(. 2 N t ud test Cl= eve Spray: N/A Ctwee Spray: torlc aclJ as.J soJime hydromlJe sole.

SER ltem CS: Initial Spray: 2000-2100 ppm Boron hecirculated Spray: 1800-2200 ppm Boron 4 . 0 - 4 . 7 '111.

6.0 - 10.0 pil Test g ray: 3000 ppm Boron, 9.5 - 10.5 pli QT,M: The actual qu llfication test duration is 30 days post-DBE which adequately exceeds the required operating time.

A- Safety-related valve operators located inside containment have bees, mechanically, thermally, and radiation aged to an equivalent of 40 years of service in accordance with IEEE 382-1972. Addi ti onally, refer to the generic discussion of SER Text Paragraph 3.7, Aging.

McDilal NixtEAR stall 0N - lHiei l r ege III novlsionI SLMMAAt er ENVIRCantMAL QUALIFICATION of eta 55 IE EQulPMENT LOCAIED IN5IDE EONIAINH(Ni (Quirr4NT MODEL 04 ACCID (NT ENVIRONMENT OPE RAslLITT OPERA 41LITY ACCURACT ACCUAACY QUAllFICAll0N IDE%ilFICAll0N HAleufACiuhER IDINilflCAllev ENVIFONMENT 10 MHCN REQulklO IN Dist(4651AAIES M(lulMS MpeQM5IRATES M FORT Aase Nim 8(4 (2) QuAttflLS ACCIDENT M&iH00 (1) sNvla0NntNT (1) (s .t spea) (s .t spen) (4)

Temp: 327 F lemp: 385 7 (Note 10) 44 de,s N/A N/A Te.t A6 port 2375.

Wsivs Solenuld larget 77CC Cpe.4 srs Rock MoJet Press: 14.8 psig Press: 66 psig post Ott 9/26/13 (L er congelament) AM. 8004 Rat: 1004 med: 5.7xt07a a.J. I.3 808a mtM 1e,t

"* Cl.ee Spray: Boris Chen Sprey: Boric acid e.1 soJlum esid and tetrek.ete sola. hydrosine SF R f.). J t

CS: Ini tial Spray: 2000-2100 ppm Boron Reci rculated Spray: 1800-2200 ppm Boron 1.0 4 le.7 pli 6.0 - 10.0 pil Test Spray: 6200 ppm Boric Acid, 8.6 - 10 pH A: Safety-related valve operators located inside containment have been mechanically, thermally, and radiation aged to an equivalent of 10 years of service in accordance with IEEE 382-1972. Addi tionally, refer to the 6

generic discussion of SER Text Paragraph 3.7, Aging.

H: The Target Rock solenoid valves are used in the reactor I.ead vent system to provide a path for removal of non-condensable gases. Core events leading to the Seneration of signi ficant amounts of non-conderisable 942s occur early in the postulated accident sequence s and are of si. ort duration; t he re fore , these valves us e only requi red to operate wi thin the fi rst fw days of the accident. The need for venting non-condensable gases is not anticipated beyond the ill day quali fication of the valves.

d 1

McGUIRE NUCLEAA STATION = UNil 3 Pap 15 SL9tM4810F Easvih0NNENTAL CdALIFICAla0m et (LASS It (QUIPM&di aevision I LOCA1(9 lNSIM C00eIAIMMENT MODEL OR ACCID (Ni (NylAONh1NT OP(AASILITV OPERA 41LITY ACCuaM= ACCUAACT Quat e flCAI1000 IQUIPnfMT Mattm51aAlte a(Poet Asse let;TIFICAlleII stANufACiumfA 18&NilFICATIGIR INVlSONMENT 10 WICN 81008810 IN M Moss 51AA189 REQulhES ACCID (Ni sellu06 (1) Nuneth (2) QuALIF8&S ElevlR000ttNi ()) (% of Spen) (1 of Spen) (4)

I man 5 min 1 0.5 pelg g 0.) psig inst h.po. : A2)l-80 Solon Iemp: 840 F leg: 150 F Olffsrential Pres. JP5tA0W Press: 15 psig post Dbt post DDL Test Asport A2%-8J sure 5=lach for Press: 14.8 palj Damper Control SH: 8001 $H: 4001 y,,,

2.14106 , p,,,,3.

(4.pper conselnment) RaJ: 8.151054 maJ:

Clem Spray Boric Chen Spray: toric aclJ enJ sodlum aclJ anJ sodlum tetraborate soln. tetrat orate soln.

S ER l t em - _

CS: Initial Spray: 2000-2100 ppm Boron Recirculated Spray: 1800-2200 ppm Boran

, 4.0 - 4.7 pit 6.0 - 10.0 pil Test Spray: 2000 - 4000 ppm Boron, 4.0 - 4.7 pil A- This pressure switch has been qualified for the 40 year normal life plus the accident envirorvuent. Additionally, refer to the generic discussion of SER Text Paragrar h 3.7, Aging.

M Within the first sixty (60) seconds following an event requiring this switch to function, the switch will actuate permitting the containment isolation damper to open. At that time the dif ferential pressure switch is electrically isolated from the control circuit and subsequent failure has no impact on safety.

ItcCLIRE NuCtfAA $1ATICf8 = letti l Page Stevenaf 0F salWI A0f31[NTAL QUALIFICAT10N OF CLAS5 IE (GUIPhiNT movision I LOCATED IN5IDE (CNTAINMENT EQulPMENT MODEL OR ACCIDENT INVI RONNINT OttmAaltlTV OPERAstilTY ACCuaACV ACCuaACV QuAta t sCaitose IDCilFICAll0sl stANufACTuafh INNilFICAll0li thylRONMENT TO WICet etQusato les N HcasiaAile SEQut RED DLMC411AAlte ELPJAI AMS (1) - lustate (2) QUAtlFIE D AC C oles i.T r.1THoa thil AottitNT (3) (I of Spen) (Z of 4 w.) (4) fisca. acel 0.G. 088alen types A.S.C. femp: 327 F lemp: 38 0 r a. e.,nt ei, s.aunths en/A se/A test s .n>, t e ( e .ga.y, Peneerations 0. t .F. G. lf, J. Press: 14.8 psig Press: 15 psig 8,wst I,Bt post CBE 8E-2$2. eru ak-221 (La.or contelnment) E.L.M. and &N* 100% AN: 100g cathodic pro- Red: 8.5x10 IR med: 2nah A Mete 2J: lest/ Acel sts.

taction pene. Chem Sprey: Boric Chen Spref: Soric tretlon acid and sodlum eclJ and suJBus (Note ll) tetreiburele sein. IvyJromlde soln.

(Nate 32)

SER lteng QT,M,CS,A: These items will be resolved pending the completion of the test program outlined below:

These penetrations have been included in the NRC Qualification Verification Program. Recently there has been an interchange of inform lion bet'.een Duke and NRC concerning a failure mechanism observed during testing conducted by Sandia Laboratories, in order to investigate the f ailure mechanism of the El'A (Electrical Penetration Assembly) test at Sandia and to verify the adequacy of the qualification of the connectors or, the EPA's, Duke Power Company plans a two part program: First, a material data search will be made to obtain a more definitive understanding of the material charJcteristics of the connector sealing gro.. mets which relate to the failure mechanism. Second, an environment' 1 qualification test will be performed to repeat the test profile performed in the original qualification prog.am by D. G. O'Brien. The test will include 1). individual components, thermally aged and irradiated, 2) various sizes of connectors, 3) a close simulation of the actual installation, 4) a variety of cable types actually used at the station.

T;e test sequence will include aging, irradiation and then .he steam environment test with electrical tests in between. All circuits will be energized with their appropriate voltages and currents.

This program is expected to be complete by January 1982 with a report available shortly thereafter. A more detailed schedule will be p:.wided as arrangements are made. Addi tionally, refer to the generic discussion of SER Text Paragraph 3.7, Aging.

McCulat NuCLEAA 51 Ail 0N

• UNii I page i7 SMAf GF Ill*300sednLL QuAliflCATION OF CLA55 lE EQulPn(Ni Sevlelo. O LOCA110 IN5IDE CONIAlledNT HODER. OR ACCeletNI (NvlAONntNT OrtAAtiLITV OPERASILITY MCUAACT ACCumMY Quat l51CAllem (QuienENT

'DENiJilCAileN Elevin0Nn&NT 10 mlCet atQutaED IN DinOsl51AATEe afQulate etsum5faA1(e htP0ai ANs IDENTlflCAll0N MANUFACTUR(2 nainos (o Nunsta (a) Q w irito ACClotNT tuvinssenNT (3) (x of sp.n) (x er spen) (4)

Iemp: 345 F 30 days 130 days N/A N/A le st lepris IN*l.

Cebla - Okunite IP insulation Temp: 327 F 1804. and Cott rol, lastrumen- Press; 14.8 psig Press; 804 psig post Ott post Det n-l. I.-3, 8001 348 pH: a001 kH:

att lun. and 2 av tr.1002 power m4J: 6.7tl0 IA pad:

methoJ: lest (Lower contalrunent) Chee Sprey: Boric them Sproy: soric eclJ and sodium acid and sadlun

• tetraborate sola, hydromlda soln.

SER ltem _

CS: Initial Spray: 2000-2100 ppm Boron Recilculated Spray: 1800-2200 rpm Boron 6.0 - 10.0 pit l 4.0 - 4.7 pli Test Spray: 3,000 ppm Boron, 10.S pH A: This cable has been quallfled for the 40 year aormal life plus the accident environment. Additionally, refer to the generic discussion of SER Text Paragraph 3.7, Aging.

I M: This deficiency was deleted per discussion wici M. Slosson, HRC-EQB, 7-8-81.

ficGulM 8eUCLEA8 STAil0* = UNii l Pep !8 SisetAav er ENVIReett!NIAL QUAliflC# ,0s0 0F CLA55 IE EQUlPMENT Revillo. O LOCATED th510E ComIAlfedNT IQUSPedNT ft00EL OR A(ClDfhi (NWIRONntui ON RAtiLITY ON RAtiLITV ACCueXY ACCunACY QUAtlFICAllem ITTIFAATlast fiAleufACiunfa itimilflCATecla taevinessMali 10 bets!** REQuinte lh MonisslinAlis MQulMe DEpiumslaAlte str0at Amt (1) Insista (2) QuALle t.a ACCIM Nr sialmoe savinossemi O) (s .i S m ) is .e Speal (4)

C ats te

• OLealse lefse t 280 Temp: 321 F 1emy; 348 F 4 asht esadayt N/A N/A felt 6eport ee 0-8 b ttreeentation latelatiba Prest: 14.8 p&lg Press: 112 palg. Pont Otil {$ept ead e e lyh)

(t oi.e r cont elnment ) RH: 1007, are: 1004 had: 8.5380 IA SaJ: 2al0 0A MM Test Chen Spray: Boric Chee Spray: Boric

, acid and toJium aclJ and toJlus tetraborate Sola. BoyJroalde sein.

SER ltem QT,H: Ope rabi l ! ty requ'i red i s 120 days. Actual test time is 130 days. Margin is 10 days.

A - This cable has been qualified for the 40 year normal life plus the accident environment. Additionally, refer to the generic discussion of SER Text caragraph 3.7, Aging.

CS : Initial Spray: 2000-2100 ppm Boron 4e:Irculated Spray: 1806-2200 ppm Boron 4.0 - 4. 7 pil 6.0 - 10.0 pit Test Spray: 3,000 ppm Boro.., 10.5 pil

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loccus ht leuCLEAR STATION - tali I Pa ,e 20 SnstetAAf GF ENvlNesedNTAL QuAllflCAltoes Et CLASS IE EQWlptetNT poolslo. O LOCAT(8 INSIDE CONTAlsedNT f* H fedNT storEL OA ACCIDINT (NvinosedNT OPE RAS 4 LliV UPERAtilliY ACCUAACV ACCURACT QuAtlFICAll0N fqmMufACTURER SHuliflCAilell Etevikoest[NT 10 nelltse ugugAgg IN pueosegiaAige MQuints puesNSIRAIED M Poti ANS 19ENa af 4CAllGII IsaettR (2) QuALIFlis ACCIN NT settacos (8) (% of Spen) (% of spen) (4)

ElevthotsetNT (3)

Cab le - StanJ kom * ?E lasulation

. Ie. ,: )?J F Temp: 346 *f 30 days 1J days ss/A N/A less see.u s F-(4a ll Centrol Press: 14.8 psig Press: II) palg post Dee post Dat '

f tes, 1001 Ase: luGI netimJ; lest (Lo = r contalament)

AaJ: 1.$n107a maJ 2 60 %

Chen Spar,: 9 wic Clem Spray; Boric ac i d and * >J f un acid and sodium tetrat, orate sein. hydromId, sein.

SER ltem _

QT,H: The actual qualification test duration of 30 days post-D8E was perfornwo at a higher steady state temperature than expec te d.'

inside containment. Tl.e operability time demonstrated, therefore, did not take credit for the additional qualificat,lon time which could be derived from proper Arrhenius Techniques. l CS - Initial Spray: 2000-2100 ppm Boron Recirculated Spray: 1800-2200 ppm Boron 4.0 - 4.7 pH 6.0 - 10.0 pH A  : This cable has been qualified for the 40 year normal life plus the accident environment. Additionally, refer to the gener'c discussion of SER Text Paragraph 3.7, Aging.

9

McCulRE esuttEAR 51Allma - tuli i Pa.p 2I SteiMARY OF ENVIROftM(NIAL Qt'ALiflCAI tml W CLAS5 tl (Ql.'8%Fl;T Aevislom 0 t0CAIED IN5IDE CostIAllet1NT MODEL OR ACCIDENT ENVeRONMENT OPE RA41tlTY OPE RAtlL11Y ACCURACY ACCUAACY QUAtlFICAll0N 1 (QulPt1NT stPoni ANS I"Nilf Plost MAleWFAC1 DEER ID4NilFICAileet LNVIRONM&Mi 10 latlCH s quinta IN etMON5taA110 miQuinto MMose51mATEo laatNR QuALIFife ACCIDENT M(IN00 (ly (2)

ENvlR0let(NT (3) (1 of Span) (1 of Span) (4) l Samuel Moore iP/Hypelon iemp: 32 f Temp. 340 I 30 days 30 days N/A N/A inst Re eve t f-C)t,9)

Cabla

• ins t rew et a t ion insulation Press: 44.8 psig Prats: 10$ psig post Ott post JBE RH: 1041 EM: 1001 es t bJ: Test (tower containment) 0 R.J: 7. Sal 0I n RaJ: 2x10 R Clam Spray: Boric Clwm Spray: boric aclJ and soJlus aclJ and sodlue tetraborate so6a. hydroalde soln.

SER ltem _

QT,H: The actua' qualification test iaration of 30 days post-DBE was pert'ormed at a higher steady state temperature tNn expected.

The operability time demonstrated, t he re fo re, did r.ot Uke credit for the additional qualification tinee which could be derived f rom proper Arrhenius Techniques.

CS : initial Spray- 2000-2100 ppm Boron ?ecirculated Spray: 1800-2200 ppm Boron 4.0 - 4.7 pli 6.0 - 10.0 pil Test Spray: 2,000 ppm Boron, pil 9-11 A -

This cabic has been qualified for the 40 year normal life plus the accident environment. Additionally, refer to the generic discussion of SER Text Paragraph 3.7, Aging.

4 4

m

plcGul AE NUCLEAR STATION = UNIT l rep 2 *"

• • vision 0 5LMMARY SF INVI ACNMINIAL QuALIFICAll(As GF CLASS IE (QUIPY. INT .

LOCATED IN5I M CONIAllAdNT P40NL on ACClotNT INVI A000tlNT OPERAtiLITY #N AA41LITY ACCUAAto ACCUR4CY QuALIFlCAliggi EqulPMLNT INN TI FICAfifti SEQUtMS IN DutosillAAffe MQulMD D(#1018518A118 '

StrDiti ANS INullFli+180il MilufACTI'Aia LatWIRONMENT 10 WHICM seinot ACCIMNT (l) IILegeER (2) QUAT lFIED ENWI A0ledNT (3) (1 of Spea) (% of Spea) (4)

(4b ts f ereleesloa/ Raychee WCSF-N Tesqs: 327 F Temp: 311 F 4 es>nths 4 awanths N/A N/A lest A posts I-C403)-)

Splice Material Sleeve s Press: 54.8 psig Press: 70 psig post 081 post Det anJ 78100 (Lower i ,atalsment) and AH: 100% AN:

100%.0 Breakouts mad: 0.$180 7A paJ: 2a10 R MethoJ: le s s / As.ely s i s Cheia 5praya Puric Chee Spray; serIc aclJ and svJlum acid on.1 sodium f

tetteborate sola. hydsonide soln.

2ER Item .

QT,M: The actual qualification test duration of 113 days post-DBE was performed at a higher steady state temperature than expected inside containment. The operability time demonstrated, the re fo re, did not take credit for all the additional qualitication time which could be derived from proper Arrhenius Techniques. Only 7 days were taken credit and mt the full Arrhenius time potential.

CS : Initial Spray: 2000-2100 ppm Soron Recirculated Spray: 1800-2200 ppm Boron 4 . 0 - 4 . 7 pil 6.0 - 10.0 pil Test Spray: 3,000 ppm Boron, 10.5 pil A -

This material has been qtialified for the 40 year normal life plus the accident environment. Additionally, refer to the generic discussion of SEh Text Dragraph 3.7, Aging.

• e

b rey, 23 McCutRE leuCLEAR 51 Ail 006 - UNii l Revisto. O StatMARY OF ENVihosedMTAL QUAlif 4AT10el of (LASS If EQuiredNT LOCAIED IN5LSE CosetAlsedNT ACCURACV Qr\LIFl( Ail 0N ENVIRONMENT OPERASILilV OPE RAttllif ACCURACY Xstote$ipATED hEr0AT Art stopfL OA ACCIDENT M QUINS M QUIDED IN 90400651 RATES patieept EQUltedui TO WHICH IDEZilf8 CATION W ACTURER $9ENil' *iiil0N ENVISDNNENT ACCINNT (1 of Span) (4) im4 Q A (2) QUAliflES (1 of Span)

(1) ENVihosenENT ())

,l N m o l u i

• sports 30 days N/A le/A isap: 340 f 5 min dated Mar ci. 3. l938 EA 180 Temp: 321 F post DBE 5t m-rsauntel Limit Menco Psess: 18e.8 psig Press: 63 psig (r te 9) mad f etawar y 20, 19 Jel EA 740 kN: 8001 5=l a c he s Rat: 800%

Rad: 2ntu8g nes%d . Test (Lower Conselnment) Red: 6.?n10 7R Ci** Sp*ey: suric them 5 prey: Soric .d sodlies

• cid scid and sodium hydronide soln.

tetreborate soln.

SER ltem QT,le: The actual qualification test duration is 30 days post-DBE which adequately exceeds the required operating tir.~.

Initial Spray: 2000-2100 ppm Boron Reci rculated Spray: 1o00-2200 ppin Boron CS 4 .0 - 4.7 pil 6.0 - 10.0 pli Test Spray- 3,000 ppm Boron, 10.5 pH A - The aging qitalification for this limit swi tch is under review. Additionally, refer to the generic discussion of the SER Text Paragraph 3.7, Aging.

L

IwSPM WCLEAR STATION - tmei 1 rege 2i StatMAAf 0F ENVI A06ecMIAL QUAllflCATION OF CLASS BE EQulPle(NT Aevisloa 0 toCATFD IN51 M CONTAlfeMENT EqulPnueT MONL CA ACCIDINT ENvlRONMENT OPf 6 1LITY OPEAASILITY ACCumACV ACCUAACY QUAL IFICAiless Itt ilFICAll0al MAfstACTuala I N NilflCAfl0m LNvlRONMENT 10 bellCM MQusMD IN Mn0N5f AAile MQutate Maces 5taAtte M ecai ANs (1) InseMA (2) Quallfl(D ACCIM NT N(tesoe

,, shvin0settNT (3) is or 5, ) (s .F 5,s.) el 5sep niteslet for 3M Scotch Cast 9 Temp: 327 F Temp: 340 F ai eturS sa d. ps t/s is/A test $a ger t 44)W-4 g

Camla intrance (XA-5240) Press: 14.8 pilg Press: 15 psig post 6st hv. 4 Fit:Ings (Lower fut: 800% RH:

SaJ: 6.7ml0 A peJ: 800 4A 2ml0 I Cuntelnswnt J Cheme 5 prey: Boric Dem Sprey: t%fic acle +=d sodlum acid i.+d sodl e tetreborate soln. hydromide mula.

SER lteir.

~

QT,H: Operability required is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ' Actual test time is 12 days. Margin is 11 days. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> operabilit < time is adequate time fo. mitigation of the containment pressure transient and termination of containment spray.

CS Initial Spray: 2000-2100 ppm Baron Reci rculated Spray: 1803 2200 ppm Boron 4.0 - 4.7 ph 6.0 - 10.0 pli Test Spray: 4,000 ppm Boron, pit is not available ,

A This mat 'rjal has been qualified for the 40 year normal life plus the. accident environment. Additionally, refer to the generic discussion of SER Text Paragr,ph 3.7, Aging.

DecGulRC NWL U A STA'iloes - tm61T I re ,e 25 5 tar' AY OF ENWIROset1NIAL QUAtlF8&Al?ON OF CLA55 11 EQulPMCNT movision 0 LOCAlf 9 IN$tDC CONIAlIINENT EQUIPe* TNT MODEL OF ACL*0(NT ENVImotmENT OP(AAsitlTV urtaAtlLITY ACCuaACY ACCURACY QUAtiflCAlless sN;ilFICAitost ItamufACiumia IPtNilFICAT1001 Elevl A010tCNT TO WHICH REQulM D IN Mit00e51841ED A&QJIMD NMOss5 MATED M POAi ANS (I) insettR (2) QuAtlFift ACCIDENT 4 ft(Th00

'NvlA00MLNT ()) (1 of Spen) (1 of 5 pen) (4) t wtainment n4JI alon General Atualc RD-2) Temp: 240 F temp: 315 t 2 n.eeks 48 J.y* tioin 20 trofe 2.0 lest a.pc,r t - -234-9eb Monitors-HI A Sange tuni s et ter. Press: 14.8 Os;g Press: 70 psig p .t 10CA post LOCA deteJ eidy 1, lydl (Lwr Containearna) Chan.ber RH: 1001 AH: 100%

sad: 8ml07A 'R.J; Note 17 MethoJ: Test /As airsl6 Chem Sprey: tur k them Sprey: Doric aclJ and sodlum aclJ, swJtia.e thlo-tefreborate soln. sulfete end sodlum hydromide i

Ctbls for Containetat Rockbestos R55-6-104 Temp: 240 f Temp: 315 F 2 m.acks 395 Jays N/A h/A last Poport: 1-2 %-%0 AsJlction Monitors. Press: 14.8 psig Press: 10 pig post LOCA post 10CA deteJ May 1, 1543 High Ran y RN: 10 kH- 100g (%t e 18)

(L w r Containment) RaJ: 84td A ReJ- 2410 A NethuJ: lesi Chen Spray: Note it them 5 prey: aoric acid, sodlies 84.1o-sulfate and sodium f.ydronide SER ltem NOTE: This equi,. ment is being installed per flRC requirements stated in feudE', 0737.

Q1 The test data for this equipment as noted a')om was recel /ed af ter the submittal of Ouke's flVREG 0588 data.

CS -

Initial Spray: 2000-2100 ppm Earon P,ar:i rculated Sp. ay: 1800-2200 ppm Boron 4.0 - 4.7 pli 6.0 - 10.0 pil Test Spray; 3,000 ppm Boron, 10.5 pil (Radiation Monitor)

The Rockbestos cable is installed in conduit and is therefore not exposed to a chemical spray environment.

A This equipment has been <(uallfled for 40 years normal life plus the accident environment. Additionally, refer to the generic discussion of the SER Text Paragraph 3.7, M ins.

e incCusM NUCLEAR STAil(W - UNii l Page StetMAAf 0F ENWlR0pettNIAL QUAllFlCAllON OF CLA55 IE EQUlPMEMT nevision 0 LOCAT10 $NilDE CONIAsletfMI EQulPMENT M0tef L A ACCIO!NT ENVIRON #41NT ortAAtitlTY OPERAtiL3TY ACCunACT ACCuaACf QuAliflCAllose 10 idNICH REQUthtD IN MMONSTRATES MQulHD MMose11 MATED MPOAi Amt IMhilflCAllGIl PWdWFACiunfA l lMNTIFICATIcss ENvlRONNENT Me Noe (1) muNeta (a) quAurite ACCluNr INWincesttNT (3) (1 of Span) (1 ef Span) (4) m Safety valve Position TEC *l4 Temp: 327 F Note 19 2 webs Note 49 N/A N/A Nose 19 ladication-Acoustic Press: 14.6 pilg post DeE Nmiters AH: 1007 ..

(Lowr Contalement) Red: 8 m lotA . ,

Chae $ prey: duric W eclJ and soJltan tetroburate soln.

SER lt23 -

QT- This equipment is beinj installed per NRC require;rnts stated in NUREG 0737 Test results are expected by August, 1981.

Page 27 Revision 0 MCGUIRE NUCLEAR STATION - UNIT 1 ENVIF,0NMENTAL QUAltriCATICH OF CLASS lE Eq'J FMENT LOCATED INSI DE CONTAINMENT Note 1 All equipment ident!' led in this table is located .ns?ie the centeinment, specifically in the lower ccmpartment except tcr the electric hyorogen recombiner, cc. tainment air return f an motors; hydrogen skimmer f an motors, containment air return isolation damper motors, differential pressure switches for damper control and cables associated with these devices which are located in tna upper compartment.

Note 2 The carameters that compose the overall worst-case containment accident environment ace as follows:

Temperature (Upper Comoartment): 180F peak; time history as shown in FSAR Figure 6.2. I'-24 (Rev 36) .

Temperature (Lower Compartment): 327F peak; time history as shown in FSAR Supplement 1, 4042.73, Figure 7 Revision 39 l

Pressure (Upper and Lower Comoartment): 14.8 psig peak; time history l

as shcwn in FSAR Figure 6.2.1-23 (Rev. 36).

Relative Humidity: 100%

Radiatfore Total i;,tegrated radiation dose #or the equipment location includes 40 year normal operating dose plus the appropriate accident dose (except for the narrow-range and wide-ran'ge RTD's). ,

Chemical Spray: Boric acid and sodium tetraborate spray resulting f rom mixing in the containment sump of borated water from the RWST and sodium tetraborate solution from Ice bed melt.

Note 3 Equipment operability requirements in the containment accident environment are as identified in FSAR Table 3.11.1-1 (Rev. 25).

. . . . - - , - ---- ._, - + - , - --

Page 28 Revision 0 i

i Note 4 Environmental qualification test reports for the following equipment have previously been submitted to the NRC Staff:

Transmitters-Barton (by Westinghouse)

• RTD's-Rosemount (by Westinghouse)

Electric Hydrogen Recombiner (by Westinghouse)

Containment Ir Return Fan Motors (by Duke) -

Hydrogen Skimmer Fan Motors (by Duke)

- Solenoid Operators-Valcor (by Duke)

- Electric Penetrations (by Duke)

- Cable Termination / Splice Mater'.al (by Duke)

- Stem-Mounted Limit Switches (by Duke)

- Ceble Entrance Seal Material (by Duke) llote 5 A requirement for McGuire Unit 1 is to limit the positive errer fue the 1

trip function of narrow-range steam generator level transmitters to +5%.

The o'r ,inal Lot 2 report noted an error of +7.3 %b ,c,e early in the steam test transient. Additicral tests were performed on the same unit using water as the process medium instead of nitrogen b,c,e: This caused thetegperatureofthe strain gage to track the temperature of the circuit borJd 'C'- more closely during the first minute and limited the positive error to less than 4 % b,c,e. the temper 2ture dif ference between the strain gage and the In other words, circuit board b,c,e has ueen reduced to a i

level compatible to McGuire Unit I functional requirements.

Note 3 Deleted ,

I Note 7 1

4 Deleted j

l Note 8 3

i Fisc minutes is adequete time to assure containment isolation and the required rep.sitioning of other safety-related valves.

Note 9 During the 30 days following a postulated accident, the containment temperature and pressure will approach normal; therefore, additional j

tervice ;an reasonably be 2xpected frem this equipment.

4 w

Page 29 Revistor. O Note 10 The Target Rock solenoid valves are used in the reactor head vent system to provide a path for removal of non-condensable gases. Core events leading to the generation of significant amounts of non-condensable gases occur early in the postulated accident secuences and are of short duration; the refo re, these valves are only recuired to operate within the first few days of the accident. The need for venting non-condensable gases is not enticipated beyond the 14 day qualification of the valves.

Note 11 Electric penetration types B,C,F,G and K are the only penetrations required to function electrically in the containment accident environmert. All electric penetrations, however, are designed ard qualified to maintain their mechanical Integrity under normal and postulated accident environmental conditions.

Note 12 The McGuire electric penetrations are protected from direct spray inpingement by galvanfred steel boxes.

Note 13 Deleted Note 14

Deleted ,

Note 13 The radiation environment for this equipment i s dependent en operating time in the accident environment. This information will be provided upon receipt and review of formal test reports by Duke Pcwer Company.

t Note 16 The cables for the containment radiation monitors (high range) which are located inside the containment are routed in conduit, and, therefore not exposed to chemical spray.

Note 17 -

The manufacturer's test report states that the detector assembly is constructed of metal and ceramic and is not affected by radiation.

i

.. .+- ==-e.,-

- _,m- e--e - - - - - '

• 'm --

P-P u-

• Page 30 Revisicn 0 Note 18 Subsequent testing by the manufacturer showed a failure of a sample of  ;

I cable at a hif er :emperature. i Note 19 This equipment is being installed per NRC requirements stated in NUREG i 0737. Qualification testing for this equipment is scheduled for completion .

In August, 1981. The results of this testing will be provided upon receipt and review of the formal report by Duke Power Company.

Wote 20 This equipment _ is being installed per NoC require.ments stated in NUREG 0737.

Overal' system accuracy should be within a factor of 2 over the entire range.

as stated in Regulatory Guide 1.97, rev. 2*. The demonstrated accuracy is under review.

4.

t 1

I a

h I

MCGUIRE NUCLEAR STATION - UNIT 1

SUMMARY

OF ENVIRONMENTAL QUAliFICATI ON OF CLASS lE EQUIPMENT LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST LOCA RECl RCULATI ON RADI ATI ON ENVIRONMENT

I 14CUIRE NUtttAA STAlless - t#ftf I F*F !

sisevuir Or ENvlAoNntNIAt euntificat:0se or st Ass et toulentN 8"8 8 8aa O LOCAIED OlllllDE (ONTAIIstENT Ah8 EXPOSED 10 Tiet P011-10CA St(ISCULAll0Il BASI Alloff ENVIR00ettNT EquiritENT ltAtlurACTwin le00ft GA Bit Att'tAllch RA0l Allose quat trl( Allose IDENilflCAll0Il SDENilrlCAllDII liADI AT10el LEWit 1014tital giront Asse pitIHOD (I) luotet a INvinoseMENT tluAttrits (110) (a) (tie) careent/ volt.g. Al ns noct ster lastr=.=ats <T:215 < i n t oin ote i Not. I (wo,s us.)

The couponent listed above ic = general application device. This component is installed in NEMA type enclosures and depending on i ts speci fic design application, may be located in various areas of the Auxi liary Building. This table addresses the qualification of this component with respect to the worst-case radiation environment (40 year normal dose plus I year post LOCA) applicable to the compo. :it's locations.

SER ITEM NOTE: This component is not exposed to a harsh post-LOCA reci rcul- tion radiation envirorvnent (Refer to Note 1).

6 s

f McCulpt leUCLEAR SIAlleel - taeli I F*** 2 SLMMARY OF ENVIRONMENIAL QUAT lFICAI1000 0F (LAS$ If EQUIPMENT Sergelen d 10 Calf; MSIDE Leef1AlteWNI Amt EEP05tB 1011e( POSI-t0CA pitlpCULAI10N RAtlAll0ld (NylRoseWNI IQUlt9ttsfi MAleUFAClumER MODEL 04 SECIDCULAI1011 SA004Ilcel quAtlFICAllois IDENilf lCAll0II O DEhilflCAil0El RADI All081 i LEvit 10 telltM REP 0ml Asse Miliw%

p) nimeta savin 0Nnams QuAtlFire l

(tie) p) (fle)

F. . euss n. enA l.6 io6 a (s.os st case) $ note 6 liose 6 e

The conponent listed above is a general application device. Thi s conponent is installed in NEMA type enclosures and depending on i ts speci fic desig~n application, may be located in various areas of the Auxiliary Building. This table

-.ddresses the quali fication of this component wi th respect to the worst-case radiation anvironment (40 year normal uo.c plus I year post LOCA dose) applicable to the' a eonent's locations.

SER 1 TEM R, QM, A quali fication test .c. 39 ram to document the radiation wi thstand capabili ty of this conponent is in progress.

M , QT, A preliminary review of conponent's materi sls li. 'icates that there are no materials susceptible to signi ficant Ql: radiation degradation, llowever, as noted above, a qualification test program is underway with cunpbtion scheduled for December, 1981. The results of this test will be documented in a revision to the NUREG 0588 submittal.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

e e 9

i McGulRE IsuttEAR 51411000 - INIIT I Page3 SteetAAY OF ENVIR0f9WNIAL QUAtlFICA110810F CtA55 IE EQUlFMNT b888.= 0 LOCAitt SU150M CONIAltpWNI AIIS EXPOStB 10 lese P05T-80CA MCORCulAlleet AADIAlloil (NVIRoemtNT (QUlFMNT MAfsuf ACTURER NOWL on AE C O RLt.tAl 12 RACI AH 0s1 OsaAt t ric Allost INNilFICATicel IMWi1FICATION RADI Al!0sl Livf L % esta(II RI v1 Asse Mlle09 (1) NwMR IIIVIRGesME NT QUAL 1F1ie (110) (2) (fle)

Fuse Bussmans kin <la10 In

(.orst c.se) Note i Note i The conponent listed above is a general application device. Thi s colt.p.snent is installed in NEMA type enclosures and depending on i ts speci fic design app?ication, may be located in various areas of the Auxiliary Building. This table addresses the quali fication of this conponent wi ti' respect to the worst-case radiation environment (40 year normal dose plus 1 year post LOCA) applicable to the component's locations.

SER ITEM NOTE: This component is not exposed to a harsh post-LOCA recirculaticn radiation environment (Refer to Note 1) .

6 I

i i

l i

l

I f

McCUlB( 99UCtf AR $1All0N = ISIII I I*98

$498tAAT OF ENVlt0B09tNIAL QUAttflCAlltel 0F (LAS$ 18 EQUIPM(Ng $8vlelo. O LOCAltB GlH$1H CONTAllMENI ANS ENPO$se 101ME P0$l-80CA DECl#CUUni10el AAtlAll001 INVIR00etENI EQUIPME NT MA88UFACTUntR M00ft 04 AECBRCU' All006 AASIAllNI QUALIFICAIIDII INNilflCAlliNe INNilflCAlleel RAtl At tesi ttVfL 10 hellCN Af rUni Asse foiIMus (l) st. met A EIfVI DOMME NI tyntiFIEe (Ilt) (2) Jilt)

Tuse lilock Sussmann )192 1.6ml06R la1010n n,,,g,pgle; P(-1367.0)

(essi case) d.ted July 9, 1981 Method: Analysis 1

The couponent listed above !:; a general application device. This canponent is installed in NEMA type enclosures and depending on its speci fic desHr epplication, may be located in various areas of the Auxi!Iary Building. This table addresses tir' quali fication of this conpont ut wi th respect to the worst-case radiation environment (40 year normal dose plus 1 year post LOCA) applicable to the canponent's locations.

SER 1 TEM R: The radiation quali fication of this canporient is as shown i n the table above.

A: Refer to the generic discussion ci SER Text Paragraph 3.7, Aging.

QM:This canponent has been qualified by analysis of previous material tests.

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McGUIRE puCJ AR STAllest - Smelt 0 '89* 5 SteetAAf 0F ENvinole(NIAL QUAtlFICA110sl 0F CLASS lE EQUIPMui as.lelon 0 LOCATES OWillH COIIIAlfedell Alte ERPOSED TO Tief Poli-LOCA p(CipCWlAlleN RA01AT10Il INVlD0084NI i

Equipmesi MAssurattuata scopf t on atCletutAll04 aAelA110N qunllfacAllrus IDtMilf tfA18006 IDiMilflC A11006 RAtl Ail 001 LEVEL TO Wl(N tirosi Asse Missos (1) lueista llevlRostWNi quAttfits (slet (a) (lle)

Fuse telock Bussmann }839 < lal0 I R No o l Note l (verst cese)

The component listed above is a general application device. This component is installed in NEMA type enclosures and depending on its specific design appilcation, may be l oca tet. f r. various areas of the Auxiliary Buliding. This table addresses the q'iali fication of this component wi th respect to the worst-case radiation environment (40 year normal dose plus I year post LOCA) applicable to the compcoent's locations.

SER 1 TEM NOTE: This c.omponent is not exposed to a harsh post-LOCA recirculation radiation envirorsnent (Refer to Note 1),

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McCulet NutttAR STAllose - Willi I P'9' b SUMMAav 0F ENWinoseWNIAL QUAllFl(All0tt OF (LASS lt (QUlfM(Ni Devlelen 0 LOCAllt OUl5lDE (00llAIIDWNi Aho EROSED 10 THE POSI-LDCA DECI ACULAII0el RADIAfleel ENVIR06 STENT (QUlrME NT ftAIIUfACTUhfR N00(L OR Af/ RCULAll0Il RAtl AIICII Quat t rittilope IDENilflCAllGII 19tNTIF IC AT1001 RAtl All0ft LEVEL is IdNICH f*P0pi Afee MElHOS (1) NtetetR ENVinoseWNi quAlif tts t

(slo)(2) tils)

Fuse blmk Oossnann 8.439 3.lal0 3 A tal010A He.e t o f i le : pc.1162.0$

(worst case) d.ted .luly 9, 1991 NethoJ- Analygig The component listed above is a genera" application device. TM s component is installed in NEMA type enclosures and depending on i ts specific design application, may be located in various areas of the Auxiliary Building. This table addresues the quali fication of this conponent wi th respect to the worst-case radi tion envi ronment (40 year normal dose plus 1 year post LOCA) applicable to the component's locations.

SER ITEM R: The radiation qualification of this conponent is as shown in the table above. ,

A: Refer to the generic discussion of SER Text raragraph 3.7, Aging.

QM:This component has been quellfir- by analysis of previous material tests.

serCUlM NUCtf AA SIATION = lasti l I'9' 7 54mMAnf 0F ENvikf4Mitel At QUAtlFl(AT1088 SF CLA5$ lE EQUIPMENT Sewleton Q

, LOCATED WlH51DE (Ost1AltmtNI AND EXPOSES ',8 THE resi 10CA MCIRCULAllost AADIAllen ENylmoseWNI EQUlthfMT MAasufACIUnta pourft OR MCimCULAllost SA06 A10010 QuALIFl( Ailogi IDENilfl(All0N lMllil* lt All088 RADI Alleel LtVfL 10 neeltl. Mront Asse hfIHop (l) h m4ER lifVIRuleWNI QUAllFitD e (Ile)(1) --

(tie)

Fuse lilock Bust,menn 4575 Inl06 , 4,lo ton stema to File: W -l%2.03 (worst case) Jeted July 9, 1981 Method; A,i,l y s i s The component listed above is a general application device. This component is installed in NEMA type enclosures and depending on its specific design application, may be located in various areas of the Auxiliary Building. This table addresses the quali fication of this component wi th respect to the worst-case radiation environment (40 year normal dose plus I year post LOCA) applicable to the component s locations. 8 SER lTEM R: The radiation quali fication of this component is as sliown in the table above.

A: Refer to the generic discussion of SER Text Paragraph 3.7. Aging.

QM:This compvient has been qualified by analysis of previous material tests.

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hcCUlRE IIUCLEAR SIAlless - Willi I f*T* b

$1PeInaf 0F ENVIRUI9dWIAL QUAT lFICAll0010F CLA15 BE EQUltedur **vis ta O E0 CATES SUI 58DE EDIITAllDIElll AND ERFOSEP 10 THE P011-LOCA BEClpCULAll0N RADIAll0Il ENW140IIMENT EQJ1FIqENT IIAmufACTURER IIODEL OR RECORCULAllelt SA9f AlloII qualitigAtleII InNilFICAll006 IDENilFICAllell RAtlAllell LEVEL TO WHICII aircal ANO ptElH00 (t) , meina E=vinowdur auntirlEs (tiel(a) (tiel Indicating Light Cut lee -H.ansmer (29 al Me6 Ale 6 The canponent listed above is a general application device. Thi s component i s ir. stalled in NEMA type enclosures and depending on i ts speci fic design applicat'on, may be located in vz.rious areas of the Auxiliary Building. This table addresses the 9t .i fication of this canponent wi th respect to the worst-case radiation environment (40 year normal dose plus 1 year post LOCA dose) applicable to the component's locations.

SER 1 TEM R, QH, A quall rication test program to document the radiation wi thstand capabili ty of this component is in progress.

M QT, A preliminary review of canponent's materials indicates that there are no materials susceptible to significant Ql: rr,di a ti on degradati on. However, as noted above, a qualification test program is underway with canpletion scheduled for December, 1981. The results of th;s test will be documented in a revision to the NtlREG 0588 submittal.

A: Ref er to tne generic discusslor, of SER Text Paragrapli 3.7, Aging.

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lec eul8f IHKLIAR 51AT1000 = UNIT l P.g. 9 St#9tAAf 0F ENVIRONMENTAL QuAllfl(All0st OF (LAS$ lf EQUIPn(NT a. lil- 0 LOCATES OUISIM COIIIAIP99 TNT Ane EXPOSED 10 INE POSI-LOCA MCipCULAllost RAtlAll0le ENViposetEMI

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iQuienswr nAnufActonen n00tt ca attistutailow mAe: Anon QuatiricAnon INullFICATI0ll IMN11Fl(AllG88 RAtl All0PI LIVEL 18 l400CN REPOSI A810 titlHDD (1) misista swVla w ar QuAttries tile) td titel weie. a i.ior t-r.. ir50 n

< i.i0sa swi. i .i

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The comporient listed above is a guaeral application Jevice. This component is installed in NEMA type enclosures and depending on i ts specific design application, may be located in various areas of the / axiliary Building. This table addresses the quali fication of this ccnponent with respect to tt'e worst-case radiation environment (40 year normal dose plus I year post LOCA) applicable to the col.nonent's locations.

SER ITEM NOTE: This component is not eg, sed to a harsh post-LOCA reci rcuiation radiation envi ronment (Refer to Note 1 ).

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i McCult! 80UCPIAA STATION = laell } P'98

! St99W1V 0F INVin0NMENIAt %MIFICATIO80 0F CLAS$ If IqulPMENT Deviel.a 0 teCAfts OUISIM COIIIAllmENT ANS REF05f n 10 THE Posi-toCA Rt.lACULAll0st RADIAlleff ENVinosettNI EqulPMitti MAllurACTUAEA McDit 04 AICintutAll0st SA90Al40N QtAAtillC A11088 INNilFICATICII INNilFICAlaedi RAtl AI1000 itVit IS inli' ) Strosti ANO f(IMOS (l) IltmetR ElfVIRGIMENT GUAt t filb

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P W Supply tambda tCS .<1n1034 Note i Nate l (wrst case)

The component listed above is a general application device. This component is installed in NEMA type enclosures and depending on its specific design application, may be located ir, ea r l ou's areas of the Auxiliary Building. This table addresses the qualification of this component with respect to t..e worst-case radiation envicanment (40 year normal dose plus I year pm, L OCA) applicable to the component's locations.

I S_ER ITEM NOTE: This component is not exposed to a harsh post-LOCA recirculation radiation environment (Refer to Note i1 4

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St99tAAf 0F INVIR0e99tlelAL QMLiflCA11000 0F (tA$$ l( IQUlMNI LOCATED OUIS10( (cetTAlletipi ANs Enro!ED 10 lief P951*LOCA RECIRCULAllose RAtlAf*0N ENvip00sttNT Bulsl*" O IquirstENT ftANUFACTUmfA lee i t OL . RECIRCULAIIcel RAtl Allose quag g rIC Allose IDENilf1 Call'W IDENin ^1Cf J1000 RADIAll0P LEVEL 10 lastCN ptreat ANs lityNoe (1) letetstm EnviposoitNT quat lFitt (tiel(a) (fle) 6 pelaY Cutler-Ilammer p23 lal0 6R Note 6 fenee 6 (wurst case)

The conponent listed above is a general application device. Thi s component is installed in NEMA type enclosures and

'epending on i ts speci fic design application, may be located in various areas of the Auxiliary Building. This table addresses the quali fication of this canponent with respect to the worst-case radiation environment (40 year normal dose plus 1 year post LOCA dose) applicable to the conponent's locutions.

SER 1 TEM R . Qt . A quali fication tCt . program to document the radiot;on withstand capability of this crasanent is in ,,rogress.

M , QT , A preliminary review of couponent's materials indicates that there are no matc lais susceptible to sign ( ricant Ql: radiation degradation, llowever, as noted above, a quali fication test progrm is underway wi th conpletion scheduled for Dewnber, 1981. The results of this test will be documented is a revision to the NUREG 0588 subtri t t a l .

A: Refer to tM generic discussion of SER Text Paragraph 3.7, Aging.

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t McCulat IsuttfAR STAllDel - UNIT F F89* 3 StmHART OF ENvlagtMENIAL QUAtlFICAll0sl OF (LAi-l If SQUl*MENI 8*'I8I**

LOCAftp CU151DE Col 3TAlletfMI AND tRr0$th 10 TNE POSI-10CA p(CletutAll011 kASIAllell INVIR00e1EPT IQUl W NMTURI% HODEL oft DECISCULAll001 AADe.ll0N a

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, } (slo)(it (Ile)

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(_ ,.. ....,

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The conponent listed above is a general application oevice. This coleponent is I istalled in NEMA type enclosures and depending on its specific design application, may be located in various areas of the Auxiliary Building. This table l

addresses the quali fication of this componer.t wi th respect to the worst-case radiation environment (40 year normal l dose plus 1 year post LOCA) applicable to the ccynponent's locations.

l SER ITEM N01L: This component is not exposed to a harsie post-LOCA reci rculation radiation environment (Refer to Note 1 ),

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PicCultf NUCLFAA $1Allons - Salli 8 E*18 !b SteetAAY OF INvlROF*NIAL QUAltflCAllest OF (1A15 lI Equif9ttily D.v1 8 O LOCATED OUISIM C080iAlletENI AND E.P05f p 10 ilet Post-tKA DECIRCULA11011 RAtl All018 Elev1poletENI (QUIPpttNT ltAIIUF ACTUR1R 3400EL Oft MC1LFtraAIl010 SAB1 Ail 018 quatiFi(AIIone INNilflCAll001 9 MNilF l( Ail 001 RADI All0st LEVf L 10 4406(N MPoni Ases paginne (1) let#tet h (Nvi p088et tei quAttflED (Ile)(I) (tie) ,

..i., A G..i. 7000 s.ri.. <.I ioin we, : e

( o, . i .... ) , ,

The conponent listed above is a general application device, i'~s component is installed in NEMA type enclosures ano depending on its speci fic design applica' f on, may be located in .arious areas of the Auxiliary Building. This table aJdrusses tl.e quali fication of this conponient wi th respect to the worst-case radiation envi ronment (40 year normal dcce plus I year post LOCA) applicable to the conponent's locations.

SER lTEM NOTE: This conponent is not exposed to a harsh posc-LOCA recirculation radiation environment (Refer to Note 1 )',

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i pes Ctr:sf NUCLEAR STA110se - UNii l P*,e 15 SIMtART Of ENWlRdMENIAL QUAtlFICAll0N OF EEA55 If EQUIMwi Dowlsle. O LOLATES Oultl0E CONTA110 TENT Allt EEF05ES TO itet POSI-EOCA DECIRCULAlleel RAtlAlleft ENVIRONMENT EQUI M wi MAleuFPC TUAER NDEL OR RECORCULAllull U + 1 All018 QUAT le 1( A fl0st IM NilflCAileN I MilipilCAT1001 RAtlA11000 eel-L TO WHICN piroat Aset let tes00 p) Nimes n ENvinomiENT e w faite tile) (a)  ;.lo)

Resistor Walte Or m i Devil <lal0 lR Note l Noec l (west case)

The conpc;nent listed above is a general application device. This component is installed in NEMA type enclosures and depending on its specific design application, may be located in various areas of the Auxiliary But Iding. 114 table addresses the qualification of this component with respect to tlie worst-case radiation environment (40 year r.ormal Jose plus I year post LOCA) applicable to the compen. nt's locations.

SER ITEM NOTE: This component is not exposed to a harsh porl. LOCA recirculation radiation environment (Refer to Note 1 ).

r i

t McCulkt NUCitAR 51All0ll

• Bauli i IT i SLMMAAV 0F ENVIA0099tNIAL QumtlFICAll0N Of CLA55 It EqulFMEN, s.' 'ision 0 10CAIES CJ151DE CONIAlletENT AND ERPOSED 10 THE P0%T-10CA DECORCULAll0II RA49All006 ENWlSOMMENI EqulFMilli MA81UFACTUREA MODEL 04 REC O R(UtAll001 RA00 All0BI QUALIFl(All01s IstNilFICATICII 4 DtNIIFit All001 RADIAI10sl livit 10 WH4CN DEPOSI AfBC MilHot (1) IILMSE R ENyl RONME NT QUALIFIES (fle)(r) (fle) surge Suppressor General 5einiconductor Transnorb l.6 10 6R 2=101A Manuf ac t urer 's Spec t f Ic at 104

( w at case) date 5td. Stk. XIII-t-l Method: Analysis The conponent listed above is a general application device. This conponent is installed in NEMA type enclosures and depending on its speci fic design application, may be located in various areas of the Auxiliary Building. This table addresses the quali fication of this conponent wi th respect to the worst-case radiation environment (40 yeai normal dose plus I year post LOCA) applicable to the conponent's locations.

SER ITEM R: The radiation qualification of this conponent is as shown in the table above.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

QM:This component has :2een qualified by analysis of previous material tests.

l

t McCulat leutttAA $1414001 - 4Allt 8 I*9*

StenWif 0F INVih00eWNIAL QuAllflCAlleel N (LASS 18 80UlfMENT Devistaa O LOCAltD OUlllH teollAllHENI ANS INFO $tD le Iset POSI.teCA pitta (ULATIost RA01Allest INvsatantNI EqulfMilff MA81ufACIWpth levelt 04 BICIRCUt AI10Il RADI4ll0II

• QUAllflCAllose IDENilf l(Ail 001 INNilfl( AI1000 RAtl AI1000 LEVEL 10 WWl(N REPOAI ANG HEIHOS (1) sNeist a (NylaceewNr euAtle ite (lle) (3) (tie)

Saltcle and ladicating tight C u t ler-Hausme r 130 1 ?v "'s loote 6 Note 6 (worstcase)

The canponent listed above is a general application device. Thi s canponent is installed in NEMA type enclosures and depending on its specific design application, may be located in various areas of the Auxiliary Building. This table addresses the quali fication of this couponent with respect to the worst-case radiation envirorvnent (10 year normal 4

dose plus I year post LOCA dose) applicable to the conponent's locations.

i SER ITEM R QM, A quali fication test . program to document the radiation withstand capability of this conponent is in progress.

H , QT , A preliminary review of conponent's materials indicates that there are no materials susceptible to significant Ql: radiation degradation. Ilowever, as noted above, a quali fication test program is underway wi th canpletion scheduled for December, 1981. The results of this test will be documented in a revision to the NUREG 0588 subn.i t t a l . ,

A: Refer to the generic discussion of SER Text Paragraph 3.7 Aging, i

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f McCUBAE leUCLEAR SI4180N = Spegg g Pege ib se,1,$ O St##e4RT OF ENViA000etNTAL QuAtlFICAlless of CLASS 18 (QUlPMElli LOCATED OU15108 toelTAlleWNi Aue f arosID 10 lief POSI-LOCA MCIRCULAllost rat 1Alleet (NVinosettui EqulPMENT st481ufACTDMR M00EL OA SEC1 ACULAll001 8A91 Allull quAtIFICAll(se INNIIFICAll0li I NNilFICAT1000 AAtlAllest LIVfL 10 WHICN MP0mi Alet MINOS atteiMn ANviposedNT quAttrits l (1) '

{119) (2) (109) 10250T 5 105n . Note & Note 6

' 5=ltch and ledicating Light C ut le r-flessner (worst case)

The conponent listed above is a general application device. Thi s canponent is installed in NEMA type enclosures and depending on i ts specific design application, may be located in various areas of the Auxiliary Building. This table addresses the quali fication of this component wi th respect to the worst-case radiation environment (40 year normal dose plus I year post LOCA dose) applicable to the component's locations.

SER 1 TEM R, QM, A quali fication test program to document the radiation withstand capability of this component is in progress.

, QT , A preliminary review of conponent's materials indicates that there are no materials susceptible to signi ficant Ql: radiation degradation. However, as noted above, a qualification test program is underway with completion scheduled for December, 1981. The results of this test will be documented in a revision to the NUREG 0588 submittal.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

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i McGUlmt leutitAR STA110es - telli I P'98 I9 0 Devision steetAmy 0F Envia0settNTAL quAtlFICAlleel 0F CLASS It EQUIPntyg 10CA1(D SlfillDi CCellAlletENT ANS (EP05tB 10 Test POSI-LOCA DECIRCULAlleII SADIAllell ElfVlR08etEMI l

stAIIWFAtiunta st0 DEL en ktC1p(ULAIf ell SAD 1 A10 set qual 4IICAIlGet EQUIrett NT strosi Ane ettinos IDENTIFICAilsop INNIlflC AIIGIS AADIAlloss LEVEL TO WillCH InstSE R tisvipeseeini quAttfitt (1)

(Tit) (3) (lit)

TWM 2.8*ml0 7R hote 6 Note 6 Terminal Block States (worst case)

The conponent listed above is a general application device. Thi s component is installed in NEMA type enclosures and depending on its speci fic design application, may be located in various areas of the Auxiliary Building. This table '

addresses the qualification of this conponent with respect to the worst-case radiation envirorvnent (40 year normal dose plus 1 year post LOCA dose) applicable to the conponent's locations.

SER TEM R , QH , A quali fication test program to document the radiation withstand capability of this compt aent is in progress.

M QT, A preliminary review of conponent's materials indicates that there are no materials susceptible to significant Ql: radiation degradation. However, as noted above, a qualification test program is underway with coupletion scheduled for December, 1981. The results of this test will be documented in a revision to the NUREG 0588 submittal.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

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{ a..l l O StetMAAf 0F (NVIAGNMfh1AL QUAliflCAll0N OF (LASS lt (QulPHENT LOCAllt OUISIDE togeTAllettlei AND (IPL 5tD 50 THE P051-LDCA PECIBCULAll04 RAtlAT10N ENVIRelettMI (Qulmt NT HAssufACiuMR MODEL ca DECIRCutA100el RAelAll0N quelltICAll04 I N NilflCAll018 INNit t lC AT1001 RADIAL 10el Ltvil IO WHICII DEPORI Aelt Mi1HDS letMelR INVIRONMENI QHALiF1(D (I) (Ile)

(tiel (I) 7.,=ia.l aluk Swhanan 5 & 15 <lal0 IA hte I %g (

i,.... ....>

~

The conponent listed above is a general application device. This component is installed in NEMA type enclosures and depending on its specific design application, may be located in various areas of the Auxiliary Building. This table addresses the quali fication of this couponent with respect to the worst-case radiation environment (40 year normal dose plus 1 year post LOCA) applicable to the component's locations.

SER lTEM NOTE: This component is not exposed to a harsh post-LOCA recirculation radiation environment (Refer to Note 1).

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CQutin(WT LOCAllD OU151DE 5tPtMAY OF CONT 4ffeilNT A INVIRONHthfAt QUAtticCulat NUC11A4 STATION lbtNilfisAll0N (4) MNUFACTURER ND 11PQ5(D TO TNE P051 LlFICAT60N OF= UN4I I CLAS5 41 IQUlPMENT thr M00EL CA - OCA A(CIRCULAll0N RADIATION ENVIR0hrt(

T I*

ee-V.y 80LNTIFICATION Reviste O Setenoid valve NtP10(A AftlatutATI0sl i RADIAll0N P u rs E NVi A0Nrt(NT AADIA T40N 265-0001 {TfD)(2) Litil TO WhitH QUAT lFl(D QUAliFIC All006 5 (ilD) RErof. ago agTNog 5 10 ^A0

( to 7)

SER I TEN (mor ;)

{

R, Ql: The for the test program est is Jradiation qualification t A. to the NUREG 0588 tal.submit anuary, program is currently in progress 1982 The results of .

The Refer to the generic dis this rest will be docexpected coinpletion date cussion of SER Text Paragr umented in a revision aph 3 7, Aging.

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McGUIRE NbCLEAR stall 0N - UNig 3 Page Bavision O SUMMARV 0F INVikUNHENTAL QUAllFICATION Cf Ct A$$ SE (QUIPMENT LOCA1(D OUTSIDE CONTAllMENI AND EXP05ED TO THE POSI-LOCA REC ORCULAT10N RADIAT1000 (NVIRONMENT 840t htE NT MAIIUFACTURER N00EL OR REC IRCutAT10el RA01A140N QUAllFICAll0N IS1hilFICA110N IDiNilFIC Alloll RADIAIION LEVEL 10 WICN RtroRT AND M11 HOD

. (1) NLM8ER INVIRONMENT QUAllFlED (ilD)(2) (ilD)

Annulus Vent Fan Unit Ferr C4- Jal0 RAD (hte 6) (Note 6)

Control Parel-Limit ing Cm,,one nt :

SER ITEM R, Ql: The radiation quali fication of the conponents in this papel is currently under review. This review and any required action is scheduled for cunpletion in January, 1982.

A: Re fe r to the generic discussion of SER Text Paragraph 3.7, Aging.

O e e

l l

I'V* 23 McGUIRE NUCLEAR STAllON = UNii I a..l.lon 0

SUMMARY

OF (NVIRONMENIAL QUALIFICAll0N OF CLAS5 If EQUlPMfMT LOCATED OUill0E CONTA1101ENT AND EXPOSED TO THE POSI-LO.A RICIRCUBATION RADIATION ENV140NHENT MANUFACTUAIR MODEL OR RECIRCulAll0M RADIAll0N QUAllFl(ATION (QUlPM&NT REPOAI AND HEIWO IDEMilFICATION RADIAll0N LEVEL 10 WHICN IDENTIF IC All0N NtMBER ENVIRONMENT QUAllfl10 (1) (150)

(110) (2)

Atru. Allison Control Penel- /)lliw a (Note 6) 3ml0 SAS (llege 6) (Isote 6)

Limitleg C w at SER ITEM R, Ql: The radiation qualification of the coiaponents in this panel is currently under review. Thi s review and any requi red action is scheduled for coupletion in January, 1982.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

l

- ~ - s , c

l P89' McCUIRE NUCitAR stall 0N - UHli i R Islaa 0

' SthMARY OF INVIRONMENIAL QUAllil( All0N Of CLAS$ It (QUIPMENT LOCATED OUT5IDE (DHTAlleilNI AND itPOSED TO THE P051-10CA RECORCULAil0N RADIATION (NVIRONMENT MANilFACTUR(R N0 DEL DR RECORCULAll0N RADIAll0N QUAllfl(All0N (QUlfMENT LEVEL 10 WICH REPORT AND P EIN00 IDENilFICAll0N RA04AT10N 10tNI4FICAil0N NLMBE R [NVIRONMfMT QUAllFl[D (I) (110) (2) (IID)

Proportional Twrature lave Controls f%, 83%. 838, 8114 81 9 , 2ml0 AAD (Note 7) (Note 7)

C ir.ii., alt.s, Sin ..a sid SER lTEM The expected canpletion date R, Ql: The radiation qualification test program is currently in progress.The results of this rest will be documented in a revision for the test program is January, 1982.

to the NUREG 0588 submittal.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

4

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f McCulAE NUCLEAR stall 0N = UNIT 4 Pe9 26 StMMARY OF ENVIRONMENIAL QUAliFICA110N OF CLASS IE EQUIPMENT E*'0808" 0 10CATED OUTSIDE (DNTAllM(Ni AND EXPOSED 10 THE POSI-LOCA RECI ACULAll0N RADIAT1018 INVI AONMENT (QUllhENT MANufACTUAER MODEL OR EECIA(ULAil0M RADIAll0N QJAllfl(All0N BD(NilflCAf toll IDENilflCAT80N RA06 Avl 0N LEVEL TO WHICH h(Poni AND MfiNOS (t) hthBE R (NVIR0hMENT QUAllFILO (110) (1) (flo)

Resistance Temperature beJ 101-I.2N-3-C-4-2-1 2midAA8 (Nota $ (hete 7)

Detector SER ITEM R, Ql: The radiation quali fication test program is currently in progress. The expected canpletion date for the test program is January, 1982. The results of this rest will be documented in a revision to the NUREG 0588 submittal.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

r. ,e 27 l NcCulRE NUCLE AR stall 0N - UNii l Revision 0 i SUMMARf 0F ENVIR0tJttNIAL QuAtlFICAll0N OF (LASS It EQUlPMENT LOCAllD CUT 51DE EONTAlmtNT AND ERPO5ED TO THE POST-LOCA REClRCULA110N BADIATION ENVIR0hMINT l

_ l MoctL OR stCIRCutAll0N RA01All0N QUAtlFICATION Equitetf MT MANUTACTunt a IDLhilFICAil0N RADIAil0N LEVIL 10 MelCN REPORT AND MiiH00 ICENilflCAT1006 quAttfit0 NW8t R thWOR0hMENT (I) (T10) (2) (ilD)

Olf terential Pressure Solo #

Switch l

l SER 1 TEM R. Ql: The radiation qualification test program is currently in progress. The expected ccxnpietion date for the test program is January, 1982. The results of this rest will ie documented in a revision to the NUREG 0588 submittal.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

l Peg. 28 l McCUlpf NUCLEAR STATION = UNIT I Sevision 0

SUMMARY

OF INVIRONMENIAL QUALIFICATION OF class if IQulPMtWT LOCATED OUT$lDE CONTAlledNT AND (IPOSED TO Titt Posi-LOCA SECIRCULATION RA01Allosi ENVinotetfMT Eq. 79 TENT MAssufACTUAEA MODEL OR AEC i pCul.ATIOll AA01A180N QuAteFICATIDW lidNilflC AT10el AADIAilON LEVEL 10l#10CM af7087 AND MEIN 00 IDENilFICAil006 NuieE R ENVIRONMENT QUAliflES (1) (rlo)

(180) (2) 8 $lete 7) (Nat. 7) slrr.r.atles pr... m s.t 7r58A8W 5=Io AAS s iuh SER 1 TEM R. Ci: The radiation qualification test program is currently in progress. The expected completion date for the test program is January, 1982. The results of this rest will be documented in a revision to the NUREG 0588 submittal.

A: Refer to the generic discua:Ina nf SER Text Paragraph 3.7, Aging.

W

I F*T' McGUltt IIUCLEAR 51AT10sl - 18101 1 b olsten 0 3484M4AY OF INVInossetNTAL QUALIFICATION of (LASS lt EquitgetNT LetATED SilistM teNTAllettatt AND inP05ED to INE f 05T-LOCA atCOMULAllest AAtlAll011 EIIWlaGesetNT mAeI Allesi quALIFICATI0lf facett sa Mt 3 ACutAllell EQUlftetNT st41REMTUAER RA41 Alle81 LEVfL 10 WIIItal MPeni ANO Mils 00 1948118FICATICII I N NilFICATieII InseMA IIfwl A0steENT GanLIFIts (t) (TID) (3) (tit) 3 (note 5) (ete 5)

Nife MIP-4 5ml0 nAo l Olesel setterles e

g Worst Case: ILOGS SER lTEM A: Refer to the generic discussion of SER Text Paragraph 3.7. Aging.

R: This deficiency was deleted per di;;ussion wi th M. Slosson, NRC-EQBs 07-08-81.

O I

-1

l i

1 P*** 30 Mcr,ular an<.t Aa sTAllc4 - m it 1 O*'I8I'" 0 I Stee%AY of EWineNMENIAL QUAtlFICAlicN OF (LAll SE EQUSPM8WI LOCATID SWillM CowiAlledNT Amt EXP95(9 TO TleF Posi-LorA MCIRCULAilen SAelAficIl ENWlheledNT leoWL ca NCIRCutAllell SAelfiless quattflCalleN EquilMENT ISHMFACTURER LEVIL 10 WHICM MPoal Ane latissos letMTIFICATIcel RASIAllc4 IMailFICAllell lReeMA ENVIRoledNT 4WAllFitt (1) tile) (a) tile)

} Realdeal Heat Resevel Piaqas l' Westinghuwee, Buffalo 11FI)4%-1572. 7tFl}4%-2572 5.2ml0 AAS 2ml0 AA8 WCAP 81% Rev i l IA and le motore 71f13495-1572, 7 5t i)495-2572 WCAP 7829 j

- l (Note 3)

MethoJ Test and Analysis l ,

SER 1 TEM

, A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging. .

B

k 1

i McGulRE 100CLE AR STA110Il - IAllT I '*18" St90mAf 0F tiiviteletENTAL lluAtlFICAllesi 0F (LASS It EWIPittui 8avlsI*a 0 LOCAftt OUT110E ColliAllesElli Ane tarcSte 10 Test Posi-toCA MCIRCULAlless RAslAlloit Elevlacesassi t@flPletIII sensIMFACTWaER ae00(L OR MCI ACt".?ileII AAtl ATICII IluAtlFl(Af teel SBENilFICATIGIR O BGlilFICATICII BAtl ATIcil LEVIL 10 tAtatal MPest Asie latieshe (1) InalMA L10W180lSEENT GaALIFIES

' (189) ff)

(fl0) i l RHA and Conselnnent sprey l A lli s--Chelme r s 9. late AAS Isl0 AAS Socumentation repstod j

g Rooms Sg Pumps IA and le Method: Test

, autors l SER ITEM i

~

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

4 J,

i

Pap M BecGulRE IIUCatAh STAlluel - Willi I #"I ' I'" 0

$4setART OF EW440BetNTAL QuALIFICAtless er (LAll 11 IQulptetui LOCAftS StiillM COIliAllBitNT AND EXPOSED 10 itet POSI-LOCA MCitCULAiltel RASIAlleII testlacesitNT leastL OR MCIMULAllOil AAtlATICII QuAtlFiCATION igulfettert stAaluFACIWA MPeni Ane Mneos 19tilllFICAT1001 BAtlATION LEWIL 10 WillCN IMwilflCAlleil talvimaleetNT es4LIFite InstMR (1) (fle) (I) (Tie)

Ana. .. v.. ell.ti S .t w /a.11.ac. II - n gos 1.lo'aAs 1.lo'nAs a.II c. t. .r 4. .a sniao r . iA . a le .or r.T ,.

SER I TEM A: Refer to t;ie generic discussion of SER Text Paragraph 3.7, Aging,

1 l

i McGUlM leutttAn $1 Allege = lslli i Page M i

! Stece4AT OF ENVlacesWNIAL tuALIFICAtless er CLASS It itWirtettei Bowlst.n 0 LOCATES ElfillDE CONTAllDetNT Ans Enreste TO Ted P051-tiTA MCIRCutAlless RASIAlless tuviteesstaf

EquiMetuit stAlluFACTuntR feettL en MCIRCULAlleel AAtlAlleII tutLlFICAileel 10tNTIFICATitel IDDITIFICATICII RAtlMical LEVEL 18 teelCII M r0ni AFS Mifute (1) IMe0ER taftleessetNT taALIFitt .

+

(Ilt) (2) (ISD) l I Aumlliery tellJIng Filtered Rellance III*862bl2 $ml0b8 2ml0 AAS Ra llance 6 4-1 suC-9. 7/1/79

! tahaust Fans IA and 18 motor j l Method Test and Analysis 3

t SER I TEM iI A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

I I

r l

I

l 1

1 I'98 0 etcCul AE IBUCLEAR STAT 10It - ISeti l bewlelea 0 548004AY OF ENWlaoledNTAL QUALIFICAlled GF (LASS IE EQUlf9 TENT LOCATED SUlllDE CONTA11841NT Ane ERP05ED TO IIIE P051-LOCA MCiSCULAileII RAtlAileII EIIVItaleENT 340ML OR MCIRCULAll0II SA80 Ail 018 Qu4LIFICATICII EQUlfttENT 844HUFACTURER DFNT Age stiging 5000liflCATICII RASI AileII LEVEL 10 ktiltal istasilflCAileII EmWan01eemi quAtifsie anmeEn (1) (Tie)(a) filel Any/Rellence IVF-273608 2alo hAD lato AAS nellensa Latter dated 8/3/00 Olesel Generator Ventilation Fans IA and 10 motors flethods Test and Analysis SER ITEM-A: Pcit:r to the generic discussion of .SER Text Paragraph 3.7, Aging.

1

I i P 3b IIssushi IIUCLEAR 5.'AT10N - tself 9 Sevisle. O e

SIDWIAAT er (IIvsa00sqENTAL qunLIFICAlleII 0F (LASS It feUIPMENT LOCAllt SWillW (eIITAlletElli AIIS (EP051910 itIE POSI-LOCA Rf CIdWLAlleII RAtl Aileil llevleeseIENT DIAlluFMium(R IIcett Oh MClpCULAlleII AASI AlleII QumLIFICAfleII i Equipm4NT RAtl ATICII LittL TG IINICil SEPOSI AIIS MitIOS l latNilflCAilell itOlliflCAil0Il ENVIRelelfui GWALIFIES j IRSISE R (3) '

(118)(3) (ist)  !

8 l

ana Pg Air Handling mellence 2TF-882)ll 7ml0 AAD 2mle AAD Aellence Report IIUC-9. 7/1/78 units IA and is setors and C5 PW Air Handllag thills halted: Test and Analysis I A and IS setore SER ITEM A: Refer to the generic discussion of SER Text Paragraph 3.7s Agi ng.

I

i P'98 McGuett IsuttEAR STAllen - UNIT I Revislen 0 Siseenav 0F ENVIRGIeWNIAL tluALIFICATION OF CLA15 It titulPygggy LOCAftB SWISIM testTA1194tNI AdIS ERp05f t TO THE POST-LOCA MCIRCULATISII RADIAllell ElfWitogeENT i

sqAssuFACTURER seceit Da atClacutAlless mASI Alless quALIFICAT10sl Eqlut tenNT RAtl Allede Ltytt Te WillCN eteeni Asse sqtissag d

IMNTIFICAlleII SDGel1FICAlleil insista t=Ve na=wur esAteFore (I) (itt) (2) (189)

I

'600 Volt toad Censers Sould K-Line 6 ale AAD lal0'SAS Report On-302-688 (Note 4)

Worst cases IELIO SER l TEM A: Refer to the generic discussion of SER Text Paragraph 3.7s Agi ng.

i i

i

McGuthE IfuttfAA SIATION - Belli i P*f* }7 LeCJsitt spillSeethAT OF INWineteetNTAL 8E teerTAlsteENT QUAllFICAlled Amo EXP05(910 SF ELA55 ffMCIRCULAlleII INE P011-LOCA f neseWNT E4UIMefNT RADIAflell ElWiBowlelen 0 Eque ftef tff SOLNilFlCAllWI fw'UFACTUREA 8000(L OR (1) 19thilFICAlleII MCI ACULAlleII RADIAllell AADIAlleit IReeMR (Evil 70 neittel geettaFICAllell i LlevlSeledNT MPeal Age MEinsee gentlFIto (fleltil (fle) 1 l factor Control.

m ,st ..te. . . D, Centers

- testeen Electric Close 1015U j itses I 6eI0 AAa let0 5AAs snelsen Electric letter 6/27/4a I Methods Test and Amelysle.

i SER I TEM _

A: .

Refer to the generic discussion of SER Text Paragraph .

, Agi ng.

37 i

i 1

1 8

4

3-18t2e e 0 rt eS s

ts 8 ly n

e ne ef a n

3 le l 1 g e fi sL n

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g I  :

Aa uo ntI d o qr i r t t s paot h t S

eoe e Wp m M I

I C S -

luls ele A lei) A ltre 0 T Aeti 1 N lTtt A(

e E t  %

S E ALu mEq I

0 V p E l L VI I

(

N O

TI TA NI dD t A PR IUI QC I

gi (I I l T )

EA IC1 rN( a i SL I0 O g U T0t A IlB lC Al tT e )s i

0 b

m A AI uA0e e rLC CI nT l s i(E RSi( e n R Av 7 uF ICRN E E b

0A R

- 01CO 3 M0L tol lT -

h t AS p

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sf

<' r lE g nlN AAI a tQ0 U r t

uL 1 a mAB P

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- tM5 0 0 t ed 0 i P 1 x

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T vN Ef n E

NA ef am ct a n R ef FN T

sOS E OE q I S

Yl e f Rl AA tT o eN e

tO SC n 1 1 o

_ K i 6

1 s

_ T s U

O u e

c t s l i A a e d C s O t u a o L

T w h g

c i

C n A i r F

u t e e N n A

4 8

h eg e

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P o C t R

s

. r r e I e m

f Tl Ie r o

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I tth R oc E  :

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P$

l

- #tl

< i l: 1 l

1. • S*

McGutet leuCLEAR 51AlicN - UNIT I se,1.lo. O StSIMAAV 0F ENWlRONMENTAL QUAliFICAll0N OF (LAll It EQUIMNT LOCATES CUTSlH CONTA199 TENT AND EXPOSED TD Teet POST-LOCA MCISCULAlleel RAtl AT10h EllVIS00 STENT fthaluFACTUM R PIODEL OR M C18CULAllesi RASI Ailoil QuALIFICA110Il EQUS PMENT I MNilFICAI1011 RAtl Ail 001 (EVEL TO UlllCil MP0Ai Afst MEileOS I N NilFICAfl0Il EINI Acteef NT DAALIFIED (I) Im840ER (119) (2) (Tit) 3alo AAD Sotork Test Report. Nil /8s.

7A,)ttW 3elG RAD Motor Operated Campers Rotos k (worst case) dated 12/70 and TA-Il6. deled 10/7)

Method: By stallerity to Rotork N42 Operator SER ITEM A: Refer to the generic discussion of SER Text Pa-agraph 3.7, Aging.

7 t

0

j 1

McCUInt NIKilAR stall 0N - UNIT I P.,. 40 SimnAny or ENvinonnihiAt quAttelCAlves Or CtA55 la f oulPntMi an g e l. O LOCATED OUT510 CONIAllettNI AND EXPOSED 10 THE PO5I-it(A pitlpCULAll0N RA06AlloN tl'Ulp0NMENI toug mt NT MANUFACiunth M00tL on DECi pCULAll0 8 mA00All0N QUAlli' Call 0N GDINilFICAT!ON IDEMI4FICAll04 RA00All0N LEVEL 10 WICH piroal AND HETH00 (1) Ntmet R ENVIP N EV. QUALIFit0 (Ilo)(2) (180) 0 Lt.It Sultch filsro Swit e L5miest Inl0 AAo . I .b l0h alcre Sultch eleport LTR #

l$031=1 SER lTEM

, A: Refer to tha generic discussion of SER Text Paragraph 3.7, Aging, t .

1 4

1 1

1 I

f 3

e"

1 1

McCul8E NUCLEAR stall 0N = UNii i Page Ii 6 ilMtARY OF ENVIR0tMENTAL QUAltflCATION OF CL A15 lE EQUIPMENT 8*'8888" O LOCATED OUI 51DE CONTAletENT AND Eur05tp 10 Ted Post-LOCA RiteRCULAll0N AADIAT1011 INvlR06ettNT (QUIPMENT MA80UFACTUAIR MODEL 04 AttlRCutfiloss AADIAll0N QUALIFICATION i IDENilflCAlloid 10DITIFICATl001 RADIATION LEVEL TO WH4 Cal REPORT Aese M(ite00 (I) IMMSER ENVIRONMfMF QUALIFIED (110) (f) (ilD)

Containment Sump tarton 386A 7 4.Inl0 AA0 2m10 RAD Test Report 4) W I Lovel Transmitters Methods Test SER ITEM A: Refer to the generic discussion of SER Text Paragraph 3.7s Aging.

Page 42 Revision 0 McGUIRE NUCLEAR STATION - UNIT 1 ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUI PMENT LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO POST-LCCA RECIRC'JLATION RADI ATION ENVIRONMENT

Note 1 Class 1E equipment that is exposed to the post-LOCA recirculation radiation environment has been evaluated for proper radiation qualification and is included in this tab is expcsed tc a total integrated dose equal to or greater than 1x10je if it A total integrated dose (i.e., forty year normal RA D.

plus one year accident radiation dose) of less than 1x103 RAD is censidered negligible.

Note 2 The recirculation radiation environment consists of the forty year normal operating raJiation dose plus the dose received from one year of post-LOCA reactor coolant reci rculation.

Note 3 The motors Installed on Unit 1 pumps will be selected f rom the shop order numbers IIsted. All motors listed have been qualified in the same manner.

Note 4 The McGuire 600 volt load centers are qualified by similarity to 600 voit load centers at Oconee Nuclear Station as reported in Report Number OM-302-618.

Note 5 Radiation testing of this equipment is not required for levels below 1x10 b RAD per Section 8.1 of IEEE 535-1979.

Note 6 Documentation of radiation cualification is currently not available for the components used in the termination boxes and area termination cabinets, if documentation cannot be obtained, these components will either be tested, relocated, or replaced by a qualified substitute.

Note 7 A qualification program is currently in progress for these components. The results of this program will be reported upon completion.

I

l McGUIRE NUCLEAR STATI CN - UNIT 1

SUMMARY

CF ENVIRONMENTAL QUALIFICATI ON CF CLASS l E EQUIPMENT LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELS ENVIRONMENT

l I

secGusM leuCitAR STATION = lasti I ** *" 0 SteetnAY of tuvsacsostu1At QuatstlCAlless or CLAS5 It squerettNT LOCA110 EUillK CORIIAIIB4 TNT Ane SEP05te TO Istt0 ENWI A01sttNT tuntiflCAllges feestL Sa Isti t 888WI A0sstINT ert hASILITY ert maltlTV ACCuMCY ACCuaACV 84WIPME NT MstDilliAAftp M4ulate 8tse0N51RAllt MPenT Ame I N NilflCATIeN ENWinesettNT TO WHICII MQUlRES IN INNilf1 CAT 1018 temenNACiunta Mta sitinee aneista (t) tuntereie tsare sensitNT (al Contlaucus M mA WCAP 875's and Duke We s t inghouse. 72FM587-157) Temp: 212 F Temp: 212 F Continuous

• analyses on Westing-Cse.arlfugal Charging Pusy Ouffalo 72FM587-257) house testles:

14 and IB Motors 72f M587-357) MCC I188.05 00-0808 72f M587 le57) MCC 1388.05 00 Ol02 (Note }) Method: Test and Analysis SER ITEM 11: These motors are totally enclosed, water cooled units which have a moisture resistant insulation system. Additionally, these',

motors are provided with space heaters that keep the motor windings dry' during non-operational periods. Therefore, the short-term duration of a high humidity condition that may result f rom a postulated pipe break would have no effect on performance of these motors.

A: Refer to tl.e generic discussion of SER Text Paragraph 3.7, Aging.

H: These motors are totally enclosed, water cooled units. As such a discussion of margin with respect to temperature and dura-tion is not applicable since the motor internals will not be exposed to the short term temperature effects of the postulated pipe break.

QM: As documented above, these motors have been qualified by a combination of test and analysis.

P: These motors are located in areas of the Auxiliary Building which by design do not allow any appreciable pressure increases to occur during a postulated pipe break event. Additionally, these motors are not subject to direct impingement resulting from a break. Therefore, pressure is not a f actor in the qualification of these motors.

McGUIRE NUCatAR STATISII = telli 1 .I O Steet4RT er (WWInosedhiAL QuattflCA14010 eF CLAll It EQUIPDEEIri LeCAlte eWillM CsNTAllotmT Asse EsteSte le lette talvleeletNT tefiresENF fueML en Istte EnlaesedNT ertA400tlTY ertaAslalTV MCuaACV ACCumACT gantIFICallem i letNilflCAllell IqmriufACTimEA SMNTIFICAlleII lifvinesetElfi le toeatu attus Me la MassesStaAfte MgseMe opetusTRAfte Mreal Ane insista (1) eentif e ts sette snee tavlmaissui(a)

Component CooIIng Westlnghouse. 72f M689-1574 lemp: 312 F Temp: 212 F Continuous Contlnuous lea taA WCAP 8753*. and Ow6e Pump suffato 72F M689-2574 enelyses on besting-181. IA2. 181 72f M 689-)S74 house testleg-and 182 Motors 72F M6894574 nCC 4581.05-00-0101 72f M690-1574 MCC 6381.05-03-08d2 7tfM690-2574 72FM690-1574 MethoJ: Test and 72fM690-4574 Analysis (Nute 3)

SER ITEM H: These motors are totally enclosed, water cooled units which have a moisture resistant insulation system. Additionally, these~

motors are provided with space heaters that keep the motor windings dry during non-operational periods. Therefore, the short-term duration of a high humidity con <tition that may result from a postulated pipe break would have no effect on performance of these motors.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

H

These motors are totally enclosed, water cooled units. As such a discussien of margin with respect to temperature and dura-i tion is not applicable since the motor internals will not be exposed to the short term temperattire effects of the postulated i

pipe break.

P: As documented above, these motors have been quallfled by a combination of test and analysis.

, P: These motors are located in areas of the Auxillary Building which by design do not allow any appreciable pressure increases l

to occur during a postulated pipe break event. Additionally, these motors are not subject to direct impingement resulting from a break. Therefore, pressure is .iot a factor in the qualification of these motors.

e

McGUIRE NUCLEAR liAlltel e Ulelf 8 , , , , 0 54seWWif er EminessetNTAL quALIFl(AlleII 0F CLA55 IE 44WIPsetNT LOCATES OUillM CesilAlleEENT Aase Isreste it selle EMIReleami Equiredui #EDML tR DEEL S EWI AONME NT OPERASILITV OPERASILITV ACCURACV ACCumACT quallFICAfsgu INNilf s CAllGIl lihanWACTunta B M Nilf1CATiell EminessetNT To WNatN migulate las MesosSinAige Meug ue etstonssinATis M peni Ass Insist ~. (1) QUALIFIED tot t8 setTesoe IIsv1DesseENT (2)

Mucts4r Service We s t inghouse. 72F)6530-1575 Temp: 212 F Temy: 212 F Continuous Continuous lea sea WCAP 8158 eecs Duke Weir Pun, Buffalo 728365)l.1575 analyses on Westiasa 13 and It Motors 72tt0936-1575 house tentlas:

72L10937-1575 ,. MCC 1381.05-00-0101 (Note )) MCC 8)St.05-00-0102 Me t t.od: iest and Analysis SER ITEM H: Tiiese motors are totally enclosed, water cooled units which have a moisture resistant insulation system. Additionally, these motors are provided with space heaters that keep the motor windings dry during non-operational periods. Therefore, the short-term duration of a high humidity condition that may result f rom a postulated pipe break would have no ef fe ct on performance of these motors.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

H: These motors are totally enclosed, water cooled units. As such a discussion of margin with respect to temperature and dura-tion is not applicable since the motor Internals will not be exposed to the short term temperature effects of the postulated pipe break.

Qfb As documented above, these motors have been qualified by a combinatinn of test and analysis.

P: These motors are located in areas of the Auxiliary Buliding which by design do not allow any appreciable pressure increases to occur during a postulated pipe break event. Additionally, these motors are not subject to direct impingement resulting from a break. There fo re, pressure is not a factor in the qualification of these motc.rs.

R: This deficiency was deleted per discussion with H. Slosson, NRC-EQB, 07-08-81.

etcGulat Nut '.T 51Alless - UNii i 549et4AV 0F tiefl A000stNi.% QUAtlFICA140sl 0F CLAll la (QulPteNT b'Es 0 teCAlt9 GU15tM ColliAllectur Asse EnPosts 10 lette tuvinciestNT tQulPettNT seuset OE istte tesvinosettNT OM AAsillTV OPERA 00tlTV ACCupACV ACCuhACT QuAttflCAlleII I N NilFICAlleil senssutMiunta BMNilflCAileN tievlhesettui 10 tAllCII atqulkit IN MMDer51RAltS MQUlMS Stft0N51AAit9 MPORI Aset ansista (t) eentirite Mts wiNoe iseve RelettNT (2)

Safety injection Westinghouse. 7)f 6%18-1575 Temp: 212 F Temp: 212 F Continuous Cor.t inuous sea sea WCAP 8754 anJ 05ke fusp Seffalo 7)f69618-2575 ana ly se s on We s t s ag-BA and it riotorn 7)F69648-}575 ho.se Testias:

7)t69618 8 575

• MCC 1331.05-00-0101 (Note )) MCC 4)88.05-00-0102 Pethod: Test and Analysls SER ITEM 11: Tiiese motors are totally enclosed, water cooled units which have a moisture resistant insulation system. Additionally, these motors are provided with space heaters that keep the motor windings dry during non-operational periods. Therefore, the short-term duration of a high humidity condition that may result from a postulated pipe break would have no effect on performance of these motors.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

M: These motors are totally enclosed, water cooled units. As such a discussion of margin with respect to temperature and dura-tion is not appl! cable since the motor internals will not be exposed to the short tenn temperature effects of the postulated pipe break.

QN> As documented above, these motors have been qualified by a combination of test and analysis.

P: These motors are located in areas of the Auv.Illary Building which by design do not allow any appreciable pressure increases to occur during a postulated pipe break event. Additionally, these motors are not subject to direct Impingement resulting from a break. Therefore, pressure is not a factor in the qualification of these motors.

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SUMMARY

OF EWIRONMENIAL QUAllFICA110N OF CLA55 If EQUlPMNT LOCATED Oui 310E CONIAlllMENT AND EXPwSED 10 MLB EWl AONMENT EqulittENT HODEL OR MLS ENVIRONMENT OPE RA88 LITY OrthAtitlTY ACCURACT ACCuRACT QUALIFICAlloil IDECilFICAil0N MAmutACTURER lDENilflC AT1000 EWlRONMENT To wHICM REQUIRED IN SEMoll5TRATED SEQUIMO SEMON 51AAIES ptPOAT Asp InsistA (f) QUAL 1F1Ee HEEe pfin0s

, EWIDONnENT (2)

" Tew 145 r C Na ,

44 .aJ 18 Motors Nato $ I6 -Q 72F 44650-1576

• U 2 F Co tlnuoos Cootl,uous mA NA wcAn ais4, a D.,Le

• '.alysis on Ws a lag-

'*S' I' St ia):

72F44650-2576 (Note 3) "CC '383.05-00-0100 M, tiod: fest anJ A,..i, sis SER ITEM H: These motors are totally enclosed, fan cooled units which have a moisture resistant insulation system. Additionally, these motors are provided with space heaters that keep the motor windings dry during non-operational periods. Therefore, the short-term duration of a high humidity condition that may result from a postulated pipe break would have no effect on performance of these motors.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

H: These motors are totally cnclosed, fan cooled units. As such a discussion of margin with respect to temperature and dura-tion is not applicable since the motor Internals will not be exposed to the short term temperature effects of the postulated

~

pipe break.

QH: As documented above, these motors have been quallfled by a combination of test and analysis.

P: These motors are located in areas of the Auxillary Building which by design do not allow any appreciable pressure increases to occur during a postulated pipe break event. Additionally,these motors are not subject to direct Impingement resulting from a break. Therefore, pressure is not a factor in the qualification of these motors.

setGulpt NUCLEAR STAlleN - laisi I E*"

5149tAAV 0F INVI A000tINIAL Qu4LiflCAll0N OF CLASS It EqulPMENT hevislaa 0 LOCAlf t OUTSIM CONIAlleqENT Asse I AP05f t it HELO ENWlmeleetNT Equ170eE3'i feosti en letts (Nvim0NMENT ettaAstLITY OPEAAtlLITY ACCunACY ACCuaACy quat lFICAftell I N NilFICAll0Il lehesuFACTUMA i M NilFlCAllelf EleVlhoself MT 10 keseCN Meulate lu Mteuse51RAIED M4 WINS MseenslaAlts MPest Asse antista (1) quAtitles Mts mines tasvinoseqEIII (1) fuel Poal Air Rallance 3ff-8823Il Temp: 132.4 F Temp: 150 F Continuous Continuous Msndling unit fe% hA M L Ward letter to g g i, MQt 1120.00 dated 7/07/80 Method: ana ly sis SER ITEH w

H: These motors are totally enc:used, fan cooled units which have a moisture resistant Insulation system. Additionally, these motors are provided with space heaters that keep the motor windings dry during non-operational periods. Therefore, the short-term duration of a high humidity condition that may result from a postulated pipe break would have no effect on performance of these motors.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

H: These motors are totally enclosed, fan cooled

• units. As such a discussion of margin with respect to temperature and dura-tion is not applicable since the motor internals will not be exposed to the short term temperature effects of the postulated pipe break.

Qft: As documented above, these motors have been quallfled by a combination of test and analysis.

P: These motors are located in areas of the Auxiliary Building which by design do not allow any appreciable pressure increases to occur during a postulated pipe break event. Additionally, these motors are not subject to direct impingement resulting f rom a break. Therefore, pressure is not a factor in the qualification of these motors.

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$19stAhf 0F ENVIResettNIAL QUAllFICAll0Il of (tA55 f t (QUIP 94 TNT "*'I*I'" 0 LeCAlt9 eul56M toNIAlesitut ANs taroste le lette ENVlacientut Iquil9ENT llueft OR MLB ENVlaceentNT IM2flFICA110Il ertliAsttify ettM81LIIT ACCIIM(T ACCUMCf Guatill(Alleil itAssuracitanta SMlliiflC AlleII flIVlmeestilst le tant (Il Attulht0 IN MH00051AAllt M4WIMS

• susteta Of fesN5 fmAlto MPeat Aug (1) quat trlie Mte M inee .

INVlaelsetNT(2)

,C e rent / Voltage R15 til2tf Temp: 132.Je F Temp: 18 0 F Continuous Contir eous Alarm 12.5% t 031 Ma^wf ac tu'*r's speci fic e-(worst case) of sp.= of sp n tien data tid. Stit. V-Ar4 ,

nett.J: Analysis t The component listed above is a general application device. This conponent is i.3talled in metal enclosures and depending on its specific design application, may be located in various areas of the Auxiliary Building. Thi s table addresses the qualification of this component with respect to the worst-case pipe break environment applicable to the coaponent's location.

SER ITEM 11: This canponent is installed in a totally enclosed, metal enclosure and is protected frun the direct effects of a postulated pipe break. Therefore, the short-term duration of a high humidity condition outside the enclosure that may result frun a pipe break would not effect the performance of this couponent installed inside the enclosure.

P: This conponent is installed in a metal enclosure which ;nay be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the qualification of this canponent.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

. M: This component is installed in a metal enclosure. Margin has been provided in the evaluation oi this component t in that the evaluation considered the full ef fects of the applicable pipe break temperature with no credi t taken for the protection af forded by the enclosure.

QM: This component has been qualified for its application by test or by analysis of the cunponents speci fic design capabiiitles.

QT: For Operabili ty Required stated as " Continuous", the component is to be functional continuously for the duration of the pipe break environment (See Note 2). For Operability Demonstrated stated as " Continuous", the component has been determined to be capable of performing its function for the duration of the pipe break environment.

Ql: This deficiency is not applicable for this conponent with regard to a postulated pipe break environment.

facculet leutttAR 51Allose - lasit I '

• ' I" O Sleet 4AT OF INVIRassefulAL QuAttfl(Alices OF (LA15 f t (QUlrMNT L0t%1ES OutSIM (0NIAlleetNI Asee taPOSit TO Istt0 t#wspessetNT 4 EquirteE NT M00tt OR tett B INVID0seME NT OPERAsillif OttmAtitlIT ACCURACT ACCURACT Quat s fl( Allees SMWfiflCA110N MANuf ACTURER IMNilflCAil0st (NVitesetENT 10 ndeettle MQUlste III Mnces5lAAlts MeulMS M n0NstleAlts att0st Ane NunstR (I) Quat itlee Mte M vuoc .

E NVIRossetNT (3)

Fust Sussmann FNA femp: 212 F Tegap: 232 F Continuous Coptlpuous N/A N/A Derates per maculac-

" **** eurer's surve $ad Se6

1. GI-A le heelud: Analysis The couponent listed above is a general application device. This conponent is installed in metal enclosures and depending on its speci fic design application, may be located in various areas of the Auxiliary Building. This table addresses the qualification of this canponent with respect to the worst-case pipe break environment applicable to the canponent's locati on.

SER 1 TEM H: This conponent is .nstalled in a totally enclosed, metal enclosure and is protected fran the di rect ef fects of a postulated pipe break. Therefore, the short-term duration of a high humidity condition outside the enclosure that may result fran a pipe break would not effect the performance of this canponent installed inside the enclosure.

P: This couponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the qualification of this canponent.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

M: This conponent is installed in a metal enclosure. Margin has been provided in the evaluation of this conponent in that the evaluation considered the full effects of the applicable pipe break temperature with no credit taken for the protection af forded by the enclosure.

Qfi: This conponent has been qualified for its application by test or by analysis of the conponents specific design capabi li ties.

QT: For Operabi li ty Requi red stated as "Conti nuous", the conponent is to be functional continuously for the duration of the pipe break environment (See Note 2). For Operability Demonstrated stated as " Continuous", the component has been determined to.be capable of performing its function for the duration of the pipe break environment.

Ql: This deficiency is not applicable for this component with regard to a postulated pipe break environment.

serGuest NUCLEAR 514f1818 - telli i I*T*

568etnaf OF tesvincestENIAL quntif a(Allose er CLA$$ 18 EQUIPMENT "**I*" 0 LOCAIED SUI 51H (0181AllIPtENI AND ERP05Et 10 SIEtt ENWitteettNI EqulPtetIIT 8 tom L OR tetLB IMillFitA110il stANufACTUM R IM1818FICAll0Il ENWlaceestNT OrtRAttilif OrtpAtillif ACCunACT AttumA(f eth,Lif etalless ENVI A0setE NT 10 44st(N MqulHe let M9400:5184119 ImeeHR (1) M4 WIRE D SEftoNS TRAllt quAtlFIts lee L O SEPOSI ANS Elevl ASIset NI (2) sis tseos .

Fusa pussmann ILTK Temp: 212 F -

Temp: 212 F Continuous Continuous N/A N/A Deeete per e auf ac-(worst case) t ueer's s ur ve 5td. Stk.

l tilt-A-tm

1. 1r timd: Analy s i s The conponent listed above is a general application device. This conponent is installed in metal enclosures and depending on its speci fic design application, may be located in various areas of the Auxiliary Building. Thi s table addresses the qualification of this component with respect to the worst-case pipe break environment applicable to the component's locati on.

SER 1 TEM-H: This conponent is installed in a totally enclosed, metal enclosure and is protected fran the direct effects of a postulated pipe break. Therefore, the short-term duration of a high humidity condition outside the enclosure that may result fran a pipe break would not effect the perfonnance of this canponent installed inside the enclosure.

P: This couponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the qualification of this component.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

M: This conponent is installed in a metal enclosure. Margin has been provided in the evaluation of this component in that the evaluatiei considered the full effects of the applicable pipe break temperature with no credit taken for the protection 4 forded by the enclosure.

QM: This canponent has been qualified for its application by test or by analysis of the components speci fic design capabi1ities.

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ItcCulM touttf an 514f 804 = lAlli l r. 10 SIS 9tAAf 0F ENvl A0089tNIAL QUAtlf t(All0010F (LAll If EQUIPMNT "Isson 0 LOCAllD SU151H CONIAIIIMENT AN8 EXP05te 10 HELB INvl AOMMINI SqulPMENT st0HL On letLS ENvifoletENI SP( Meltlif OrtMeltlIV AttumACT ACCupACT euAt t ritatless l

INNilflCAIl981 ItAIEWFACTUMR IM NilflCAllest tievlR00setNT 10 nellCN pequlH D IN NMostSIMitt piqulM D elft0NSIMits M reat Ane I sneesta (O ouAttritD utte ENvleeseitNT (H MM0e .!

l fuss l. lod Sussmann 3792 temp: 282 F Temp: 250 F ' Continuous Continuous N/A N/A Busseaww st anuf ac turing (worst case) eepos t d.tcJ J/1)/13 NethoJ Analysis l

l The component listed above is a general application device. This conponent is installed in metal enclosures and depending on its speci fic design application, may be located in various areas of the Auxiliary Building. This table l addresses the qualification of this conponent with respect to the worst-case pipe break environment applicable to the I conponent 's loca ti on.

SER I TEM 11: This component is installed in a totally enclosed, metal enclosure and is protected from the di rect ef fects of a postulated pipe break. There fore , the short-term duration of a high humidity condition outside the enclosure that may result frun a pipe break would not effect the performance of this conponent installed inside the enclosure.

P: This conponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulateo pipe break event. Therefore pressure is not a factor in the qualification of this conponent.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

. M: This conponent is installed in a metal enclosure. Margin has been provided in the evaluation of this conponent in that the evaluation considered the full effects of the applicable pipe break temperature with no credi t taken for the protection af forded by the enclosure.

QM: This conponent has been quali fied for i ts application by test or by analysis of the conponents speci fic design capabiIitles.

9

II McCuiet NUCtiAt STAIlost - UNIT I '*"

St99tAAf 0F ENVl A000tENIAt QUAttfitAll0II 0F C' A15 It EquiftetNT ' 0 LOCAIED GuillH C0fl1AlletEIII A880 IIPOSES Ifr lettB ElIVlRONMillI Equil9 TENT 190081 OR Nitt ENVlh0NMENT OrtRAtitlIT OPERADIlltf ACCWmACT AttumACT quAtititAlless INIllflCAll0It It4ssuf ACluaER IDENilf1 CAT 10Il (NVIncettt NT 10 kNitN REqueste IN sinosellAAlt0 REQUIRES ttstogelinAllt ptrost Ang saateta (1) quAttr e ss ste Minnoe .

INVIR0settNT (3)

Continuous Crntinuous N/A N/A suswnn pienuf aturlag

, e block sussmann 3839 te.p: 212 F Temp: 250 r repos t dated 3/13/?)

(worst case) Analysis Hethml l -

l The canponent listed above is a general application device. This conponent is installed in metal enclosures and depending on its speci fic ca tsi, pplication, may be located in various areas of the Auxiliary Building. This table addresses the quali fication oi , e eponent wi th respect to the worst-case pipe break environment applicable to the conponent's locati on.

SER lTEM H: This conponent is installed in a totally enclosed, metal enclosure and is protected fran the direct effects of a postulated pipe break. Therefore, the short-term duration of a high humidity condition outside the enclost e that may result fran a pipe break would not effect the performance of this conponent installed inside the unclosure.

P: Thi s conponent is Installed in a metal enclosare which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the quali fication of this canponent.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

M: This canponent is installed in a metal enclosure. Margin has been provided in the evaluation of this component j in that the evaluation considered the full effects of the applicable pipe break temperature with no credit taken for the protection af forded by the enclosure.

QM: This canponent has been qualified for its application by test or by analysis of the conponents speci fic design capabilities.

0 1

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McCUSM IIUCLEA4 STAlloII

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1839444f 0F ENVIR00Dt(NIAL Qu4LiflCAll0010F CLAll 18 EQUIPMENT "*

• 0 Le[AIES OUI 5lH CCIIIAINMENI Aset EXPOSES 10 setLS INVlRONMENT EQUlrMENT HostL 04 lefle ENVlh0NMfMT OPillASILITY OPERAtiLITY IMZilflCAlleII HA81UFACium(R INNilFICATI0li INVlaciottNT T0 lAtlCN MCumACT ACCumACT quallil( Alless HQUlMS IN HMose11 malts M4UIMS St#40N51RAlt0 ptPoet ANs iNeium til ouAtirt re Nits maino. .

ENVla0 sewn (2)

Fess klmk sus smann 8,139 Temp: 282 F Temp: 250 F Continuous Continuous as/A is/A gaswarwn escula tur lag -

"I ***N repos t dated 3/13/79 rwj : A-.y .s The conponent listed above is a general application device. This conponent is installed in metal enclosures and depending on its specific design application, may be located in various areas of the Auxiliary DullJing. This table addresses the qualification of this couponent with respect to the worst-case pipe break environment applicable to the conponent's locati on.

SER 1 TEM H: Thi s conponent is installed in a totally enclosed, metal enclosure and is protected from the direct effects of a postulated pipe break. Therefore, the short-term duration of a high humidity condition outside the enclosure that may result fran a pipe break would not effect the performance of this component installed inside the enclosure.

P: Thi s conponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These creas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the qualification of this component.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

H: This couponent is installed in a metal enclosure. Margin has been provided in the evaluation of this component in that the evaluation considered the full ef fects of the applicable pipe break temperature with no credit taken for the protection af forded by the enclosure.

QN: This conponent has been quali fied for i ts application by test or by analysis of the conponents speci fic design capabi11 ties.

O

i licCUIM llu(LEAR SIAllCol = lAlli j

• U SUPE 14af 0F invinceentNIAL QuAttflCA11011 0F (LAll if IQUIPlotNI

• • 'a 0 teCAltD OUlllM (CNIAlletENI Aus tsp 05tB 10 NEIS 500WORONMENI EQUIPMENT HDDit OR lettS ENVIRONMENT ON M88tlif DNMeltliT AttuMCY AC(umACT quAttritAtless INNilFICAlless ENvinesettNT 101444(N REQUltte GN MMostSIMitD MeulMS stageII51AAltB DE Pea t Amt I M IflFICAllell lemssutAttumER let geese lasteta iI) qu4iF1Ie let ta .

Ileve A000ttNI (2) reeip: 212 F lemp: 250 F Contimuous Continuous N/A N/A S wam M.ewixturf$q Fuse block sussmann 4515 reges t JateJ 7/74/80 (worst case)

MethoJ imelysis The component listed above is a general application device. This conponent is installed in metal enclosures and depending on its specific design application, may be located in various areas of the Auxiliary Building. Thi s table addresses the quali fication of this component wi th respect to the worst-case pipe break environment applicable to the component's location.

SER lTEM H: This conponent is installed in a totally enclosed, metal enclosure and is protected from the direct effects of a postulated pipe break. Therefore, the short-term duration of a high humidity condition outside the enclosure that may result from a pipe break would not effect the performance of this couponent installed inside the enclosure.

P: This canponent is inf alled in a metal enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the qualification of this conponent.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

. H: This couponent is installed in a metal enclosure. Margin has been provided in the evaluation of this cunponent in that the evaluation considered the full effects of the applicable pipe break temperature wi th no credi t taken for the protection af forded by the enclosure.

> 014: This cunponent has been qualified for its application by test or by analysis of the canponents speci fic design capabilities. .

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McGUIM NUCLE AR 51A10000 = UIlli 8 .. ,1 0 i SipetAAV 0F ENVineseGIAL quAtitlCAllose OF CLAll IE EQUIPMENT i toCAIED SUlllM C0011AllettNI AIIS (IPOSES It lette ElBVI AOMMENT EQUlPMENT MDML 04 sette teeVISOMMENT OPERAtitiff OrthA06tilV ACCUIIACY ACCURACV guAtlt lC Allell INZilFICAfl088 leAsasFACTUMA BM NIlflCAll0N INVIncestill! TO UtiltM Afgul M D IN MNOII51AAlt0 MQUIMS afsteesst:: Alto attest Ane Instett (4) guntirite into Mtisios .

tNV1a01sttNI(2) intactting tlght Cut ler-H.enene r (29 Temp: 28 0 F lemp: 2$$ F Continuous Continuous N/A N/A Duke 5tc : Produc a len (wrat case) Quali f ic at ion & lest f acilit y Res= e t IR-010 I Me ilmd: lest l

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The canponent listed above is a general application device. This canponent is installed in metal enclosures and depending on its speci fic design application, may be located in various areas of the Auxiliary Building. This table addresses the quali fication of this component with respect to the worst-case pipe break environment applicable to the canponen t 's l oca ti on.

SER ITEM 11: This canponent is installed in a totally enclosed, metal enclosure and is protected fran the direct effects of a postulated pipe break. There fore , the short-term duration of a high humidity condition outside the enclosure that may result from a pipe break would not effect the performance of this conponent installed inside the enclosure.

P: Thi s conponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur durilig a postulated pipe break event. Therefore pressure is not a factor in the qualification of this component.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

M: This canponent is installed in a metal enclosure. Margin has been provided in the evaluation of this component in that the evaluation considered the full effects of the applicable pipe break temperature with no credit taken for the protection af forded by the enclosure.

QN: Thi s compo,isi-t has been qualified for its application by test or by analysis of the contonents specific design capabilitles.

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$489 TART OF ENVIR00sttNIAL QuAttfl(Allose OF CLAll If IQUlftttNI

• • "Q LOCAlt0 OUISlH (ceIIAllettNI Asse ERP05f t 10 sett e ENv1poletthi l

l Equif9tfNT le0HL OR MLS INVIRONME NT OPtRAtillIV 0FIRASillif ACCURACT ACCURACT QuAtiflCAlleN IN35flCA180st seANutAClutatR INNilflC All001 (NW O ROBett NT IO WHl(N Mquipit lli MitD8e118AlfD Bf QUIMS C184080%IRAlf B RIP 005 ANS lastett (1) quAtlfite Net s m inee .

INylRosettNT (I)

Op Ical isolator E-ften 175082) lemp: 132.l F i Temp: 11e0 F runtinuous Continuous t . *2 *. 2 51 specified la M*avals 1 (worst case) a .p~ of span Crt-il)8. h C32 (NM-1))S.00-03)

Metkd: Analysts '

The couponent listed above is a general application device. This canponent is instal id in metal enclosures and  ;

depending on its specific design application, may be located in various areas of the Auxiliary Building. Thi s table addresses the qualification of this couponent with respect to the worst-case pipe break environment applicable to the component 's loca ti on.

SER 1 TEM H: This cunponent is installed in a totally enclosed, metal enclosure and is protected frun the direct effects of a postulated pipe break. The re fore , the short-term duration of a high htunidity condition outside the enclosure that may result fran a pipe break would not effect the performance of this corponent installed inside the enclosure.

P: Thi s conponent is Installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the quali fication of this conponent.

A: Refer to the generic discussion of SER Text Paragraph 3.7 Aging.

M: This conponent is Installed in a nie t I enclosure. Margin has been provided in the evaluation of this cunponent in that the evaluation considered the full effects of the applicable pipe break temperature with no credit taken for the protection af forded by the enclosure.

Qtt: This component has been quali fied for i ts application by test or by analysis of the canponents speci fic design capabilitles.

McCulpt seutttA4 $1Allost - RAlli I #*** O St#0tAAV 0F INVI AUsettNIAL QUAliflCAll0es OF CLAS$ It EQUIPetENT LOCAlt9 OUlllDE CONIAINMENT A800 laPOSES 10 HEtt EMylbONMENT EqulF9 TENT NUDEL OR letit (NVip0NMENT opt 9ASitBIV Of'IRAtitlTV ACCunACT A(CtsAACT Quattft(AI1000 INIllflCAllest immseufAttumER INNilFICAT1001 (NVt hosett NI 10 4AttCM StQU18tB IN DiftDe6518 Alto MQUIM D BEMOstsimAIE D DEroat AMs Oneteta (I) QuAtirite NEta navn00 .

tMVinessit Ni (a) fwer Supply tambda . LCS Temp: IM.8s F Temp: 160 F Continuous Continuous ilu% regulation a 1% replation os ts.nuf.c t ur er 's spec i f Sc a-(worst case) of output valtage output voltage tica desa StJ. StL, eVII M.-l ite t hod /*4 lysis The conponent listed above is a general application device. This conpone.nt is installed in metal enclosures and depending on its specific design application, may be located in various areas of the Auxiliary Building. This tabic addresses the qualification of this cunponent with respect to the worst-case pipe break environment applicable to the canponent 's loca ti on.

SER ITEM H: This cunponent is installed in a totally enclosed, metal enclosure and is protected fran the di rect ef fects

. of a pcstulated pipe break. Therefore, the short-term duration of a high humidity condition outside the enclosure l that may result from a pipe break would not effect -the performance of this cunponent installed inside the enclosure.

P: Thi s conponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pine break event. Therefore pressure is not a factor in the qualification of this component.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

. M: This conponent is installed in a metal enclosure. Margin has been provided In the 7 valuation of this conponent in that the evaluation considered the full ef fects of the applicable pipe break temperature with no credit taken for the protection af forded by the enclosure.

QM: This canponent has been qualified for its application by test or by analysis of the conponents speci fic design capabi l i ti es.

QT: For Operabili ty Required stated as " Continuous", the component is to be functional continuously for the duration of the pipe break environment (See Note 2). For Operability Demonstrated stated as " Continuous", the component has been determined to be capable of performing its function for the duration of the pipe break environment.

01- This deficiencv is not annlicable for this component with regard to a postulated pipe break envi ronment.

McCulM toutttAR $1All001 = lAlli l I*I*

Q

$499tAAf 0F (NVip00ftENfAL lltaAtlpl(All0EI 0F (LAll IE EQUlftetWi ' "

LOCAIED SulllM COIIIAlleMENT ARG EIP0$fB It IEEtt INVIR0leqENT IQUIPMfMT N004L 0A IM !ilFICAlleN IsEL O fuVIRONMENT OPERAstllif OPERA 41LliV ACCURACT InnleutACTURER SMhllflCATl001 ElfVl A000tlNT 1014 tlc N MQUIMS Ill ACCURACY llUAllflCalleel MMON11RAlft MQUIMS gEnou5 thAIES #fPeel Asse OneiMn (1) QuAtarine Nete painee .

tNVin0seitel(1)

• Eetry Cut ler-flamene r 02) Temp; 2f.0 F lemp: 255 F Con t irasous Continuous N/A N/A Duke Steam f roJec tion (worst case) (t=44 BIIt et ion 6 Test Facility keport 13-060 ke lle J . Iett The conponent listed above is a general application device. This couponent is installed in metal enclosures and depending on its speci fic design application, may be located in various areas of the Auxiliary Building. This table addresses the qualification of this canponent with respect to the worst-case pipe break envirorvnent applicable to the couponent's locati on.

SER 1 TEM H: This conponent is installed in a totally enclosed, metal enclosure and is protected fran the di rect ef fects of a postulated pipe break. There fore , the short-term duration of a high humidity condition outside the enclosure that may result from a pipe break would c.ot ef fect the performance of th!s conponent installed inside the enclosure.

, P: This conponent is installed in a nie t a l enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the qualification of this canponent.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

M: This couponent is installed in a metal enclosure. Margin has been provided in the evaluation of this conponent in that the evaluation considered the full effects of the applicable pipe break temperature with no credit taken for the protection af forded by the enclosure.

QM: This component has been qualified for its application by test or by analysis of the canponents speci fic design capabi 1i ties.

e e

18

=suiM Nut ti Am SiA18'" - "" '

SupetmRV OF ENWlR000tlNiAL quAtif t(Ail 000 $F CLASS If EQUIPtetNT *

• I" o LOCAIES Out5lM CosetAlfeitest Aase taPosts To sette toevehoNMENT SQUIPMENT 190s:t OR NEtt ENVIRONMENT OrtMeltlif Sti ptitBIY ACCURACT lM',Il FICAllell hallufACTURER IMNilFlCAll0Il INVIResetE NT 10 nattCN REQUIRED la ACCURACT k quattfitalleel Meeuses MIES R44WIMO cassuM5Iutts MPeni Asse insista (I) quat e Fit e wie maiNoe ,

aIIV1R41stitii lI)

Ralsy Cut le r-Haasner 026 leap: 28e6 F Temp: 255 F Cutinuous Continuous N/A N/A DaAc Steen Prodouica (worst case)

Q alificatives & ItSt

" Facility Erport ia-080 Ik t hvJ. Test L

The component listed above is a general application device. This conponent is installed in metal enclosures and depending on its specific design application, may be located in various areas of the Auxiliary Building. This table

addresses the qualification of this canponent with respect to the worst-case pipe break environment applicable to the canponent's locati on.

SER ITEM 11: This conponent is installed in a totally enclosed, metal enclosure and is protected fran the di rect ef fects of a postulated pipe break. Therefore, the short-term duration of a high humidity condition outside the enclosure that may result fran a pipe break would not effect the performance of this conponent installed inside the enclosure.

P: Thi s couponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the qualification of this cunponent.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

I M: This component is installed in a metal enclosure. Margin has been provided in the evaluation of this canponent in that the evaluation considered the full effects of the applicable pipe break temperature with no credit taken for the protection af forded by the enclosure.

i Q)i: This canponent has been qualified for its application by test or by analysis of the canponents specific design capabilities.

9 9

McCusM IsutttAn 514f1011 - tself I P i9 SimetAar tv tavlacientat*t quAteretAttesi OF CtA55 It EQUIPMesi 8* ' 8 ' '*" 0 tetAlle Outllet (OIIIAllettaf Ages EsPolte le utte tuvinesettet E4WlPfetNT MOMt et lett e INvlaosmetNT ertaAsigliV ePtaAstLIIT IM lllf1CAilell seAsastAttuata IN N14Fl(Allest taevinessetNT ACCUIIACT AttunACT tuAlltif Attees 10 naestes NeueMe In MeecessleAtte atquente massassinAlte atPeat Afst utsesta (Il quAttre te Mte niunoe ,

tesvlamentalt (3) mally 5trutliers-evna 289 reap: 212 F tesip: 222 F Contlaucus Continuous N/A n/A nec.,g,. nus,.,go,igo.

I"*'8%****I Pipe auptwee Ieepesatuse Compwment lest file: 65- %O.00 fiei4d . Te. s t The canponent listed above is a general application device. This conponent is installed in metal enclosures and depending on its specific design application, may be located in various areas of the Auxiliary Building. Thi s table addresses the qualification of this component with respect to the worst-case pipe break environment applicable to the component's locati on.

SER ITEM H: This component is installed in a totally enclosed, metal enclosure and is protected fran the direct effects of a posttilated pipe break. There fore , the short-term duratica of a high humidity condition outside the enclosure that may result fran a pipe break would not effect the performance of this component installed inside the enclosure.

P: Thi s canponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the qualification of this component.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

. M: This component is installed in a metal enclosure. Margin has been provided in the evaluation of this component in that the evaluation considered the full effects of the applicable pipe break temperature with no credit taken for the protection af forded by the enclosure.

Oft: This canponent has been quali fied for i ts applic.ation by test or by analysis of the couponents speci fic design capabi11 ties.

T: The temperature qualification for this component is as shown in the table above.

I McCUlpt OfUELEAR SIAllogg testi l I 9' suseiART or sNvimoun NIAt quattricAutose or ctass la toutrwrNT R.'. l . i O LOCAllt OutllH (ON AINHENT Alle (EPGslO 10 litLB INWIRelettNI i

SqulPMENT MOHL OR letLS ENVihoNME NT OPERA 81LITT OrtRASILITY ACCURACT ACCURAC' quallflCA180eg IDC ilflCAll0N MANUFACTURER INNilfl( All000 (NVimesetf NT 10 lAtl(N H QulRit IN MM000 STRATE D Alquinie IRDettR eineN51RAlle AtPORt Asse (1) QUALIfIE9 MtL9 MtTHD9 .

Nv1RountN (I) r In A ustat noo s.<1 3 T=,: no r T p: 165 r Catinuous coatinuou. N/A N/A s p.i., ,, a r u ,,i a.,

k rat <*>=1 -

o. . sia. sit. vu c-s l m ema: A-. i y a .

The couponent listed above is a general application device. This canponent is installed in metal enclosures and depending on its speci fic design application, tr,ay be located in various areas of the Auxiliary Building. This table ,

addresses the quali fication of this component wi th respect to the worst-case pipe break environment applicable to the couponent's locati on.

SER ITEM H: Thi s couponent is installed in a totally enclosed, metal enclosure and is protected fran the di rect ef fe of a postulated pipe break. Therefore, the short-term duration of a high humidity condition outside the encit ~

that may result from a pipe break would not effect the performance of this conponent installed inside the enclosure.

P: This conponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

1 These areas of the Auxiliary Building by design do not allcw any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the qualification of this canponent.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aulng.

M: This conponent is installed in a rue ta l enclosure. Margin has been provided in the evaluation of this component in that the evaluation considered the full effects of the applicable pipe break temperature with no credit taken for the protection af forded by the enclosure.

) QM: This component has been qualified for its application by test or by analysis of the conponents specific design capabilities.

T: The temperature qualification for this component is as shown in the table above.

QT: For Operability Required stated as " Continuous", the component is to be functional continuously for the duration of the pipe break envirorunent (See Note 2). For Operability Demonstrated stated as " Continuous", the component has been determined to be capable of performing i ts function for the duration of the pipe break environment.

McCutM seuttEAa Statiese - tasti 4 Suretmat CF ENVI A0IeWNIAL QUAtiflCAll0ld 0F CLA15 f t EQUIPMNT .I O LeCAlte OUf51DE COIIIAlteetNT Aus tapeste 10 patte ENvipessetNT IquiptGNT 9toML en letts INylpoisetNT I N NilFICAll0II OP(IIAtitITV Ort 9AslaltY It4NufACiuntA INNilflCAll0Il ElIWinesett ui is natf(M M quiett tu AttuRACY ACCURACT quAllfl(All0Il Nieista MesosellmAllt MetHalt effensestnAlis (1) quAtitIt e enae elecat Ano 6NvlRossetNT (1) miesoe .

nesister ol=ni te erown Devil Temp: 431.8s F Tese: 140 F Continuous Cuntlauuus 3 3% et resistor 11% of resistor Derated s,e r manuf ac etrer 't (worst case) W*Iue '" l4* IO* sed un cur va bt d - 50k. 38-8 2 the temperature ha t tuJ- As.alysis coeffic6ent and 4 10*F shift la ti.e en,Itoseens al temp )

The component listed above is a general application device. This conponent is installed in metal enclosures and depending on its specific design application, may be located in various areas of the Auxiliary Building. This table addresses the component's location. qualification of this conponent with respect to the worst-case pipe break environment applicable to the SER ITEM H: This component is installed in a totally enclosed, metal enclosure and is protected fran the direct ef fects of a postulated pipe break.

Therefore, the short-term duration of a high humidity condition outside the enclosure that may result from a pipe break would not effect the performance of this component installed inside the enclosure.

P: Thi s conponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These postulated pipe break event. areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a Therefore pres:. ore is not a factor in the qualification of this conponent.

A:

Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

H: This component is installed in a metal enclosure.

in that the evaluation considered the full effects of the al.plicable pipe break temperatureMargin with no credit taken has been prov for the protection af forded by the enclosure.

QM:

This canponent capabilities. has been qualified for its application by test or by analysis of the conponents speci fic design T: The temperature qualification for this component is as shown in the table above.

QT: For duration Operability of the pipe Required stated as " Continuous",

break environment (See Note 2). the component is to be functional continuously for the component has been determined to be capable of performing its function for theFor Operability Demonstrated stated a break envi ronment. duration of the pipe

8ktutet NutttAR SIAllell tigelt I i'9 Stoemay er teevemoseWNIAL qualsFICAttgu or (LA$$ It (qqgegegest me,'l.sem 0 teCAlto eWillM COIIIAtleetmi Asse tareste le lette amygacesismg Iquif94ENT MOstt eR IIEtt thylmosetEIII OPEMeltliV ertMeltI TY ACCun4CY ACCum4Cf guntettCagless leCilf1 CAT 10Il einesWFACiunta INNIIFICAlleII IIIVIh0IeetNT 10 neelCN Siqul M e im MncesstMIES atquente egnaNSIMile MPeet Ane sneesta (1) quatitles este winee .

I18viScesitNI (2)

Surge suppressor I.eaeral Seml* Transrosb Temp: 212 F temp: 302 F Continuous Continuous N/A st/A Du&e r..terial/Ceepotent conductor (worst case) leucumectat ion form Sad.

5th III-C-l Method: Analysis The conponent listed above is a general application device. This canponent is installed in metal enclosures and depending on its spec!fic design application, may be located in various areas of the Auxiliary Building. This table addresses the quali fication of this component wi th respect to the worst-case pipe break environment applicable to the conponent's locati on.

SER 1 TEM H: This canponent is installed in a totally enclosed, metal enclosure and is protected from the direct effects of a postulated pipe break. Therefore, the short-term duration of a high humidity condition outside the enclosure that may result fran a pipe break would not effect the performance of this couponent installed inside the enclosure.

P: This conponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the qualification of this conponent.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

. M: This conponent is installed in a metal enclosure. Margin has ! een provided in the evaluation of this component in that the evaluation considered the full effects of the applicable pipe break temperature wi th no credi t taken for the protection af forded by the enclosure.

QM: This component has been quallfled for its application by test or by analysis of the canponents speci fic design capabilities.

4 4

McCutRE leuttfA4 SIAllell = leHi 8 '*

Q 54ee#AV cr ENVipessettelAL etantite(Allen er (tAtt It EqulPMauf g,, ,g teCAlte SUISIM (esetAllettWI Alle IBPe5Es le lette llevlRefectill ,

A EqutPMimi Hoeit eR IIELO ENViteNMENT eM m etLITV ert MeltlTY AttunACT IMEilflCAf teII samanstAtlunth IN NilflIAlleII (*VimessetIII is 14 Hist AttumACV Santif 3(Algess piqueste In etnomsIMite atquente elseoss5IMite strosi Asse snoista (1) e atersae setie MiMoe '

anVimesental(2)

I' Swtt cle and Indicat- Cutler-Nameser E30 Temp: 282 F Temp:

• 255F Contlauous continuous N/A It's tight *

(. erst case) m/A o.4e ste . Product ion

} Quellficat!<=. & Test Facility Regiust in-Ol0 fee t hnJ: lest a

The cuaponent listed above is a general application device. This conponent is installed in metal enclosures and dependle;9 on its specific design application, may be located in various areas of the Auxiliary Building. This table addresses the qualification of this conponent with respect to the worst-case pipe break cuvironment applicable to the j conponent's locati on.

SER 1 TEM 61: This canponent is installed in a totally enclosed, metal enclosure and is protected fran the direct effects of a postulated pipe break. Therefore, the short-term duration of a high humidity condition outside the enclosurf.

that may result fran a pipe break would not effect the performance of this canponent installed inside the anclosure.

P: Thi s conponent is installed in a metal enclosure which may be located in various areas of the Auxlliary BuiIding.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a I

postulated pipe break event. Therefore pressure is not a factor in the quali fication of this couponent.

j A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

H: This component is installed in a metal enclosure. Margin has been provided in the evaluation of this component in ti.at the evaluation considered the full effects of the applicable pipe break temperature wi th no credi t taken for the protection af forded by the enclosure.

DJt: This ccuponent has been qualified for its arplication by test or by analysis of the canponents speci fic design capabilities.

P e

1

1. • '* 24 WGusat IsuttiAA SIATION - testi I O 549994Af 0F tuvimosettleIAL quALIFICATIose OF (LASS It EQUIPMENT **"

LetATED SulllM CosetAleestaf Aset tarette to Ispts tesvin0NMtut l

Equ1PMini McM L DA Nit e E NVI RONME NT SPERASILITY crit stLIII MCumACT AttumA(v slumLIg itaticar INNTIFICATICII ptAssurActUnta IMult FICAllell IIIVIn00 set NT 10 natitII t.84 WIRED IN M MON 51AAltB M4WIMS DEMON 5IRAlt e ptrent Asse Insteth (1) QUAT e FIES Ittt D ME ttepe .

Ettv1RosettNT (2) 5=I tc h Cut ler-Mammer 10250i 1emp: 255 F h/A Temp: 2'+0 F Cetinuous Contir*ons N/A bube Ste.se Favouction (west case) Quellfacetaca & lest Tecility pepert 18-083 Me t tu4: lest The conponent listed above is a general application device. This conponent is installed in metal enclosures and depending on its specific design application, may be located in various areas of the Auxiliary Building. This table addresses the qualification of this canponent with respect to the worst-case pipe break environment applicable to the couponent 's Iocati on.

SER 1 TEM H: This conponent is installed in a totally enclosed, metal enclosure and is protected from the direct ef fects of a postulated pipe break. Therefore, the short-term duration of a high humidity condition outside the enclosure that may result fran a pipe break would not ef fect the performance of this canponent installed inside the enc osure.

P: This canponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the qualification of this conponent.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

H: This component is installed in a metal enclosure. Margin has been provided in the evaluation of this component in that the evaluation considered the full effects of the applicable pipe break temperature with no credit taken for the protection af forded by the e.. closure.

QM: This component has been quali fied for i ts application by test or by analysis of the canpanents speci fic design capabi 1i tles.

O

McCUlst peutttAR 51411011 - taelt i I* "

$UP944RT OF (NVIROtetENIAL QuRLIFICAlloII 0F CLA$$ It EQUIPWNI '* "" 0 LUCAIED Suf 56K CosetAlesitui Asse tarosts to sette fuglacesitut IQUlFttENT MUM L OR tott a E NVi p0NME NT DetmAtitiff OPERAgillTV ACCtsmACY ACCURA (f quAtligCAllges IN NilFICAllogt SqmaguFA41Unth IN NilflCAll0N EIIVitosettNT 10 tatsCN RiqulM t IN NMosellAAVES StqUt M e SENoselinAlts Hroei A g I

Nieteth (Il quAtirit s wie M IMoe .

tuvip0NMENI (3) istminal Olx k States net temp: 280 F Ten.p: 31.6 F Cont l.euous Contlauuus N/A N/A 0=Ae St em Freh t ion (wusst case) Qualificatise E luit Fac ili t y mee.or g 18- 4 6 Meth,J- 1est The couponent listed above is a general application device. This component is installed in metal enclosures and dependir.g on its speci fic design application, may be located in various areas of the Auxiliary Building. Thi s table addresses the qualification of this component with respect to the worst-case pipe break environment applicable to the conponent's locati on.

4 SER 1 TEM H: Thi s canponent is installed in a totally enclosed, metal enclosure and is protected frun the direct effects of a postulated pipe break. Therefore, the short-term duration of a high humidity condition outside the enclosure that may result frun a pipe break would not effect the performance of this couponent installed inside the enclosure.

P: Thi s conponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the quali fication of this conponent.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

. M: This conponent is installed in a metal enclosure. Margin has been provided 1n the evaluation of this canponent in that the evaluation considered the full effects of the applicable pipe break temperature wi th no credi t taken for the protection af forded by the enclosure.

Qft: This canponent has been qualified for its application by test or by analysis J the couponents specific design capabilities.

e

I e

McCulM IIUCllAR $1All001 = INell l P898 26 5459444T OF INVIRoletfNBAL quAllfl(All0ll DF CLA$$ l( (QUltngNg Sovision 0 LeCATED SUlllM CONI 4!IpefMI AIIS INPe5tB To istt0 ENvlacsIMENT EquirttENT Hooft OR let t s 5 __

Elev8 AQset(NT OrtpAtlLITY OM AAttiliY IDClifl(Allet* M tuaACT AttvelMY SUntifitAtleN It40suf ACTURER IN ullFICA110N INyltosetiNI 10 lata (M REQUIPES SN MitDN11RAliS MqulMS BE MOIISIRAIE S SEPORI Act IR800ER (1) Quat t flle MLS MINot .

tNvim0NMEN (Il icewinal stock suchanen Solid Link Icay: 132.8e F Temp: 302 F Continuous Continuous N/A N/A Sah.a a Specific ation SS , TS (worst case) d.t a 5t d. 50 k. I v-t-2 &

Iv-e-i Methud: Aa. lysis The couponent lis u i above is a general application device. This conponent is installed in metal enclosures and depending on its spe.ci fic design application, may be located in various areas of the Auxiliary Building. This table addresses the quali fication of this component with respect to the worst-case pipe break environment applicable to the

,:anponent's Iocati on.

SER ITEM H: This couponent is installed in a totally enclosed, metal enclosure and is protected fran the di rect ef fects of a postulated pipe break. Therefore, the short-term duration of a high humidity condition outside the enclosure that tsay result fran a pipe break would not effect the performance of this conponent installed inside the enclosure, i

P: Thi s conponent is installed in a metal enclosure which may be located in various areas of the Auxiliary Building.

These areas of the Auxiliary Building by design do not allow any appreciable pressure increase to occur during a postulated pipe break event. Therefore pressure is not a factor in the quali fication of this component.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

M: This component is installed in a metal enclosure. Margin has been provided in the evaluation of this component l In that the evaluation considered the full effects of the applicable pipe break temperatu e with no credit taken for tha protection af forded by the enclosure.

Oft: This component has been qualifieC for its applicacion by test or by analysis of the components specific design

capabilities.

QT: For Operabili ty Required stated as " Continuous", tIse component is to be functional continuously for the duration of the pipe break environment (See Note 2). For Operability Demonstrated stated as " Continuous", the compoo'

• has been determined to be capable of performing its function for the duration of the pipe brea. - -orvne n t .

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28 susuiu Nuct An seAvieu - unii i 0,7,,,,, 0 54petAAY OF ENvia009dNIAL quALIFICAT10ee OF (LA15 IE SQulPettui LOCATES SuTSIM CGIITAltstENI AN9 EXPOSED 10 stile toevineseqENI EqulPMNT pece(L en sette (NvinceedNT ortaAal;lTV crtaAstitiv MCumACV MCumACY lluntIFitAlltel l I N NTIFICAll0II leAan*ACiunta I M uilflCATION Elfvlh01eetN* V0 4Atl(N REqutRES IN MstomlihA1(9 MgulMS SEJe0N5thATES REP 0mi Ane  ;

lassen tu enAtirise Mts MNeo '

ENW190IsttNT (2)

Vstwo notor Operators Limitorque SM8 Temp: 212 F Temp: 250 F Continuous Continuous E NA Ljmitorque Test Report:

Order Numbers: B00,8, 1/11/80 175826-A, 375834-A 175829-A, 375835-+ Method: 3*st 05831-A, 379664-t 175832-A, 3/9857-r 675833-A SMS Temp: 212 F Temp: 340 F Continuous Continuous NA NA timitorque Test report :

Order Numliers: 90058, 1/11/80 383584-A and AV i.v.p

• 391179-A .

SER lTEM H: These valve motor operators have been quali fied by test for operation in a 100'4 relati ve humi di ty envi ronment.

I P: These valves are located in various areas of the Auxiliary Building. These areas by design do not allow any l appreciable pressure increases to occur during the postulated pipe break event. Therefore, pressure is not a factor in the quali fication of these valve motor operators.

l A- Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

l H: The margin with respect to temperature is as noted in the table above.

QH: This equipment was quali fled by test as noted in the table above.

l ,

29 McCUlRE NUCLEAR STATION = teelf I hav slan 0 StNedRT OF INVIRONM[NTAL QUALIFl(All0N OF CLASS 1E (QUlfMENT LOCA1(D OUISIDE CONTAINMENT AND EXP05Q TO 4WLS (NVIRONMENT EQUI PMFNT MOD (L OR NELS INvi kONMENT OPERA 81LITY OPERA 81LI TY ACCURACV ACCURACf QuRLIFICATION l M;ilFICAllGil leMUFACTUM R INNilflCAT1081 EleVIR088WNT TO W8:H MQUIMD lN D(MohllAAIED MQUIRES 3D00N51 RATES MPORT Ass 0 lets;ttR (1) QUALIfIEO tef & B MEINot ENV1RONMENT (2)

V;lve Mottr Operators Rotork 7hA2 10NA2 Temp: 212 F Temp: 16) F Continuous Continuous M NA Rotork fest Reports:

IINA2 le0NA2 (Note 36) Nll/4, CeCeedser 1970 14NA2 70NA2 T ft l l6. 0c t o*2e r 1973 16NA2 9062 IR222, Jarie 1975 IR3025, April 1980 Method: Test 7NAl 30NAl Temp: 212 F Temp: 380 F Continuous Continuous MA NA Rotort Test Reports:

IINAl le0NAl Nil e, CeCedar l'J70 l'4NAl 70NAl IRll6, October 1973 16NAl 90NAl IR222. June 1975 Method: Test SER ITEM H: These valve motor operators have been quali fied by test for operation in a 100% relative humidi ty envi ronment.

P: These valves are located in various areas of the Auxiliary Building. These areas by design do not' allow any appreciable pressure increases to occur during the postulated pipe break event. Therefore, pressure is not a factor in the quali fication of these valve motor operators.

A: Refer to the generic discussion of SER Text Paragraph 3.7, Aging.

M: The margin wi th respect to temperature is as noted in the table above.

QM: This equipment r 4s quali fied by test as noted in the table above.

e e i

McCulpt NUCLEAR SIAil0N - =mli l SupetARY OF INWIRONMENIAL QUAtlFl(All0N Or' CLAll If EQUIPMENT l ,1 0 LOCAlts OUillDE CONIAINMENT ANS IIPe$E3 TG teELO ENWlRONMENT (WIPMENT N00tt OR tetLS I M ITIFICAil0N INvlDONME NT crt hAtilliV OP(MelllTV AttuRACY ItAnutACiumER IHittlFICAil0N ENVIROIMENT 10 4AlltM MQUIDED IN ACCURACT QuatIFitatteu IRMelm (l) M MONSIAAlfD RtQUltit DEstGat$1AAllB REPOSI AND lluntlFitt 18fi0 setIN00 .

10111RONMENT l2)

Stem Mounted tielt NAMCO E A-l?O-302 temp: III F lemp: 248 T 5=ltches *e.hinuous Continuous NA hA WeC0 lest Depart for (A-170-102 dated 1/28/80 Oet h, k

• IO;(

SER 1 TEM T:

The tempe tesiing ture quali fication for this limi t swi tch has been upgraded fran 212*F to 248"F based on aJdi tional by NAMCO.

11:

This limi t swi tch is quali fied for operation in a 100% relative humidity environment.

P:

This limi t switch is located in various areas of the Auxiliary Building. These areas by design do not allow any appreciable pressure increases to occur during the postulated pipe break event. Therefore, pressure is not a factor in the qualification of this limit switch.

A: Refer to the generic discussien of SER Text Paragraph 3.7, Aging.

M: The margin with respect to temperature is as noted in the table above.

4+ This equipment was qualified by test as noted in the table above.

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e

McCutRE leuCLEAA STAitose - UNIT l 54metARV 0F ENVim00 MENTAL QUALIFICAT10N OF CLASS lE EQulPPENT slaa 0 LOCATED Sili51H CONTA18 STENT Asse EXPOSES To sette ENVIRONMENT EQUIPMENT at00EL OR DIELS ENVIRONMENT OPERASILITY GPERASILITY ACCumACV ACCuaAfV QUAllFICATICII IMWilFICA11014 DamasuFACiumEM INNilflCATICII E81 Vim 01 STENT TO WNaCM REquists IN M nossStaalts REquinES SEse0N5faATis street Aus Nunein (1) QuAtifits sete minee .

ENWl80IstENT (2)

Lielt 5=ltth NAMCU EA180 Temp. 212 F Temp: 340 F Continuous Co,st.We4 NA NA NAMCO Test Reports EAJ40 detes 3/3/18 6 2/20/79 -

Method: Test NOTE: These limi t switches are identical to those installed inside the containinent. Refer to the SER response for i ncont ai runen t equipment, i

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e e e e i e ,

Pag 2 32 Revision 0 McGUIRE NUCLEAR STATION UNIT 1 ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUI PMENT LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELS ENVIRONMENT Note 1 The methods employed to evaluate pipebreaks and to dete.. Ine the resulting environmental parameters are discussed in Duke Power Compacy Report MDS/PDG-77-1.. The Evaluation of the Effects of Postulated Pipe Failures Outside Containment for McGuire Nuclear Station.

Note 2 The HELB envi ronment is assumed to exist for 2i hours based on 30 minutes at the peak temperature after which action by the operator isolates the break .

and allows Auxiliary Building temperature to decrease to normal ambient in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Note 3 The motors installed on Unit 1 pumps will be selected from the shop order numbers listed. All motors listed have been qualified in the sane manner.

Note 4 Rotork Test Report TR-3025 shows that when the qualified temperature for these valves is exceeded, the torque switches may fail on the next operation of the valve. Since at least one additional operation is available af ter the valve's temperature quailfication has been exceeded, the valve can be relied upcn to move to its safety position.

i I

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