ML20077C669

Forwards Justification for Continued Operation of Electrical Equipment in Categories I.B,Ii.A & Iv.Final Submittal for Remaining Items Will Be Sent by 830729

ML20077C669
Person / Time
Site:	Sequoyah
Issue date:	07/20/1983
From:	Kammer D TENNESSEE VALLEY AUTHORITY
To:	Adensam E Office of Nuclear Reactor Regulation
References
NUDOCS 8307260207
Download: ML20077C669 (52)

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TE$NESSE:E VALLEY AUTHORITY ihy;;-

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- Director of Nuclear. Rdetor Regulatz.on Att.Jntion:. Ms. E. Adensam, Chief 7

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Q U.S. Nuclear Regilahry"Cocaissicm,

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Washington, D.C. ~20555 l

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Dear hs. Adensas:

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Docket Nos. 50-3>7 d

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Pisase refer to y%ar letter to"H. C. Parris dated April 26, 1983 concerning i

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the, Safety Evaluacion Report (SER) for Environmental Qualification of U-Y*

Sarcty-Palated Elect::%al Pquipment 6 i.be Sequoyah Nuclear Plant (SQNP).

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~j Frevious.corraspcoder.oA regirding this letter %s submitted from L.'E Mil.ls tc you csl-}hy 12 and Jane 2,1983 Yodr 1ctter requested for items in NRC Categories I.B, II.A, and IV, as j

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ident,1fied in the Tec)4c2(Evalaation Rsport (TER), that TVA reverify the L.

juetification for, contisigd operation (JCO) for any qualification def1M.enoies.docu/ated>in Section 5 of the TER and provide JC0 for any

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j ' equi;neent n66 pr@iously povided. JCOs for NRC Categorier I.B, II.A,.and IV ere ?rntainef. in Eaciostare 1 with a summary table listing the TER item t

s numburs forsthis n6Emittal,.' A final submittal for the remaining items will y

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be.subg.tted 'nean July 29, 1983

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~ Also provided ai Enclosure 2 are JCOs for' equipment which is not fully l-qualified and thi.oh was -not reviewed in the SQNPcBER/TER due to changes in l

TVA's environmental.fqualification pecgram sin' e the submittal of reports on c

which the SER/TER was ba 4

10rdMay.20,1983,.TVA.provided (. submittal on the environmental qualifica-IQ

. tion oG3afety-g-elated-CqiaipQnt in acccedance with the 10 CFR Part 50.49 l/

final.Jtale. As a resulttof deficiencies noted in the SER/TER for the TER

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item % umbers identified -in. Enclosure 1,.ir&hment Nos.1, 2-LCV-3-174 and r

-175 identified in the 10 CFR Part 50.49 ieiponse have had their status H

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9' TVA,has complied with part. graph (a) and (b) or" 10 CFR 50.49 for all our

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previous submittals of JVA's Electrical Equipment Environmental L

Qualification Report by our compliance with,NUREU-0588 and its supplements M

with the exception of part (3) of paragraph (b) that requires certain post-accident monitoring. equipment be covered by the rule with specific guidance j4 coming from Regulatory Guide 1.j7 (Rev. 2).,TVA responded to the require-E ments of Regulatory Guide 1.97 (Rev. 2) in our letter dated March 15,-1982.

E Any additions and/or upgrades required to comply with Regulatory Guide 1.97 (Rev.;2) will be~ evaluated'ror, environmental qualification requirements in l

.accordance with the proposed integrated schedule provided in the lotter.from L. M. Mills to you dated Apefiri5, 1983, which was TVA's

@. / 7 response to Generic Letter 82-33 Piile the table submitted by h

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F Q' B307260207 830720 PDR ADCCK 05000327 983-TVA UOTH ANNIVERSARY P

PDR 9 Art Equal Orportunity Employer m

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. U.S. Nuclear Regulatory Coimaission July 20, 1983 TVA in response to 10 CFR 50.49 does not specifically contain Regulatory Guide 1.97 (Rev. 2) PAM, it does include display instrumentation required under NRC NUREG-0588 and its supplements which is required for accident mitigation.

In addition, your letter requested TVA to discuss the methods TVA used to identify the nonsafety-related electrical equipment whose failure could prevent satisfactory accomplishment of a required safety fbnction(s) as covered by paragraph 10 CFR 50.49(b)(2).

TVA has performed a systematic evaluation of the environmental effects resulting from high energy pipe break, inside and outside containment upon nonsafety-related systems. This evaluatiori is documented in the Sequoyah FSAR Section 7.6, which provided information in response to IE Information Notice 79-22 on environmental qualification of control system. The evaluation discussed the method used to identify potential adverse system interaction and the required operator action to ensure safe shutdown. The evaluation concluded that a safe shutdown can be achieved at SQNP even if a postulated accfdent is compounded by environmentally-induced inappropriate control system ictuation.

l If you have any questions concerning this matter, please get in touch with l

K. P. Parr at FTS 858-2685.

Very truly yours, TENNESSEE VALLEY AUTHORITY l

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D. S. Kammer Nuclear Engineer Sworn p p d subs ibed before me this Ul& day of I-1983 0ld Notary Public Q

pg My Coimaission Expires /"

~6 'f' Enclosures (2) cc:

U.S. Nuclear Regulatory Coinnission (Enclosures)

Region II Attn:

Mr. James P. O'Reilly Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 i

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a ENCLOSURE 1 SEQUOYAB NUCLEAR PLANTS Eauinment Reauiring Justificatioi for Continued Operation i

Units 1 and 2 TER Item No.

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89 (unit 2 only)

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TER Equipment Item Mos. 47 and 48 4

Cutler Hasuser Model 10250 T Status I Resolution of Deficiency TER item Nos. 47 and 48 concern Cutler-Hao model 10250T handswitches located'inside containment and in several areas of the auxiliary building.

The switches inside ccatainment are inoperable during plant operation. The TER states that documented evidence of qualification is inadequate because environmental effects on the switch can and the washer used in sealing the switch when mounted to an enclosure were not considered.

In our response to the SER, we analysed the switch components whose failure we believed would most likely affect the performance of the switch, namely the can and contact block. Both these components are composed of mineral filled phenolic, as is the switch operator. The washers, which are Buna N rubber, are the only components of the switch which are not metal or phenolic. We do imt believe that even total degradation of the washer would allow sufficient moisture to enter the enclosure and affect switch

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suitable for esiitinuous use'at 3000 F, per the Insulation Directory /Enev-

'clopedia, Number 7, dated June / July 1968. The most severe temperature environment experienced by the switches in a safety-related application

.is 3070F, but only for one minute before dropping below 3000 The material also retains at least 50 percent of its physical properties (tensile strength and elongation) at radiation levels up to 8x108 rade genna, per "The Use of Plastics and Elastomers in Nuclear Radiation," dated October 1970 by W..W. Parkinson and O. Sisman.. The most severe total radiation environment experienced by the switches in a safety-related application is 5x107 rada.

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Based on the above, we believe the switches are qualified for use in their 7_. -..... intended areas of, operation.

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• -rican Insulated Wire (TVA Type SROLT Cable)

Status I Resolution of DeficI==ev TER item No. 78 states that qualification of this equipment has not been i

The TER further states that sufficient information has not established.

been provided to establish adequate similarity between the cable installed

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and the cable tested. The test report referenced was for General Electric but the installed cable vos American Insulated Wire.

The explanatica is as follows:

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'AIW used GE silicone compound SE-725 to manufacture the s l cone catie for contract 822502. AIW also manuf actured the silicone cable which GE submitted to the Franklin Research Center for testing, covered by report AIV used the GE SE-725 silicone compound to make.

F-C5119, dated May 1979.

the specimens identified in Table 1 of report F-C5119 as C5119-1666A and 822502 and for GE's test C5119-1669A.,,The cables made by AIW for contract at Franklin Research Center are identical.

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'The supporting letters are:

4 TVA to AIW dated April 3,1960 (EEE 800403 933)

GE to TVA dated March 26, 1980 (EEE 800401 011) 4 AIW to TVA dated March 21,1980' (EEE 800325 009)

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g GE to TVA dated March 14,1980 (EIB 800319 008)

Based on the above, it is concluded that the cable is qualified.

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TER Equipment Item No. 79 Rockbestos ' TVA type SROAT and SROAM cables Statu's 1

Resolution of Deficiency TER item No. 79 states that sufficient information has not been provided to es.tablish that the equipment described on the SCEV sheets (EQS-EEB-CBL-2) is the same equipment described in the referenced qualification data.

The explanation is as follows:

Rockbestos used the same silicone rubber insulating compound on the cables fur.ished to TVA and the qualification reports. This is documented in the TVA contract files either by letters from the vendor or as part of e

the contract acceptance. The cables on this TER were furnished by Rockbescos on four, separate contracts WB87235, 824308, 823428, and WB821729.'

The supporting docussacs are:

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WB821729 TVA to Rockbestos dated April 24, ]978 (EEB 780426 912)

WB821729 Rockbestos to TVA dated May 9,1979 (EEB 790517 025)

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WB821729 TVA to Rockbestos dated June 26,1978 (EEB 780621901) 824308 Contract acceptance dated June 30, 1978 (QAS 780706 524)

WB87235 Rockbestos to TVA dated August 17, 1978 (EEB 780824 006) 823428 Rockbestos to TVA dated June 13, 1978, made part of contract acceptance dated July 27,1978 (QAS 780803 534)

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O TER Eoudnrmi ITEM NO. 80 Anaconda-Continental (TYA Type SROAJ and S10&J-R Cables)

Status I tasolution of Deficiency TER item No. 80 states that qualification of this equipment has not been j

established and the pre-aging data was not evaluated for the plant conditions.

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The resolution is as follows:

Report F-C2935 should not have been included in the NUREG-0588 - NRC SEE and will be removed from EQS EES-CBL-3.

i Anaconda Continental Report No. 79117 is the applicable report and insulation material CC-2193 (the tested specimens) is the same material as that provided on contracts 85861, 83999, 85112, and 825018. See the list of supporting letters and memorandums below:

1. M. Stewart to,.M.~N. Sprouse, January 3, 1973 (No MEDS No.)

Contract 85861 dated August 1,1974 F.W.ChandlertoW.S.WilsfondatedJuly 18, 1974 ZYA to Anaconda-Continental dated May 11,1979 (EEB 790514 915)

Anaconda-Continental to TVA May 4,1979 (EEE 790507 010)

F. W. Chandler to'T. L.~ Aaron dated July 5, 1979 (ERB 790706 934)

T.LIAarontoF.W.ChandlerdatedMay 31, 1979 (EER-790605 051)

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The TVA cable types, BROAJ and SROAJ-R, single and multiconductor, have silicone rubber insulation, glass-braid jacket over each single, and asbestos braid overall. Type SROAJ-R, mark WPR-1, has a 2000C rating and type SROAJ, has a 1250C rating...

An analysis of the data of report 79117 shows that samples were aged 7 days at 2100C and 28 days at 2100 Using the Arrhenius plots, an analysis indicates a temperature range of 1300C to 1450C for 40 years. So we have conservatively rated the cable for 1250C for 40 years. The 2000C rated cable has specific high temperature applications, such as the pressurizer heater. Using the Arrhenius technique, an analysis for this specific application, indicates the cable vill perform at 1500C for 40 years.

Conservatively a 2000C rating ~for 5 years has been assirned for this application. A representative samp1'e of these '200"C cables will be tested (Hi-Pot & MEGGER) at the and of approximately 5 years ( to coincide with a refueling outage). An evaluation of the cable will then be made to determine if replacement is required.

Based on the above, it is concluded that the cables are qualified.

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TER EQUIPIENT ITEN NO. 81 The Anaconda Commanv. ILPE Status I

Resolution of Deficiency TER item No. 81 states that stfficient information was not provided to establish that the equipment described on the SCEF sheet (EQS Sheet No. EEB-CBL-4) is the same as the'equ bment described in the qualification test report.

The following cable descriptions are for the cables referred to on EQS Sheet No. IIB-CBL-4 (WA and WYC):

WYA - One twisted pair, No. 16AWG Class B, stranded, tinned annealed cooper conductors, 25-mil nominal flame resistant cross-linked ethylene propylene rubber insulation (PREP), silicone glass tape with 10 percent overlap,18AWG tinned copper drain wire, 2-mil aluminum /

mylar tape, aM 30-mil nominal chorinatend polyethylene jacket (CPE),

inominal outside diameter of 0.312 inches.

WVC - Same construction as above except 4 conductors with nominal outside diameter of 0.359 inches.

The above cable is covered by cable specimens 26.4 and 26.5 of the

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qualification test report ; submitted for contract No. 87232. These cables are qualified by IEEE 383 Table 1. Representative Cable for Type Tests.

The support letters are:

TVA to Anaconda Company dated May 10, 1978 (EEE 780511 945)

Anaconda (telex) to TVA dated May 2, 1978 (EEB 780503 014)

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' TER iten To. 82 states that sufficient information was not provided to

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establish that the equipment described on the SCEW sheet (EQS Sheet No. EEB-CBL-5) is the same as the equipment described in the qualification test report.

The following cable descriptions are for the cables referred to on IQS Sheet No. EEB-CBL-5 (WTA ):

WVA - One twisted pair, No. 16 AUG Class B stranded.. tinned annealed copper conductors,25-311 nominal flame resistant cross-linked polyethylene insulation,18 AUG tinned copper drain wire, 2-sil aluminum /nylar tape, 30-mil-nominal chlorosulfonated polyethylene jacket, nominal outside diameter of 0.352 inches.

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The qualification tes'tNas done on a signal conductor f16 AWG with 20-sils

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nominal of flame resistant cross-linked polyethylene insulation. This l

sample represents a more severe test profile'than does the use of a shielded, jacketed cable furnished on the contract. This cable is qualified by IEEE 383 Table 1, Representative Cable for Type Tests.

1 The supporting letters are:

TVA to letter to Rockbestos dated September 23, 1977 (EIB 770930 008),

Rockbestos letter to TVA dated March 7 1978 (EEB 780314 010)

TVA letter to Rockbestos dated March 29, 1978 (EEE 780331 923).

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TER Ecuipment Iten No. 83 ITT Scorenant Division TVA Type WYA(ILPE)

Status 1 Resolution of Deficiency TER item No. 83 states that sufficient information has not been provided to l

establish adequate similarity between the cable installed and the cable tested.

The explanation is as follows:

The cable supplied on this contract is TVA-type VVA which is a two-conductor, No.16 AWG, twisted, shisided, jacketed, signal cable. The cabAe is covered on EQS-EEB-CBL-6. The test reports applicable to this cable are Isonedix Test Report 375-02 dated March 1975 and Franklin Institute Research Laboratories Report F-C3961 dated October 1974. Both reports included samples which are exactly the same construction as supolied on this contract. The crosslink polyolefin. insulating ccapound e.-

t used on theecontract is the same as those tested.

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The support document is:

ITT Supprenant Division"to TYA dated Nov' ember 20, 1978 (EEB 781128 002).

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Resolution of Deficioney TER item No'. 84 states that sufficient information was not provided to i

establish that the equipment described on the SCEW is the same as the equipment described in the referenced qualification report (Franklin

- In.*titute Report F-c4113).

The cable referenced on EQS EEB-CBL-7 (TTA ID No. WTC) was purchased from 7775-822000 and is described as the Brand Rex Company on contract No.

four No.16 AWG stranded, twisted, finned copper conductors, each i

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insulated with 24 mils average (20 mils minimm) flame retardant cross-linked polyethylene (ILFE) anterial, with an overall shield, with an overall jacket material of 34-n11 chlorosulfonated polyethylene (hypalon). This cable is represented on the qualification report referenced above'by samples 3 and 4.

The report was approved via Tvi's We era soliciting lettw to Brand.*at dated June 9,1978 (EEB 78060'r 928).

certification from the vendor.

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The Okanite Ca=a=nv - TYA type EPSJ (Mark WWE)

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Statum I Resolution of Defiefanav TER item No. 89 states that sufficient information has not been provided to establish adequate similarity between the cable installed and the cable

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l The explanation is as follows:

l The cable is TYA type EPSJ Hark WNE which is a 1/o, No. h00 MCM, ethylene propylene rubber insulated, chlorosulfonated polyethylene jacketed cable rated at SkV. The cable is covered on EQS-EEB-CBL-12.

The LOCA test report submitted was not necessarily intended to apply to a given contract. The report covered a representative cross section of the EP cables actually installed at the plant. The test results show that i

generically-the'EP will servios up tg a 12-minute, 3850F temperature transient after receiving up to 2x10 rads of gamma radiation and pass a

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post-LOCA test. It is our engineering judgment that the report indicate

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qualification then it will easily survive the EELB envirnoment they are located in.

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TER EOUTPMENT TTEM NO. 40 A=arican Tnnulated Vire Corneratian. Genermi Electrie Wire and Cable. The okonite Cn=nanv. r==er TVA Tyne PLI

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f TER item No. 90 states that sufficient information has not been provided to l

establish adequate similarity between the cable installed and the cable l

tested.

The explanation is as follows:

The cable is TTA type PZJ which is a single conductor cable with flame-retardant crosslinked polyethylene insulation (FRILPE). The cables are l

oc,vered on E@-E2-T3L-13 The five LOCA test reports submitted were not necessarily intended to apply l

to a given vendor on a specific contract..The reports oover a l

representative cross section of the FRILPE cables actually installed at the 12 minute,385Ftemperaturetransientafterreceivingupto2x10guptoa plant. The test results show that generically FRILPE will surviv 0

rads of samma. radiation and pass a post-LOCA test. It is our enginering judgment-that the, reports indicate that if a generic compound FRILPE will meet the l

more demanding LOCI qualification then it will easily survive the HELB

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TER Enuinsmant Item Mo. 41 Okonite, Belden, Rockbestos, Eaton Corporation, Samuel Moors, Anacona-Continental, ITT Surprenant, Times Wire & Cable, Boston Insulated Wire, TVA Type ILPE Status I Resolution of Deficiency TER ites 91 states that sufff vie'nt information has not been provided to establish adequate similarity between the osble installed and the cable tested.

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The explantion is as follows:

The cable is TTA type ILPE which is multioonductor insulated signal cable; 1 kd the individual conductors are insulated with flame retardant cross 1n e j

polyethylene (FBILPE) or flame retardant ethylene propylene rubber - FREPR.

The cable is covered on EQS-EEB-CBL-16.

l The,nine LOCA test reports submitte'd were not necessarily istanded tc apply to a given vendor on a specific contract. The reports cover a representative cross section of the FR2LPE and FREPR cables actually The test results show that generically FR2LPE and8 installed at the plant.

FREPR will survive up to 3850F temperature transient after receiving 2x10 It is our engineering rads of gamma radiation and pass a post-LOCA test.

judgment that the reports indicate that if a generic compound FRILPE and FREPR will meet the more demanding LOCA qualification then it will easily survive the HELB environment they are located in.

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TER Equipment'Ites No. 92 TETZEL-insulated cable by various manufacturers Status I Resolution of Deficiency TER item No. 92 states that sufficient information was not provided to establish that the equipment described on the SCEW is the same as the The TER also equipment described in the ' referenced qualification report.

states that establishing similarity of raw materials for different cables is unacceptable proof of environmental qualification, and-that type testing of actual cables must be done.

The cables. furnished by Anaconda (contract 85838), Carolina (826505),

Teledyne (825280), and Times (84555) are all insulated with TEFZEL, which is Dupton's ' tradename for their ETFE fluoropolymer material. This material is more than just a raw material used by cable manufacturers. This material is essentially a final' product which is merely extruded over-copper wire to create the cables.. Nothing is added to the material that changes its basic ' properties (flame retardancy, etc.).

Since the extruded TEFIC. used by each of the cable manufacturers meets the requirements of MIL-W-22759, it can be assumed that the cables are composed of basically the same materials and that they will all perform alike under like environmental conditions.

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Because of the above, we believe that qualification of all the TEFZEL-insulated cables by means of similarity to Okonite produced cables is a rational and justifiable method of qualification.

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TER EQUIPMENT ITEM NO. 94 i

Pammw amar f ean Ynsulated Wire Cornaration.

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TER item No. 94 states that sufficient information has not been provided to establish adequate similarily between the cable installed and the cable tested.

The explanation is as follows:

The cable is TVA type PZHJ which is a multiconductor cable, with flame-retardant crosslinked polyethylene insulation (FRILPE) on the individual conductors. The cables are covered on EQS EEB CBL-14.

I1 y The five,LOCA test reports submitted were not necessarily intended to apply to a given vendor on a specific contract. The reports oover a representative cross section of the FRILPE, cables actually installed at the 12 minute,385Ftemperaturetransientafterreceivingupto2x10guptoa plant. The test results show that generically FRILPE will surviv rads of 0

gamma radiation and pass s' post LOCA test. It is our engineering judgment that the reports indicate that if a generic ocepound FI2LPE will meet the more demanding LOCA qualification then it will easily survive the HEL3 environment they are located in.

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e TER Eauionant-Item No. 97 General Electric types EB-5, EB-25, and CR-1513; Westinghouse Style No.

80520 Series; Cutler-N - r type 10987.

Status I Resolution of-Deficiencv TER item No. 97 concerns terminal blocks of the above types which are located inside and outside containment. The TER states that qualification

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of this equipment has not been established because of inadequate qualifi-cation documentation.

The terminal blocks are comprised of single piece molded, cellulose filled phenolic material with vasher-head binding screws for circuit vire connections. They are rated for 30 superes and 600 volts (7500-volt break-i down voltage). All terminal blocks are mounted in sealed, gasketed enclosures that provide isolation from submergence, humidity, and other

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adverse conditions of the surrounding environment.

The phenolic material of the blocks retaina 50 to 100 percent of its physicalproperties(ttngilestrengthandelongation)atgammaradiat{on doses up to 5x10* radskil, and has a deflection temperature of 36 0 F 2) at ;66 psia with a"inaximum recoussended service temprature of 3500F 2),

These ratings envelope the environmental conditions in all areas of the plant in which the terminal blocks perform safety-related functions. Also, the terminal blocks have been~ aged to s late a_40-year life at 1580F

- ;n prior to an accident qualification test Results of these tests showed' that they were not affected by aging.

Based on the above, we conclude that the terminal blocks are qualified for use in their service environments for 40 years.

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1.

Radiation data from "The Use of Plastics and Elastomers in Nuclear Radiation," dated October 1970 by Parkinson and O. Sisman.

2.

Temperature and pressure data from Materials Enrineerina. 1981 Materials Selector, Volume 92(b), dated December 1980.

3.

Aging data from'QSR 010-A-01 of Wyle Report No.17742, dated October 20, 1982, " Environmental Qualification Assessment Program."

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TER Item Nos. 135. 179 Manufaeturer/Ncde1 No.

Namco Controls /Model EA 170 j

~

Status I l

l Resolution of Deficiencies switches 2-ZS-30-46, -47, and -48 are located in the reactor 1.

Limit building (Annulus Elev. 823). Limit switchas associated with 1, 2-FCV-90-107, -111, -113, and -117 are located in the reactor building Limit switchas are required to operate for five (Annulus Elev 718).

to fail detrainental to minutes af ter the start of an accident and not safety for periods of up to 100 days thereafterl (depending on plant which accident, occurs).

Limit switehts,2-25-30-46, -47, and -48 and those associated with 1, 2-FCV-90-107, -111, -113, and -117 are subject to LOCA/EELB conditions.

2.

~

2

.: -4they are required to operaue in the is11owing environmentt

c.

N-

w-

.= w g.:.., u.

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Normal Accident Temperature 1100F 150*F (Figure 1)

ATM ATM Pressure Relative Humid 2.ty 80%

100Z 7

5x10 2nds 7

2x10 Eads Radiation (40-Yr TID)

Spray / Flooding

• N/A N/A Limit switch'E associated with FCV-12-79 are located in the auxiliary Limit switches are required to 3.

building (Elev 690/Al General Spaces).

operate for five minutes after the start of an accident and not to fail determinatal to plant safety for periods of up to 100 days l

l thereafter3 (depending on which accident occurs).

Limit switches associated with FCV-12-79 are subject to LOCA/EELB 4.

conditions. They are required to operate in the following 4

environment.

Required operating time reevaluated - EN DES calculations, System 1

30 (NEB 830228 221), System 90 (NER 830228 227).

SQN/WBN Environmental Data Drsving 47E235-47 2

Required operating time reevaluated - EN DES Calculations 3

(NEB 830208 218).

4 SQN/WBN Environmental Drawings 47E235-55, -58.

l 1

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O Normal Accident Temperature 1040F 1130F Pressure ATM ATM Relative Humidity 801 100%

2x10 g de (1xio4bda 2

Radiation (40-Yr TID)

Spray / Flooding N/A N/A The manufacturer's specifications for the EA170 limit switches are:

5.

Temperature 1940F ATM Pressure Relative Humidity 100%

Radiation 2.4x108 Rads 6.

The Namco Model EA-170 limit switch has been thermally aged, No IDCA test was irradiated, and mechanically and seismically tested.

The test criteria and results are documented in performed.

" Qualification -of Namco Controls Limit Switch Model EA-170-II302 to

('75) and Parts I and II of IEEE Standard "J82 ('72)".

• IEEE Standard 34A Revision 1, -dated. 3uly 24,1978..

u_' _.

The tests consisted of:

~

Haat aging for 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> at 2000F.

a.

b.

Mechani' cal aging for 100,000 actuation cycles under electrical load.

Irradiation to a level of 204 megarads.

l c.

. e.

d.

Seismic testing to a==i== of 9.52g's.

Namco, by analysis (see Attachment 1) has estimated the qualified 'lif e I -

7.

to be 20 years, assusing the contacts are cleaned every two ' years and relubrication is done every five years, f_

p.

9 l

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The normal and accident conditions to which the limit switches are 8.

exposed are within the manufacturer's specifications and less severe than the conditions to which the switch has been tested.

The limit switches perform their safety-related function within five minutes following an accident. Once the limit switches have operated, contact transfer mist reoccur for limit switches to fail detrimental to Limit switches have been naismically qualified and plant' safety.

shorting due to environmental donditions is highly improbable.

The above information shows ths.t the limit switches are fully qualified for operation in thei.r envirorments, per IMLEG-0588 cuidelines.

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wco ecmmaus TER Itas No. 135 Attachment Novcmber 9, 1979 -

Estimation of Service Li fe ist Item No.135

~

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l Of EA170-XX3.02 Limit Swi tches For Class IE Use, Outside Of The Containment Area Of Nuclear Power Plants,

I l

Qualification Report Dated 3/17/78 & 7/24/78 Switch P/No. EA17,0-11302 Rev. E Through G.

i The purpose of this presentation is to show that the service life of the EA170 series limit switch exceeds 20 years, under normal service conditions.

The Namco Controls' Quali fication Test Procedure included three types of aging; thermal aging, mechanical aging and rad-lation aging.

As a result of an Engineering study the components of the switch were classified into three groups:

el astomeric seal s, other non'-metallic components and metallic components.

The metallic camoonents, such as, zine alloy housings, steel alloy covers, steel alloy -shaf ts and f asteners are not affected by the thermal condit cns of service or test.

Non-metallic components; the contact carriers and blocks j

are made from thermoset plastics which has been supplied, by our vendor, to the industry for over fi fteen years.

T,his m

thermoset plastic is listed by UL with an index of 130 C, the average _ endurance time being 100,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> (12 years) for this temperature.

Extrapolation of the. regression curv.s provides an estimated li fe of greater than '50 years.

The lubricant man-ufacturer wa's unable to provide thermal aging characteristics for the synthetic lubricants used, howev: r; our experience in-l dicates the -proper application of the proper amount is more critical than the thermal aging characteristics of the lubrl'-

l cant.

b I

Relubrication of the swit.ch on a five year cycle would

.y extend the li fe of the switch beyond the 20 year estimate.

Elastomeric seals, the cover gasket material is a methyl.

vinyl (VMQ) type silicone rubber, generic aging information for this type.of material indicates that minimal physical,

changes occur af ter exposure to temperatures of.150 C (320 F) for less than one year. (1) (2).

Catalog data from the two 1eading manufacturers of silicone, rubber states a service l

- life of from 10 to 20 years at 150 C and when conservatively projepted indicates a service life of greater than 90 years at.90 C (3).

e e

Novcmber 9, 1979 v

-.+

.L t

is a viton o' ring, generic aging informa-The shaft seal in

- tion tori.thi s type of materi al indicates, that no change 148 C and other physical durometer occu.rs af ter 11 months atcharacteristics. actually improved as a' static seal). -indefinite service life

~

these' conditions (4).

(

The EAh 70-XX)02 series. swi tches have a maximum rated Service temperatures for outside the temperature.of 90 C.. area (as proposed in '!EEE 382 Dr,afts) range frdm cop t ai nmen,t

.40 C to 60 C.

I t is impractical to thermally. age. the switch' assembly a high enough temperature or long enough duration of time to cause a significant change in the three groups of materials at low temperature and still simulate the long service life at causing unusual outga.ssing and physical changes.

without the switch was heat. soaked at 200 F for 200 Therefore, hours to s'tabilize,ali the components.

the radiation ebres-The data search also disclosed. that hold of damage for..viton and silicone rubber is as low asThe radiation agin 11X 10 Rads for some compounds (1) (4).

of the quali ficatian test procedure, is.20.4 X 10' Rads.gli Therefore, it can be conclu'ded that the elastomeric seals as required

~

were at or beyond the condition of "end of life",Before the switch was su by lEEE 323 (5)..

conditions.

Based upon the Labove data we'can. consider the estimated L

service life of the EA170-XX302 series switches to be -approx-imately 20 years, assuming the contacts are cleaned every two years and. relubric. tion 'is carried out every five years.

a r

References:

y L

_ '(1)

General Electric Company Technical Data Book S-lE '

'Silic'one Rubber Technical Information

.bowLCorning Corporation (2)

Designing with Silastic Silicone Rubber Bulletin 17-158, Date:

10/72 L

(3)

'E. i. DuPont De Nemours & Co. (inc.)-

El as t ane r1Chemi cal. D epartmen t Wilmington, Del aware

- Upgrading Seal. Performance with DuPont Viton i.

l Catalog A98591 kN mot *T**

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g u o e a-r h o s e 7 M m,

-,,___,~,..--,,-_.,_,,,,.,~,,.,m..,__

um.,_,,...

c

. November 9, 1979 (4)

E. 1. DuPont De Nemours & Co. (Inc.)

Elastomer Chemical Department Wilmington, Delaware.

Properties of Viton

-The Engineering '4/69 Catalog A65D53, (5 )_

IEEE 323-1974, section 6.3.3 Aging s

Std. For Quali fying Class IE Equipment for Nuclear Power Generating Stations e

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TER Item No. 137 Manufacturer /Model No.

Namco Controls /Model EA 180 l

Status I i

' Resolution of Deficiencies.

1.

Connections / Interfaces Teflon tape is not used as a thread seslant at the interface conduit connection to the Limit switch botias.

T 3 ::

Liquid tight flexible conduit with a synethetic jacket (Anaconda Coupsny,. Brass DJ risios, "Sealtite Type UA" or Equivalent) v:A approvsd L.)". 'liquidtight' Eonnectors are used to interface the rigid' conduit system l.' ' ?. '._

'. with'the limit switches..The limit switch housing has American Standard Taper Pipe Threads (NPT) which assures a tight connection.

W:,..

2.

Qualified Life (Post Accident)

Limit switches are required to operate for five minutes af ter the start i

of an accident and not to fail determinental to plant safety for l

periods of up to 100 days thereafterl(depending on which accident...

occurs).,'

The mandiacture's LOCA test profile (figure 1) more than satisfies the requirements of the actual MSLB/LOCA Profile (figure 2).

In addition, the LOCA test extends out to 722 hours0.00836 days <br />0.201 hours <br />0.00119 weeks <br />2.74721e-4 months <br /> (30 days) at 2000F which is a j

more severe environment than denoted by the latter portions of the-actual LOCA profile.

• 3.,,.t

.,A-l The limit switches perform their safety-related function within five minutes following an accident. Once the limit switches have operated, contact transfer must reoccur to allow premature opening of isolation valve upon reset of containment isolation signal. Limit switches have been seismically qualified and shorting of contacts due to moisture /

spray is highly improbable due to sealing of conduit connection.

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Based on Engineering judgment, the above information justifies qualification of limit switches for their accident and post-accident environment.

4 3.

Limit switches are not subject to submergence.

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Required operating time reevaluated.

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,-Manufacturer /Model No.

- Namco Controls /Model EA 180 status IV er

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. - -~,,q mLimit switche's associated with FCV-62-72, -73, -74, FCV-77-16 and t

" ~ *;.

.i --

The FCV-87, -8 are subject to'sabeergence'during accident conditions.

7 l/"

control logic for the isolation. valves is being revised to delete limit switches from the control circuit and provide seal-in signal by means of electrical, relays.-

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Namco Controls /Model EA 740 - Limit Switches on FCV-77-127 i'

Namco Controls /Model EA700 - Limit Switches on FCV-77-128 Status I - Limit Switches on FCV-77-127 IV - Limit Switches on FCV-77-128 Resoittt.8.on of Deficiencies and/or Justification-

.[i

S.9..../.ec;...for Continued Operation y

I.' TER Item No.146 Limit Switches Associated with FCV-77-127

~~

1.

Connections / Interfaces Teflon tape is not' used as a thread sealant at the interface conduit connection to the limit switch housing.

g_

Liquid tight flexible conduit with a synethetic jacket (Anaconda Company, Brass Division, "Sealtite Type UA"~or Equivalent) and e

approved liquidtight connectors are used to interface the rigid

~;

conduit system with the limit switches. The limit switch housing has American Standard Taper Pipe Threads (NPT) which assures a tight connection ~.

2.

Thermal Aging / Basis; Qualified Life Thermal aging is being addressed on a basis of a surveillance and maintenance program instead of mathematical analysis ss. denoted in license submittal EEB-1018.

A materials breakdown of limit switches shows the presence of age subsceptable materials; EPR and NPR in cover gaskets and seals and a thermoset plastic (glass filled polyester) making up the switch l

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TER Item No. 146-Sheet No. EEB-1018 Figure 1.

Appendix 2 Revision 2 Sheet 5 of 11

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terminal block and contact carrier. Namco ' addressed the potential I

for aging in these materials in their qualification testing.

No

. noticeable determintal effects were found af ter completion of qualification testing.

l TVA vill, however, monitor these switches for detrimental aging

' effects with TVA's established maintenance program that operates in

('

accordance with TVA's Nuclear-Operation Quality Assurance Manual (N-l-

(N-OGAM) (designed to meet the requirements of Appendix B 10CFR50) and ANSI-18-1976.

N 3.

Qualified ^ Life (Post-Accident)

Limit switches are required to operate for five minutes af ter the start of an accident and not to f ail determinental to plant safety for periods of up to 100 days.thereafterl(depending on which accident occurs).

' The manuf acture's LOCA test profile (figure 1)more than satisfies the

^

requirements of the actual MSLB/LOCA Profile (figure 2).

In addition,2the_LOCA test extends out to 722 hours0.00836 days <br />0.201 hours <br />0.00119 weeks <br />2.74721e-4 months <br /> (30 daya) at 2000r which ~isya more severe environment than denoted by the latter

,e-r-

portions of 'the actual LOCA profile.

The limit switches pesform their safety-related function within five minutes following an accident. Once the limit switches have' operated, contact transfer must reoccur to allow premature opening of isolation valve upon reset of containment isolation signal. Limit switches have been seismically qualified and shorting of contacts due to moisture / spray is highly' improbable due to sealing of conduit connection.,

g.

Based on Engineering judgment, the above information justifies qualification of J.init switches for their accident and post-accident environment.

1.

Required operating time reevaluated.

II. TER Item No.147 Limit Switdhes Associated With FCY-77-128 1.

Limit switches are located in the auxiliary building (690/A28. A29; j

Pipe Chase). They are required to operate for five minutes after l

the start of.a LOCA/RELB inside contaimsent and not to fail in a l

l manner detrimental to plant safety for 100 days thereafter.

2.

The switches are subject to LOCA and HELB (Volume 17) conditions.

They are required to operate and not to f ail in the following Z

environment :

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Abnormal Accident i.

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Temperature 104*F 1100F 1100F l

Pressure.

ATM ATM N/A l

Relative Humidity 80%

90%

N/A4 5

I Radiation

- 3.5x10 Eads N/A

< 1x10 Rads (40-Yr TID)

(LOCA) l N/A N/A N/A Spray / Flooding.

i 3.

The manuf acturer's specifications for the model EA700 Limit Switch are:

I Temperature 1940F Pressure ATM Relative Humidity WRMA 4 Enclosure Radiation Not specified l

4.

See generic position 4.1.5 for radiation.

i

5. ' The normal and. accident conditions with exception of radiation to which 1

the limit switcass are exposed are virhin the manuf acturer's 4l.{ -

e f1 specifications ' f or these ' devices.. Radiation for an installed interim period 'is negligible and considered not detrimentai~ to ' the ' safety function of these devices as the.y will be replaced as specified in paragraph 6 below.

6.. The above information shows that the linit switches will function

~

properly as required and are therefore qualified for an interim period. However, due to the lack of documentation required by NUREG-0588, TVA vill replace these devices in.accordanchtwith 10CFRSO.49

~-

requirements.

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Required operating time reevaluated.

1.

2.

See SQN/NBN environmental data drawing 47E235-64.

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TER Item No. 153 Manufacturer /Model No.

Fenval Model 27120-50 Se.atus III Resolution of Deficiency i

is TVA's position that 'the justification for continued operat on It provided by EQS No. EEE-1022 for temperature switches TS-12-91A through

. -99A and TS-12-91B through -99B is adequate (see page 3A of TER item No.

153).

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TER Item No.'156 Manufacturer /Model No.

Fenval Model T675A i

Status N/A Resolution of Deficiencies

+

The safety function of the temperature switches 1, 2-TS-74-43, -44, -45, l-and -46 has been reviewed and the'y are 'now classifed as category C devices' i-per NmtEG-0588 guidelines. Failure of these switches during any accident and in any mode is acceptable, and environmental qualification for harsh environnents is not required.

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TER Item No.-160 i

Manufacturer /Model No.

L:

Foxboro/Model E13 DM (MCA)

Status-I m..

Restl t' ion of Deficiencies si y-Information (proprietary) documenting the Environmental Qualification of Foxboro Model E13DM (MCA) transmitters was transmitted by letter No.

NS-PLC-5023, dated April 26,.1978 (see attachment) from Westinghouse Electric Corporation Power Systems to E. G. Case, Acting Director, Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission.

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Forty (20) :::ics ef 1:estf r.ghs:se Test Plan' ?:- Im. la:t : ceu (ann-Pr:.-rietary).

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DCLOSURE 2 ADDITIONAL EOUIPMENT REOUIRING JC0 NOT REVIEWED IN SER/TER w

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Additional Eauinment 1-ES-46-1AC 1-ES-46-IDC l

l-2-ES-46-1AC.

2-ES-46-1DC l

Powell Electrical Manufacturing Company Transfer Switches

(.

I Status IV Environmental ~ Analysis and Justifi' cation-for Continued Ooerstion

.The transfer svitehes are located'in the auxiliary building, elevation

[

669, room A1. They must remain operational to perform safety-related functions in the event of a high energy line break (ELB) accident. The i

[.

environmental conditions in which they sust operate in the event of an 4

accident are 1340 F, 100 percent relative humidity, and lx10 rads gassna radiation dose.

I l-The switches Iack er.vironmental qualification data to substantiate their required operation following an ELB, and Nonconformance Report (NCR) 1 SQNEEB8311 has been wr2.tten to document this deficiency. The switches will l

h un '

be either 3dplaced or relocated to a non-harsh environment. Until I

corrective action is complete,'though, we believe the switches are suitable for' interim operation for the following reasois:

1.

The switches are contained in NEMA 1 enclosures which offer a measure of protection from adverse environmental effects.

)

2.

The HELB conditions are relatively mild.

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033164.06 I

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......,,,... -,,.... - _ _ _.. _ ~. _. _,. -., _,.,.. _,. _.,,,. _.....

TER ITEM NO.

N/A MANUFACTURER /MODEL NO.

Bailey /Model 555 STATUS IV JUSTIFICATION FOR CONTINUED OPERATION For equipment added to SQN 10CFR50.49, Table 11.

Flow tranmeitters 1,2-FT-3-157 and -155 are located in the. auxiliary building (714/16, A10). Flow transmitters 1,2-FT-3-163 and -170 are located 1.

in the auxilary building (690/16, A19). They are required to operate for 100 days after the start of a LOCA/HELB inside containment and for i acnth after the start of all HELBs outside containment.

Flow transmitters 1,2-FT-3-147 and -155 are subject to HELB (Yolume 14) and 2.

LOCA conditions. They are required to operate in the followir.g 1

environments :

Accident h

'2-= ? e -

Temperature:

1040 F 1920F Pre.ssure:.

Ata Ata Relative Hamidity:

805 1005

~

Radiation:

3 5x104 rads

<,1x104 rads (40 yr. TD)

(LOCA)

Spray / Flooding:

N/A N/A l

Flow transmitters 1,2-FT-3-163 and -170 are subject to HELB and LOCA conditions (Volume 15). They are required to operate in the following environments 2:

Normal Aceident f

Temperature:

'1040 F 1960 F Ata Ata Pressure:

Relative Bualdity:

805 1005 4 rads U1 - 1 75x103 rads (1x10 Radiation:

(40 yr. TE (LOCA)

U2-35x10j rads (40 yr. TD)

Spray / Flooding:

N/A N/A 3

The manufacturer'.s specifications for the flow transmitters are:

1 0

0

-20 F to 185 F Temperature:

Pressure:

Ata Relative Humidity:

Not specified*

Radiation:

Not specified

' Rated for all outdoor installations.

l

,,-,----,----,,-,e-.

---

,-----,,,--_,,,,aw,.

--r,<--

.,-w-,,n..-

See generic positions 4.1.5 for radiation and 4.1.8 for relative humidity.

4.

During an HELB, the 5.

The==r4=2m normal operating temperature is 1040F.

temperature will rise' to 1960F within 625 seconds, and then decrease The.

normal operating temperature within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

linearly to the marimim 11 F temperature rise above the manufacturer's specified maximum operating 0

temperature of 1850F is of such short duration that it will not effect the operation of the transmitters.

6.

The above information shows that the flow transmitters will function properly as required and arei,therefore, qualified for an interim period.

However, due to the lack of documentation required by NUREG-0588, TYA will replace these devices in accordance with 10CFR50.49 requirements.

1 ee SQN/WBN Environmental Data Drawing 47E235-83, -52.

S 2 ee SQN/WBN Environmental Data Drawing 47E235-59, -60.

5

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TER ITEM NO.

N/A MANUFACTURER /MODEL NO.

Masoneilan/Hodel 496-2 AIAIHa 1Y l

JUSTIFICATION FOR CONTINUED OPERATION For equipment added to SQN 10CFR50.49, Table 11.

1.

Limit switches associated with 1,2-FCV-70-85 are located in the' auxiliary building (pipe chase area, Elev. 690/A28, A29). They are required to operate for 5 minutes after the start of an accident and not to fail detrimental to plant safety for 100 days thereafter.

1 2.

Limit switches are required to operate in the following environments :

M Abnormal Accident Temperature:

-1040 F 1100F 1100 F Pressure:

Ata Ata N/A Relative Bumidity:

80%

905 N/A

. Radiation:

3 5x105 rads E/A 1x104 : ads (40 yr. TID)

(LOCA)

Spray / Flooding:

N/A-N/A N/A 3

.The manufacturer's' specifications for limit switches are as follows:

l Temperature:

1800 F Pressure:

Ata Relative Humidity:

NEMA 4 Enclosure i

Radiation:

Not specified 4.

See generic positions 4.1.5 for radiation and 4.1.8 for relative humidity.

5.

The above information shows that the limit switches will function properly as required and are, therefore, qualified for an interim period. However, due to the lack of documentation required by NUREG-0588, TVA will replace these deviceis in accordance with.10CFR50.49 requirenents.

1 ee SQN/WBN Environmental Data" Drawing 47E235-64.

S e

i l.

l l

e i

l TER TTEM NO.

N/A.

Namco Controls /Hodel EA700 MANUFACTURER /MODEL NO.

EAIDs

. IV For equipment added to SQN 10CFR50.49, JUSTIFICl? ION FOR CONTINUED OPS'#1 TION Table 11.

1. ' Limit switches 2-ZS-1-181, k182, -183, and -184 are located in the react building, lower containment, Eley. 712.

minutes after the start ot-an accident and not to tail in^a manner detrimental to plant safety for 100 days thereafter (depending on which accident occurs).

s They are required to Limit switches are subject to LOCA/HELB conditions.

l 2.

operate and not to fail in then following environment :

Nomm1 ibnomm1 Accident 1200F 130 F 3270F Temperature:

Pressure: '"

14 7 psia 14.7 psia 26.4 psia Relative Bumidity:

80%

1005 1005 Radiation:

2x107 rads

• N/A 1x100 rads

~ (40 yr. TID)

Spray only Spray / Flooding:

N/A 3.- The manufacturer's specifications for the switches.are:

I 1940 F Temperature:

Ata Pressure:

l NEMA 4 Enclosure

( -

Relative Humidity:

Not specified Radiation:

l The above information indicates that limit switches will function properly l

[

for an interim period under normal and abnormal conditions (until replaced 4.

Limit switches are not qualified for their required per NCR SQNEEB8309).

operating accident environment.

TVA will replace these limit switches with qualified switches 5

in accordance with 10CFR50.49 requirements.

1 ee SQN/WBN Environmental Data Drawing 47E235-45.

S

~.

e N/A TER ITEM NO.

MANUFACTURER /MODEL NO.

Custom Components /Hodel 604G

}

STATUS IV JUSTIFICATION FOR CONTINUED OPERATION For equipment added to SQN 10CFR50.49,

. Table 11.

i Pressure switches-1,2-PS-3-160A,-160B,-165A and -165B are located in the j

1.

auxiliary building (west valve vaults, 706/A1, A11). They are required to to operatate for 5 minutes after being subjected to a main steam line

' break or a feedwater line break inside valve vaults and not to fail detrimental to plant safety for 100 days thereafter.

2.

The pressure switches are required to operate in the following environmentsl:

Normal Accident

~

Temperature:

1300F 3070 F Pressure:

Ata 22.9 psia 11elr.tive Hr.addity:

50%

1005

~*

Radiation:. --

~

1 75x103 rads N/A

'~

(40 yr. TID)

Spray / Flooding:

N/A N/A

~

l 3

The manufacturer's spec 1fication for the pr'ssure swithces are:

e l.

Temperature:

1600 F Pressure:-

Ata Relative Bumidity:

NEMA 4 Enclosure Radiation:

Not specified 4.

See generic positions 4.15 for radiation and 4.1.8 for relative humidity.

5.- The above information indicate's that these switches are not qualified for their accident environment. These switches will be located to an area with less harsh environments and replaced with fully qualified devices in accordance with 10CFR50.49' requirements.

~

I ee SQN/WBN Environmental Data Drawing 47E235-79 S

8 4-.

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._,,.,.,--,,,--,,..---r_-,.

. - - - -, - ~

TER ITEM NO.'

N/A MANUFACTURER /MODEL NO.

Masene11an/Nodel 8012 STATUS III JUSTIFICATION FOR CONTINu w OPrWATION For equipment added to SQN 10CFR50.49, Table 11.

'I.

1.

Positioners on each of 1,2-LCV-3-148, -156, -164, and -171 are located in the auxiliary building (.714/11). They are required to operate for 100 days after the start of a LOCA/HELB inside containment and for 1 month' after the start of all EELBs outside containment.

[

The positioneis are subject to HELB (Volume 12) and LOCA conditions.

2.

l They are required to operate in the following environmenta :

Harmal Ancident TempIrature:

.1040 F 1290F

. Pressure:

Ata Ata Relative Hum.tdity:

805-100%

~[~

~

Radiation:'

.5x102 rads

< 1x104 rads (40 yr. TID)

(LOCA)

N/A N/A Spray / Flooding:

3 The manufacturer's specifications for the positioners are:

Temperature:

1800 F.

Pressure:

Ata Relative Humicity:

NEMA 4 Enclosure l

Radiation:

Not specified l

~

4.

See generic positions 4.1.5 for radiation and 4.1.8 for relative humidity.

f I

An accident simulation test to temperatures in excess of 3200F has been f

S.

performed at Wyle Laboratories and has shown that these positioners will function properly 'as required and are, therefore, qualified for an interim period. Further testing is being done at'Wyle Laboratories in Huntsville, Alabama, to provide qualification documentation as required by NUREG-0588. Testing will be completed by June 1, 1984.

I I ee SQN/W51N Environmental Data Drawing 47E235-49, -50.

S t

o-

..a Positioners on each of 1,2-LCV-3-172, and -173 are located in the II.

1.

auxiliary building (714/A6, A10). They are required to operate for 100 days after the start of a LOCA/HELB inside containment and for 1 month after the start of all HELBs,'except for an AW pump turbine steam line break, outside For an AFW pump turbine steam line break, positioners are containment.

classified category C.

The positioners are subject to HELB (Volume 14) and LOCA conditions.

2.

2 They are required to operate in the following environments :

Nor==1 Accident Temperature:

1040 F 1920F Pressure:

its Ata Relative Humidity:

805 1005 Radiation:

1x106 rads (1x104 rads (40 yr. TID)

(LOCA)

Spray / Flooding:

N/A N/A 3

The manufacturer's specifications for the positioners ara:

.=

Temperature:

180* F l

Pressure:

Ata Relative Humidity:-

NEMA 4 Enclosure i

Radiation:

Not specified 4.

See generic positions 4.1.5 for radiation and 4.1.8 for relative humidity.

An accident simulation test' to temperatures in excess of 3200F has been 5.

performed at Wyle Laboratories and has shown that these positioners will function properly as required and are, therefore, qualified for an interim period. Further testing is being done at Wyle Laboratories in Huntsville, Alabama, to provide qualification documentation as required l

by NUREG-0588. Testing will be completed by June 1, 1984.

~

2 ee SQN/WBN Environmental Dat'a Drawing 47E235-83, -52.

S I

l l

i 9

=

, _ _ _ _ _. _, _ - -. _.. - - _ _. ~.... _ _ __ _. _ _.. _ _.. _ _... _.. _ _,. _ _ _. _ _ _ - -.

S e.,:.,

Positioners on each of 1,2-LCV-3-174, and -175. are located in the They are required III.

1. -auxiliary building (west valve vaults, 706/A1, 111).

to operate for 100 days after being subjected to a main steam line bred

~

or a feedwater line break inside valve vaults.

The'positioners are required to operate in the following environments 3:

2.

Nor-ini Accident Temperature:

130 F.

3070F Pressure:

Atm 22 9 psia Relative Humidity:

505 100%

Radiation:

1.75x103 rads N/A (40 yr. TID)

Spray / Flooding:

N/A N/A 3

The manufacturer's specifications for the positioners are:

4 Temperaturer~

1800 F Atm Pressure:-.

• f-~

Relative Humidity:

NEMA 4 Enclosure Radiation:

Not specified 4.

See generic positions 4.1.5 for radiation and 4.1.8 for relative

~

humidity.

~'

An accident simulation test to temperatures in excess of 3200F has been 5

performed at Wyle Laboratories and has shown that these positioners will i.

function properly as required and are, therefore, qualified for an Further testing is being done at Wyle Laboratories in interim period.

Bunts tille, Alabama, to provide qualification documentation as required by NUREG-0588. Testing will be completed by June 1,1984.

d 3See SQN/WBN Environmental Data Drawing 47E235-79 Wh*

1 e

1 e

i

....... ~. _.. _. _ _ _.,....

e *,

TER ITEM NO.

N/A Bailey /Model 556 MANUFACTURER /MODEL NO.

STATUS IV For equipment added to SQN 10CFR50.49, JUSTIFICATION FOR CONTINUED OPERATION Table 11.

Pressure transmitters 1,2-PT-3-122A are located in the auxiliary building They.are required to operate for-100 days after the start of a 1.

LOCA/HELB inside containment and for 1 month after the start of a (690A1).

outside containment.

The pressure transmitters are subject to HELB (Volume 9, 19) and LOCA l

They are required to operate in the following environments :

2.

conditions.

l Normal incident Temperature:

1040 F 113 F (Volume 9) 1180 F (Volume 19)

Ata Ata Pressure:

100%

805 Relative Humidity:

4 rada 5x102 rads

<1x10 i

Radiation:

(40 yr. TID)

(LOCA)

N/A N/A Spray / Flooding:

The manufacturer's specifications for the pressure transmitters are:

3 1800F Temperature:

Ata Pressure:

NEMA 4 Enclosure Relative Bumidity:

Not specified Radiation:

The temperature and pressure environment in which the tran==1tters are located and the accident temperature and pressure environment to which they 4.

See may be subjected is less s'avere than the manufacturer's specifications.

generic positions 4.1.5 for radiation and 4.1.8 for relative humidity.

I I

The above information shows that these pressure transmitters will function However, due as required and, therefore, qualified for an interim period.

S.

l to lack of documentation required by NUREG-5088, TVA will replace these devices in accordance with 10CFR50.49 requirements.

I ee SQN/WBN Environmental Data Drawing 47E235-55, -57, and -58.

S

., -. ~ -.. _

. ~.

m..-.

.,-,.-,_--,,.cm-w

x-e o*,.

TER ITEM NO.

N/A

\\

i MANUFACTURER /MODEL NO.

ITT Barton/Model 288

)

~

STATUS

'IV JUSTIFICATION FOR CONTINUED OPERATION 'For equipment added to SQN 10CFR50.49, Table 11.

1.

For flow switches FS-65-25A/B-0-FS-65-25B/A O-FS-65-311/B 0-FS-65-31B/A 0-FS-65-44A/B 0-FS-65-44B/A O-FS-65-55A/B 0-FS-65-55B/A l

2.j,0-7S-65-56A/B

.1":-0-FS-65-56B/A e

---i;.

,;. y l

Flow switches are located in the murilary building (734/116). They are 2.

For i

required to operate for 100 days following a LOCA inside contcinment.

l all HELBs, flow switches are classified category C.

1 Flow switches are required to operate in the following environments :

3 M

ibnormal Accident Temperature:.

1040 F 110 F 1100F 0

--Pressure: 4 --

Atm Atm N/A

.. Relative.Eunidity:

80%

90%

N/A

~

2 rada N/A 1x107 rads

. Radiation:

3 5x10 (40 yr. TID)

'(LOCA) i Spray / Flooding:

N/A N/A N/A 4.

The' manufacturer's specifications for limit switches are as follows:

Temperature:

2000 F-Pressure:

Ata Relative Humidity:

NEMA 4 Enclosure Radiation:

Not specified l

5 See generic position 4.1.8 for relative humidity.

i l

Flow switches are not qualified for their accident radiation environment.

6.

TVA will electrically remove (per ECN L5124) flow switches from control circuit to eliminate their safety function until environmentally qualified-replacements are-installe'd.

l.-

I ee SQN/WBN Environmental Data Drawing 47E235-81.

I S

l

,--t t

w r,

e---e:

,-+m,-

wv rr ee m

- - +

w--w pv, w

• -e,r--av

--eenw----

~er

-*~=-r-e**we+

a 4

TER ITEM NO.

N/A MANUFACTURER /MODEL NO.

Custom Components /Model 604G STATUS IV JUSTIFICATION FOR CONTINUED OPERATION. For equipment ' added to SQN 10CFR50.49, Table ii.

Pressure switches 1,2-PS-3-121A, -1213, and -121D are located in the 1.

auxiliary building (669 A6, A26). They are required to operate for 100 days ~ af ter.the start of a LOCA/EELB. inside containment and for 1 month after the start of all HELBs, except for an AFW pump turbing steam line break, outside containment. For an AFW pump turbine steam line break, pressure switches are classified category C.

The pressure switches are subject to HELB (Volume 5) and LOCA conditions.

2.

They are required to operate in the following environments Normal Accident va 1040 F 1720 F Temperature:

Atm Ata Pressure:

.a.;.

Relative Humidity:

80%

90%

4 rads Radiation:

5x102 rads lx10 (40 yr. TID) '

(LOCA) i

" N/A N/A Spray / Flooding:

The manufacturer's specifications for the switches are:

3.

I j

i Temperature:

160,0 F i

Pressure:

Ata f

Relative Humidity:

NEMA 4 Enclosure I

Radiation:.=-

Not specified

.- p. i

)

See generic positions 4.1.5 for radiation and 4.1.8 for relative humidity.

4.

The maximum normal operating temperature is 1040F. During an EELB, the temperature will rise to 1720F within 650 seconds, decrease to 1440F I

within 800 seconds (from start of accident) and then decrease to the maximum normal operating temperature within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The 120F temperature rise above the manufacturer's specified maximum operating temperature of 1600F is of such short duration that it will no't effect the operation of the i

pressure switches.

The above information shows that the pressure switches will function 6.

properly. as required and are, therefore, qualified for an interim period.

However, due to the lack of documentation required by NUREG-0588, TVA will l

- replace these devices in accordance with 10CFR50.49 requirements.

1 ee SQN/WBN Enviromnental Data Drawing 47E235-71, -72.

j' S

I TER.1 1

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