Text

Forwards Info Identifying Proprietary Portions of Franklin Research 821222 Safety & Technical Evaluation Repts on Environ Qualification of safety-related Electrical Equipment Per Request.Proprietary Portions Deleted
	ML20071C347
Person / Time
Site:	Point Beach
Issue date:	02/22/1983
From:	Fay C; WISCONSIN ELECTRIC POWER CO.
To:	Clark R, Harold Denton; Office of Nuclear Reactor Regulation
References
	NUDOCS 8303010697
	Download: ML20071C347 (47)
	v • d • e

{{#Wiki_filter:T O W POWER COMPANY 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 February 22, 1983 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. R. A. Clark, Chief Operating Reactors Branch 3 Gentlemen: DOCKET NOS. 50-266 AND 50-301 PROPRIETARY INFORMATION IN TECHNICAL EVALUATION REPORTS ON ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Mr. Clark's letter dated December 22, 1982 forwarded a Safety Evaluation Report (SER) and a Technical Evaluation Report (TER) prepared by the Franklin Research Center concerning the environmental qualification of safety-related electrical equipment for each unit at the Point Beach Nuclear Plant. Portions of the information supplied in the TER's included test reports and other documents which contained information which had previously been accorded proprietary protection. Wisconsin Electric was requested to contact the owners or originators of this information and clearly identify which information still required proprietary protection and provide the specific rationale and justification for this protection. As discussed in our letter to you dated January 26, 1983, we provided the TER's to the Westinghouse Electric Corporation, the owner of the information, and requested that they complete a review of this information and clearly identify the proprietary details. Westinghouse has completed this task. For your convenience we have attached a listing, by Equipment Item Number and page, of those sheets from the TER's which still contain proprietary information. Please note that except for item numbers 69 and 70, those equipment item' numbers listed apply to the TER's for both Point Beach Nuclear Plant, Units 1 and 2. Item numbers 69 and 70 refer only to the Unit 2 TER. DR DO K O O 6 P PDR

Mr. H.-R. Denton February 22, 1983 We have also enclosed each of those pages' identified' as containing proprietary information. The specific elements of information contained on those pages which are maintained by Westinghouse to be proprietary have been' deleted. Applications for withholding of this information together with affidavits presenting the specific rationale and justification for providing this protection from public disclosure were submitted.to the NRC-when the proprietary documents, from which the information for these TER pages was extracted, were originally submitted. These applications and affidavits are still relevant and are the basis for continued proprietary treatment. Please notify us if you have any question concerning these matters. Very truly yours, C1 [/hU Vice President - Nuclear Power C. W. Fay Enclosures Copy to NRC Resident Inspector l l

LISTING OF PAGES CONTAINING PROPRIETARY INFORMATION IN TECHNICAL-EVALUATION REPORT. 4 ON ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 EQUIPMENT ITEM NUMBER PAGE NUMBER . Item No. 10 Sf Sg 5h Item No. 32 3a 5c 5d Se 5g Sh Si Sj Item No. 36 3a Sb Sc 5d Se Item No. 54 3a 3b Sg Item No. 56 3a 3b Sg Item No. 61 3a 3b Item No. 62 3a 3b Sj Item No. 63 3a Sj Item No. 64 3a Sg Item No. 65 3a Sj. ~

r t' t EQUIPMENT ITEM' NUMBER PAGE NUMBER Item No. 66 3a Sg.

Item No.'69'(UNIT 2 ONLY) 3a-5c

-5d. .' 5 e Sh 5i Item No. 70 (UNIT 2 ONLY) 3a' Sg i i o l r. I I (- I i l..

franklin Research Center FRC Project No.C5257 i MtlETARY Pago mwvomrummo. mm-w-o FRC AssignmentND.}3 INFORMATION 5f A DMs6on of The Frankhn Instuwe 20th and Race Streets. Phde.. Pa. 19103 (215) 448 1000 FRCTask NO. (d4/fv"7 EQUIPMENT ENVIRONMENTAL Q JALIFICATION REVIEW OF EQUIPMENT ITEM NO. / d ~ n. The Licensee cited

Reference:

944 63[ as evidence of qualifica-tion. , ~ ~~ With respect to Reference Q 7 FRC notes that the information base is not easily ascertained. Reference Ny4dMCAP-7410-L, Vol. I of II, Section 4) describes environmental testing programs performed on process instrumentation. such as pressure and differential pressure transmitters manufactured ~ by ITT-Barton, Fischer & Porter, and,Foxboro. FIRL Reports F-C2639 A and F-C2667 are cited by M.m/fL-T *.u**as evidence of qualification " ~ for pressure and temperature steaA environmental accident conditions. FIRL Report F-C2639 describes results of three tests conducted on various Foxboro and Fisher & Porter transmitters. Teoc' No. 1 was conducted using four pressure transmitters as test ~ specimens, Test No. 2 was conducted using four differential pressWe transmitters, a7d Test No. 3 was conducted using two specimens previously tested in Test No. 2 plus two new pressure transmitters. A Foxboro differential pressure transmitter, Serial No. 2013081, was used as a test specimen in Test No. 2. Due to difficulty in maintaining a constant inout dif ferential cressure, this transmitter was retested in Test No. 3. F-C2639 did not specifically state the test temperature / pressure profile utilired in Test No. 3; however, the report implied that the same generic erivironmental profile was reasonably duplicated in all three tests. Following the environmental tests, Foxboro unit Serial No. 2013081 was seismically tested and subsequently radiation tested. WithrespecttoReference43[,FRCnotesthats The referenced test stated that a Foxboro differential pres'sure transmitter, Serial No. 2013081, was used as a test specimen. l The Guidelines rewira that equipment exposed to radiation as an environmental sr.il:e condition must be qualified to integrated j dose levels vM ct. ce a combination of the ndemal operating dose l level plue Mr am dent dose level. A gamma dose of 20 Mrd iis consideret rWW.a h for general PWR containment areas. The Licensee suted tnac the total integrated radiation level af ter a DBE is 160 Mrd. FRC precumes that the difference between 160-Mrd and 20-Mrd values is in part due to beta radiation contribution. The referenced test stated that the Foxbore tran siAter, Serial No. 2013081, became inoperative during the _f icit/ Jhours of the irradiation test at an intecrated dose ofJ 'MYd." Westinghouse stated that the unit would be exali%1 to%statlish the cause of l

d Fr:nklin R:se:rch Center NRC Contract Ns.NRggyt rm. Pags FRC Project N3. C5257 , A Dwieson of The Frankhn Instaut: FRC Assignm:nt No.1 FORMATION 5g 20th and Race Sereets. Phde.. Pa 19103 (215) 448 1 2 0 FRC Task No. 'C~o (a f7M EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /_D. i i NOTES: failure. If the cause of failure could not be corrected, Westinghouse suggested shielding the units, which are required to operate long-term post-accident, so that total dosage would be less than 1 Mrd. FRC concludes that beta radiation doses are not significant for qualification of this equipment. In addition, FRC concludes that sufficient evidence of test specimen transmitter's performance (accuracy and stability), prior to l failure during the test, does not exist to yarrjnt a determination of satis. factory operation up to a level of Mrd. Therefore, thetransmitterqualificationtotheanticEpateoradiation environment is deficient due to evidence of failure during the type test. The Guidelines require that equipment exposed to chemical sprays must be qualified for the.most severe chemical environment by either test or analysis. In addition, the effects of enclosure pressure boundary integrity and fluid in-leakage must be considered. As discussed previously, these transmitters could become submerged in the chemical solution. The test program () has not addressed the potential for chemical attack on elastomer seals and gaskets, cocumentation () providing evidence (in the form et...ter testing or analysis) i that the performance of this equipment is not degraded due to ""T" l containment spray solution should oe provl.ded. a The Guidelines require that equipment operational modes during. testing should be representative of the actual plant application requirements. In addition, failure criteria should include instrument accuracy requirements. Tha referenced test stated that the maximum error of the Serial No. 2013081 transmit _ter's output signal during LOCA environmental testing was fin 0 to 10 seconds andl ~' lfor the total test duration.'~ FRC concludes that'th'.a.s presumably unacceptable and reflects failure of the transmitter to perform with adequate stability. Unless the Licensee provides justification for acceptability of this maximum error range, FRC concludes that the unit has failed to qualify under environmental testing.

dddll Franklin Research Center FRC Project No,C5257 PROPRIETARY paga A DMoon of The Frm Insmews FRC Assignment N2.14 INFCRMATICN 5h 20th and Rac Sweets. Phda.. Pa. 19103(2154 444 1000 FRC Task N3. T o 6 / T o ~P EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO../_d NOTES: The Guidelines require that the test chamber temperature / pressure profile envelop the service conditions for a time equivalent to the period from the initiation of the accident until the service conditions return to normal values. As stated in the referenced test report', the test chamber time-dependent temperature / pressure ? crofile exceeded the postulated accident profile for ]but did not totally envelop the required eftvironmental serv cj renditions. The referenced test time duration, stated to be minutes, did not envelop the required accident profile

8. -hcir interval.

The required environmental service conditions m such that the temperautre ceturns to normal (125'F) and the calculated worst-case presrure returns to normal (o psig) in 8.3 hours after the. initiation of the accident. The Guidelines require that radiation exposure should be applied during the test sequence concurrent with or prior to the temperature and pressure / steam environment if it is known that the device contains materials which can be degraded by irradiation. FRC notes that the unit was seismically tested and subsecuently irradiated af ter the temeerature and pressure / steam environmental testing. It has been established that the transmitter is susceptible to radiation exposure as a result of testi'ng. In light of this, FRC concludes that the test sequence for this device should have included irradiation exposure prior to or concurrent with the temperature / pressure testing. i l l t 1

= r. NRC Contract N3. 'NRC 03-79-118 P 03 nidin Research Center FRC Project NO.CS257 A De of The Frankhnineswe FRC Assignment N2.13 3a 20th and Race Seeses. Phde.. Pa. 19103 (21N 4481000 FRC Task No. to c / Tc'7 EQUIPMENT ENVIRONMENTAL QUAUFICATION REVIEW OF EQUIPMENT ITEM NO. 32.. LICENSEE RESPONSE R. The Reactor Coolant System loop RTDs were only tested to Rads gamma and were not thermally aged during qualification testing. The above radiation dose allows over 10 years of normal one.ation followed by one week of post-LOCA containment radiation. This would be sufficient time after a postulated accident to place the plant in a stante condi-tion such that the RTDs would not be required. In addition, back-up indication such as steam generator saturation pressure or Residual Heat Removal systes temperature are available depending on the mode of alant cooling. Therefore, continued safe operation of the plant is assured. It is our intention to continue evaluation of the present RTDs for thermal aging and a higher radiation dose in order to fully qualify these RTDs to the DDR Guidelines. High normal ambient temperatures and hign normal radiation dose rates make the environmental qualification of these cong'onents extremely difficult. It is our intention to replace them with fully qualified RTDs by the. environmental qualification deadline, if possible. G e F l E

NRC Contract No. NRC-03 79-118 4N dd Frtnklin R: search Center FRC Pr: Ject NO.C5257 PROPRIETARY Pago 5c a om a The Frzakiin in.atura FRC Assignmcnt No.13 toc- (e INFORMATION 70 1 20th and Race Saeets. Phda.. Pa. 19103 (215) 444 1000 FRC Task No. EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 3 2 DEFICIENCY NRC REQUIREMENTS WITH SECTION REFERENCE LICENSEE QUALIFICATION (X QR (DOR /0 588-I/0 588-II) SUBMITTAL 00CUMENTATION NOTE NO.) CombinedwithDBEexposuref. Radiation Aging, Dose (rd) Not stated g Radiation Aging, Dose Rate Radiation Aging, Method I Materials susceptible Not stated Not stated (Radiation) (5.2.4, 7.0/-/-) ! Operational Aging 1 M (g 1 ! y' jg (-/4.2/-) Other Age Conditioning M(A t l' fg y (-/4.2/-) (J Qualified Life Claimed / 1 !ote9'10 N ! y\\,,,,..ggj. Post-accidentRC{ g, Established (5. 2. 4/ 4.10/-) X Normal Ambient Temperature 120 F Normal Ancient Radiation %+ q.y 1 200 R/h Normal Ambient Humidity ! g4,g4,g 1 Not Stated I on-Going Surveillance and '3,. stated Preventive ~ Maintenance (7.0/~/-) On-Going Analysis of N/A Failures and Degradation ( 7. 0/-/-) I ! ot stated Margin (General) N (6. 0/ 3. 0/ 3. 0) Margin (NC?EG-0588, 1 Nd4bb1 Cat. I) (-/ 3. 2/-)

1. Temperature (+15'F)

2. Pressure (+10%,

10 psig max)

3. Radiation (not required)

4. Time (+104, +1 hour

+ function time minimum) l

1 NRC Contract NO. NRC 03-79-118 E FRC Project No.C5257 PROPRIETARY $d 000hrank!1n R:se:rch C:nter FRC Arsignm:nt N3.13 TWV6 )(FORMATION 1 A cia.on of The Frankhninsatute ' 20th and Race Streets. Phda.. Pa. 19103 (215) 44a.I000 FRC Task No. EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIE DEFICIENCY (X OR NRC REQUIREL. "1TS QUALIFICATION LICENSEE NOTE NO.) WITH SECTION REFERENCE DOCUMENTATION SUBMITTAL (DOR /0588-I/0588-II) 1 1 ACCIDENT CONDITIONS _ IDCA/MSLB/HELB/Uncontroll'ad !),,0CA/Sg!SLB (4.1, 4.2, 4.3.1, 4.3.3/, 1.1, 1.2, 1.5/1.1, 1.2, 1.5) ! (,.mug g,,, . Radiation Type I Radiation Dose (ed) 1 ,g Not Applicable (4.1.2/1.4/1.4) !.6 Mrd/h Raciation Dose Rate (rd/hr) 1 Radiation Qual. Method (5.3.1/-/-) !NM Prcximity to Concentrated Radiation 4 ( 4.1. 2/1. 4. 6 /1. 4. 6) ! ot stated N Equipment Susceptible to Beta Radiation (4.1.2/-/-) y!, Radiation Dose (Norr d + 1 p Mrd 4', Accident) (4.1. 2/-/ -) 1 1 I ! ot stated 1 N Plateout Dose Considered 1 1 (-/1. 48/1. 4 8) I 1 C2mma + Beta Dose (rd) 1 g 100 Mrd (4.1.2/1.4.7/1.4.7) b*f 40 Y e% 8 o ped few,

4 NRC Contract N2. NRC-03-79-118 !j0hlj Franklin R:se:rch Center FRC Project No. C5257 p,qcpRIETARY Pag 3 A oiw. ion of The Frankhn insmue2 FRC Assignm:nt N3.13 NFORMATION 5e 20th and Raca Streets. Phila.. Pa. 19103 (215) 44a.10n0 FRC Task No. ToCe[To i EQUIPMENT ENVIRONMENTAL QUAllFICAT10N REVIEW OF EQUIPMENT ITEM NO. 33: NRC REQUIREMENTS DEFICZENCY WITH SECTION REFERENCE LIOSEE QUALIFICATION (X OR (DOR /0 588-I/0 5 88-II) SUBMITTAL DOCUMENTATION NOTE No.) ENVIROR 21TAL PROFILE OF ACCIDt.NT CONDITIONS 17 9 Rate of Temp./ Press. !T2.%i4 g! ~ Increase ! Ttf[O[/'**/O te*[27$ 1 Peak

F/psig/RH/ Time

!"/D I otes 12,13 N Decre'ase To: *F/psig/RH/ Time'2es/q[e./4'

F/psig/RH/ Time ! 15 5i[-/see[- !.

Decrease To: Decrease To: *F/psig/RH/ Time ! tu j Equipment Surface Tempera-Not scated ture (MSLB) (-/1.2.5.C,

2. 2. 6/1. 2. 5.C, 2. 2. 6) 1 Spray Qualification Method

!~ (5.3.2/1.3, 2.2.8/1.3, giote 14 est 2.2.8) 1 1 1 ! g.pl. H 00j 1.14w/o boric acid 1 I Spray Composition 3 (4.1.4/1.2, 2.2.8/ ! a,9 w[, goq 0.17 wt: NaOH 1

1. 3, 2. 2. 8)

! p H y gis- !(=4% wp-H) 2 Spray Density (gym /f t ) !Not stated ! Not stated hote 14 1 I Spray Duration !Not stated ! Not stated hace 14 I Submergence Duration !N/A !N/A 1 ( 4.1. 3/2. 2. 5/2. 2. 5) In-Leakage Considered 9(g !N/A ( 5. 2. 6, 5.' 3. 2/-/-) Time to Summergence 4O 1N/A Dust Environment 1N/A g (-/ 2. 2.11/ 2. 2.11) t I

RRC Contract NC. RRC-03-79-118 4[!U Franklin Resetreh Center dO FRC Project N3. C3257 PROPRIETARY Pcq3 ~ A Oheon d The Franiin insatut2 FRC Assigntn:nt N3.13 INFORMATlON 5, 20th and Race Saeets. Phda.. Pa. 19103 (215) 44810m FRC Task N3. W. / Tc; ~7 8 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 3 A i NOTES Note 5 Westinghouse has stated 4-out of-3 RTDs must meet accuracy requirements corresponding to reactor trip (narrow range temperature) and post-accident monitoring (vide-range te=perature) applications. A failure is per=1cted if it is random, i.e., not indicative of co==on mode failure. No rationale was provided for the 2-out of-3 acceptance criteria or technical bases for determining when a failure is not common mode. See related Note (, Note 6 WCAP - 9157 reports accuracy require =ents of t 5%. Testing performed did not provide information on worse case error under design basis accident conditions. Also, the qualification program did not address the ability of the RTDs' time response with respect to primary loop temperature changes and trip points under SL3 conditions. It appears this information is an important consideration for this device. Rosemount specifications on DWG 176KF (Rev E ) states: q l [ l 1 1 l- ~ l l WCAP - 9157 indicated that calculated temperatures based on manufacturer's l resistance tables at the 32'T cali cion-point were not within spedified accuracy (i.e. excyde criterion). Calculated temperatures were I be av thec'alibration te=perature of 32*F. Calibration tempe acures of 725'T and 625'T were not used in the cese program. The Rosemount specification drawings, Dwg. No. 176KF (Rev.J) and 176KS l (Rev state ,/ Oca three 176KF RTDs was not within the repeatability imits during the post l environ = ental test calib.ation at 2500 m. 1

l' NRC Contract N. NRC-03-79-118 P g2 FRC Project Nc.C5257 PROPRIETARY 00 FranklinResearchCenter FRC Assignment No.13 (NFORMATEN 5k . A h of The Frankhn tnatuute FRC Task No. TOC I Tc7 20th and Race Streets. Phde.. Pa. 19103 (215) 448-1M EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIE NtstESs Nate 7 The test described in WCAP 9157 consists of an pitial 24 H t,x}ansiegt. ~ A [. er ture/ pressure decreasing to's taken as equiO11ent to a 13 day seve p2riod'vich t condi ns exposure at ~ (In-cogeainmqt average camperature according to WCAP 9157.) cnvironment xpos e at over a 2 week period fo owingaSL3is{ time is a simple chemical reaction rate The basis for accelerating test (This model is more conservative it.w model given on pg 2-7 of WCAP 9157. il and tempera-than an Arrhenius model based on similat governing mater a s tures) Acceleration of the test interval through inc s(d_t,e g e= eratures for cne temp ratures not usually accg29able for steam exposures.Jand the d.eyices considered 4 duration of[feptabley aq:w.u.qJaftertheinitial24Etransien prest. should be at: L,3,4c w g. $4 -.. <.; M g g 4 = y.4 (e.g.sy Q 4 ~ 4,-d . It %, 'T % W ed Q 4LeeM O ~ v J o e a f m

sy NRC Contract N3. NRC-0 %&gy,, ULd Franklin Research C'nter FRC Project N;. C5257 Pag 3 A DMsaon of The Franklin Insttnas FRC Assignment N3.13 gFORMEON 5 j', 20th and Race streets. Phda.. Pa. 19103 (215) 44810m FRC Task No. To c,/ So 7 EQUIPMENT ENVIRONMENTAL QUAllFICATION REVIEW OF EQUIPMENT ITEM NO. 3 L NOTES: Note 9 Radiation doses for RTDs are based on application. Gamma dose for wide range RCS post-accident monitoring is determined from centerline dose in primary loop (hot lag) piping; narrow ranga reactor trip RTD dose is taken as y surfacegon this piping. [QQ 3.S e ' Note 10 is based on dose rate Qualified life claim in WCAP-9157 ofL J and operating time calculations performed by Westinghouse. Thermal aging has not been included in the qualified life evaluation. See note 15. Note 12 Peak test chamber controlled pressure is stated as 66 psig; however,- no additional oressure data has been provided in WCAP 9157 Facility setup supplies steam at saturated conditions except for i initial transient period where superheating is possible. 100% RH is assu=ed at saturation conditions. t ,i

NRC Contract No. NRC-03 79-118 Prg3 FRC Protect N3. C5257 gIMRY 5j 00 Frr.nklin Rwatch Center FRC Assignment No.13 D A Neon d The Fr.akhn Insuun FRCTask No. %c./Te 20th and Race Sweets. Phoe.. Pa. 19103 (215) 448-1000 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF E Note 13 Actual temperature data was ' Conditions stated are for test profile.This data indicated an overshoc to provided for thef rst 25 S only. cpproximately ~ F at 25 S. ..-) Nor.e .s WCAP 9157 indicates on Spray density and duration are not stated. pg 5-1 that spray can be injected via spray nozzles or main inletNo inform steam piping to test chamber. approach used in this test. Nota 15 Rosemount Dwgs. 176KF and 176KS state that the lead termination Based on the construction of 0 F. area should be limited to 200 the RTD and reactor coolant piping temperatures this temperature Thermal aging of specificationappearstobeeasilyexceeded.bestoranalysis. 7 has not been addressed,bv l component parts O o L e e e w l l l

rerm wntract Ns. NMG-03-79-113 nidin Rmarch Center FRC Project N3. C5257 P g3 A ous.on of The Frankhn Insemuse FRC Assignment N3.1g 3g 20th (nd Rac2 Streets. Phda.. Ps. 19103 (215) 448 1000 FRCTask Nc. 4~d6 /(J7 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.JA LICENSEE RESPONSE ~'ID 'NRC SER GG. The electrical cable splicas used inside containment for safety-related applications were made up in accordance with Sechtel Drawing No. SK-E-165 using Raychem Type SFR heat shrinkable tubing (silicone rubber) as confirmed by Westinghouse letter WEP-78-531 dated June 28, 1978. The environme'ntal qualification tests for these splices were documented in WCAP-7410L. "Ja, environmental tests i luded. hermal aging to the equivalent of jydars, irradiation t and a three w[uek LOCA simulation whic Rads gamma radiation, nelud chemical spray and 100% relative humidity. See Wisconsin Electric's September 11, 1981 letter to Mr. Harold R. Denton concerning response to the PSNP environmental qualification SER (specifically Enclosure 1, Section 3.7) for a further discussion of aging. The chemical spray consisted of a 1.5 weight percent solutten of bcric acid (H,80 ) buffered with sodium hydroxide (NaCli) to a pH value of approximately 9.25. Since all postulated PSNP 3 accident parameters are enreloced by the test profiles, the splices are considered fully qualified to the 00R Guidelines. e 4 ~ ~ "

1 l NRC Conhet N3. NRC 43 79-118 ~ ^ 00 Fr:nklin Research C:nter FRC Project No.C5257 PROPRIETARY Paga FRCTask No. Fd a /re NFORMATIO FRC A0signment Nc.13 I 5b A DMeson of The Franklininsatute 20st and Race Streets. Phde.. Pa. 19103 (215) 448 1000 y EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 3f-NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588 './0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) 1 1 1 Acceptance Criteria g 1 gg 1, 4 1 (5.2.5/2.2.1/2.2.1) l ( M/[/ 1 Accuracy (5.3.5/-/-) j j Number of Specimens /T 1 Test Instruments Calibrated W 1 O 1 / i Safety Function (Active / MM 1 / Passive) (-/2.1.3/2.1.3) 1 3 Test Duration (5.2.1/-/-) Y p p g(, Accident Duration (Envir. 1 1 1 Above Normal) (5.2.1/-/-) [ i Required Function Time ./ Test Sequence (General) g l ( 5. 2. 3/2. 3.1/ 2. 3.1) "T Test Sequence (NUREG-0588, Cat. I) (-/ 2. 3.1/-) Q pg._m-O."'! (

l. Representative Sample I

1

2. Baseline Data 1

1

3. Performance Extremes

4. Thermal Aging 1

1 1 l S. Radiation Aging

6. Wear Aging 1

1 1

7. Vibration / Seismic

8. DBE Exposure

9. Post-DBE Exposure

10. Inspection j

M f Aging 1 1 ! IM.4 'g gy ! l (5.2.4, 7.0/4.0/4.0) 1 Thermal Aging / Basis ( .L P. -! 1 Material Aging 1 v4 Qg Evaluation (7.0/-/-) ( k h Materials Susceptitic l (Thermal) (5. 2. 4, 7.0/-/-) O 1 [V4 - 1 Radiation Aging, Type 1 1 ____m v-- I

NRC Contract N3. NRC 03-TB-118 P:ge FRCProjectN2.C5257 PROPRIETARY 00 FranklinResearchCenter FRC Assignment No.13tNFORMAT10N Sc ' A DMeon of The Frankhn inanute 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRC Task No. fab / Td-7 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW DEFICIENCY (X OR NRC REQUIPJHENTS QUALIFICATION LICENSEE NOTE NO.)_ WITH SECTION RE"ERENCE DOCUMENTATION SUBMITTAL (DOR /0588-I/0588-II) e. af SMg/ f { Radiction Aging, Dose (rd) Radiation Aging, Dose Rate Radiation Aging, Method \\) 1 Matsrials susceptible (Radiation) (5.2.4, 7.0/-/-) ! 1 Oparational Aging (-/4.2/-) . \\[ 1 Oth2r Age Conditioning 1 1 (-/ 4. 2/-) 3 I I Qunlified Life Claimed / ! //d M j Established (5.2.4/4.10/-) A/af578 y/4 1 Nntmal Ambient Temperature 1 d f Normal Amoient Radiation 1 Normal Ambient Humidity (7.0/-/-) !((f gg ! On-Going Surveillance and Pr0ventive Maintenance 7' On-Going Analysis of V Failures and Degradation 1 (7.0/-/-) 1 1 Margin (General) j$. 1 1 1 (6.0/3.0/3.0) k k Margin (NUREG-0588, Cat. I) (-/3.2/-)

1. Temperature (+1S*F) 1

2. Pressure (+10%,

l 1 10 psig max) 'I

3. Radiation

/ { \\/ (not required)

4. Time (+10%, +1 hour

+ function time minimum)

4 NRC Contract N3. NRC 03 79-118 UUUU Fr::nklin R:setrch Center FRC Project No.C5257 PROPRIETARY Pag) A Dive of The Frankhn Inesuuss FRC Ansignment N2.13 JNFORMATION 5d 20th cnd Racs Serests. Phde. Pa. 19103 (215) 448-1000 FRC Task No. 0 e/Tb""7 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _J NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCI.MENTATICN NOTE NO.) ACCIDENT CONDITIONS 1 IDCA/MSLB/HIlLB/ Uncontrolled (4.1, 4.2, 4.3.1, 4.3.3/ ! LOC) ! /_, C(, jg-1.1, 1. 2, 1. 5/1.1, 1. 2, 1. 5) ! Radiation Type 1' 1 _f ___m 1 y Radiation Dose (rd) 71 1 !* b/# ( 4.1. 2/1. 4/1. 4) ,A Radiation Dose Rate (rd/hr) 1 4k 2W l Radiation Qual. Method 1 (5.3.1/-/-) !y l 1 1 Proximity to Concentrated Radiation // [ l ( 4.1. 2/1. 4. 6/1. 4. 6) l 1 Equipment Susceptible to Beta Radiation (4.1.2/-/-) f I I g Radiation Dose (Normal + 1 Accident) (4.1.2/-/-) 1 1 1 0 Plateout Dose Considered (-/1. 48/1. 48) 1 1 1-Ganna + Beta Dose (rd) (4.1.2/1.4.7/1.4.7) V l i l l l

l ~ NRC Contract No. NRC-0;h79-118 4000U Franklin Reseach Ccnter FRC Project N3. C5257 r'NOPRIEIAft y Paga FRC Assignment No.1dNFORMATl0N 5e A Den of The Franan Insattute 20th and Race Streets. Phita. Pa. 19103 (215) 448-!M FRC Task No. Te & / FJ 7 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO DEFICIENCY NRC REQUIREMENTS WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE No.) ENVIRONMENTAL PROFILE 1 1 ~ OF ACCIDENT CONDITIONS j p g4 Rate of Temp./ Press. Increase s 0 0 Park: 'F/psig/RH/ Time !.t*rr[f"3 -f/***1 Decrease To: 'F/psig/RH/ Time !(22 c l 1 Decrease To: 'F/psig/RH/ Time p-C-F~ Decrease To 'F/psig/RH/ Time ! Equipment Surface Tempera- / 2 ' g# g. ture (MSLB) (-/1. 2. 5. C, 2.2.6/1.2.5.C, 2.2.6) 1 Spray Qualification Method (5.3.2/1.3,.2.2.8/1.3, 2.2.8) N ut n 14 22 / N 1.3, 2.2.8) I I Y 3-e ff tpyrrS 7j./..,, 7* : 2 Spray Density (gpm/f t 3 g ! Nof S'-/ A.V M ! [M Syay Duration l f1 Submergence Duration 8 1 (4.1.3/2.2.5/2.2.5) ) In-Leakage Considered (5.2.6, 5.3.2/-/-) Time to Submergence l I } Dust Environment (/ (-/2. 2.11/2. 2.11) 0

1 NRC Contract N3. NRC 03-79-118 ldj Fr::nklin Research Ccnter FRC Project No.C5257 P:ga FRC Assignm:nt N2.13 3a A bison of The FrankhnInumwe 20m and Race Seems. Phsa.. Pa.19103 (215) 4481000 FRC Task No. J"o G/fo 7 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT I LICENSEE RESPONSE TO NRC SER The temperature profiles for the specification and the qualification H. test are essentially equal. The specification temperature was computed using extremely conservative assumptions. The highest possible superheat temperature from a steam leak at the highest secondary p* essure was calculated for the peak temperature. This also assumed no cooling by I the surrounding air or equipment and that a jet of steam impinges The test temperature,durdng qualf-directly on the affected equipment. fication was saintained for a much longer duration than the duration of Therefore, peak temperature from a staas line break outside containment. the internal tasperatures of the equipment being tasted (e.g., valve i entor operators) reached higher levels during qualification testing l than that which could result from a short-duration steam ifne break accident. Electrical cables are run in conduits near high energy ifnes so that direct steam impingement on cables is impossible. Therefore, the temperature profile of the test is considered adequata to qualify the equipment to the specification tasperature profile. l i The Limitorque Model SM8 valve motor operators inside containment (or V. near a high energy line outside containment) have either Rolf ance or Peerless motors with Class 8 insulation. Generic environmental tests on these operators are documented in Westinghouse WCAP-7410L and Limitorque Test Report No. 80"03 (Qualification References 18 and 168, respectively). The tests included thermal aging to the equivalent of greater than 40 years at an annient tamperature of 40*C (104'F) assuming the "10*C Rule." All safety-related valve operators inside containment are located outside the primarf shield walls where the ascient tamcer-atures during operation are maintained by design at less than 105"F and by experience at less than 100*F. Safety-related valve operators in the aumf11ary building outside containment have ascient tamperatures The qualification tasts also which are maintained bet 1reen 65 and 85'F. included mechanical and vibration aging. The potantial for unexoected j degradation due to aging is addressed by periodic inspections, electrical i tests, and sechanicai tests. Periodic maintanance keeps these valve operators in an "as now" condition over their 40 year qualified life. See Wisconsin Electric's Septanner u,1981 letter to Mr. Harold R. Denton i concerning reponse to the environmental qualification SER (specifically ., Section 3.7) for a further discussion of aging. l The tests doc:ssented by WCAP-7410L included irradiatipof both Reliance and Peerless motors with Class 8 insulation tal gRads gamma. The tests documented by Test Recort No. 80003 incib6ed irradiation of g Rads Reliance sotors with Class 8 insulation to greater than 2 x 10 gamme and irradiation of the coerators including the gearey 1f ait switches, torque switches, seals, and f uericants to 2 x 10. Rads gamma. l ~ " " " ' ' ~ " ~ -

p NRC Contract N2. NRC 03-79-118 OU Frr,nklin Research Center FRC Project No.CS257 P:ga A pvmon of The Frankhn inemWe FRC Assignment No.13 3b Xhh and Race Seese. Phas.. Pa. 19103(215) 448-1000 FRCTask No. Sofo/5d7 EQUIPMENT ENVIRONMENTAL QUAUFICATION REVIEW OF EQUIPMENT ITEM NO.En I LICENSEE RESPONSE '!O NRC SER (Continued) The operators were successfully.$asted for LOCA conditions inside l containment for a duration of JhoursasdocumentedinWCAP-7410L. The test included chemical sp ay with a 1.5 weight precaint solution of T i beric ?cid (H 80,) buffered to a pH of 7.85 with sodium hydroxide 3 ( (NaOH). The pH Ts at the bottom of the pH range specified. The short required operating time of the units (maximum of 14 hours and usually l only 30 minutas) would not allow a slightly higher pH solution to l significantly increase the chemical corrosion of the units over that solution which was used in the test. The boric acid concentration was much higher in the test than that required for PSNP. The specified tamperature and pressure profiles were both enveloped by the tast profit operators were tastad successfully periodically through-out th urs of testing. The ra were exposed to saturated steam a sig for an additional after which they failed to operate p erly. The cause of failu was analyzed and datarsined to be the entry of chemical spray into the unit through the motor lead cutouts. The motor lead cutouts are sealed at PSNP with flexible conduit and associated fittings. Although these fittings have not been qualified, their design indicatas that no significant amounts of chemical spray could entar the units via this path. In addition, the tests documented by Test Report 80003 demonstrata that the units can survive a saturated staan environment at 10 psig for at least 16 days. This demonstratas their qualification for operation in 1005 relative humidity and steam for long periods of time. The valve operators wev1d therefore be considered qualified for an operating time of 24 hours following a design basis accident except as limited by the radiation qualification of the operator. The qualified level of radiation integrated dose 7 postulated for the PSNP containment reach 2 x 10 Rads at approximately 12 hours following a design-easts accident. Therefore, these valve operators are considered qualified for a maximum operating time of 12 hours in a LOCA or HELB environment inside containment. In conclusion, these Limitorque valve operators are considered qualified for LOCA or HEL8 envir9nments inside containment, 100% relative humidity, i chemical spray, 2 x it. Rads gamma radiation, a 40 year lifetime, and l an operating time following an accident of 12 hours. O e M e 6 .n ,... ~,.- - ~ ~ -, ---,a

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I NRC Csntr ct No. NRC-03 79-118 00J Frsnklin Rzserrch Canter FRCProjectNo.C5257 PROPRIETARY Pags a onn on d The Frsnkhn insntuts FRC Assignmtnt No.131NFORMATION 5g 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000 FRCTask No. Sad /5o' 7 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.d!E. NOTES: so4 em ces,d>,ael n l During the past 18 years, few operating problens have been ex- 'perienced because of inadequate radiation resistance of lubri-t cants. In irradiated zones, factors other than radiation levels, 'such as elevated temperatures, moisture or ozone are almost al ways the limiting factors. Conventional petroleum based lubri-l ' cants are available which "have sufficient radiation resistance to tubricate mechanisms subject to radiation under almost all opera-ting conditions in CANDU generating stations;# rhe L; ensee d, d nd da, -n. / s4 1,-./m. d he /m /A 4 r/- d i / Abi.-am/ and M/,, r,4,./ iA M in 4 //.,/ e su,a-i,/rl.r. 2 - een- - s o /c i.,,,,.e-x. xe., a & g. A A 4,4,L. y a a,.~,,s J / e m>Jo'ee / si /fe Ars/a /4 e/- eu.u,*m,in / eaaaffan//r i/m av,, A 8 m- " J / _ raf/r d ' A _r b s - n as b / A k%*.122 9. J/3Aa //A* ma/J Ad/ A8 Ar-s v ,2df e l t*Ynose 1A >>en" PrI*.@Af t*kal/*e3 2

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R NRC Contract N3. NRC 03-79118 Paga 4 FRC Project N2.C5257 000U Franklin Research Center FRC Assignment NO.13 3a A Devmon of The Franan insmute FRCTask Nr. Sc6/ro7 20th and Race Streets. Phda. Pa.19103 (215) 4481000 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMEN LICENSEE RESPONSE TO NRC SER The tamperature profiles for the specification and the qualification H. tast are essentially equal. The specification tamperature was c:mputed using axtremely conservative assumptions. The highest possible sucerneat temperature frsa a staas leak at the hfgnest secondary pressure was This also assumed no cooling by calculated for the peak tancerature. the surrounding air or equipment and that a jet of stans f acinges The test tancerature during quali-directly on the affected equipment. fication was saintained for a such icager curation than tne duration Jf Therefore, peak temocrature from a staan line break cutside containment.the int motor operators) reached higher levels during qualification tasting than that which c:uld result from a short-duration steam line treak Elect.ical cabier are run in conduits near nigh energy lines accident. Therefore, so that direct staas facingement on cacias is faccssible. the tancerature profile of the tas. *s c:nsicered adequate to qualify the equipment ta the specification tamperature profile, I V. The Limitorque Model SMS valve notar operstars inside containment (or near a high energy ifne outside esntainment) Nave either Reif ance or Peerless actars with Class 8 insulation. Generic environmental tests on these operators are documented in Vestinghouse wCAP-7410L and Limit:rque Test Report No. 90003 (Qualification References 13 and 158, respectively). The tests included thersal aging to the equivalent of greatar than 40 years at an ancient tascerature of a0*C (134*F) aasuming the "10*C Rule.' All safety-estated valve operators inside c:ntainment are located outside the primarf shield walls where the amef ent tameer-atures during c:eration are maintained my design at less than 105'F and by experience at less than ICC'F. Safety-elated vafve operators in the auxiliary tutiding outside containment have ameient tanceratures which are saintained tet een 65 and a5'F. The qualification tests also included sechanical and vibration aging. The potantial for unexeected degradation due to aging is addressed by periodic inspec*.fons, siectrical r tests, and sechanicai tasts. Periodic saintenance keecs these valve operatsrs in an *as now" c ndition over their 40 year qualiff ed life. See Wisconsin Electric's Septascer 11, 1981 Tottar ts Mr. Marold R. :enten concerning recense to the environmental qualification SER (scocifically t, kction 3.7) for a further discussion of aging. The tests doc.sented my WCAP-7410L included f etadiati of both Reliance and Peerless actors with Class 3 insulation tos Racs gamma. The L tasts documented ty Test ReDort No. 90003 incit: cec irrelciation cf Reliance motors with Class 8 insulation to greater than 2 x 10" Rads gamma and irradiation of the ocerators inc!uding the gearey finit switches, torque switches, seals, anc luericants to 2 x 10 Rads gansa. I

4 NRC Contract No. NRC 03 79-118 UUUU Frankhn Rtsearch Ccnter FRC Project No. C5257 Piga M Dhmon of fhe Frmahn inan* FRC A:signmcnt No.13 Tb 3hh and Race Seeses. Phde.. Pa.19103 (215) 448-1000 FRCTask No. 50G /Sa 7 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.,ff I LICENSEE RESPONSE '!O NRC SER (Continued) The operators wre successful 4estad for LOCA conditions inside containment for a duration of purs as cocumented in WCAP-7410L. The test inclueed chemical with a 1.5 weignt procent solution of boric acid (H.80 ) buffered to a pH of 7.85 wie sodium hydroxide 3 i (MaOH). The $H Ts at the bottom of ce pH range specifled. The short required operating time of the units (saximum of 14 hours and usually only 30 minutas) would not allow a slightly higher pH solution to significantly inc ease the chemical ccrresion of the units over that solution wnich was used in the test. The boric acid concentration was i much higner in the test can that required for PSNP. The specified tamperature and pressure profiles were bou enveloped by the test profilear e coarstars were tasted sue:essfully periodical.ly througn-out the~ urs of testing. The.oe ators were exposee to saturated N sig for an adattional days after which they failed to l steam a operate reperly. Thecauseoftk.e 11ure was analyzed and catarsined to be the entry of. chemical spray into the unit through me motor lead cutouts. The motor lead cutouts are sealed at PSMP with flexible conduit and associated fittings. Although these fittings have not been qualified, their design indicatas that no significant amounts of chemical spray could entar the unita via this path. In addition, the tests docuented by Test Report 50003 demonstrata that the units can survive - a saturated staes environment at 10 psig for at least 18 days. This demonstratri their qualification for operation in 10C5 relative humidity and s*.sas for long periods of time. The valve operators would therefore be considered oualifted for an operating time of 24 hours following a design basis accident ascept as Itaited by the radiation qualification of the oDerstor. The qualified level of radiation integrated dose 7 postulated for the PSNP containment reaches 2 x 10 Rads at accroximately 12 hours following a design-tasis accident. Therefore, these valve operators are considered qualified for a maxiom operating time of 12 hours in a LOCA or MEL5 environment inside containment. l In conclusion, these Limitorque valve operstars are considered qualified for LDCA or HEL5 enviryments inside containment,10c5 rotative busioity, 1 chemical spray, 2 x 10 Rads gassa radiation, a 40 year lifetime, and an operating time following an accident of 12 hours. e 4 h } _ - - _ _ _ -. = = ~ = =

NRC Contract No. NRC-03-79-118 4 FRC Project No. C5257 PROPRIETARY Pags 000U Franklin Research Center FRC Assignmcnt No.13 (NFORMATION 5g 4 % a TheFr.akimin.neuis 20th and Race Sweets. PMs.. Pa. 19103 (215) 44s,1000 FRCTask No. Sad /So' 7 a EQUIPMENT ENVIRONMENTAL CllALIFICATION REVIEW OF EQUIPMENT ITEM NO.i( O NOTES: sah m cos,dn*J During the past 18 years, few operating problens have been ex-

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A NRC Contract Nr. NRC-03-79-118 U000 Fr:nkan Research Center FRCProjectND C5257 P:g3 Apwwon of The FrankhnInema FRC Assignm:nt N3.13 3a 20pi and Race Seests. Phde.. Pa.19103 (21514481000 FRC Task No. 5O(. / 50V EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO..(a.l LICENSEE RESPONSE TO NRC SER W The Limitorque Model SM8 valve motor operators inside containment (or near a high energy line outside containment) have either Reliance or Peerless actors with Class 8 insulation. Generic environmental tests on these operators are documented in Westinghouse WCAP-7410L and Limitorque Test Report No. 80003 (Qualification References 18 and 168, respectively). The tests included thermal aging to the equivalent of i greater than 40 years at an ambient temperature of 40*C (104*F) assuming the "10*C Aule." All safety-related valve operators inside containment are located outside the primary snield walls where the ambient temoer-atures during operation are maintained by design at less than 10S*F and by experience at less than 100*F. Safety-related valve operators in the auxiliary building outside containment have ancient temperatures which are maintained between 65 and 85'F. The qualification tests also i included sechanical and vibration aging. The potential for unexoected degradation due to aging is addressed by periodic inspections, electrical tests, and mechanicai tests. Periodic maintenance keeps these valve operators in an "as new" condition over their 40 year qualified life. See Wisconsin Electric's September 11, 1981 letter to Mr. Harold R. Denton i concerning reponse to the environmental qualification SER (specifically j, Section 3.7) for a further discussion of aging. l The tests documented by WCAP-7410L included irr.adiati of both Reliance and Peerless motors with Class 8 insulation to ads gassaa. The testsdocumentedbyTestReportNo.80003inc1buedirradiationof Reliance actors with Class 8 insulation to greater than 2 x 108 Rads gamma and irradiation of the operators including the gearey Ifmit switches, torque switches, seals, and lubricants to 2 x 10. Rads gamma. The operators were successful.1x 1pstad for LOCA conditions inside containment for a duration off fours as documented in WCAP-7410L. The test included chemical sifeby with a 1.5 weight precent solution of boric acid (H 80 ) buffered to a pH of 7.85 with sodium hydroxide (NaOH). ThehHTsatthebottomofthepHrangespecifled. The short 3 required operating time of the units (maximum of 14 hours and usually only 20 minutes) would not allow a slightly higher pH solution to significantly increase the chemical corrosion of the units over th.?t salution wnich was used in the test. The boric acid concentration was such higher in the test than that required for P8NP. The specified temperature and pressure profiles were both enveloped by the test profile 4 e operators were tested successfully periodically through-I out th / ours of testing. The ators were exposed to saturated psig for an additional,gp steam a days after which they failed to operate properly. The cause of the ilure was analyzed and determined to be the entry of chemical spray into the unit through the motor lead cutouts. The motor lead cutouts are sealed at P8HP with flexible conduit and associated fittings. Although these fittings have not been qualified, their design indicates that no significant amounts of chemical spray could enter the units via this path. In additioni the tests documented by Test Report *80003 demonstrate that the units can survive a saturated steam environment at 10 psig for at least 16 days. This demonstrates their qualification for operation in 10C% relative humidity ' and steam for long periods of time. The valve operators would therefore be considered qualified for an operating time of 24 hours following a design basis accident except as Ifmited by the radiation qualification of the operator. The qualified level of radiation integrated dose /

NRC Contract N2. NRC-03-79118 00 Fr:nklin Research Ccnter FRC Project N2. C5257 Paga A Dimsson of The Frankhn Insutute FRC Assignment N2.13 3h 20th and Rao Streets. Phda,. Pa. 19103 (215) 448-1000 FRC Task N2. EO(o/507 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO..(2.L LICENSEE RESPONSE 'IO NRC SER (Continued) 7 postulated for the PSNP containment reaches 2 x 10 Rads at approximately 12 hours following a design-basis accident. Therefore, these valve operators art considered qualified for a maximus operating time of 12 hours in a LOCA or HELS environment inside containment. In conclusion, these Limitorque valve operators art considered qualified for LOCA or HELS envirynsents inside contatraent,10C% relative humidity, chemical so-ay, 2 x 10 Rads gamma radiation, a 40 year lifetime, and an operating time following an accident of 12 hours. J X. These valves are used to asstst in placing the plant in a cold shutdewn condition via the RHR cooling mode. Since the PSNP was'not Ifeensed to requirt reaching cold shutdcwn folicwing a design basis event, the RHR systam and these valves are not safety-related. As ciscussed in Note V, these valves would be qualified to cperate for 24 hours following a designpasis accident except for the radiation qualification level of x 10 44 ads on the cperator itself. The motors are qualified to Rads. Since the specified radiation dose dcas not take credit for shi~e'Iding (see General Note 5) and the operators art outside the primary snield, these operators could unty experience a postulated dose reduced by a factor of approximataly 2.7 by the snielq (see WCAP-8587, e

p. 5-6).

The unynf elded radiation at 24 hours follcung a postu}ated LOCA is 2.7 x 10 Rads. The shielded dose at 24 hours of 1 x 10 Rads 7 is well within the operator's qualification len1 of 2 x 10 Racs. Therefort, these coerators are considered qualf'fied for an operating time of 24 ho rs following a design-casts acef det. 1 l 1 --,~

V i hEranklin Research Ce PRC Project N;.C5257 3a FRC Assignment No.13 [6Of A owwon of The Frenianlamewe FRC Task Nc. SC/n 20m and Race Seveu. Phde.. Pa.19103 (215) 4481000 EQU1PMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. LICENSEE RESPONSE TO NRC SER ___ _._ V. The Limitorque Model SMB valve motor operators inside containment (or near a high energy line outside containment) have either Reliance or Peerless motors with Class 8 insulation. Generic environmental tests on these operators are documented in Westinghouse WCAP-7410L and Limitorque Test Report No. 80003 (Qualification References 18 and 168, respectively). The tests included thermal aging to the equivalent of greater than 40 years at an ancient temperature of 40*C (104*F) assuming the "10*C Rule." All safety-related valve operators inside containment are located outside the primary shiel'd walls where the ambient temoer-atures during operation are maintained by design at less than 10$'F and by experience at less than 100*F. Safety-related valve operators in the auxiliary building outside containment have ambient temperatures-which are maintained between 65 and 85'F. The qualification tests also l included mechanical and vibration aging. The potential for unexoected degradation due to aging is addressed by periodic insoections, electrical tests, and mechanical tests. Periodic maintenance keeps these valve operators in an "as now" condition over their 40 year qualified Iffe. See Wisconsin E'.actric's September 11, 1981 letter to Mr. Harold R. Denton concerning reponse to the environmental qualification SER (specifically, Section 3.7) for a further discussion of aging. The tests documented by WCAP-7410L included i iatip9 of both Reifance and Peerless motors with Class 8 insul'ation to _J Rads gamma. The tasts documented by Test Report No. 80003 included irradiation er g Rads Reliance motors with Class 8 insulation to greater than 2 x 10 games and irradiation of the operators including the geare9 Ifmit switches, torque switches, seals, and lubricants to 2 x 10. Rads gamma. The operators were successfu1]y., tested for LOCA conditions inside containment for a duration ofy hours as documented in WCAP-7410L. The test included chemical spray with a 1.5 weignt precent solution of l l boric acid (H 80,) buffered to a pH of 7.85 with sodium hydroxide 3 The short The pH Ts at the bottaa of the pH range specified. j j (MaOH). required operating time of the units (maximum of 14 hours and usually l only 30 minutas) would not allow a slightly higner pH solution to j significantly increase the chemical corrosion of the units over that solution which was used in the test. The boric acid contentration was such higher in the test than that required for PSNP. The specified tamperature and pressure profiles were both enveloped by the test profiles..)The operators were tastad successfully periodically tnrougn-out thef. ours of tasting. The o ators were exoosed to saturateo steem atEpsig for an additiona1{p days after wnich they failed to e The cause of tNe 11ure was analyzed and determined r operate properly. to be the entty of. chemical spray into the unit through the motor lead r The motor lead cutouts are sealed at P9NP with flexible F cutouts. Although these fittings have not been conduit and associated fittings'. qualified, their design indicatas that no significant amounts of chemical lr In addition, the tests ( spray could enter the units via this path. documented by Test Report 80003 demonstrata that the units can survive This a saturated steam environment at 10 psig for at least 15 days. demonstratas their qualification for operation in 100% relative humidity and steam for long periods of time. The valve operators would therefore be considered qualified for an operating time of 24 hours following a design basis accident except as ifmited by the radiation qualification of tne operator. The qualified level of radiation integrated dose g gr -s % L,_

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NRC(cRntreGiNO. rerverw-s s. Pag 3 FRC Project N2.C5257 3b Lg Frrnklin Research C:nter FRC Assignm ntN3.13i A om of The FrankkInwause FRCTaskNo. 506 ISO 7-1 20th and Race seeses. Phde.. Pa.19103 (215) 4e81000 EQUIPMENT ENVIRONMENTAL QUALIFICATION R LICENSEE RESPONSE TO NRC SER (Continued) i 7 Rads at approximately postulated for the P6MP containment reaches 2 x 10Therefore, these valve 12 hours following a design-Dasis accident. operators are considered qualified for a maximum operating time of 12 hours in a 1.0CA or HEl.8 environment inside containment. In conclusion, t'.nese Limit?rque valve operators are co Rads gamma radiation, a 40 year If fetime, and chemical spray, 2 x 10 an operating time following an accident of 12 hours. These valves are used to assist in the prevention'of bo W.- As discussed in Note V, these valves"would be qualified to operate for 24 hours following a designgasis accident excepe-for an accident. x inw Rads on the operator the radiation qualification level of I Rads. Since the specified itsel f. The motors are qualified t or shiO ding (see General Note 5) radiation dose does not take credit and the operatars are outside the primary shield, these operators could only experience a postula.ted dose reduced by a factor of approximately [ The unshield9d radiation 2.7 by the shield (see WCAP-8587, p. 6-8). dose at 14 hours U Rads. The shielded. dose at 24 hours of ) x 10 Terefore, these coerators are Rads. qualification level of 2 x 10 considered qualified for an oper: tin; *ima of design basis accident.' [ 3 B 'O .I l 1 3

8 - 1 NRC Contract N2. NRC-03 79-118 . D Franklin Research Center FRCProjectN3.C5257 PROPRIETARY P g3 A'h ed The FrosiniIrumans FRC Assignment N2.13,'NFORMATION Si aan ad nace se.eu. PMe.. Pa.19103 WS 4481000 FRC Task No. Ed/e/S04 EQUIPMENT ENVIRONMENTAL QUAUFICATION REVIEW OF EQUIPMENT ITEM NO. 3L

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NRC Contract NO. NRC-03-79-118 P 00J Franklin Research Ccnter FRC Project No.C5257 P ga A Dndon of The Frankan Instnute FRC Asignrn:nt N3.13 3a . 20th and Race Sesets. Phda.. Pa. 19103(215) 448 1000 FRC Task No. 6d(o DY-g r EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. fc.3 1 i i LICENSEE RESPONSE TO NRC SER l V. The 1.f attorque Model SM8 valve motor operators inside containment (or near a high ensrgy line outside containment) have either Reliance or Peerless motors with Class S insulation. Generic environmental tests on these operators are documented in Westinghouse WCAP-7410L and Limitorque Test Report No. 80003 (Qua'ification References 13 and 158, respectively). The tasts included thermal aging to the equivalent of greatar than 40 years at an ameient temperature of 40'C (104'F) assuming j the "10'C Rule." All safety-related valve operators inside containment are located outside the primary snield walls where the ambient temper-atures during operatic. are maintained by design at less than 105'F and by experience at less than 100'F. Safety-relatad valve operators in the auxiliary building outside containment have amoient temperatures which are maintained between 65 and 85'F. The qualification tasts also included mechanical and vibration aging. The potantial for unexceeted degradation due to aging is addressed by periodic inspections, electrical tests, and mechanicai tasts. Periodic maintenance keeps these valve operators in an 'as new" condition over their 40 year qualified life. see Wisconsin Electric's September 11, 1981 letter t-c Hr. Harold R. Denton concerning reponse to the environmental qualification SER (specifically ', Section 3.7) fpr a further discussion of.ging. The tests documented by WCAP-7410L included i atfer! of both Reliance and Peerless motors with Class 8 insulation to Rads gama. The tasts documented by Test Report No. 80003 inclu ed fr Mdiation af 3 Reliance motors with Class 8 insulation to greater than 2 x 10 Rads i gasuna and irradiation of the operators including the geareg limit switches, torque switches, seals, and lucricants to 2 x 10. Rads gamma. The operators were successfu1%f,astad for 1.0CA conditions inside containment for a duration of JhoursasdocumentedinWCAP-7410L. Y The test included chemical sp ay with a 1.5 weignt precent solution of F l boric acid (H S0,) buffered to a pH of 7.85 with sodium hydroxide c j (NaOH). The hH Ts at the bottom of the pH range specified. The short required f.,cerating time of the units (maximum of 14 hours and usually c only 30 minutas) would not allow a sligntly higher pH solution to e significantly increase the chemical corrosion of the units over that 5 solution which was used in the test. The boric acid concentration was 5 much higher in the tast than that required for PBNP. The specified tamperature and pressure profiles were both enveloped by the test j profiles e operators were tastad successfully periccically through-out th ours of testing. The ators were exposed to saturated staan a psig for an additional days after wnich they failed to operata properly. The cause of 11ure was analyzed and datarnined i to be the entry of chemical spray into the unit through the motor lead n-cutouts. The motor lead cutouts are sealed at PBNP with flexible I conduit and associated fittings. Although these fittings have not been g qualified, their design indicatas that no significant amounts of chemical 2 spray could entar the units via this path. In addition, the tests p documented by Test Report B0003 demonstrata that the units can survive c: a saturated staam environment at 10 psig for at least 15 days. This demonstratas their qualification for operation in 100% relative humidity and steam for long periods of time. The valve o tors would therefore be considered qualified for an operating time of hours following a design basis accident except as limited by the rad tion cualification 3 of the operator. The qualified level of radiation integra*ad dose I n s bo

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NRC Contract N3. NRC-Obi-118 @Ohrgnklin Ressarch Center U FRC Project No.C5257 Pag] A Divmon of The Frankhn leanute FRC Assignment NO.13 30 20th and Race Streets. Phila.. Pa.19103 r2iG e431000 FRC Task No. SCG/Eo7 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. la.4 LICENSEE RESPONSE TO NRC SER U. The Limitorque Model SMS valve motor operators outside containment at Point Beach Nuclear Plant have either Reliance or Peerless motors with Class 8 insulation. Generic environmental tests on these operators are documented in Westinghouse WCAP-7410L and Limitorque Test Report No. S0003 (Qualification References la and 168, respectively). = The tests included thermal aging to the 6cuivalent of greater than 40 years at an amoient tamperature of 40*C (104*F) assuming the "10*C Rule." The tasts also included mechanical and vibration aging. The potantial for unexceeted degradation due to aging is addressed by periodic inspections, electrical tests, and mechanical tests. Periodic l maintanarca keeps these valve operators in an "as new" condition over their 40 year qualified life. See Wisconsin Electric's Septancer 11, 1981 lettar to Mr. Harold R.' Oenton concerning response to the PSNP environ-mental cualification SER (specifically Enclosure 1, Section 3.7) for a further discussion of aging. The tasts doct.sented by WCAP-7'410L included irnadiat' of both Reliance I and Peerless actors with Class S insulation to ads gamma. The f tests documented by Report No. 80003 included Madiagion of Reliance motors with C' ass 8 insulation to greater than 2.x 10 Rads gamma and irradiation of the operators including gepred limit switches, torque switt.hes, seals, and lubricants to 2 x 10 Rads gam:na. The operators were successfully fastad for LOCA conditions inside hours (documented in VCAP-7410L) and containment for a duration afg, for MELS conditions outside cont:inment for a duration of 16 days (documented by Test Report 80003). The qualification of these valve l operators for 10C". relative humidity is demonstrated b 9e successful tests in saturated staa:s at elevated tamperatures fo ours in one test and 16 hours in another test. l Therefore, these Limitorque valve operators fre considered generically l qualified for 10C". relative humidity, 2 x 10 Rads ga=ma radiation, ane a 40 year lif etime. $1nce these valve operators have succassfully operated for years in their normal environment and since elevated tamperatures and high humidity are not expected in the auxiliary building where these operators are located, the operators are judged to be qualified for a sinimum operating time of one year.

.'l!MC' Contract No.rmv veiv us mO FRC Project N2.C5257 PROPRIETARY Page B00J Fr:nklin Research Center FRC Assignment N7.13[I ggggy $g t A owon or m Frankhniniature 20th and Rue 5:eets. Phde.. Pa 19103(215) 44s.tmo FRCTask N:D. SOla EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQU t NOTES: 1A w-DA21-12s i WYs!!A lk YA > r} sb. 22) f j /rL Y0 U /AA 0 2La )) )> J k )f2Y/. f a\\ V' Ai OJu'JL,','N ^ o, m a % % !L eto d % -t o m _osk,b,iA: i I [/'II;:C.N >M C Ar ( E # #^- Y [ 6ASI5 _ T-m Pm A et2O F T t M c' elsa 40.JG u t-M C AJ E .e CEAeEb t. i m i-r ' su irrA I Mo ra r TCN1Q tlG 3 wh t-Ctr4 _ dom PLCT1-L4 Assowatrh h i MOVE OPG(? ATioM A L MVA C IPCket( cAo k f-u.nM O u aos d i s c. b oe bra.ke / t.c.m, wt, f,,h L , vu,:=ri ma ras-ewe m a = < <- t -r, ~.s com m,cor me:i'Fbos*/RH-[ xop mvA 4 1 u-t-j e9. P, 6 NI 6h ~,A A,Nk Juli vijua M w-s, f*T m [ ,m o uJos. ffSR A 43% ~ o '&i_ <uasU dmv" h,, E,w bb so ( a AAMin r ~ 9 Lwas. wh> ,x PM '6 m % ~ d '&n D m 0 Nu a su id Ji} n,abA L,,3 ~ w h, .is LA J% os M i l n -JA d,L 0 w eu d l

v-3g FRC Assignment No.13 j SO0 AM A Owsion of The Frankhn Inveuse f 20m and Race Sweets. PMe. Pa. 19103 (215) 448 1000 FRC Task N3. EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIE LICENSEE RESPONSE 'IO NRC SER The 1.initorque Hodel SM8 valve motor operators inside containment (or near a high energy line outside containment) have either Reliance or V. Peerless motors with Class 8 insulation. Generic environmental tests on these operators are doetanented in Westinghouse WCAP-7410L and Limitorque Test Report No. 80003 (Qualification References 13 and 163, The tests i;ncluded thermal aging to the equivalent of respectively). greater than 40 years at art ancient temoerature of 40*C (104*F) assuming All safe 1!y-related valve operators inside containment the "10*C Rule." are located outside the primar/ shield walls where the amoient temaer-atures during operation are maintained by design at less than 105'F and Safety-related valve operators in by experience at less than 100*F. the auxiliary building outside containment have ancient temperaturesThe qualif wnica are maintained between 65 and 85'F. The potantial for unexoected included sechanical and vibration aging. l degradation due to aging is addressed by periodic inspections, electrical l Periodic maintenance keeps these valve i tests, and mechanicai tests. operators in an "as new" condition over their 40 year qualified life. letter to Mr. 1 11, 1981 See Wisconsin Electric's Sept.ner concerning reponse to the environmental qualification SER (specifically, Section 3.7) for a further discussion of aging. The tasts documented by WCAP-74101 included f era f aticA of both Reliance Rads gamma. The and Peerless actors with Class 8 insulation . ed irftdiation cf [ tasts documented by Test Report No. 30003 inc 3 Rads Reliance motors with Class B insulatio9 to greater than 2 x 10 L gamma and irradiation of tas operators including the gearop limit switches, torque swite.hes, seals, and luaricants to 2 x 10. Rads gamma. The operators were successful

ested for LOCA conditions inside nours as documented la WCAP-7410L.

containment for a duration of The test included chemical spray with a 1.5 weignt precent solution of O boric acid (H S0,) buffered to a pH of 7.85 with sodiure hydroxide The snart The !H Ts at the bottom of the pH range specified. lU required operating time of the units (maximum of 14 hours and usually (NaOH). only 30 minutes) would not allow a slightly higher pH solution to [ significantly increase the chemical corrosion of the units over thatThe boric solution wnich was used in the tast. The specified L much higher in the test than that Ftquirtd for PSNP, tamperature and pressure profiles were both enveloced by the [ profile L out th cars of testing. The ators were ex osed to saturated days aftar wnich they failed to sig for an additional 11ure was analyzed and detersined staan operate p perly. The cause of to be the entry of chemical spray into the unit through the motor lead [ The motor leait cutouts are sealed at PENP with flexible C cutouts. Although these fittings have not been conduit and associated fittings. qualified, their cesign indicatas tha In addition, the tests spray could entar the units via this path. documented by Test Report 30003 demonstrate that the units can survive y j This a saturated steam environment at 10 psig for at lea and steam for long periods of time. nours following a q be consicered qualiffed for an operating time ofLdesign bas -{ The qualified level of radiation integrated dose of the ocerator.

NRC Contract No NRC-03 79118 ] 4 000U Fr:nklin Research Center FRCProjectN2,C5257 FRCPRIETARY Page A Devmon of The Frank!!n insatute FRC Assignment N2.13 FORMATION 5) i 20th and Raci Streets. Phde., Pa 19103 (215) 4481000 FRC Task N2. A d 6 5 0 g EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 4,5 l U I ni,A 'n, J,;A as L,uo '1h AsA kon,N d <L to uuAc' 0 1 Ow2b ,>.,JL uA %M . b im A %; a i h L A, L iti ,h % x E k U e i \\. % W E DAs-u Ai A w 'a w %,, & 1 i s j,u '7 L. a s ;,,. A, o p y - i 40 u MA a m ),J',3 A A)'s. // Q.\\ A -l) hi m o/ j %~!L a n d % f si - mks$,22: i ,, - c. g p.- e -r n mo m,uo-easi s cnon eco r-b kb % % Tw i T ' St.Ap iTt.4 II .h MOME - M ord E' 'Tcf2.QtAG 3 w s t c_9 t 1 d o m Pt,P r p t-/ A4SEM,1 l wove oesa mica mva" C kPCbt < m k f-u.n' d a.,< % w& c ~ e e. rmuis% w_a

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NRC Contract ND. NRC 03 79-118 4 UOOU Fr:nidin Research C:nter - FRC Project N2 C5257 Paq3 A DNwon of The Frankhn innume FRC Assignment N1.13 30 20th and Race Streets. Phas.. Pa. 19103(215) 448 1000 FRC Task No. SD4/Fo7 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO..(4/cp LICENSEE RESPONSE TO NRC SER U. The t.f aitorque Mcdel SM8 valve actor operators outside containment at Point Beach Nuclear Plant have either Reliance or Peerless motors with Class 8 insulation. Generic environmental tests on t.*ese operators are documented in Westinghouse WCAP-7410L and Limitorque Test Report No. 80003 (Qualification References IS and 168, respectively). The tests included ther nal aging to the equivalent of greater than 40 years st an amotent tamperature of 40*C (104*F) assuming the "10*C Rule." The tests also included mechanical and vibration aging. The potential for unexceeted degradation due to aging is addressed by periodic inspecuens, electrical tests, and mechanical tests. Periodic saintenance keeps these valve operators in an "as new" condition over their 40 year qualified life. See Wisconsin Electric's Septammer 11, 1981 letter to Mr. Harold R. Denton concerning response to the PENP environ-mental qualification SER (specifically Enclosure 1, Section 3.7) for a further discussion of aging. ~ The tasts documentad by WCAP-74101 included i att of both Reliance and Peer 1 css motors with Class B insulation to. Rads gamma. The tests documented by Report No. 80003 included adia on of Reliance cotors with Class B insulation to greater than 2 x 10 Rads gamma and irradiation of the operators including gepred limit switenes, torque switches, seals, and lunricants to 2 x 10 Rads gamma. The operators were successful) estad for LOCA conditions inside containment for a duration of ours (documented in WCAP-7410L) and for HELS conditiens outside cLm in=ent for a duration of 15 days (documented by Test Report S0003). The qualification of these valve e successful operators for 10C". relative f.umidity is demonstrated my f"n: curs in one tests in saturated staam at elevatad tamperatures for{ tast and 16 hours in another tast. Therefore, these Limitorque valve acerators fre considered generically qualifisd for 10C'. relative humidity, 2 x 10 Rads gamma radiation, and' a 40 year lifetime. Since these valve operators have suecassfully operated for years in their normal environment and since elevatad temperatures and hign humidity are not expected in the auxiliary building where these operators are located, the operators'are judged to te qualified for a minimum operating time of one year. s I

e 4 NRC Contract N3. NRC-03-79-118 000Dr nk!!n Research Ccntr FRC Project N3. C5257 PROPRIETARY P g3 A Dwison of The Frankhn Instaute FRC Assignment No.13 }NF08MATION 5g 20th and Race Streets. Phda. Pa a9103 (215) 448-tm0 FRCTask No. M~O6 /801 I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EOUIPMENT ITEM NO. _/nfo 2- % Q md. O,r0 w amalmL>i, & A wh~EliJN'7kishL,. L i e r 40uun am AJ,J A yi. l V OJJJY Ya um a hi aN '7h % !L ad % f i,- mbh,uA: a i r,-c g neasis n m.,, n o a n o,- r-p e ruo-b $ M%Y _dI TOR.Q u G s w% t c.4 Mo4E' does PLM LV Ass EM8tth / O MGATid4At MVA" MOOE PCbt < w k t-uE N dt N oe bro.he w_ a S t. <. <. 2 _ i-I M 60E ,a mm, compn e s-07 T i mW A m M ATTA(EF eAseX mvA 41 u+ 199. P, 6 m,c; 1: !i co19 9,/ x o n g-b) v >A AL, O s$a n k>-e n l owns >A fAse a un n a '&, im em d M If ku oss a sL7~ as Al Mus e o a 9 L>-us2. E [ 2A) M JALd/ ,L bk b Y ain n) JD ud2 c!w,,s ~ ~!kl '7Li L-,,JA 'nA i w-us v&A i ARJ,1, J% h

1 4 NRC Contract N3. NRC 03-79118 30MFranklin Research Center FRC Project NJ. C5257 P:g3 A De of The Fr=*nn hannute FRC AsalgnmeniNo.13[TO 3a 20th and Race Saroots. Phas.. Pa. 19103 (215) 44810m FRC Task No. _ 90 f, EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPM LICENSEE RESPONSE R. The Reactor Coolant System loop RTDs were only testad to- ~~l gamma and were not thermally aged during qualification tAting.JRads acove radiation dose allows over 10 years of normal operation followed The by one week of post-LOCA containment radiation. tion such that the RTDs would not be required. time after a postu e condi-indication such as staam generator saturation pressure or Residual HIn ad Removal s cooling. ystem tamparature are availacle depending on the mode of plant eat It is our intention to continue evaluation of the present RTD thermal aging and a higher radiation dose in order to fully these RTDs to the OCR Guidelines. qualify of these comp.adiation dose rates make the environmental qualificationM high normal r onenta extremely difficult. deadline, if possible.them with fully qualifted RT3s by the environmental qualificati on f.. l c t

NRC Contract No. NRC 03-79113 f OU(d Franklin R: search Center FRC PrIject No. C5257 PROPRIETARY Pao A o on of The Frsawin inwaun FRC Aa:Ignmcnt No.13 INFORMATION 5C 20th and Race Seems. Phde.. Pa. 19103 (215) 448 1000 FRC Task No. Tofa[Tc2 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. M NRC REQUIREMENTS DEFICIENCY WITH SECTION REFFRENCE LICENSEE QUALIFICATION (X OR (DOR /0 588-I/0 5 88-II) SUBMITTAL DOCUMENTATION HOTE NO.) Radiation Aging, Dose (rd) CombinedwithDBEexposuref Not stated Radiation Aging, Dose Rate Radiation Aging, Method Materials Susceptible ! Not stated Not stated (Radiation) (5.2.4, 7.0/-/-) 1 1 1 Operational Aging Min 1 1 3fg (-/4.2/-) Other Age Conditjoning NN N/A (-/4.2/-) 1 1 1 Qualified Life Claimed / ! \\* 'f * *> 4 Established (5.2.4/4.10/-) . (AO.D<w= f. Post-cccident RC I

N J

Normal Ambient Temperature Wo 5 120*F e Normal Ancient Radiation ! b& g4M 200 R/h O 1 Normal Ambient Humidity ! Nov g bhf ! Not Stated ' I Q On-Going Surveillance and ! ot stated v I N Preventive

Maintenance 1

(7.0/-/-) 1 s j on-Going Analysis of I N/A, .Tailures and Degradation (7.0/-/-) Margin (General) ! ot stated N (6.0/3.0/3.0) 1 1 1 Margin (NUREG-0588, ! g4 pq ! Cat. I) (-/ 3. 2/-) I

1. Temperature (+15*F)

2. Pressure (+10%,

10 psig max) 1 1 1

3. Radiation (not required) 1 1

1

4. Time (+10%, +1 hour l

+ function time minimum) I i

~ NRC Contrcet No. NRC-03-79-118 '8' 4,lin Rese:rch Center FRC Project No.C5257 PROPRIETARY f $d .% rank FRC Assignment No.13ToWWeJNFORMATION 4 w of ne Franian tmme19103 (215) 448 1

FRC Task No.

m.nd Rxe Saem. Phda.. Pa. EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIP DEFICIENCY NRC REQUIREMENTS QUALIFICATION (X OR LICENSEE WITH SECTION REFERENCE DOCUMENTATION NOTE NO.) SUBMITTAL (DOR /0588-I/0588-II) ,1 3CCIDENT CONDITIONS _ toCA/MSLB/HELB/ Uncontrolled !b*CAlKesG !S L B (4.1, 4.2, 4. 3.1, 4. 3. 3/ 1.1, 1.2, 1.5/1.1, 1.2, 1.5) ! 1 Aw% gm, Radiation Type Radiation Dose (ed) ! \\So N f 3ng gppige,31, (4.1.2/1.4/1.4) Raciation Dose Rate (rd/hr) !.6 Mrd/h 1 Radiation Qual. Method (5.3.1/-/-) I Prcximity to Concentrated ! N/A Radiation 1 ( 4.1. 2/1. 4. 6/1. 4. 6) 4 I ! ot stated Equipment Susceptible to N Beta Radiation (4.1.2/-/-) e e e ! g, g # ] >r Radiation Dese (Normal + P Accident) (4.1.2/-/-) 1 O ! ot stated Platcout Dose Cc,nsidered N f (-/1.48/1. 48) r-e f h e k ) Gamma + Beta Dose (rd) (4.1.2/1.4.7/1.4.7) {, w a. (

Ucw% has dded 15o Nd accid yb SooHed. %e tio New oy%.

i hw Az 9 9 m I a

A NRC Contract N2. NRC43 79118 .dfiU Franklin Rese:rch Center FRC Project No.C5257 PROPRIETARY Page A Dhoon of The Franklin Insneute FRC Assignm:nt N:3.13 l g RMATl0N 5e 20th and Race Streets. Ptula.. Pa. 19103 (215) 44810M FRC Task No. toc /Tc7 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. h1 5 l NRC RIQUIREMENTS DEFICIZHCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL Doct: MENTATION NOTE No.) k k k ENVIRONMENTAL PROFILE OF ACCIDENT CONDITIONS 1, !p Rate of Temp./ Press. 1")#F[hkf5)5 5 g ~ Increase Peak 'F/psig/RH/ Time %"19[43[fe= f f f a ! otes g,\\ !t Q3/ goo le4 N Cecrease To: *F/psig/RH/ Time '1,og /iy[,.of lq t 'F/psig/RH/ Time hy3 -fles[' l Cecrease To: Decrease To: 'F/psig/RH/ Time ! l Equipment Surface Tenpera-Not stated ture (MSLa) (-/1.2.5 C, 2.2.6/1.2.5.C, 2.2.6) g' E Spray Qualification Method !~ p' aceto est l (5.3.2/1.3, 2.2.8/1.3, 2.2.8) hI' O #ih D 5 1.14v/o boric acid I Spray Composition l (4.1.4/1.3, 2.2.8/

'3

! 0.17 wt: NaOH 1.3, 2.2.8) 1(* % 'r* * $ Spray Density (gym /f t ) !Not stated !Not stated hote le [ 2 I Sptsy Duration !Not stated !Not rested hote to I ( Submergence Duration !N/A !N/A (4.1.3/2.2.5/2.2.5) .N/A h l In-Leakage Considered ( 5. 2. 6, 5. 3. 2/-/-) i l l Time to Suomergence 1 !N/A [ I Cust Environment ! N/A 1 (-/ 2. 2.11/ 2. 2.11) l l l

f N RC Contract N r. N RC-03-79pg] p R g ET A,:p og Pag] {000 FrankIfn Research Ccnter FRC Project N2.C5257 JOFORf.W'd'- A chmen of The Nakha insmun FRC Assignm:nt N2.13 5\\ 20th and Race Streeu. Phde.. Pa.19103 (215) 4481000FRC Task No. Toc,/vo ; EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. b I "='

NoteII, I

The test described in WCAP 9157 consists of an initial 24 H transpqt rature/pressuredecreasingcof J A[J Jday period with to a 13 day severe

g exposure at F condiporg is taken as equivalent anvironment exposure att JF.

(In-con at average temperature 5 over a 2 week period following a SLB is F according to WCAP 9157.) i The basis for accelerating test time is a simple chemical reaction rate lav =odel given on pg 2-7 of WCAP 9157. (This model is more conservative than an Arrhenius model based on similat governing =aterials and tempera-L cures) L Acceleration of the test interval through increasgd test,te=@peratures not usually acceptable for steam exposures. 1For TnE' tee'p ratures i z l 1 jande devices considered here however, a test ays after the initial 24 H transient period duration of/ ] days Ece{ ;.eoiq W-est. should be acceptable y a3 towg-4e,% tehucd%4 op4cq HoA (e S g t yve) CafMh kas wi N 446,ua % N Gr eme a.e,. l L Note -l years is based on dose rate Qualified life claim in WCAP-9157 of Thermal aging and operating time calculations performed by Westinghouse. l has not been included in the qualified life evaluation. F u l W e

g M 4 NRC Contract No. NRC 03 79113 UUUU Fr nklin R: search Ccnter FRC Project NO. C5257 PROPRIETARY Pag) A Divwon of The Franklin Instuute FRC Assignment No.13 1 20th and Race Sweets Phde., Pa. 19103(215) 448 1000 FRC Task No. T%/ E~DRMA 5 + 7 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW O I NOTES: Note S Peak cast chamber controlled pressure is stated as 66 psig; however no additional oressure data has been provided in WCAP 9157 Facility setup supplies steam at saturated conditions except for initial transient period where superheating is possible. is assumed at saturation conditions. 100% RH Noce 9 Conditions stated are for test profile. Actual temperature data was provided for the f4rst 25 S only. This data indicated an overshoc to approximately{ _lF at 25 S. Note to Spray density and duration are not stated. WCAP 9157 indicates on pg 5-1 that spray can be injected via spray nozzles or =ain inlet steam piping to test chanber. No information is provided on specific approach usec in this test. e

~ h NRC Contract N ?. NRC-G3 79118 00 Fr:nklin Research Ccnter FRC Project Nr.C5257 Pag 3 A Dumon of The Franm instmuse FRC AsslGnment No.13 2 l1 "O 20th and Race Streets. Phda.. Pa. 19103 (215) 448-loco FRC Task No. SOV EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. lQ i LICENSEE RESPONSE 'IO NRC SER U. The Limitorque Model SMS valve motor operators outside containment

at Point Beach Nuclear Plant have either Reliance or Peerless motors with k

Class 8 insulation. Generic environmental tqsts on these operators are documented in Westingneuse WCAP-7410L and Limitorque Test Report No. SCC 03 (Qualification References 13 and 168, respectively). The tasts included thermal aging to the ecuf valent of greater than 40 years at an amoient temperature of 40*C (104*F) assuming the "10*C Rule." The tests also included mechanical and vibration aging. The potantial for unexeected degradation due to aging is addressed by periccic inspections, electrical tests, and mechanical tests. Periodic saintenance keeps these valve operators in an "as new" condition over their 40 year qualified life. See Wisconsin Electric's Septescer 11, 1981 lettar to Mr. Harold R. Canton concerning response to the PENP environ-mental qualification SER (specifically Ecclosure 1, Section 3.7) for a further discussion of aging. The tasts documented by WCAP-7'410L included ir iattaji of both Reliance and Peerless motors with Class S insulation to , Rads gamma. The O tests documented by Report No. 80003 included readiagionofReliance motors witn Class 8 insulation to greater than 2 x 10 Rads garaa and irradiation of the coerators including gepred limit switents, torque switches, seals, and tuoricants to 2 x 10 Rads gar.2 a. The operators were successful astad for LOCA conditions inside [ containment for a duration of ours (documented in WCAP-7410L) and L for HELS conditions outside con nment for a duration of 16 days ( (documented by Test Report 20003). The qualification of these valve l operators for 100% relative humidity is demonstrated y a successful l tests in saturated steam at elevacad tamperatures for hours in one l tast and 16 hours in anctner test. Therefore, these Limitorque valve operators fra considered generically l qualified for 10C% relative humidity, 2 x 10 Rads gamma radiation, and-a 40 year lifetime. Since tasse valve operators have successfully operated for years in taef e normal environment and since' elevated temperatures and hign humidity are not expected in tne auxiliary building l where these operators are located, the operators are judged to te g qualified for a minimum coerating time of one year. I I l 1 I I

NRC Contract Nr. NRC-G3-79-114 h 00 Fr:nklin Research Ccnter FRC Project N3. C5257 Pag 3 A Dwenson of The Franklin Instmuse FRC Assignment No.13 30 20th and Race Streets. Phda. Pa. 19103(215) 448 1000 FRC Task No. SOY g EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 29 l LICENSEE RESPONSE 'IO NRC SER i J U. The Limitorque Model SMS valve ac*,or operators outside containment'at Point Beach Nuclear Plant have either Reliance or Peerless motors with L t Class B insulation. Generic environmental tests on these operators are l documented in Westingneuse WGP-7410L and Limitorque Test Report No. 80003 (Qualification References 13 and ISB, respectively). The tasts included thermal aging to the equivalent of greater than 40 years at an amotent temperaturs of 40*C (104*F) aJuming the "10*C Rule." The tests also included mechanical and vibration aging. The potantial for unexcected degradation due to aging is accressed by periodic Inspections, electrical tests, and mechanical tests. Periodic saintenance keeps these valve operators in an "as new" condition over { their 40 year qualified life. See Wisconsin Electric's Septemeer 11, 1981 1etter to Mr. Harold R. Denton concerning response to the PENP environ-mental qualification SER (specifically Enclosure 1, Section 3.7) for a further discussion of aging. ~ The tests documented by WGP-7410t. included i iatie9 of toth Reliance and Peerless motors with Class S insulation to s Rads gansa. The O tests documented by Report No. 80003 included rradiagionofReliance motors with Class B insulation to greater than 2 x 10 Rads gamma and [ irradiation of the operators incli.cing geared limit switches, torque E. switches, seals, and luoricants to 2 x 10' Rads gassa. The operators were suctessfulyi *ested for LOG conditions inside [ containment for a duration of[ ours (documented in WGP-7410L) and L for HEL3 conditions outside containment for a duration of 15 days (documented by Test Report 30003). The qualification of these valve operstows for 100% relative humidity is demonstrated )y *he successful [ tests in saturated steam at elevated tamperatures for( hours in one L tast and 16 hours in another test. Therefort, these Limitorque valve coe-ators fre considered generically l qualified for 10C% relative humidity, 2 x 10 Rads ga.ma radiation, ana-E a 40 year lifetime. Since these valve operators have successfully ocerated for years in their normal environment and since' elevated temperatures and hign humidity are not ex ected in the auxiliary cuilding l where these operators are located, the operators ars judged to te g qualified for a minimum operating time of one year. I l I l I l l I

NRC Contract NO. NRC-03-79-118 p U0tJhranklin Res' arch Center FRC Project No. C5257 PROPRIETARY P g3 e A Dms.on of The Frankhn instrute FRC Assignment No.13 INFORMATION 5g 20th and Race Streets. Phila.. Pa 19103(21',1 448,1 2 0 FRC Task No. 50 'E EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. M tmzss S. O, JLh-t. 2A W amalmio,,RA n r j,; i 7 b a b,% of o 40 uw an A1,FA Di. l / 1 af'7xi OJJ1k ]s ~ n a h, % !L asb % f i,uw mb>$ud: eg s 8 Asis i -u ctw koOcoT 7 t M c-Twm Psef2 A ruo = CEAEED L i m i r ' sta i ro-I MoME Tet2.Q u G sesTcu M o M E~ rdom PLML / ASSEM8trhI l cereQ ATico A L mvA" I MOOE \\ A _m a., w sa d C _R rse_ m i u t

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