ML20002C524

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Responds to NRC 771223 Request for Info Re safety-related Equipment Environ Qualification.Discusses Design Basis Events Re Environ Qualification Criteria & Electrical Equipment Documentation Availability & Acceptability
ML20002C524
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 02/24/1978
From: Bixel D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Desiree Davis
Office of Nuclear Reactor Regulation
References
NUDOCS 8101100411
Download: ML20002C524 (22)
v • d • e


Text

{{#Wiki_filter:s 5 s U e v, g - Y ConSilm crS . O t P0Y!ct t i company o.n...i ome..: m w..t wenia.n 4..nw.. sac =.on. wenia.n.o2oi. 4,.. coa. et7 7ee osso February 24, 1978 01.'ector of Nuclear Reactor Regulation j i 4tt: Mr Don K Davis, Acting Branch Chief Operating Reactors Branch No 2 'US Nuclear Regulatory Cornission ~ Washington, DC 20555 \\ :.'. s ' DOCKET 50-155 - LICENSE DPR BIG ROCK POIUT \\Q( PLAUT - RESP 0 HSE TO Lm.x DATED DECD4BER 23, VU 1977: E3VIR03 MENTAL QUALIFICATION ~ By letter dated December 23, 1977, Consumers Power Company was requested to address the Environmental Qualification of Safety-Related Equipment for the Big Rock Point Plant. Discussions and meetin6s with the staff helped clarify the type of information necessary to adequately respond to this letter. The purpose of this letter is to provide our response by identifying the Design Basis Events considered at Big Rock Poir.t Plant,by providing the environmental qualification criteria, by specifying the documentation available for electrical equipment necessary to operate under these Design Basis-Events, and by conclud-ing upon the acceptability of this documentation. The time frame allotted for this response has been established at 60 days. This has not provided adequate time to fully research and analyze data to ensure that all available environ-j mental qualificaticn documentation has been utilized. While the sut=ittal rep-resents the most accurate information compiled to date, the time frame has not J alleved completion of a formal review of the sub=itted findings. If, on the basis of further review, the derived conclusions are other than these specified, the staff vill be notified ir=ediately. The Design Basis Events identified as being environmentally limiting for Big Ecek Point are the Loss of Coolant Accident (inside of containment) and the Main Etes: Line Break (outside of containment). The various environ =ents caused by the postulated occurrences are described in Attachment 1, and are derived fro: pre-viously docketed submittals. The equipment that cust operate to ensure safe shutdown of the plant during these Design Basis Events, and the environ = ental criteria and qualification of this equipment is identified in Attachment 2. It is important to note, however, that only the equipment that is subject to a potentially hostile environnent is addressed. Further, as discussed in the pre-vious paragraph, Attachnent 2 is limited. First, the list of systees and equip-ment has not yet received a ec=pleted fornal review and, therefore, is subject to chan6e. Second, the qualification docu=entation that is listed represents the data co= piled to date, and does net necessarily represent the cost conclusive infor:ation on record. I \\ O / \\ k ~~ ( g 81011 oo it t l \\

( y 4 Specifically, the Method of Qunlification' column of Attachment 2 represents only that qualification documentation that affords. complete retrievability. Further, because of the limited time fra=e, little ' detailed environmental qualification data was obtained through contacting various vendors or in researching other dockets for equipment test results. Performing these tasks vould, undoubtedly, r,nhance the status of the qualification data submitted. For that equipment that-marginally meets the acceptance criteria, the Method of Qualification column of -Attachment 2-provides justification and/or a course of. action to be taken to raise the level of qualification. During the course of investigation for determining the status of environmental qualification of equipment, several potential areas of concern vere discovered that required further investigation. These areas include: (1) The. potential for a. corrosive / caustic chemical environment in containment should the liquid 4 poison system SQUIB primers detonate under LOCA conditions; (2) the credibility or potential ramifications of-a rupture of the lov energy heating pipe in the electrical equipment room; and (3) the potential explosion of nonsafety-related motor control center panels (due to impingement from containment spray systems) causing dama5e to the reacto: vessel lov vater level sensors. Further evalua-tion of these potential arena of concern is being conducted. l In analyzing the qualification data derived for-each system, it becomes obvious that the spectrum of data covers the period from plant inception to the present time. Inherently, this means that the criteria met no one single guideline but 3 met the specification in effect at the time qualification was accomplished. Based on our assessment of the bounding environmental conditions and the quali-fication data presented in Attachment 2, Consumers Power Company concludes' that there is reasonable assurance that Big Rock Point vill continue to operate without endangering the health and safety of the public. N i David A Bixel i Nuclear Licensing Administrator CC: JGKeppler, USHRC i 4 'l 1 i 2 %. 4 .-.m,m-- _ ~ - . ~.,

\\ ATTACICIENT 1 Environmental Design Conditions When considering the Design Bases Events of LOCA and high energy line breaks outside of containment, the following adverse envf ronments are postulated: Environtent 1 - Containment During LOCA Temperature:

  • Figure 1 Pressure:
  • Figure 1 Humidity:

100% Chemical: None Radiation:

  • Table 1
  • Letter to Division of Reactor Licensing - HRC fro R B Sewell dated May 15, 1975 Environ =ent 2 - Pipe Tunnel and Condensor Roo During High Energy Line Break Te=perature:
  • 210 F Pressure:
  • 2.2 Psig Humidity:

100% Che=ical: None Radiation: Normal (Outside Centainment)

  • Bechtel report dated April 25, 1973, " Consumers Power Company Big Roch Plant -

Report No. I - Effect of Compartment Pressurization due to Pipe Syste Break Outside Containment." Environ =ent 3 - Electrical Penetration Room and Adjacent Areas During High Energy Line Break Temperature: ' Normal Pressure: "Homal Humidity: 100% Chemical: None Radiation: Normal (Outside Containment)

  • Bechtel report dated April 25, 1973, " Consumers Power Co=pany Big Rock Plant -

Report No. II - E.*fect on Safety-Belated Equipment due to Pipe System Break Outside Contain= eat," states that for a break in the pipe tus nel, the blevout panel in the tunz el and the automatic shutoff da per in the ventilation duct connecting the tunnel to adjacent areas prevents steam from reaching the elec-trical penetration roc = and adjacent areas, and thus the electrical equipment and cabling in these areas is sufficiently protected from the effects of a pipe break in the tunnel. If the break is in the turbine hall, significant arounts of moisture would reach these areas; however, due to the volume of the hall and i 1 e

( because porticas of the hall siding are designed to relieve at 0 5 psig, the temperature in the hall and cc:t::ranicating areas would remain essentially unchanged. These design environments are used to evaluate actual equipment environmental qualifications as described in Attachment 2. i 2

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TABLE 1 Integrated Absorbed Dose (Rads) at Time T After Initiation of LOCA Location T = 11 Seconds T = 1 Minute T = 1 Hour T = 1 Day T = 30 Days Submerged Beneath h 6 6 6 Mater Surface 570 3.h x 10 2.h x 10 5 9 x 10 7 0 x 10 At Water / Air k 6 6 6 Interface 370 2.1 x 10 1.3 x 10 3 2 x 10 h.1 x 10 In Contain=ent 3 5 5 6 Atmosphere 160 7.6 x 10 1.7 x 10 6.0 x 10

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k ) ATTACEMENT 2 EQUIPMENT ENVIRONMENTAL QUALIFICATION SUICIARY SHEETS 1. LEGEND PIS - Post-Incident System FPS - Fire Protection System CIS - Containment Isolation System R'4S - Radvaste System RDS - Reactor Depressurizing System RVG - Reactor Vessel General RPS - Reactor Protection System NA - Docu=entation not # 9:licable (in the Case of Radiation, Expected Dose Levels < 105 RJ (-) - Indicates Documentation Dot Found SUB - Submerged C - Containment 0 - Outside Containment II. ROOMS k00 - Steam Drum Enclosure 42h - Recire Pp Inst Rs 307 - Main Cont. 1 Room 105 - Station Power Rocc 407 - Cont Rod Drive Rm Access h27 - Core Spray Ex Room 12k - Laydown Area - Railroad Access 104 - Shop h22 - Core Spray Tank Area hh7 - Personnel Lock Area 418 - Fuel Pit Pps Ex hh6 - Platform 621.0 - Supply Air P 1 Area h51 - Refueling Floor h36 - Pipe & Cable Tray Area 110 - Cable Penetration Area (Outside Cont) kh5 - Elev 616.0 (Vent Panel Area) h52 - Emer Cond Area 405 - Accunulator Room i 1 r

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1,imittr4 >;nvironner.tsal in.sidn Qualification f517 P d f oi:10 Envirorunental Shcet u cf 11 hl Chemicals P.ettio2 cf (califint!>n lyster. Psiction q Ares Sub i i<oorn Mcsiel (TyT.e) Criteria Psia F 4 ation 'o Nw mal P!- 113 Pressure InJ1ca-0 Ho 307 Fontoro Ik.T ki-122 M HA NA tbt required. located in control D If0"*""E 112 tor for 11-106 g 6SPVOtfG room and will experier.ce norwsl is-I'13 tv-136 Power Foxtoro 2165 Jupply 6l04 l'r-PIS Enclosure Pres-0 No 110 Rosemourt/ ilarmal Ib.T -20 to 200 100 1.2x HA tbt required. tocateJ in cable lij sure Transmitter 1152414 2.nvironment I penetrattun : )om and/or coutrul 10 N (Vacuum iteller room and will experience smirmal Autc) Control) ambient ogcratlnd cotida tions-PIS-l'ressure Indica-307 StrAa/9270 NA 1(3 tor for IT-lTI IT-Enclosure Pres-110 Rosemount/ -20 to 200 100 1.2x id* sure Transmitter 1152G04 10 H (Vacuum heller Auto Control) I'l-Pressure Indica-307 81ona/9270 WA IB( tur for IT-187 lu-PIS Actuate it)-70iA 0 No 110 Static O-rinc Normal 14.7 200 T$ NA NA flot required. Incate.1 ise e:a ble op toclosure Pres-kNN-E-hal-knvironment penetration room aral will experi-aure Uwitch VX$'1T enee norm 1 ambient olerattn:r conditions durinc IUt'A. 10-Actuate 6ebT06d b 1( taclosure l'res-mare Switch s ti-Pf3 actuute mid-7064 0 !E 110 Static O-Iting; Normal. 14.7 200 75 NA NA root required. Incated in cuble Q 7tn% A l'ressure Switch 121,-AA54SS Environment penetration room an.1 will emperl-ence ru>rmal ambient or-rat isw. lu-Sctuate Ho-Tof.h emw11tions during IDt'A. (OMB Pressure Switch Ir " " l 13 a t.le C Yes Kerite/(FR) 96.7 325 100 1.2x A Quatt ried t,y type test con.tucted Q 8 t,y Franklin Insti tut e and d., cia-

  • 13 19(O g

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  • ut Gasketed t.) R 15 Cherba dated ',/.~*)/TS-If/4 Covers l2:-

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Located 'n stration Panet PIS Uphere Instru-0 No 105 ITIUP115 IhWIFU'**"t j' mient and Control power room und will cape'lence Ibwer Panel norswal ambient operating conditions. Qualirted by type test for f. PIS Cable Splices C No b36 Amp /Certi-thvironment 1 392 g CIS for Control Seal Wire tea.perature, conducted by :P cv Cables Connectors Hesearch and Testing leatnr atbry,

  1. 32h990 and iteport No I-8-AT5 datel 3,27/15 332h5b9 Herer to Footnote-3 6

Refer to rovtnote 6. (Replacecment UV-CIS Air to CV 40')l, C Ho Out-ASCO/831620 invironment 1 bl.7 150 100 3x10 IIA lerts for 831620 are quattried by h&T9 CV b'))2, CV 1093 side (3-Wuy 115 smnufacturer's certificate of 6 b26 VAC) compliance. ) DV-Air to CV-h031 C Yes 424 ASC0/030060ltF t:nvironment 1 4'.7 37,0 100 hx 06 ltA 4'alified by evalu>= tion as duce,- mented in letter D E 11uegcenburg 1 L6') (3.Way 115 to H D Cherba dated h/B/T5 in 4 VAC) response to telephone conversa-tion with manufacturer, urad SV-Air to CV leo 25 ludicate41 type test results. hfi91 UV-itWG Air to CV teok9 C No Cable fH92 Pene-c::s 6 UV-CIG Air to CV kO27 C Yes h?b ASCO/HTX8300 Divironment 1 41,7 f15 300 6x10 g3 Q har6 C61!<F ( 3-Way 115 VAC)

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>+ 4 1 Limitin3 a;aivtron:2.ntM Desirpi Quulla ication alc Per r aint 1.nvironmental Sneet 10 cr ii Manu a tu m / Qualification Wessun hmp ratun Humidity BR -{ Chemi cals E thod of Ca llflatit* Ib3* " Area b I T.am Model (Tyre) Criteria Psin F ( ation o 1

  • jster Function

-o Tlw uto Hisc Junction C Yes Metal Enclo-Divironment I l.17 235 100 Cat stA Qua t t ried by evaluat iot. 8 m,i on Jh0 1 Isoxes sure With NUS '111-sD-Il6 test repoo' itend i a. 2b2 1 Gasketed tion quattricatinn strir ley Covers evaluation. Ilmasey 7.- Electrical t k.nvironment 1 6 PIG Cable for Core C Yes Cerro Wire & 84.7 2f30 100 2x10 r i4A Quattried by type test ec,nducted Spray Vulve Cable Co/(FH) by Franklin Institute 'leport 1 l Helocation Mod F-C 3f93, tiarch 197 6 W-3yo Cable C Yes From Various bnvironment 1 250 Cut NA Qualirted by type test, rur (Installed Sources temperature only, conducted I,y 1960-t</69) CP Co ltescarch and Teating bab-o rntory. Qualirted by evaluation for radiation as d.setenented t.y Jetter H B Chertua il<*ted S/22/75 Herer to Footnote S. t *r-HVG lienetor Pressure C Yes 405 Itosenrsunt / bivironment 1 8b.7 316 100 'ix t ok NA Qualified by manuructurer's IA-070 Trhnaultter 1152GP certiricate o' con.ptinnce, in-l'ower Cource ros 0 No 307 Roset= >unt / Normal Ib.7 lb0 80 N) Not required. located in c..ntrui IA30 Reactor I>ressure SP3-21018 t;nvironment room and will expertenee norm 1 Transmi tter luip ambient operating rontleions. PI-Heart nr Prescurt O No 307 Analogic I Atr> Inilica t or Hensurometer/ PJ2bb5/C/2 la 10 11 West Gteam Drum C No 400 Yarway/bb20C Divironment I b:.7 270 100 5.6xld NA tierer to Qwslification llettmat<> log y lt hoe.A (d)" evel Swit ch for i kD) (Page f.). I4*liricutions as describe.1 in the utt: test were u:- 6:ast ut. oru, unde. Herer to ltt)-BHP-78-lO It D%It es" le *el GwItcli or 2/17/78. an m. Ili-Glems lirtin low ICOA W st e r icwe t ':u 443-Uterike titum lhw lit.'O b Water level SW r--

f 1.lmitive eficow.w,,, wj u Qualification dic Poet Fa*.t g Errironmental St.eet 11 o 11 1 'h* M*"" * '* 1 88"#' Y8 Chew *?als licthol of 4 alifiutic * 'lystem Punction Area Sub Room Model (Type) Criteria Pala F i ation Do 6 IW-I;lG Ucrum Pilot C Yes 401 ASCO/fl31622 tuvironment I kl.7 2t0'* 100 1x10 1 NA Herer to Qualirleution liethotology uCJT Valves With IIVI A 90-Intermitten for SV 4960 (Page 9). Hefer to A/AQ kkl-1A 220' Footnote 6. Thru Conversion Continuous UV-k'?27 FSBQ Centuinment C No k36 Hundel/ Putted Environment I kk.7 274 100 Sat HA Qualified by evaluatico os Ele =* t ric al documented by letter M H Waue Penetration to W G Skibitsky dated 2/16/78' (Wade 03-78). Containment

  • Amphenol horf.

Electrical Electronics Penetrations Corp / Coaxial l't-CIU t.nclosure Pres-0 No 110 Boneunun t / kavironment 3 14 7 -20 to 200 100 1.2x1 NA Hot required. incated outstJe of I containment and will experience 174 sure Transmitter 1152Cl$ 10 H normal ambient operatird con 11-tions. I'l-Esclosure Pres-307 Si ya/9270 yaf 1.ur.e Indicator 0 Envirorunent 1 41.7 235 100 1x10 ll NA Qualified by vendor aun.11ed Hid Wire Terminal C No Amp Special doctmeentation 1,used on.orin(crin.: Connections Produc ts test report *bp Gi R-TIS-9;i" vs n-ducted by AMP and Franklin institute Q quali rted by evaluation, b> *d on Ric Termlnn! Dlocks C No States Hlock/ Enviroweent I 41 7 2b 100 1xiO9: na dlm'lWED-Ll6 test reert. NT UV-NC Hi"J Scrwa Master C Yes 401 ASC0/811622 Environment 1 kl.7 2h0* 100 1x10h NA Refer to qmlification method-22A, b Pilot Valves With HVA Intermitten ology for SV-k980 (Page 9). Q 90-hht-1A 220' Conversion Continuous nummmmme UV-dC HIS [hmou Tunk Vent C Yen 401 A W /A'41(O'> vnvi raramant 1 hl.7 7448 100 t wl d'! MA ncter to it.alifiestion methoJ-

2. 'F, G Vulves With HVA 90-Intermitteni alvay for CV-4930 (Puce 9).
11. J h05 Conversio.

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i FOOTUOTES 1. The definition of " Qualified by Evaluation" was provided in a May 15, 1975 letter (R B Sewell to Division of Reactor Licensing) in response to staff questions concerning Special Report No 21, " Investigation of and Correction of Discrepancies Associated With Equipment Required To Operate During a Postulated Loss of Coolant Accident." This definition specified the fol-loving: "The term ' Qualified by Evaluation' says that certain equipment which must function in the LOCA envivonment was tnvestigated and a judgment made with respect to its ability to withstand the LOCA environment and perform its required function with reasonable assurance. The equipment so qualified was reviewed to determine: 1. Its location; 2. Its operating principles; 3 Which materials used in its construction are essential to reasonably assure operability; k. If the essential materials remain functional under postulated LOCA conditions. This was established through one or a combina-tion of the following: a. Star.ard engineering handbooks, b. ' ale ~ phone contacts with vendors regarding unusual materials, Vendor catalogs and design application data, and c. d. Where possible, comparison of Big Rock Point equipment to qualified models of current manufacture, and e. Experience. Eased upon the above information and consistent with the FHSR and the applicable design and equipment specifications at the time of procurement, a judgment was made regarding the ability of the equipment to perform its safety function with reasonable assurance in the LOCA environment." Core spray level and pressure actuation switches are evaluated to withstand 2. k radiation levels of at least 3.6 x lo rad. Attachment 1, Table 1, lists the integrated absorbed dose after LOCA. Inherent in this table is the con-cept that release begins (ie, core melt starts) at time t = 0. Since the core spray system is obviously designed to operate (the pertinent control functions being accomplished) prior to the beginning of core melt, it is conservative to assume that the need for the level and pressure actuation switches is ove well within the first tinute of the postulated core telt. Thus, since the Tdiation dose for submerged components one minute after inception of etre release is 3.h x 10" and the radiation qualification cf the cited switches is evaluated to be at least 3.6 x 10", it is/ concluded that the radiation qualification of the core spray level and pressure switches is satisfsetary. 1 r

I ( 3 The existence of cable splices within containment for sa'ety-related systems at Big Rock Point was initially identified and addresrad in the Big-Rock Point Fire Safety Analysis dated March 29, 1977 At that time, Consumers Power Co=pany co==itted to modify these splices to ensure their environmental qualification initially for waterproofing and later extended to include LOCA conditions. Presently, alternate methods of qualification are being evalu-ated in preparation for performing the necessa. y modifications during the 1978 refueling outage (scheduled for mid-Nove=ter 1978). In the interim, the satisfactory high-te=perature testing completed on the splices offerc a neasure of assurance of their ability to withstand adverse environ =ents. Additionally, the majority of the splices have 3een in existence since the initial construction stages of the plant, and none have experienced any known electrical faults. h. Although the specific type test referenced for the RDS penetration qualifica-tion stipulated a maximum temperatur. of 223 F, an alternate test conducted successfully on similar penetrations provided additional data. The test parameters were: 260 F for 30 minutes, then 220 F for 30 minutes, and finally 150 -170 F over the next 175 hours with an approximate 2h-hour hold period. These test parameters are not fully consistent with the conditions specified in the qualification envelope of Attachment 1; however, in all cases, the test parameters cited above meet or exceed the containment te=perature transient predictions for the various coolant pipe break sizes that were considered in constructing the s,alification envelope. Thus, it is concluded that the environmental qualification documentation that exists for the RDS penetrat'^ns is adequate to ensure their capability to perform as designed. 5 There is approximately 250,000 feet of cabl_ng supplied by Anacenda, Okonite, Plastic Wire and Cable Corp, Rome Cable and General Electric that was part of the initial construction package at Big Rock Point. This viring is used for both safety-related and nonsafety-related equipment; no viring segregation or detailed identification has been accomplished or is contemplated. The cables have been tested and shown capable of withstanding LOCA temperatures, although no other type testing has bean done. Because of the age cf the cabling, it is anticipated that no further documentation vill be retrievable. 6. Valves SV-h879 and SV-NC-27-3 vere determined not to be environmentally quali-fled to withstand postulated LOCA temperatures. In accordance with Technical Specification 6.9 2.a corrective action was taken and proper notification was made. The apprcprial e permanent corrective action is being evaluated. Below is the notifier tion statement: "During equipment review associated with the Syste=atic Evaluation Progra=, two pilot solenoids ve.3 deemed to be inadequate to perfor= in the small break LOCA environment in the reactor containment building. The pcstulated failure mechanis= is related to the lov temperature rated nylon exhaust port disc which is attached to the solenoid moving core. One valve is designated SV/h879 in the reactor clean-up resin sluice system which controls containment isolation valves CV/h091, CV/h092 and CV/h093 I 2 r

i I "These valves are prer.ently closed and administrative controls to preclude opening of these valves have been established until evaluation and/or modifications can be made. The inadequate solenoid valve is an Automatic Switch Co. valve, Model 831620. The second valve is deaignated SV-NC-27-B and is associated with scram valves CV-NC-10 and CV-NC-9 for centrol rod drive F-2. This pilot solenoid has been de-energized and its exhaust function verified, and administrative cont-1s have been established to maintain it in the de-ener61:ed condition until evaluation and/or modifications can be made. This inadequate solenoid valve is an Automatic Switch Co. valve, Model WP 831612. Plant operation continues at 67 MWeg. This confirms a teleph :4e call to D R Prater from D E DeMoor at 1700 hours on February 22, 1978." l 3 r

( "' ) t. REGULATORY INFORMATION DISTRIBUTION SYSTFM (RIDS) DISTRIBUTION FOR INCOMING MATERIAL 50-155 REC: DAVIS D K ORG: OIXEL D A DOCDATE: 02/24/78 NRC CONSUMERS PUR DATE PCVD: 02/27/79 DOCTYPE: LETTER NOTARIZED: NO COPIES PECEIVED SUB JECT: LTR 1 ENCL 1 FORWARDING RESPONSE TO NRC"S LTR DTD 12/23/77.. FURNISHING INFO RE 'THE ENVIRON GUALIFICATION OF SAFETY-RELATED EOUIPMENT FOR SUBJECT -FACILITY. PLANT NAME: BIO ROCK PT REVIEWER INITIAL: XJM DISTRIBUTOR INITIAL: . 4-c o * * *

  • 4+ 4-4,4- +- *
  • DI5!RIBUTION OF THIS MATFRIAL IS AS FOLI.OUS
          • H********

GENERAL DISTRIEUTION FOR AFTER ISSUANCE OF OPFRATING LICENBE. (DISTRIEUTION CODE AOO1) FOR ACTION: EP CHIFF '7TFMANN44.W/7 FNCL ,,,. #""'J %, INTERNAL. [ REG FILE **W/ ENCL. NRC PDR4*W/ ENCL I k. E*+U/2 EllCL OFLD**LTR ONL.Y '" 'H AN AUER++ W/ ENC L CHEClOHN/ ENCL EISENHUT*+W/ ENCL SHAOnW/ENCi BAER** W / ENC ! BUI'LER**W/ ENCL GR I t1Est r U/ ENCr J COLLINS

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LTR 40 ENCL 39 CONTROL NBR 7" " % S SIZE: IP+19P I

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