ML19330B159

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Forwards Response to IE Bulletin 79-01B, Environ Qualification of Class IE Equipment. Summaries of Equipment Qualification Evaluations,Based on Encl 4 Criteria,Encl.Full Response Will Be Forwarded When Evaluations Complete
ML19330B159
Person / Time
Site: Browns Ferry  
Issue date: 07/18/1980
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-79-01B, IEB-79-1B, NUDOCS 8007300572
Download: ML19330B159 (54)
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Text

{{#Wiki_filter:_ _ _, TENNESSEE VALLEY AUTHORITY CH ATTANOOG A. TENNESSEE 37401 400 Chestnut Street Tower II July 18, 1980 c 2 Mr. James P. O'Reilly, Director j.9 Office of Inspection and Enforcement 0 U.S. Nuclear Regulatory Commission j Region II - Suite 3100 g 101 Marietta Street Atlanta, Georgia 30303 -c.

Dear Mr. O'Reilly:

OFFICE OF INSPECTION AND ENFORCEMENT BULLETIN 79-01B - RII:JPO 50-259, -260, -296 - BROWNS FERRY NUCLEAR PLANT Enclosed is our response to the first part of Action Item 4 of IE Bulletin 79-OlB, dated January 17, 1980, for the Brosms Ferry Nuclear Plant (Enclosure 1). The enclosure consists of summaries of equipment qualification evaluations based on bulletin Enclosure 4 guideline criteria. Also enclosed are revisions and supplemental information to the initir'. response provided by a letter from H. G. Parris to you dated April 30, 1980 (Enclosure 2). The Equip-ment Qualification Plan required in the second part of item 4 will be submitted by November 1, 1980. The enclosed.information does not comprise a complete response to IE Bulletin 79-01B for the Browms Ferry Nuclear Plant. Additional work under bulletin items 1, 2, 3, and the first part of item 4 has been determined as necessary as a result of the extension of Bulletin 79-OlB's scope identified in the letter from J. P. O'Reilly to H. G. Parris dated February 29, 1980. Also, we have identified additional equipment in primary containment needed for migitation of a LOCA or HELB which has not been previously considered. The results of these additional evaluations will be submitted to you as soon as they are available. In my letter to you dated April 18, 1980, I stated that we would submit the enclosed information by July 11, 1980. In a June 10, 1980, telephone call between members of my staff and Ray Hardwick of your THIS DOCUMENT CONTAINS POOR QUAUTY PAGES g00'I,,oh r:ec1AL con an cou.i opportunity empiover

Mr. James P. O'Reilly July 18, 1980 staff, we requested and were granted an extension of time for submittal until July 18, 1980. If you have any questions, please call Jim Domer at FTS 857-2014. Very truly yours, TENNESSEE VALLEY AUTHORITY f,' TT M. Mills, Manager Nuclear Regulation and Safety Subscribedandsworntobefore me this / f day of yJ d 1980. f Notary'Public My Commission Expires I,[Nd Enclosures cc: U.S. Nuclear Regulatory Commission (Enclosures) Office o'f Inspection and Enforcement Division of Reactor Operations Inspection Washington, DC 20555 i 1

ENCLOS*JRE 1 RESPONSE TO IE BULLETIN 79-01B ACTION ITEM 4 (FIRST PART) BROWNS FERRY NUCLEAR PLANT -(DOCKET NOS. 50-259, -260, -296) Section 1 Supporting Information Flood Level in Primary Containment Equipment Operating Time Section 2 Bulletin Action Item 4 Evaluation Sheets Qualified'Componenets Section 3 Bulletin Action Item 4 Evaluation Sheets - Unqualified Components 4 i Section 4 Bulletin Action Item 4 Evaluation Sheets - Insufficient Qualification Data - Unacceptable Qualification Data Section 5 Qualification Data Unavailable i i l O

SECTION 1 This part of Enclosure 1 contains general statements regarding the flood level expected in the drywell and the required operating time for the equipment during a LOCA which was assumed. e O e

Flood Level in Primary Containment .In our submittal dated April 30, 1980, the flood level elevation in the Browns Ferry drywell was specified as 606 feet. It has been determined that the assumptions used in establishing the flood level were overly conservative. It was assumed that all safety systems were lost following a LOCA and that the flood level in the drywell had a contribution from outside sources of water. Using the guideline criteria of IE Bulletin 79-OlB, and based on plant design, it has been determined that there will be no problem with flooding of the Bre as Ferry drywell. All safety-related equipment is above the expected flood level elevation in the drywell. Equipment Operating Time Unless noted otherwise, required operating tLEe for purposes of evaluating equipment qualification was considered to be 24 hours. i l 1

SECTION 2 This section contains the evaluation sheets for those safety system components which were found to meet the guideline criteria of IE Bulletin 79-01B, Enclosure 4. No outstanding items are identified and no additional work is planned. 1 l l

IIR0'c1!!S FERRY EllVIRO:!I'.El!TAl. QUALI FICAT10'! I[ P.UI.l.ET I!! [9-Oli; - El'CLOSUi:E 4 fiUl!El.li!f S Ifl51DE PRffhl:Y CO:iD,lT:::Uli System: All Systems Plant IDA: il/A Component: Electrical Connectors (Bendix) liodel !!o. : 10-214628-515 (Plug) and 10-214028-41P (Recp) 10-214636-785 (Plug) and 10-214036-78P (Recp) Test Re;3crt: Hyle Laboratories Report 44107-1 dated September 19, 1978 Sunreary: The electrical connectors met all the requirements for type testing in Section 5,2., Enclosure 4, with clcrificaticr. of certai:t iter.s es fqllows. Aging (thermal and radiation [ Gamma)) has been determined to be acceptable as per the guidelines in Enclosure 4 and is no longer an outstanding iten. Beta radiation qualification is acceptable since connect::rs are in a metal enclosure. l e O

T DR0'..'f!S IT.RRY D!Vil:0:!ME!!T AI. OUAl.ll'lCAT10'l IE litiOll'iii'79?ill: - Lf:CLodif:il T (:WiiE O !iiX lii' f6E P R il'i.RY C0ill All:Mi:lli i S,ys tem: All Systems Plant ID flo.: fl/A Component: Electrical Connectors (Gulton' , l'odel !!o. : 6448-1 or 2 Plug and 6445-1 or 2 Recp. Test Report: l!ylie Laboratories Report 43854-1 dated March 23, 1978 Su:mu ry: The electrical connectors met all the requirements for type testing in Section 5.2, Enclosure 4, with clarification of certain items as follows. Aging (thermal and radiation [ Gamma). ) has been determined to be acceptable as per the guidelines in and is no longer an outstanding item. Beta radiation qualification is ccceptable since connectors are in a metal enclosure. 9 N e e G \\

4 BROWilS FERRY 1:ll'/TR07:t1EllTAL QUALIFICATI0:1 IE' Bul.LEllf! 79-01C - El;CLO50::E 4 GUIIEL il:ES lil3]DE l'Rii1ARY cuitTAli:iEllT System: All Syste:ns Plant ID flo.: !!/A , Component: Electrical Penetration Assembly liodel ilo. : GE liodular Series 100 Test Report: GE Report 74-502-3 Suanacc: The electrical penetration assembly met all the requirements as stated for type testing /EccmT)has been determined to be in Section 5.2, enclosure 4. Aging (thermal and radiation' acceptable es per the guidelines in enclosure 4 and is no longer an outstanding item. Beta radiation qualification also . has been determined to be acceptable, o 9

BROWNS FERRY Ef1VIR0fiMEllTAL QUALIFICATION 1E BULLETIN 79-01B - EflCLOSURE 4 GUIDELIf;ES INSIDE PRIMARY CONTAll1 MENT System: All Systems Plant ID~ flo. : N/A Component: Electrical Penetration Assembly (unit 3') Nodel !!o.: General Electric Cannister - Type Test Report: General Electric Reports EPAQ-007, -008, -009, -046, -055, -056, -057, -061 1 [ Summary: The electrical penetrations met all the requirements for type testing in section 5.2, enclosure 4, with clarification of certain items as follows. Aging (thermal and radiation-Gamma) was done on the cast epoxy (See attached - Epoxy Life Tests not previousl,y submitted) used as a scalant independently of the LOCA/HELB test and was determined to be acceptable as per the guidelines in enclosure 4 and is no longer an outstanding item. Beta radiation is acceptable since epoxy is behind a metal enclosure and there are-redundant seals. e 4 9 O 4 I e* i y 9 -g na-

BROMilS FERRY Ef1 VIRO D1EllTAL QUALIFICATI0:1. IE BULLETIll 79-01B - EfiCLOSURE 4 GUIDELIllES INSIDE PRIf4ARY C0!!TAlflMEilT System: All Systems Plant ID flo.: 11/A Component: Electrical Penetration Assembly. 14cdel flo.: Physical Science Penetration Test Report: Wyle Laboratories Report 43854-1 Summary: The Physical Science Penetration.and..the.Gutton Electrical; Connectors in the above referenced test report are one integeral unit (See Photograph 1 and 2 in section IV of test report). Since the Gutton i l k.' Electrical Connector has met all the guidelines of enclosure 4, section 5.2, and the penetration is part of the connector, the penetration is therefore qualified. Jio problem is seen for the leak tightness of the penetration during an accident since the penetration seals are not effected by temperature, pressure, humidity, and radiation (camma and Beta). The conductor penetration seals are glass to metal based on vacuum tube technology and the aperture seals are a metal to metal field weld. As with the Gutton Electrical Connectors and due to the fact of the contruction of the seals, aging is no longer an outstanding item. G e e e O w~--

.Illif['EIS...l].I..IIST..ly I P.0,5%f(1l " ()UAl.I F1C/.TI0'f 11: 1:ULLi'Tli! 7'J-Oll: - El'Cl.G:' 4 Gull 6LiliLS 1Ils1IIL l'iiini.IIY COT 1YA.. ":1 i Syntcy:.All Systems h Plant ID Ho. : N/A Electrical Cable Coj>nent_: CPJ (XLP with PVC Jacket), CPJJ (XLP i'ulticonductor with j !?odel !!o~. PVC Jacket),and Vulkene (GE XLP) ~ 4-Test !!crort: Wylie Laboratories Report 43854-3 dated April 26, 1978 The electrical cable met all the requirements ~ as stated Sumery: for type testing in Section 5.2, Enclosure 4, with clarification of certain items as follows. Aging (thermal and radiation [GammE.) has been determined to be acceptable as per the. guidelines in Enclosure 4 and is no longer an. out-standing item. Beta radiation has also been determined to 4 be acceptable. l l t J o I .l. i: 4 1 - e f

II fil:01U!S ff.RRY fi: VIRO:!:T!!T.".l. OUAI 1rICATJfrl 1[ t:!!1.1.F11fl MI6iiC~diiliiSiiiOTf3inill!iiffs' - DiSTiiL"l'lifShl:Y d2TMll!9.flil' I' Systen: All Systems Plant ID ilo. : N/A Com;vanent: Electrical Cable (ITT Suprenant Exane) I lbdel - :o. N/A Isomedix_ Report 375-02 dated March 1975 Test Py art: i i, Surnarz: The electrical cable met all the requirements as stated for type testing in Section 5.2, Enclosure 4, with clarification of certain items as follows. Aging ( thermal and radiation Dantnij)has been determined to be acceptable as per the guidelines in Enclosure 4 and is no longer an cutstanding item. Beta radiation also has been determined to be acceptable. 4 O i + N 4 .h I e e 6 e i 3-i. 1 i 5 O y 4 v + --c - = ,yvv-nr,

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c. I I'R0'!iiS ffI!::Y 1.I!Vi1:n':lli'llTAl. OUT.LIl iI:A f10:1 11: lillt 1.1.1 li! '/9- 011: - Fi:Cl 05U::E 4 GU;I!;.l.li !5 lilSI DL ly:li'.Al:Y CO::l Aliti!i.ilf O SystJJi): All Systems Plant ID !!o._: fi/A Component: Cable Splices Type CPJ, CPJJ, and Vulkene (Raychem) lbdel ':o. : II/A Test P.cport: Wyle Laboratories Report 43854-3 dated April 26, 1978 Su:r.Ta ry : The cable splices met all the requirements as stated for type testing in Section 5.2, Enclosure 4 with clarification of certain items as follows. Aging (thermal and radiation [garna'! ) has been determined to be acceptable as per the guidelines in Enclosure 4 and is no longer an outstanding item. Beta lladiation also has been determined to be acceptable. \\ i a e 5 e e

BROWNS FERRY ENVIRONMENTAL QUALIFICATION IE BULLETIN 79-01B - ENCLOSURE 4 GUIDELINES INSIDE PRIMARY CONTAINMENT System: Containing Inerting (76) Plant ID No.: N/A ~ Component: Electrical Cable ,Model No.: PDfJ Test Report: N/A Summary: The Browns Ferry containment inerting system will be modified at the next scheduled refueling outage for each unit. The environmental qualification of the above referenced cables has been determined to be not necessary since CPJJ Cable (qualified) will be pulled for the containment inerting system instead of the PXMJ cable as stated in our initial submittal. (Letter from H. G. Parris to J. P. O'Reilly dated April 30, 1980.) 3 9

l t Dl!0'.1:15 rEl:ItY Ellvil'0::Mr.:IT/,I. 0!!A!.11 ICATIO'l IE l!Ui.1 Ell!! '/9-013 - i.i!L!.05Uhi. A Ct!!!)i.l.ll:l S 1)iil lil."Rili-t/si(Y CO:flA1illTCil ~ System: Contaiment inerting ~ Plant ID !!o. : FSV-76-49, -51, -53, -55, -57, -59, -61, -63, -65, -67 / Conponent: Flow Solenoid Valve liodel !!o.: 526D (Valcor Engineeririg Corporation) Test !!oport: Valcor Document flo. QR-526, qualification Test fleport for V526 Series, IEEE Class lE Solenoid Valves Supa r',': The solenoid valves met all the requircmalts as stated for' type testing in Section 5.2, Enclosure 4 tiith clarification of certain itens as follows. Aging (thermal and radiction [gann8) has been determined to be acceptable as per the guidelines in Enclosure 4 and is no longer an outstanding item. Beta radiation qualification is acceptable since solenoid is in a metal enclosure. 1 O e

-CRO',!;!S FERRY Fi: VIRO::'*r:flTAL 03ALIFICAT10:1 IE 00i.I.Lilil [ Sill; - !:;Cl.05U::E 4 GUIDill!;LS OUIE15E'I51I7.IiY C(!:ffhIIMOIf ~~~ ~~. System: All Systems Plant 10 I!o.: ft/A Component: Electrical Cable !!odel f:o. : SROAJ Cable Test report: Anaconda-Continental Report I:o. 79117 ~Sunrna ry: The electrical cable met all the requirements as stated for type tqsting in Section 5.2, enr.losure 4. Aging (thermal and radiation /Ganua/)has been determined to be acceptable as per the guidelines in enclosure 4 and i

longer an outstanding item.

BROWNS FEFRY ENVIRONMENTAL QUALIFICATION IE BULLETIN 79-OlB - ENCLOSURE 4 CUIDELINEs OUTSIDE PRIMARY CONTAINMENT System: All Systems Plant ID No.: N/A Component: Electrical Cable Model No.: CPJa and CPJ Test Report: Wyle Laboratories Report 43854-3, dated April 26, 1978 Summary: The electrical cable met all t..' requirements as stated for type testing in Section 5.2, Enclosure 4, for all phases of qualification including radiation and aging. (See qualification for these cable types for inside primary containment.)

DI;0'fil5 fl 1:!:Y l'!!Vil:'rl.".!!!TAL 0:!A!.11'1 CAT 10'! ) E lytt.1 I I I!! W2filli Tilb.i Ostilit? OliflilllliiX ~"Dif t.E ' dif~l [OI9:llil0id,fl i U'5 ~ i j S,ys t_cjil: Containment. Inerting (76) Plant.10 ilo_. : il/A Component: Electrical Cable __I'mici !!o. : PX!1] Cable s Test !!cnort: f!/A Su w.ry: As stated previously for tile PXitJ cable inside primary containment, tiie cable will not be used; instead, CPJJ cable (qualified) will be used. e e g G 9

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I;l;0'.!NS ITI:RY l'!!'!!i:0:! '.!.irlI.I. OUI 1.1 fI CAT 1If f 1E l'IllilTi }il"/!i-hlli ~iIII.i.IiM!ii'IiMilI!l.llIlli .O.UI.S!DE PRI:t!J:Y CO:Fl Alt:",r.f;T hystcn: Containment Inerting (76) I'lant ID !!q. : FSV-76-50, -52, -54, -56, -58, -60, -62, -64, -66, -68 Compaiwnt: Flow Solenoid Valve liodel A._: 526D (Valcor Engineering ' Corporation) i Test I:eport : Valcor Document !!o. QR-526, Qualification Test Report for V526 Series, IEEE Class lE Solenoid Valves EEEEO The solenoid valves met all the requirements as stated for type ~ testing in Section 5.2, Enclosure 4, with clarification of certain items as follows. Agina (thermal and radiation [ gamma'), has been determined to be acceptable as per the guidelines in Enclosure 4 and is no longer an outstanding item. f 1 't G D w._ e _....,_,..,.,,,,..._,,y.

SECTION 3 This section contains the evaluation sheets for those safety system components which were found to not meet the guideline criteria of IE Bulletin 79-01B, Enclosure 4.

BROWNS FERRY ENVIRONMENTAL QUALIFICATION IE BULLETIN 79-OlB - ENCLOSURE 4 GUIDELINES INSIDE PRIMARY CONTAINMENT System: Containment Inerting Plant ID No.: H E-76-37, -37A, -38, -38A, -39, -39A 2 Component: Hydrogen Analyzer (GE) ~ i Model No.: 47E226428-G2 Test Report: General Electric Report IRT-QRT-063 dated March 12, 1976 Summary: The hydrogen analyzer met all requirements for type testing in Section 5.2, Enclosure 4, with clarification of certain items as follows. The test pressure was 50 psig versus 55 psig required. This has been determined to be acceptable since the . total test temperature pressure curve was much more conservative than required, except for a short time when the 55 psig pressure was required. Therefore, these outstanding items can be considered closed. The hydrogen analyzer was d_termined not to be qualified in terms of radiation and aging (thermal and radiation [gampa])according to ' he guidelines of Enclosure 4; t j therefore, these are to remain outstanding items. These analyzers are scheduled to be replaced by a qualified system at the next scheduled refueling outages for all units. 4 h s- ~ m- -e n e --~-g g,m--e- -- n -,

SECTION 4 This section contains the evaluation sheets for those safety system components for which the qualification data found was either insuf ficient or unacceptable, i.e. the test parameters were not in accordance with the guideline criteria of IE Bulletin 79-01B, Enclosure 4. An Equipment Qualification Plan will be developed for each of the components listed in this section.

BROWNS FERRY ENVfRONMENTAL QUALIFICATIOM i IE BULLETIN 79-01B - ENCLOSURE 4 GUIDELINES INSIDE PRIMARY CONTAINMENT System: All Systems Plant ID No.: N/A Component:. Terminal Blocks / Terminal and Junction Boxes j Model No. : N/A Test Report: N/A Summary: Possible qualification exists in industry for terminal blocks if the manufacturer, model number, and serial number are known. No qualification data exists for the junction boxes; therefore, the qualification of the terminal blocks and the junction boxes as one unit would not be certain even if the terminal blocks were qualified. \\ l a 1 e i a 7 9 i se -en -,. = -ywg ,-%y v.-e- --w e t-Mywe-r -y y-+y --M

BROWNS FERRY ENVIRONMENTAL QUALTFICATION IE BULLETIN 79-01B - ENCLOSURE 4 GUIDELINES INSIDE PRIMARY CONTAINMENT System: Main Steam (1) Plant ID No.: PSV-1-179, -180 Component: Pressure Solenoid Va'lve Model No.: 1/2 SMS-A-01 (Trombetta Corporation) Test Report: Target Rock Report 2199A dated January 9, 1979 Sumn.a ry : The above referenced test report has been determined to be unacceptiale according to the guidelines of Enclosure 4. The qualification data which exists is not acceptable according to the guidelines of Enclosure 4 for the outstanding items of radiation and aging. I

DRO'.!;!S Il.'RRY flP!l PO:l:7Ml'lif Oll/.l.Ii1Cf1Ifri !E lhif,. l1i; 79-Oll: - 1itCl OMNS.~IldifliOlifil l ~ ~ ~ " l US1 DL l'R D'.OIY CD; iia'lldi!I;i~ ~ Sgrg: See attached sheet Plant ID I:o.: See attached sheet Component: Flo'.i Solenoid Valve l'odel !!o. : See attached sheet, Autbmatic S.iitch Company (ASCQ) .T_est I:eport : Plant Equipment Design Engineering flemorandum fio. 126-62. Sun: nary: The above referenced test report has been determined to be unacceptable according to the guidelines of Enclosure 4. It has been deternined that there exists no qualification data in industry or from the i vendor for the refFenced ASCO solenoid valves. e O e

/;. / .II_R_0]jl,S _JJ JJRJ,_(!!V I RO';jji_ljT[i., OJ!,'sj,1 F_l,CA,Tl_0,] l IE 1;ULLI:ll!! 79-Oll! - 1.i!Cl.05U!C 4 Cllll>! Lll!I.S j ]!:S]Ird l'Rl;'ARY CO:! s t.li::Kil f o } .S)'11C3 1. Main Steam (1) 3. Residual lleat P.emoval (74) 2. Sampling and Uater Quality (43) 4. Core Spray Cooling (75) Plant 10 flo. : 1. PSV-1, -4, -5, -18, -19, -22, -23, -30, -31, -34, -41, -42 2. FSV-43-13 3. FSV-74-54A, -68 4. FSV-75-26A, -54A 11odel llo. : 1. UPi!TX 83008-6?.r 2. 8300B-61F 3. HPilTX 8300D-45G 4. UPliTX 834472 4 e \\ 1 i t J

r 111:0;fi!5 fi1:!;V 1:l!V1l'R!:'.!!!TAL O!!/.I.1I ICAl10'! IE Islili i fi['/ti!61ii Tiik if9flif '4 Gtlilii1.li!!.S ~ Dul.(::!)E Pitll'/,i:V CO,; Tali;:iff;T SJJ_lgt: All Systems Pl ant 10 I!o.: il/A Coy anent: Terminal Blocks / Terminal and Junction Boxes l'adel flo. : il/A \\ Ter t iten. ort.: il/A Sinner : See comments on Terminal Blocks /Terninal and Junction Boxes for Inside prir. cry containacnt. O e O e 0 / r S e e d e

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IIIW.!;15 f! P.llY l';!V1I:0:!!'.I!!I AI. DU/-l_1 fICAII0'l It l'iiO'ITlii'iti~619 -- l i:C 0T.U::I 4 M!)iEl.!;;f S '"-olii'dijE"P!UiilliV 10!!IAl::.5III,~~~ Syr.t en: Reactor Core Isolation Cooling (71) e l>l an t 111 I!o.,: FSV-71-40 Conoonent.: Flow Solenoid Valve I:odel !!o. : UPHTX-834472 (Automatic Switch Company) 1 i Test ?:epoQ: Plant Equipment Design Engineering Merr.orandum flo.126-62 Sun n.'.r. The above referenced test report has been determined to be unacceptable according to the guidelines of Enclosure 4 It has been determined that there exists no qualification data in industry or from the vendor for the referenced ASCO solenoid valves. O I s O e 4 e o e O mm-0 e e O e

til:0'..'; S I El!!:Y 1:!Vila!!!!rAl Ot!AI.II'ICAT10:1 IE liil.'l t I'l!i'N iiil; 'lifOii91!iii 'i diflTO':lli t ~~ PUT_.".DE l'lj,1 'Ai'Y CO::TAlt ::U;T ~ ' _Sy.1 cm: Al1 Systems P1 an t. 1 D _!_!o_._: 11/A = cogjggn,t,: Electrical Cable _11._o. del !!o. : Pil, PilJ, and PJJ Cable s Ter.t !: no_r_t_: ll/A Su;na c.;: !!o qualification data exists for any of the above referenced type cable. e .O. e O eW " 8 e a e G e 9 0 e '6 g ~. 1 l

BR0k'NS FERRY ENVIRONMENTAL QUALIFICATION IE BULLETIN 79-01B - ENCLOSURE 4 GUIDELINES" OUTSIDE PRIMARY CONTAINMENT System: All Welated Systems Plant ID No.: N/A Component: Hand Switch Mode 1 No.: N/A Test Report: N/A Summary: No qualification data exists for any type of hand switch for type testing for ramperature, pressure, or steam as required by Sections ; O and 5.2 in Enclosure 4 for adverse conditions. __.m

SECTION 5 The following is a list of safety system components for which no information has been available to date. We expect that the environ-cental qualification data will be available in the near future. The results of our evaluation will be provided to you as soon as they are available. 1. Solenoid Valve: Automatic Valve Co., Model Nos. C5497-lH, C4988-8H, and C5577 2. Solenoid Valve: Cowan Dynamics, Series 20, Style GS-5 3. Temperature Switch: Fenwal, Inc., Model 17002-40 4. Temperature Switch: SCAM Instrument Co., Model 11-PX2 5. PVC Cable 6. Motor Operated Valve: Limitorque, Inc., SMB Series

ENCLOSURE 2 REVISIONS AND ADDITIONS TO INITIAL BULLETIN 79-01B RESPONSE LETTER FROM H. G. PARRIS TO J. P. O'REILLY DATED APRIL 30, 1980 BROWNS FERRY NUCLEAR PLANT (DOCKET NOS. 50-259, -260, -296) The enclosed pages are to replace the appropriate pages in the April 30, 1980 submittal. Several new pages are being added.

.FAc1LTTY: Browns Ferry 1)0CKLT 110. 2 50-259, -260, -290 insTI:n 1.IsT S!!EET 1:0. 3 SYSTI:ti: Main Steam (1) ~ ~ ~ C011PO.';E!!TS Location Plant Identification inside Pri. mary Outside Prima ryl Number Generic 1:ame Conta i nt.:en t Containment Electrical Penetration Penetration EE Assembly X Control CPJJ Cable Cable X SitLD Cabic (PVC) X CPJ Cable X ~ . Box Type JBD Junction Box X Term D,lk Pi1D Terminal Block X l Bendix

  • Electrical 10-21<i628-51 S Plug Connectors 10-214 023-51P Reca (Unit 3 only)

X Gutton Electrical 6448-1 cr 2 Plug Connectors 6445-1 or 2 Re'p (Units 132 only) X c t,aDie dplices Cabie Type CPJ, CPJJ, & Splices Vulkene (Ray chem) (Unit 3 only) X '

  • Add Bendix Electrical connector model riumbers: 10-214636-78S Plug

'10-214036-78P Receptacle 4

BrownsFerrb,-290 FACILITY: 50-259, -26 p sTtn List SilEr.T 1:0. 1 . liOCnnT !!O. SYSTr.;f:' Sampling and k!ater Qua'lity (43) h COMPONENTS Location Plant Identification luside Primary Outside Prir.iary Nu:r.be r Generic Name Containment Containment Flow Solenoid FSV-43-13 Valve X Control CPJJ Cable Cable X ~ Control CPJ Cable Cable X Box Type JBC Junction Box X Electrical Penetration . Pe'netration EB X Assa-hlv Term Blb PMB Terminal Block X Bendix ff Electrical 10-214628-515 Plua Connectors ([) 10-214028.:51P Rec 6 (Unit 3 only) X Gulton Electrical 6448-1 or 2 Plug Connectors 6445-1 or 2 Reco (Units 152 only) X ~ Cable. Splices Cable Type CPJ, CPJJ, & . Splices Vulkene (Ray chem.i (Unit 3 only) X '

  • Add Bendix Electrical connector model n' umbers: 10-214636-78S Plug

'10-214036-78P Receptacle ji

ii: . TAC 11,irl: ' Brouns Ferry DOCKET 110.: 50-259, -260, -290 psn:n 1.IsT SilEET 1:0. l U:!IT 1:0._1_ 2 _3 SYSTD!: Reactor 1!ater Recirculation (58) CO.'! PONE!;TS 1.ocation Plant. Identification inside l'rir::ary outside Prn.ia ry Number Generic Nerne Containment _,, Containment Flow Control FCV-58-1 Valve X ~ FCV-68-3 X .FCV-68-77 X FCV-63-79 X Electrical Penetration EA Penetration Assemb1v X Penetration EB x Penetration EE g Penetration EF X Control CPJJ Cable Cable X CPJ Cable x Bendix ** Electrical 10-214628-51S Plug Connectors 10-2140?8-51P Reco (Unit 3 oniv) X Gulton Electrical 6448-1 or 2 Plug Connectors 6445-1 or 2 Reco (Units 132 only) X 0 Junction Box type JSA is deleted because the box has no association with the referenced rive Add Bendix Electrical connector model n' umbers: 10-214636-78S Plug ~10-214036-78P Receptacle g

BrownsFerrf,-290 TACILITy: ~1)oci:t;T 1:0. : 50-259, -26 y3sTI:P. I.IST SilEr.T 1:0. 1 U:nT l'O.

1. 2.1_3 SYSTfff: Reactor !!ater Cleanup (69) b

' COMP 0;;E!;TS Location Plant Identification inside Primary outside Prir.>a ry Nuuher Generic 1:ame Containt.mnt Containment Flou Control FCV-69-1 Valve X Electrical Penetration Penetration EA Assembly X Penetration EB a' X CPJJ Cable' Control Cable X ~ Bendix

  • Electrical 10-214628-515 Plug Connectors 10-2_14_028-51 P Reco (Unit 3 only)

X Gulton Electrical ~ 6448-1 or 2 Plug Connectors 6445-1 or 2 Reco (Units 182 only) X 0' Cable Splices Caole Type CPJ, CPJJ, & Splices Vulkene (Ray chem) (Unit 3 only) X i e

  • Add Bendix Electrical connector model numbers: 10-214636-78S Plug
  • 10-214036-78P Receptacle 6

FACILITY: Browns Ferry 1)dCl;r.T No. : 50-259, -260, -290 psTt:P. _Li sT SilEr.T 1:0. 1 SYSTE!: Reactor Core Isolatinr. Cooling (71) ) CO.'! PONE!;TS Location Plant Identification luside Prir.:a ry Outsid TPrimary llumbe r Cencric 1: age Containment Containment flow Control FCV-71-2 Valve X t.lectrical Penetration Penetration EE Assembly X Penetration EF X CPJJ Cable Control Cable X Bendix 96 Electrical 10-214628-515 Plug Connectors 10-214C23-51 P Rocn (Unit 3 only) X Gulton Electrical 6448-1 or 2 Plug Connectors 6445-1 or 2 Reco (Units 1&2 only) X 4 Cable 5plices Cable Type CPJ, CPJJ, & Splices Vulkene (Raychem) (Unit 3 only) X (

  • Add Bendix Electrical connector model n' umbers: 10-214636-78S Plug

'10-214036-78P Receptacle O,

FACILITY: Broups ferry ' 130C!;LT !;0,: 50-259, -260, -200 psTr.n 1.1sT S!!Er.T 1:0. 1 SYST):!!: High Pressure Coolant Injection (73) C0!! PONE!!TS Location Plant Identification Inside Prir.!ary Outside Pri..iary Number Generic !!ame Con ta i n:.:en t Containment flow Control FCV-73-2 Valve X

t. l ec t ri ca l Penetration Penetration EA

. Assembly X Penetration EB X Control CPJJ Cable Cable X 1 .CPJ Cable X Bendix

  • Electrical 10-214628-515 Plug Connectors

~ X 10-214028-51P Reco (Unit 3 only) Gulton Electrical 6448-1 or 2 Plug Connectors ). '6445-1 or 2 Reco (Units 1&2 only) X Cable Splices cable Type CPJ, CPJJ, & Splices X Vulkene (Raychsm) (Unit 3 only) I ~ e

  • Add Bendix Electrical connector model numbers: 10-214636-78S Plug

'10-214036-78P Receptacle ~ 1 0 ~ L

bbbl'If bb.5 2 50Sb9,-260,-296 MASTER LIST SilEET !!O. L UNIT NO. 1_P.1 SYSTDI: Residual Heat Removal (74) COMP 0 net;TS i.oca tion Plant Identification Inside Primary Outside Primary Number Generic Name Containment Containment Flow FCV-74-48 Control Valve X / Flow FCV-74-78 Control Valve X Flow FSV-74-54A Solenoid Valve' X Flow FSV-74-68 Solenoid Valve X Box Type JBD Junction Box X Term B1k PMD Terminal Block X Electrical Penetration EA Penegt, ion Electrical Penetration EB Penetration Assemb1v X Electrical Penetration EC Penetration Assembly X Control CPJ Cable Cable X Control CPJJ Cable Cable X Bendix Electrical 10-214628-515 Plug Connectors 10-214028-5!P Reco (Unit 3 only) X Guiton Electrical 6448-1 or 2 Plug Connectors 6445-1 or 2 Recp (Units 1 & 2 oniv) X Cable Splices Cable Type CPJ, CPJJ & Splices Vulkene (Raychem) (Unit 3 only) X .=

  • Add Bendix Electrical connector model numbers:

10-214636-78S Plug 'IO-214036-78P Receptacle e g - .g

FACILITY: Drowns Ferry

  • Doci;cr 1:0.:

50-259. -2GD, -290 psTr.r.1.isT Sil' r 1:0. 1 SYSTDI: ' Core Spray Cooling ( 5) CO.'iPO!!EllTS l.oca t i on Plant Identification inside l'rimary Outside Prirary Nurabe r Cencric 1:ame Containment Containn:ent Flow khnid FSV-75-26A y F V-75-54 A X Electrical' Penetration Penetration EB Assembly X Penetration EE X Control .CPJJ Cable Cable X ~ CPJ Cable X Junction 4 Q Box Type JBD X Box Type JBE X Term B1k PMD Terminal Block y Bendix -k Electrical 10-214628-51S Plug Connectors 10-214028-51P Deco (Unit 3 only) X Cul ton ~ Electrical 6448-1 or 2 Plug Connectors 6445-1 or 2 Reco (Units 1&2 'only) X Cable Splices Laote Type CPJ, CPJJ, & Splices Vulkene (Raychem) (Unit 3 only) X 9

  • Add Bendix Electrical connector model numbers: 10-214636-78S Plug

'10-214036-78P P.eceptacle i

FACILITY: Browns Ferry DOCKET NO.. 50-259, -260 -296 MASTER LIST SHEET NO. 1 UNIT No. 1,2,3 SYSTE!!: Containment Inertinq (76) C0!IPONF.NTS Location Plant Identification Inside Primary outside Primary Number Generic Name Containment Containment FSV-76-49 Flow Solenoid Valve X 'FSV-76-51 X FSV-76-53 X FSV-76-55 X FSV-76-57 X FSV-76-59 X FSV-76-61 X FSV-76-63 X FSV-76-65 X FSV-76-67 X PXMJ Cable Control Cable X Electrical Penetration Penetration EB Assembly X Penetration EF X Bendix-10 Electrical - 10-214628-51S Plug Connectors 10-214028-51P Reco (Unit 3 only) X Gulton Electrical 6448-1 or 2 Plug Connectors 6445-1 or 2 Recp (Units 1&2 nniv) X

  • Add Bendix Electrical connector model n' umbers: 10-214636-78S Plug

'10-214036-78P Receptacle 9 7

c SYSTEM COMP 0NENT EVALUATION UORK Sill'ET Facility: Browns Ferry Unit: 3 Sheet No. 1 Docket: S0-296 ENVIR0tMENT 00CUMEllT ATION REF QUALIFICATION OUTSTANDING METHOD ITEMS EQUIPrit:T DESCRIPTION Speci fi-Qualifi-Specifi-Qualifi-Parameter cation cation cation cation System: Al1 Systems Plant ID No. N/A Operating Component: Electrical Time Connector Manufacturer: Bendix Tem ture SEE ACCIDENT AND t TEST PROFILES PROVIDED 1 2. Simultaneous Model Number: Pressure Test 10-214628-51S Plug (PSIA) 10-214028-4?P Recp Function: Cable Penetrathn Re.la tive 100 100 4. 2. Simul taneous Termina tions ilumidi ty(%) Test Accuracy: Spec: N/A Demon: N/A Chemical N/A N/A Spray Service: Penetration 7 Connectors Radiation 2.0 x 10 6.9 x 10 5. 2. Sequential (RAD) Test location: Inside Primary Nt Not Containment Aging 3. Required Required Flood Level Elev: 606' ~ Above Flood Level: Yes Submergence Not Not 3* No X Required Required

  • Add model numbers: 10-214636-78S Plug: 10-214036-78P Receptacle Notes:

1. See references on Accident Profile for LOCA/HELB. 2. Wyle Laboratories Report 44107-1 dated September 19,1978 (Wyle used same temperature-pressure Profiles as given 3. In the FSAR submergence and aging were not considered; will be in our next submittal by TVA for quali-fication. 4. From Accident Profile,100% Relative Humidity is intuitively obvious 5. TVA Design Calculation for LOCA/HELB at surface of primary containment.

l'ac i Ii ty: lirowns Icery SYSit fd Com'umNu tvmuA: tul! Vold..lili I Unit. 1&2 V Docket: 50-2S9, -260 Sheet No. 3 EfiVIR0i:MEftT DOCUMEf!I ATION REF QUALIFICATION OUTSTANDING P.E710D ITEMS EQUIPMEfT DESCRIPTION Specifi-Qualifi-Specifi-qualifi-Parameter cation cation cation cation System: All Systems Plant 10 No. N/A Operating Comp':nent: Electrical Time Penetrations Simultaneous Manufacturer: General Tempergture SEE ACCIDENT AND 1. 2., 6. Test

  1. Electric

\\oF1 TEST PROFILES PROVIDED Simul taneous Mddel Number: flodular Pressure 1.

2., 6.

n Test Series 100 (PSIA) Function: Cable Simul taneous Penetrations Relative Test Humidity (%) 100 100 4. 2. Necuracy: Spec: N/A Demon: N/A Chemical N/A N/A Spray Service: System Sequential Terminations Radiation 2.0 x 10 5 x 10 5. 2. Test (RAD) location: Inside Primary Not flot Containment 'g "9 3. Required Required Flood Level Elev: 606' Not Not, Above Flood Level: Yes Submergence No X Required Required 3. Notes: 1. See references on Accident Profile for LOCA/HELB. 2. , General Electric Report 74-502-3 3. In the FSAR submergence, and aging were not considered; will be in next submittal 4. From Accident Profile, 100% Relative humidity is intuitively obvious. 5. TVA Design Calculation for LOCA/HELB at surface of primary containment !A Tun... i l l nl un thn tnct nrnfiln in oranhical fnrm in next submittal / (Attache,n

/.. o -.,e.O s O -r e a d G u w "n w z

  • u O-C w

.s 9 A P af 7" Q O P 4 u a e a 0 E-e c-e e-e v o w p 2 o a o o a 4 w e 2 A r e %L .o in 0 4 l .. 3- 'e!J t_ ^ r a, e u z e n-g O w ci c e 1, e.- e LA A. a oo a' 1 N yi M O u L a> .is .o o c. 2 7 o e n 8, o o o o o 3 4 a g u 1 (J.) sacup3J u a L

  • \\

t

FacilityTiirowns Ferry SYSILf4 C0hl'Ohtlff EVALUAfl0N LORK SitLET U.ii t : 3 Docket: 50-296 Sheet No,, ENVIRO:OiEiT COCU:Ef!TATION REF QUALIFICATION OUTSTANDIf;G EQUIPME!;T DESCRIPTION METHOD ITEMS Specifi-Qualifi-Specifi-Qualifi-Parameter cation cation cation cation System: Al i sys te;r.s Plant 10 No. N/A Operating Cc.moonent: Electrical Time Penetrations Simultaneous Manufacturer: General Temperature SEE ACCIDENT AND 1.

2., 6.

Test Electric \\oFl TEST PROFILES ']"i taneous Model Number: Canister-Pressure 1.

2., 6.

t Type (PSIA) Function: Ca61e Penetrations Relative Simultaneuous Humidity (%) 100 100 4 2 Test Accuracy: Spec: N/A f Demon: N/A Chemical N/A ft/A Spray Service: System Sequential g Terminations Radiation 2.0 x 10,- 10 5. 2 Test (RAD) . Location: Inside Primary Containment, Aging Not flot 3. Rec uired Required Flood Level Elev: 606' Not flot ~ Above Flood Level: Yes Submergence Required Required 3. l'o X Notes: 1. See references on Accident Profile for LOCA/HELB

2. ; General Electric Reports EPAQ-007, 000, 009, 0/16, 055, 056, 057, 061 3.

In the FSAR, submergence and aning were not considered; will be in next submittal 4 From Accident Profile,100% R61ative llumidity is intuitively obvious. I TVA Dee,ign Calculation for LOCA/llElit a t surface of primary containment 5. 3. ..n m i -

F .e. o 'l c d K n. e, s, en p p, O^ =% gg US ( I& ,c0 g u n a .v 7 Y r et e' W Fe =- 2 C' M q m ts U -e P O o ge v N O r 0y u ,a w g <w. C

  • /

Yl er in e 3 2 M* yo O g J C,. V e .8 a 6 s p E N b 94 o A J r4 9 O e g 2 e ~ s ec 0 v r 9 7 tr >= S V .cd n O P O Y L o T O d P k e . e, o y e E O v y-O M g g f -{de} N "hldb31-O I

Facility: Hrowns Ferry SYSIEM C0r1P0flEtlT EVALUAl N)ll HORI','Silll:I

  • 1 l

Unit: 1, 2, & 3 0 cket: 50-259, -260, -296 Sheet No. 4 ENVIRONMENT 00CUMEllT ATI0ri REF QUALIFICATION OUTSTANDING EQUIPMEtlT DESCRIPTION METHOD ITEMS Specifi-Qualifi-Specifi-Qualifi-Parameter cation cation cation cation System: Main Steam (1) Plant ID No. (See Attache i Sheet) Operating 3. ~ Component: Pressure Time Solenoid Valve Simul taneous SEE ACCIDENT AND 1.

2., 6.

Test Manufacturer:. Automatic Temgture Switch Company TEST PROFILES PROVIDED Model Number: Pressure 1.

2., 6.

Simul taneous WPilTX8300B-68F (PSIA) Test Function: Main Steam Relief Control Relative 100 100 4. 2. Simultaneous fiumidity(%) Test Accuracy: Spec: N/A Demon: N/A Chemical f1/A N/A Spray Service: Main Steam 7 3.0 x 10 5. 2. 7. 7 Sequential 4 Relief Valves Radiation 6.0 x 10 Test (RAD) location: (3ee Attached Not Not 3. Sheets) j Ag ng Required Required Flood Level Elev: 606' Not Not Above Flood Levei: Yes Submergence Required Required 3. No X Notes: 1. See references on Accident Profile for LOCA/IIELB 2. Plant Equipment Design Engineering Memorandum flo.126-62 3. In th'e FSAR submergence, aging, and operating time were not considered; will be 'in next submittal 4. From Accident Profile, 100% Relative Humidity is intuitively obvious. 5. TVA Design Calculation for LOCA/IIELB at center of primary containment b. TVA will place the test profile in graphical form in next submittal -.a

c..,,,, a u ;,,, ;,,,, r,

,,,,n, g n n,,na,,,i ll rnnnet in novt submitta,

= n .L._....-^.--~~ .. ~ ~ - -

_ '^ ~

- ~ ' u t 7. TVA will research their files and talk to vendor for qualification for reducticn and will repsrt in next submittal l 8. TVA will. place the Test Profile in graphical form in next submittal. 9 Attached) Main Steam (1) ~ PSV-1-179 & PSV-1-180 Pressure Solenoid Valve Manufacturer: Trombetta Model No. SMS-A-01 9 O h a 1 l l

(. . s. s em Om o e 3 A o' T .> k C n 2 ~T W nos g f* " r t$ ( ( *o, O Ow E dd l e$ " a se v) en1 c' J J t) C' D U H O ^ s L t h. .a n a,W - } <t.j NS n s v a a-1e v n a u ^*. n DJ 8,,',f cs [ en p

c. n i.

O ^ Y r 'e u, et ? Z n 5 a e es er v vi , ~, =, y e 1 s P' o _e,3 ts-t O 5 m u a = s a y t c:r.n v \\ J = v w 7.W l .2 ~ ~--.. ~ ~ --~...-- f 5 ~ O e s O *u t.t -p.a .~ p r ') e-f E- -fip & non n /** A -9 % S'- 0 o* E o mye E' s V n-en \\ { l~' g ,- o O o n n -o o p a e n n' n e n u e (J.) 4V o n U11dW3 L a. D 0 e

q, SheetNo.( ta L L: Sb $9, 60, -29ti ENVIRONMENT DOCUMENTATION REF QUALIFICATION OUTSTANDING EQUIPMEHT DESCRIPTION METHOD ITEMS Specifi-Qualifi-Specifi-Qualifi-Parameter cation cation cation cation System: 5. Piant ID No. FCV-73-2 Operating Component: Flow Control Time Valve Simultaneous 1' 4** 6* Test Manufacturer: Limitorque Temperature SEE ACCIDENT AND 1 Fi TEST PROFILES PROVIDED Simultaneous Model Number: SMB-2 Pressure 1. 4;, 6. Test (PSIA) Function: HPIC Steam Line Simultaneous Inboard Isolation Relative 100 100 2.

4., 6.

Test

lumdity(%)

i Accuracy: Spec: N/A Demon: N/A Chemical N/A N/A Spray Service: HPIC Steam Line 3* 4., 6' Independent 7 3 Rcdiation 6.0 x 10 2.00 x l'0 Test (RAD) location: Inside Primary 4higot Agir.g pfl quired R quired 4 Flood Level Elev: 606' Above Flood Level: es Submergence quired .P quired 5. 9.- v.'. ~

  • High Pressure Cooling Injection (73) 4 Notes: 1.

See references on Accident Profile for LOCA/liELB 2. .From Accident Profile, 100% Relative llumidity is intuitively obvious 3. TVA Design Calculation for LOCA/HELB at center of primary containment 4. Limitorque Corporation Test Lab Report 600456, November 1974 November 1968 Franklin Institute Research Lab Test' Report F-C2232-01, ~ 5. In the FSAR s'ubmergence, aging., and operatin() time were not considered; will b6 in next submittal f cne 8, m el 'nf fbic e k r.r. f- \\_--

l'.ic i l i ty : Brown',' l erry SYSILM COMPUtlLill LVAI.UAlluti UOltt '.lli t.I (T Sheet No. 'Joit: 1, 2, 3 Docket: 50-259, -260, -29G ENVIRONMENT 00CUMEtlTATION REF QUALIFICATION OUTSTANDING EQUIPMENT DESCRIPTION METIIOD ITEMS Specifi-Qualifi-Specifi-Qualifi-Parameter cation cation cation cation Plant ID No. (See Attache.1 7 '- Sheet) Operating Component: Hydrogen Time t Analyzer-1. 4., 6. Manufacturer: General Tem ture SEE ACCIDENT AND Electric TEST PROFILES PROVIDED Mod 21 Number: Pressure 1. 4., 6. 7. 47E226428-G2 (PSIA) Function: H Accident A alysis Relative 100 100 2. 4. liemidi ty(%) Accuracy: Spec: t4fg Demon: ft/A Chemical fl/A N/A Spray Service: }{2 Analysis ~ 7 7 Radiation 6.0 x 10 3.2 x 10 3.

4., 5, 7.

(RAD) location: Inside Primary Not flot 7. Containment Aging (See Attached Sheet) Required Required Flood Level Elev: 606' flot flot 7 Above Fload Level: Yes** Submergence Reuqired Required No Notts: 1. See references on Accident Profile for LOCA/ilELB 2. From Accident Profile,100% Relative Humidity is intutively obvious 3. TVA Design Calculation for LOCA/HELB 4. General Electric Report IRT-RT-063 dated fLrch 12, 1976 7 5. A radiation dose of 1.6 x 10 RADS given before test, and then an additional dose of 1.6 x 10 RADS after test, giving a total of 3.2 x 10 RADS l ,... s.. t. 4,.,1 r,. 4 ..r..,+ c. 43.w i t t ; 1/ ( A.,.i. ,n ) r v... si3 .s .i. r:i

i e. hh, . e, e 4 W pd l' 4-C 2 g e I o. h o es O 7 O 2 Cf G H r* v4 l W e w I Q. .lrc

11. o. o o vi o

O 0l-C o e4 3 e e J = ? C i o 1 d4 6 -t i tt

  • ,o t

e e D3 s ~L 0 Lg ni og - t h ss I l e J+

u. E o.

o c. Dc& s es* r .r) ,,. ? E e r u - J w 4 n o p9 to m I f.*. s 8'l fl. M o r 1w nM + o o o o m e o o A 9 . e4 N (.s.) n et tus3.sw3.L 0 4 e O g M. e....

I.n. i l i t y : Urowns Ierry NY'illil COMi ufil'NI l. val.llAI lilli UUld. *.1111.I %Q i Unit: 1, 2, 3 Doctet: 50-259, -260, -296 Sheet No. 1 ENVIRO:;.:ENT DOCU::Et;TATIGN REF QUALIFICAT10N OUTSTAtDIt;G EQUIPMENT DESCRIPTION METil0D ITEMS Specifi-Qualifi-Specifi-Qualifi-Parameter cation catic.n cation cation g System: Plant ID No. FSV-71-40 5. Operating Component: Flow Solenoid Time Valve Simul taneous Manufacturer: Automatic Temoerature SEE ACCIDENT AND 1. 3., 4. Test Switch Company \\OF1 TEST PROFILES PROVIDED Simultaneous Model Number: WPilTX-Pressure 1. 3 4* Test 834472 (PSIA) Function: Test CHK Valve Simultaneous Relative 100 2. 3. Test Accuracy: Spec: N/A Demon: N/A Chemical N/A N/A Spray Service: RCIC 14ater Sequential 3 7 Radiation .9.0 x 10 3.0 x 10 1. 3. Test (RAD) location: Outside Not Not Prim &ry Containment (Main Aging 5. Steam Vault Room. 565') Required Required flood Level Elev: N/A Above Flood Level: Yes Submergence N/A N/A. No Notes: 1. TVA Design Calculation for HELB 2. From Accident Profile,100% Relative Humidity is intuitively obvious 3. Plant Equipment Desi5n Engineering Memorandum No. 126-62 4. TVA will place test profile in graphical from in next submittal 5. In the FSAR, aging and operating time were not considered; will be in next submittal -}}

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