ML17320A661

Qualified Test of Electric Cables Under Simulated Loca/Dbe by Simultaneous Exposure to Environs of Steam/ Chemical-Spray & Radiation.

ML17320A661
Person / Time
Site:	Cook
Issue date:	11/30/1975
From:	ISOMEDIX, INC.
To:
Shared Package
ML17320A662	List: ML17320A661 ML17334A477
References
REF-SSINS-6820 NUDOCS 8308160311
Download: ML17320A661 (97)

Text

QUAY XFXCATXO J '"3 ST OF ELl'iCTRXC CA".L)"S UNDER A SXl IULA'I'iD LOCA/DBE BY Sl t!Ufr'.I"ANEOUS EXPOSURE TO ENVXRONHEINTS Ol Si'EAl",/CHEHXCAL-SP. >.Y 'ID PuXDXATXON c

PERFGK"'D FOR ESSEX XNTERNATXONAL PO'lZR CONDUCTOR DXVXSXON LAFAYETTEi XNDXANA qa O0C. iliOE SER,I +

OAn ~l J KeYrIDRQs BY THE CO"1PONENT TES'J.'XNG DXVXSXON 2~

I X SOYA I)XXr XNC.

s.

PARSXPPANY~ NEh JERSEY REF, CXP, NOVP.ID3ER, 1975 ACCEPTED FOfi g/A BY El.ll'"i(tlv GEHERATlOH SE rl0$ ~f.!"'..C, ll. Y, 8308i603ii 8308i0 PDR *DOCK

't ACCEP7ED CY:M+

050003i5 PDR W,tt: ~~M.~~

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-~r I atilt di> lt-rt.- 2~ FO.ttn nS iSi~d PO- ilip~ny t"0 y J.t"y (201) GO'i'i'00 tT'g~ {g tsstlirrct jidcrcss: nnst olfisc tiox 117, I'nriltrt~ny, I':csv Jersey olOq4 CIIIChGO 0 I'VIGIOrt ~ 2020 N pic Avc., t torlon Crorr, Illtnnts 00083 ('312) ".00 I I GO

TAnLr O>" Co'iTi WTS Section Page

1. Xntroduction and Sununary...-------.--..---..-.-. ~ ~ ~ 0 0 ~ ~ ~ 0 1

2. Description of Cable Samplrs.. - . - - - - - - - - - -- ~ ~ ~ ~ 0 ~ 0 0 ~ 0 ~ 0 0 30 Test Program........................o...........

~s ~%I ~ ~ ~ ~ 0 ~ ~ 0 ~ 4 301 Purpo4)e ~ ~ 0 ~ ~ 0 ~ 0 ~ 0 0 ~ 0 ~ 0 ~ h0 ~ 0 ~ 0 ~ ~ ~ 0 ~ 0 ~ 0 ~ 0 ~ 0 ~ ~ ~ ~ ~ ~ 0 0 ~ ~ ~ 4

~ 3.2 D lscusslonss ~ ~ 00 ~ ~ 0 ~ 0 ~ -.

~ ~ ~00 ~ ~ ~ ~ ~ 000000 ~ 0 ~ 0 ~ 0 ~ ~ ~ ~ ~

0

~ ~ 4 t

3.2.1 Phase l. Thermal/Radiation Aging- - '- - ~- ~ 0 0'0 04 3.2.2. Pha es XX and XXX ,. LOCA Simulat:ion and Post-LOCA Cooldomn....-.-.-'.------- ~ ~ 0 ~ ~ 0 ~ 00

3. 2. 3 Pos t-LocA Tes ts............. - .'- . - - - - - ~ - - - - 0.05 4 est Procedure................;.....-.-- ~ ...... 0 0 ~ 0 ~ 0 0 ~ 0 7

~ r r -'; 1 Cable '3dounting'. r.'...".. 0 0 0 0 0 0 ~ ~ 0 0 4.2 Lrlectrical Energizing and Xnt:erconnections.........7 4 .3 Dose Unl.forml.ty................'..',........'........'.8

4. 4 Neasuremen ts o f Xnsulat.ion Res is tance (IR) ......... 8

4. 5 High Volt:age Niths tand Tes ts r

(Hi-Pot)..... 0 0 0 0 ~ 0 ~ 0 h

10 T eSt ReSult S 0 ~ 0 ~ 0 0 0 0 0 0 0 0 0 0 0 0 ~ ~ 0 0 ~ 000 ~ 0 ~ 0sltl 5.1'ctual Temperhtur'e 'Pro+i3,e....'........".....

r'0 0 0 0 ~ ~ ~

5. 1.1 Thermal/Radiati'on Aging........--.-.

. 5.1.2 Phases IX a>>d XXX I'OCA Simulation and Post,-LOCA Cooldsson................. ~ ~ 0 ~ 0' 0 ~ 13 5.2 Performance of Test: Cables.... -. -. -. - - - - - - - - - - - ~ - 015 5.3 Xnsulation Resist:ance Hcasurements... ~ shs 0 0 0 ~ ~ ~ 0 ~ ~ 0'15 1

5.4 High Volt:age tJithstand Te't (Hi-pot) 0 ~ 0 ~ 0 0 0 ~ ~ 0 \ ..18 J

6 Cert1flcatlon..........,..............

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000 ~ 0000000 ~ ~ 19 Appendix A Radiation Certification

L'EST 01'IGUlU'.S Figure No. Page Specified Environmental Exposure Profile..........;6

2. Schematic representation .of T'.nergizing C circuitry.;.........................

1 4 ~ 0 0 ~ 4 ~ 0 ~ 1 9

3. Actual Temperature Profi le Ob tained D urging Test....................,...................12 '

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( LXST OF TAf3T.ES Table No. Page Description of Cable Samples.........---- ~ 0 t ~ ~ ~ ~ ~ 0 0 ~ ~ 3

2. Summary o f Cable Removal From Energizing C'rcuztry........................... o s ~ ~ 'o o ~ e ~ a 16 3'. Measurements of Zn ulation Resistance......... -. -. -l7 4 ~ Results of gati-pot Tests Performed at Conclusion of 37 Day Environmental Exposure......18

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1 SECTXON 1 XNTRODUCTXON AND SUHL'IARY qualification,test on electric cables ~ras performed 9.n accordance with the suggestion contai.ncd in XLEH 323-1974, F

"IEEE Standard for Qualifying Class lE Equipmc>>t for Nuclear Power Generating Stations", and XHEE 383-1974, "XEEE Standard F

for Type Test of Class lE Electric Cables, Field Splice C

and Connections for Nuclear Power Generating Stations."

1 ~

~ ~ ~ ~

F r,

Twenty-five 1/c-12 Awg cable samples were subjected to a.7 day simultaneous t:hermal/radiati.on aging exposure, F

~ ~ ~

followed by 'a '30'ayimultancious e'xposurc to environments.

of radiat:ion stcam and chemical-spray, while electrically

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nergized at rated volt:age and current loadi.ng. This loading

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consisted of a potential of 600 volts (a.c.) between conductors

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and to grounQ and current loading. of 15-20 Amps. on, each F

conQuct.or.-

F F F I

Approximately 50,. feet of each pable sample was subjected to the exposure environments. Thc sample. srcre irradiateQ in

, a Cobalt.-60 field of gamma radiation at a rate resulting in a F

total accumulat;eQ exposure of 200 megarads, air equivalent, over the entire test period.

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l~easurcrncnts of in ulation rcsi. tancc wore made periodically durin'g tho expo"urc period at 500 volts (d-c-).

'Eligh voltage with. tend tc ts werc conducted at: thc cnd of the exposure period following a 40 diameter mandrel bond Z

test with the cables imrnc rsod in water. 'I

~ l Thirteen cable samples wi thstood the entire tes t exposure and. succes fully complc ted the high-pot tost performed't the end of the program. The high-pot test ::-

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gas conducted at a voltage lovel of 2.2 HVAC corresponding I

'to baize the r'ed vol'thq'e..plus"'a .1000'olts A.C. 'Current

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I leakage measured during the high-pot

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tost varied'otweon

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1.2 milliarnps and 5.5 milliamps. ~ ~

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~ r The test program was conducted during October and .

November of 1975 "at the test 'facilitics ofme'dix,'nc..'

I in Parsippany, New Jersey. C

,C 0

'ECTION 2. DESCRIPTION OP CABLE SA)4PLHS

~! .

Twenty-five cable arnples were received from E,ex, ranging in sizes from .162OD to .230 "OD. The following table describe" the samples as they were received from Essex with the sample numbers as affixed to tho cable 1)y E. scx and the corresponding tag nur'aber af fixed by Xsomedix.

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TABLE 1

~

DRSCRXPTXOH OF ShlaPLH Xsomedix Ta ~

lJo. Essex Tag No. Dosoription ~of Sam lo Nhite, brittle 2 Brown, brittle 3 35,,

'. s Nhite, brittle Brown, brittle

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Nhitc, brittle

.. 6.

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.Nhite, flcxi'ble ..

S 7 Black, flexible (

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8 8 Black, flexible 9 ~,

'(

26 ~ h

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fbi:te, flexible.'

r 10 10 Black, flexible ll Black, flexible 12 12 Black, flexible

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13 Grey, pongy.h

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14 Brown, brittle '.

15 1S Brmrn; brittle Purple, brittle.

'.6 17 . Black, flexible 18 ~ ( Black, flexible Black, flexible

omedix Tag Ho. Essex 'L'ag Ho. Descry>Lion of Sneple 20 20 Yellower, brittle

~

21 21 Black, flexible 22 22 Brown, flexible 23 23 Black, flexible

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'24. 24 (  :. 'rorrn, flexible

~ 4. F 25 .".,': Grey, 'spongy i ~

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SECTXON 3- TEST PROGRAM

, '3. 1 PURPOSL..

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The purpose t:1ie program was to 'prove.de qualify'.cation

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tests on electric I

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cables in accordance with the suggestions'

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. . .contained in XEEE 323-1974,'XFEE Standards for Qualifying

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Class lE Equipment for Nuclear Powered Generating Stations",

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,and XEEE .38'3-197.4, "XEEE S,t.andard. for Typ.e. Test of lE'.

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I Electric Cables, Field Splices and Connections for Nuclear Powered. Generating Sta'tions". ~ 'f

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I 3.2 DXSCUSSXONS. rC

3. 2. 1 PI)ASE 1. T1IEIU4AL/RADXATXON AGXNG The cable samples vere installed inside of pressure I

vessel and placed in a radiation chamber and subj cted to'a 7 .day thermal/radiation aging environment with.the 4 temperature inside the vessel maintained at 250 F. FRadiation ~ias from

a Cobalt-60 source of gainma radiation at an exposure rate re ulting in an accumulated equivalent air dose of 50 megarads during this period.

3. 2; 2 P)iA."ES XX AND XXX X OCA . XHUI ATXON AND POST-LOCA COOK DOh~il At the conclusion of 'h'is simulated installed-life aging cycle, the samples vere e>:posed to a simulated loss-of-coolant accident'LOCA) environment by simultaneous

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application of radiation/stcam and chemical-spray for a

'eriod of 30 days in accordance with the temperature

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..:.profile s)io~m in. Figure'Al..of Apper dix A og-'XEf,E 323-an,d I as shown on Figure l. The samples sprayed with a chemical solution consisting boron as were continuously h

of boric acid in solution with 0.064 mo3.ar sodium thiosulfate buffered with sodium hydroxide to' pH 3000 ppm 5

\

. between 9 and ll 0" at room tempexature. The sprav rate was I

, approximately.. 2..gpm corresponding to .0.15, gpm/ft2 of the surface area .of the mandrel. I rC ~

C The cable samples received an additional radiation dose of .150 megarads, air equivalent, during thi" portion of the test program.

3. 2. 3 POST-LOCA TESTS At the conclu. ion of the simulated LCrCA event, the vessel was t aken out of the radiation chamber. Tne samples

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PHASE ' 1

-" '- ": '." ' '. ' PHIZ:II '" '-. '

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.-. ':". -.-.. ' 3

'- PHASE III Thermal/ LOCA Simulation by. simultaneous.: . Po t-LO~

Radiation. en(:a.l Z-closure (S/C/R)....- '."... '-.

itin Cooldovn

..:."..:.'.'nviron.

~ging (T/R') I I.

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IQ3. e...~335/95 )P

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'46/113 1

t (S/C/R)

Q Gc . IR ':" ~315/69 I-:::

.IR G

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265/28 j...

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A 280/70 ~ ~

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'50 l50 215/2' g Brad . Iegarad (daily) r

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'I iII, Twl.ce

~, Each week

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14D/0 3'HR.:".'."i'9hZ. ',.1 HZ. 1 aZ .:.:

.h Days,,'.

'R

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'hK r ... '...'...: Days'-

. 4 Di IR Temperature/pressure p"ofile'or simlation of loss-of-coolant accident (LOCA) design ba"is event (DBZ)'y. simultaneous steam/chemical-spray/radiation environ-mental exposure (al.ter XZZE 323-197 ficrore Al of Appendiv A) ~

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were removed from the mandrel, straight:ened and recoiled around a mandrel whose cliamcter was 40. times the cable diameter. While so -wound, the cables were in pected for I II cracks, inner ed in ~rater and ubjected to high voltage withstand te ts at 80v/mil (a.c.) of insulation.

t SECTXON 4. TEST PROCEDURE

~ ~

4 1 CABLE HOUNTXNG

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The cable samples were mounted on holding rods positioned between thoro end cap flanges of a 'vertically I

hei'd'etal mandrel, approximate'ly I~ ~

2'0 'inches in diameter.

t Steel wire was used to secure the cables in po.,ition /

relative to the vertical rods. Approximat:ely four feet of each cable end was brought up through the middle of the,magdr 1. These ends'tere brought through head.

penetrations in the pressure vessel, s'ealed and connected to-'he energizing lead wire. 'ealing ~ras effected by I

securing the cable ends in aluminum tubes with an. epoxy compound. The t.ubes were secured to t: he vessel by I

standard tube fittings.

4.2 ELECTRXCAr. EwERGXzXr)G AND XNTERCONWECTXONS The cable ends frere -ecured to terminal blocks mounted on the ve el head. The lead wire, suppliect by E sex Xnt:ernational, connected the energizing svritc)> box wi.t:h t: he test cable.s at. tl>c. tc.nninal'lock on the ve..e'1

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head- The switch box con..isted of knife switches arranged so that each cable could be individually monitored; removed from the circuit if a failure.occurcd, or isolated

\ 1 during measurements of in ulation resi tance.

Figurc 2 is a schematic diagram showing the energizing circuitry and cable connections.

~ ~ rr 4.3 DOSE UNXPOHHXTY

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Dose un'. formi ty was ob tai>>ed by ' rcpos itioning the

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'5 Cobalt-60 source at various s tages throughout the exposure and by rotating .the vessel.. Rotation was performed

'ycle 1

~1 $ ~ ", '

% Bays -aft'e'r ',initiating 'belie. seven day thermal/radiation aging and again fifteen days after the initiation of the

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steam exposure cycle'.

1 1

1 1

Appendix A contains the certification of radiation

..exposure and describ s the dose di tributiori and source I \

positioning.

r 4~4 MEASVRFMENTS OP XNSUI,ATXON RHSXSTANCE (XR) '1 XR measurements werc made periodically during the exposure cycle a a >neans of monitoring the relative degradation of the'est satnplcs.

Specifically, the XR mca urcments werc made at /he following time during the proqr<<m:

l. Upon receipt of samples, prior to radi<<tion aging, whileI wrapped on the inandrcl <<nd irrtncrscd in water. ~

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CUf<Rf: N T POTENT I.AL TRANS f'ORAL R CUPPFNT TRANS f'R! 1i'R TRANSFOR!!ER ODD

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8 ~10 12,'.4 1S . 20 ,22 ,24 r + ~

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2 S CHEMATI.C , REPRESENTATION -OF.ENERGIZI NG, CI.RCUI TRY r t. '.:"i; '

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2. EEalfway through the even <lay tlrcrmal/radiation aging period.

3. At the end of the thermal/radiation aging per'iod..

'4. At each dwell during the high temperature phases

. of the Steam/Chemical/12'.Qiation exposure perioQ.

5. 'nce each day during the four day dwell at 265 .P.

6. Twice per week during the balance of'he 30 Qay 1

~ \ .t period and at the conclusi'on of the exposure cycle.

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'L The me'asurernents were made a.fter application of I 500 Vdc held for one minute','nless specifically noted othe'"ise,

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,,j by reading between the concluctor'irectly to around.: '..

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c Prior to actual'ly.-mr~king the measurements, the

'.'.'urrent and potential load were removecl for approximately

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ten to fiiteen minutes. At the conclusion.oi .the IR

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- -"-'..:..";"applic'ation measuiements, all cables were.put back into the circuiting unless excessive leakage was observed that pronibited the of thh full-potential load or.

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7 short-circu'it 1 I ~

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'"I:.'., '" to ground had occured.

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HIGH VOLTAGE NITEESTAND TESTS (EEI-POT)

Samples that jer formed satisiactorilv during the

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straightc.nod and wound around a mandrel having a diameter 40 times the cable diameter; r

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The amp le s while wou>>Q on the mandrel, were immersed in wate r with the ends free. The conductor was connected to the high voltage lead and the ground wire inserteQ Qi rectly in the water. The required test voltage was 2200 Vac, or twice rateQ voltage, plus 1000U. r t

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The specified voltage level was applied for a 1 ~

perioQ of 5 n>inutes af ter which time the charging current was'ecorded. I

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SECT1ON 5. TEST Rl'SULTS

5. 1 ACTUAL TE;biPI'iRATURH 'AOFXLE 5 1 1 Thermal/Radiation Aging The temperature profile obtained during the actual test phases is shown in Figure 3. The test was initiated by'nergizing the cables and placing the cobalt source in position.

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... Strip heaters on the. vessel,Here utilized.

I in conjunction with the cable current. heating loads'o raise the temperature from room ambient to the aging level.. EEeater controls and current loads were adju ted 'o that the temperature remained at 250 + 10 E" throughout the remainder of the seven day I

~ ~ ~ ". '41 "L'UAh 'J.'5i'i "j"LCAYUJ(e'i6..'L t 05'L'A~B~U UUlCLLVU S XYiGLTANEOUS S " A~i/CHB<" 78~-S P BAV/RADIATZO~I~

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ENVXRONYiEa<TAL SiJiiE r I ~

';nd ls't . ~I ~ 'I

. Tra.".sient i-Indicates XR read--.c o ~ 0

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I 33814or

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P 330 ~

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314+2or: ', I

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ncrease ".~ '. I f

~ k to 3 38or within 5 min.- $

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266P2oP ~ I I' ~ 1~ 4

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." End Test

'tart

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of Sp'C/R

'Exposure I'

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25 50 50 3 5

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8 Elapsed Time (ET) Hrs. Frc.

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'. 15 Start of S/C/R .Exposuie

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96 723 I

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period. Four and one-half days after starting,

'. the system was shut down so that XR measurement could be made.

~ ~ I 5.1.2 Phases XX and XXX LOCA Simulation and Po't-LOCA Cooldown

.At. the start of. the.

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steam expo ure, the

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cables were energized and. the ambient temperature

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the exposure was underway. ~:

I To initiate the exposure, steam was rapidly

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1 admitted raising- the temperaLure" and pres'sure I I~

to'38oF

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psig within I

~ and 112 10 minutes.

Approximately fifteen minutes later, a leak was h

detected in a pres ure fitting that necessitated a drop. in pressure to atmospheric during the next.

~

twenty-five minutes.

The steam remained off for a period of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

'while the temperature was myintaiiied at 240 F us'ing

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electric heaters to avoid a severe thermal hock when the steam was reinitiated.

The nece sary repairs'were made 0

to the fitting and the exposure was resumed by reintroducing steam that increased the teriperature from 260 >" to 340oF during the next. five minutes. The temperature was maintained at 330~ doF Cor the remainder of the three hour period of the transient.

1 Q) )()

() ll of thi period, ' controlled l

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~o+peraturc (lr((l) " initiated that reduced the turo to 'e<')pora over the next l. 5 hour".

transient was then'nitiated by Lntroducin(J ) (

(l,l:) that r .i 'cd tho temperature

".o 338 F witI)i>> pf v'. minutes and held it. at that

>,.t '"hree hours.

po> nt. for the ras then reduc 330 F and hc 1(~

re reducin 3140 F and 314 hol(~ j(il. ~n additional four liours-I

'( (ll.. tiulel'a -co)ltrollod drop was,'

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initiated that ,.('lu:.cd the temperature to 268oF

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'I over the nov.t ~ f,~I())) t} minutes and w>ls maintained

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. at 266+2oF nor. t~) c balance of four days at which .

ti)ne the temp())" ,, turc was reduced over the next 1,~, for

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/+I ( nomina 1, the remainder

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half h hour to t7

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..;of 'the. <.'A...o

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a expeisur() .

The )) l'>>,,ly solutionwas injected into t~ r.. I

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tho chamber ono mi nute o f tarting the w~

exposure at 0

, (~ c of appro'ximately l.5 gpm an(l was rocir('<'~,)

~>>tc(l within. the next oven minutes.

~,.)y .olution p?f was between ho

pray was tuinod off (lurillg ~

> 5 and 10. 5.

turnod back on six hour ,f,<<f r period (nd

>h('-n the cxp(l('>>'

was rcinitiatcd. The spray J(1()haut tho romai)ldor OC t?le rclnaincd on gl

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evposure.

At an Elapsed !ime (t'.T} of 539 hours, the sy tern was shut: down anQ'he'essel rotated 100o to maintain uniformity

. of the dose distribution.

At a total test time of 37 days,'he last 'I

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set of reading frere made and the system shut .Qo;rn.

The vessel was removed from the cell, the samples removed from the vessel, inspected and me surementsI of withstand voltage made. ~

~

I 5.2 'ERFORMANCE OF TEST CABLES

~ " ~,

,The cables. frere electrically energi?ed at *a

'otential of 600 Vac between conductors throughout the

( entire evposurc period except during vc sel r'otation and periods when XR measurements ~rere made.

'I

'I The current loads were maintained within

l5.5 anQ 19.5 Amps during 'the entire test" period.. Table

, 2 shocks the times when the cables were removed from the t ~ ~

energizing circuitry.

5. 3 . INSULATION RESISTANCE NEASURFHENVS

'Measurements of XR frere made at the times previously mentioned and the rc ults are shown ip Table 3 as a function of the environmental parameters.

TABLE 2 I I ~ ~ ~

SUixlMARX OF CABLE REEK)VAL FPOwl Eel'RGIHXHG CX'RCUXTRY Sample No.

'3~ 18~ 24*: '" ':" "'

Elapsed Time(hours) 185.3

'191

Phase simultaneous phase.

'uring of Test During 1st transient of $ /(

1 .'

'"'::"..:..: .. 2nd 'transient.

'.';: '4, .'25.7 g

,'23* 225.5, at dK'1ell

': " . During 4

265oF.'0

~

282.1 During Post-LOCA Cooldo.rn.

~

4, ' . 205.1 ':

During Po t-LOCA Cooldoirn.

2 ...:.

'2, '22.7,

. During Post-LOCA Coolcro'rn.

5,-. 15,, 16 During Post-LOCA Coolc~o;;n.

.. 10 ~

'55..1 'uring

'uring Post-LOCA Cooldo!~n.

~

.".'.;.'. -.13 ,'- ., "..

'," ".,."....,';". 778.0 I,

658.7

. During Post-LOCA Cooldo"In.

Post-LOCh, Coolclo'.~n.

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. "Put.back into circuit at.elapsed. time of 253.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. g

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TAaLE 3(1).

MEASUREMENTS OF INSULATION RESISTANCE (1)

Elapsed (2) Phase Temp Press Time (hrs.) (3) oF si . 1 2 3'.68xlp Pr'e 70 0 1.1xlp 9 1.4xlp 0.78xlp 9 Sxlp.

91.7 TIR 240 0 0.78x10 184.5 END TIR 101 0 2.1xlp . 1.8xlp 2. 4xlp?

187.3 LOCA 339 110 0.51x106(4) 1.1xlp" 4000 (7) 192.9 . LOCA 336 105 11 (7) , 1.2xlp? 2000 (7) 197.5 LOCA 316 74 14 (7) 3.1xlp 7.5xl02(7)

'204.1 LOCA 268 25 13 (7) 1 3x108 2. 8 (7) 277 3 LOCA 266 30 13 (7) 1 Sx108 800 (7)

,,251;2: Post .13.(7) ...

282.5 Post LOCA LOCA F68 214 .

0 '1613

.>0,.:

'(7)

- ~

1,.6x108-...

'3x104(7) 90Q. (7) 800 (7) 325.4 420.0 Post Post LOCA LOCA '06 218 2 0 13 (7)

(7) 400 (7) 480 (7) 75 (7) 1000 (7) 15.3 92.1 Post Post LOCA 194 216 0 17 (7)

(7) '50 1300 (7)

(7) 1200 (7) 13

'00 LOCA 0 683.1 Post LOCA 205 0 12 (7) 600 (?) 1.104(7) 756.4 Post LOCA 204 0 13 (7) (7)

'P6.6 Post

'i est LOCA ?P P l.gxlP11 0.55xlP11 0.9xl011

'(1') 'Al'1'easuremens made'at 500 Vdc, held for 1 minute,. a'nd all resistance values in ohms, unless otherwise noted.

(2) Elapsed Time (ET); total thst time from the start of Thermal Radiation

-.(3) Test phis'es p'er'outline described in section.'- J (4) Measurement made at 300 Vdc.

(5')'easurement niade at 100 Vdc.

(6) Measurement made at 75 Vdc.

(7) Measurement made at 3 Vdc.

(8) Measurement made at 200 Vdc.

(9) Measurement made at 10 Vdc.

6 7 0 7xlp12 3xlpll 0. 88xl viz xl pl2 0.64xlplz 2. Zx] pll 0.8xlp Sx107 4 . 4x107 ' l.. Ox 1 0 1.25xlaj 4. 9 -1O6 3.ZxlO9 0.7x107 0.74x107 0 52x106(5) 1.8x107 3x106

2. 2xlo 9 l. Sxlp 1.57xlo 0.8x106 1 2x106 1.ZxlOS(6) 0.7v107 0 58x106(5 1.7xl06 0.55y106 0.56xlo (8) 1.3ylo~(6) 4x107 '.

lxl06(5 3.5x106 ,O. 7xlO6 0. 61xlf (S3 0.68x108 Sx106 1.3xl07" 5. 7xl06 2.4xlo SxlO4(7) 0.68x108 S.2xl07(5) 1.7x107 S.ox106 Z.ZxlO6 2.2x105(6)

.0.58xl08 2.1v106(6) 2.1xl07 4.5xl06 2.0xlo 1.1xlo~(9)

2;8xl 0 .- ':1;1xl'06 ' 'S.ox107 S,px107 1 Sxlo" 5;Ox105<'6)

"(7:) (7) '- 5. Ox'1'07 k;-4x107 a.'lxla5,"6) 7'70.0

- - L 3.0x107'.5x107 2200 (7) 7 (7) 1. 6xl08 2.2yl07 3.0xlp~(6) 6000 (7) 10 (7) 0.54x109 2 4x1.08 1.3x108 1.2x105(6) 00 (7) 7 (7) 2.0x108 5 Ox107 3.0xlp" 1.2x105(6) 00 (7), 7 (7) 4.6x108 1.0x108 4.Sx107 Z.ZxlpSC6) 00 (7l 8 (7) 0.64xl09 l.lv108 0.52>x)OS 0.76xj05(6) 4.3xlol" 1.5x107 4xlpll 1P10 4xlO" 3xlo P V

/R) ag ing .

~ ~

,~ 1

10 12

. 66x1II 0.78x1312 4.5xlpgll . S.

1011 1.7x10192 5x1 pll

.4xlpg . 2. 221.0 5.2xlpg 3. Zx 1 08 1.2x1010 5.10

.Oxlp 1. 7xl0 2.2xlp 4.0x 106 1.5xlp 2.0xlp g

.Sx107 5.0xl06 1.2x107 1. Zx106 1.7x107 0.74x107

~ 5x106 5 'x106 1.3x107 1:SX <o 2 x107 0.92x107 82x106 6.8x107 1.7x107 px >06 1 Sx107 2x 107

.Ox107 3.5x107 1.6xl08 1 1>10 2.4x105(6) 1.1xlps

.2xl'07 2.lx107 2.0xlps 1 3xlp 3.4xlps 1 lvlps

.'. 25x1 g?

.1xl.p"',

. 1. 56x1.0.7. -2'.Oxlps 3x.lo 3..4xlps . 1;lvlps

.Oxl07 1;2xl.p~: .:- .

o"6o'1) 8 "1..4xlpg '0;.53x~pg;,

0.82xlps 0;94x3.gg-'.9vlp" 3 Px lP 14 (7) 12 (7)

(7) 0.83xlQ8 0.9xlpg 0.81ilf 24 (7) 10 (7) 4.0xlp" 1.8xlpg px ) 0 40 (7) 13 (7)

O.sx108 1.05xlpg p 9)i106 34 (7) 7. 5 (7) 1.4xl08 240 (7) 280 (7) 36 (7) 8 (7)

(7) 1.3x108 300 (7) 220O (7) 35 (7) S.3 7) xlplp 4.4x107 0.95xlp 2.. 8%10 5x10 1 ~ iso ~ rr ~

~~

l'jc-0

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16 18 19 20 3.5xloll 0. SX1012 p 9xlp12 1. 2X1012 1.59xlg 5xlpll 3.4x109 1.2xlp l.lxlp 0.6xlp 1.7xlp Sx106 S.oxlp 1.7xlp 1.0xlo 2.6xlp 0.64xlOS 1.6x108 6500 (7) 1.4xl06 8000 (7) 2.1xl07 0.7x106 1.5xlp" (7) p.8xlp6 1.2x104(7) 1.5X107 1. x10 ~ ( I) 3.5xlps(6) l.lxlp6 l.sx10"(7).- 1.5xlo S.lx105(6)

~

2.-6x105 ~

p 7xlp7 15 xlp 1 3xlp. 42 x>03(7) 2..6xlos(6)

~

2;4xlps(6) .p.'75xj.p7'6'3.03;'(7); 1.;4~107. 30 "x103 ('7.) ,2 lxlps.(6.).

2.1x105(6) 12 x103(7) 1.4x107 '.56xl'07 (7) '8'103 2.2xl05$ 6) 4.5x106 S.pxlp7 13 xlo~(7) l.lx1088 120 0.52xlp~(S)

(7) SxlP7 4SOO (7) '.4xlo 2.1xl08 7

1.6X10~(6) 2.1X105$ 6)

7) 5 Ox107 120 (7) 150 (7) 8 6>lp8 190 (7) 0.88xlg 500 7 0 82xlgo 5.4 (7) 4.5x107 70 (7) 2.4xlo~ 1.7X10>(6)

S.S .(7). 0 78xl08 70 (7) 4.5x108 100 (7) 2.2xlps(6)

6. 5 (7) 0.74xlp lp

• 9O (7) 2.5x105j6)

.3;SK10 .

55 lp9 3

"'p 1.9xlp

~ ~

~~

22 23 25

~

~ 1.5xlo O.gxjo Sxlo 1.8x1010 0.53x199 3xlo 0.8xl07 1.4xl07

~

1.1xlolo 0.72x108 2.8x107 0.52xl09 0.96x107 0.8x105$ 6) l.sx105 6 1.05x107 0.71xlQS(6) 1.2xlOS 5 0.8xlOS 6 2.5x107 O.'8xlOS(6) 1 ..Sxlos (5) '.2xlUS(6) 1.4xl08 1.4xlos(6) SS x103(7) 1.6xl05(6) 1.35xlg8 2.x104(7) 2.0xlos(6) 1.8xlos(6) 1.3xlo~ 1.15xlos(6) 3.0xlos(6) 1,.5x105,{6) .

~ ...'.0. S8x197 .2.8xl055 63 4. 4x1A~S 6

' S.oxlo~ 2.6xlos 6f- 1.8x105 6 3.6xlO8 0.86xlo (6) 4.0x105(6) 5.4x106(6 1.3Sx109 1.6x106 1.1x106 2 Ox106 3.0xlo~'.slx109 2.6xlos(6) 0.88xlOS(6) 2.8xlos(6) 1.4x105(6) 0.9xlos(6) 1.7xlos(6) 0.54xlg 3.0x/II~I;6) 0,9x10556) 2.0xlgs(6) 0.7x10 Sxlo 0.57xl0>1 Sxlolu

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4 EIXGE{ VOX,TAG{" NXTIISTAND TI! TS (E{X-POT)

Table 4 present" the xe.,ults of- the hi-pot tests performed at the conclusion of the test program.

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Tahar.E"; 4 Result of'Ii-pot Tests Perfo rmed o'f 37 Day I".nvironmen{='al Expo. ure Iw 'at'onclusi'o>>'equired r

'-: Sample No. 'ctual Cur en&(m.A) Comments l 242

'2.2 242 5.5 for 5 min.

5 ~

1. 5. >15 Did not. hold.

~

~ .

i, 7 '.22.2 2f2 2 2.2

' ~

1 5

2. 1.

Iield for 5 min.

for 5 inin..'

2'eld

'eld

~

.11 8

9 ~ '.2..

'. 2-.2.

2.2 2.2 2-.2:,"

2.2 1.6 1.9, E{eld for 5 min."

E{eld for 5 min.

.Held for 5. min. ..~

~ .':17..'-.- .: '

~ ~

.Splice in c1ater '

2.2 2.2 1.9'.1 for 5 mirn.' 'eld

~- 19 2.2 2-2 E{eld for 5 min.

2-2'. 2.2'.2 240 Held for 5 min.

2.2 1.9 '.. Held fox 5 min.

2.2 2.2 2.4. Held for 5 min.

24'25 2.2 2.2 1. ,'Iqld for 5 min.

2.2 Held for 5 min.

9'.

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(,I<'fON 6. CERTXFXCWZXON

~ ~ .r 1E, The under a.gned certifies that this report pre'ent

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I I 11 a account of the. test conducted 1 1 EE

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and the results obtained.

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' Testing

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I' APPE51DXX A RADXATXON CERTXPXCATXON

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November 21, 1975 Xnter Company Memo I ~

Bur t:c'in'

~

To  : Nissen M.

Manager, Qualification Testing 4': ~ '. r, . I I 'I

, From:, 'George R. Dietz

~ ~

Manager, Radiation Services \ ~ I Thi,"s will surrimarize the parameters periir>ent to the rec nt simultaneous

...'te', chemical spray and radiation exposure test conducted for

~ Essex Xniernational, Xnc.

Xrradiation for the Phase X 7 Qay test was begun on October 10, 1975 and concluded on October 18, 1975. During Phase X; che cables re-

~ -.: ceived,

~ a minimum Qose of. 51.1 Mrad'and maxiInum of 53. Mrad. Jshere

"': possi:ble, we u'tilized -the irradi'.ltor co proc<.ss other'x-oduct con- .

" ': .currentl~j with. the'.6 st; jhich 'neccss'stated'ccasional short'periods t=he radiation field was reduced to zs z-o. The details of source osi.'tioning, dose. rates and toial dose is .)rown in Figure l.

'here I

ase XX of the test. began on October 21, 1975 ancE concluded on

'." November 20, 1975. During t: he approximat:ely 705 hour0.00816 days <br />0.196 hours <br />0.00117 weeks <br />2.682525e-4 months <br /> radiation '."

exposure, with simultaneous stcam/chemical spray per your profilef

.cables received an additional minimurrI dose of lj)8.8 Nrad, and,

-" in 'Figure 2. ~

~

.=

s '

.." ma>:imum dose of 152.0 Mrad. The.'etails of irradiaiion are shown

~ ~

..'....:~-

Xn'",su~as~, 'total dose to thel cables over th'e entire test period

~; >anged from;200 to 205;4-"Mrad,-~d.th an estimated source positioning'.

", error of +5-o 'in dose rate.

~

~ ~

I Dosinetry was performed using a Victoreen'Model 555, Xntegrating Dose Rate )1eter and Probe. The unit was calibrat:ed on October 16, 1975 by 'the Victoreen Xnstrument Company', using cobalt-60 and cesium-137

~ '.'whose calibration" are t:raceable t:o the U.S. National Bureau of Standards. Backup Qo"imetry using a Red Perspex ..ysiem provided by Atomic Energy of Canada, Lt:Q. confirmed thc Victoreen readings.

ll t ~

4'losures 'I

. <ce'oi(f~"'i4- Dlc Lr Manager, Radiation ~irvices

~

I D:km s lsornocix )nc. 25 I:0sreasss 000', PsrsirsIany, tlo.v J isey (201) co7 470) hljllhsg Addscsss post ossico Isnx I ll, pjsslp..jny, I'lcw jcsscy 070)4 CHICAGO OIVISIOhi ~ yil"0 IljrjlcAvc., hsot Son Grove, Illinois 000 jl IDI I 000 sJG0

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Do e <<50 Hrad l

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Rate'>>d Do.,e

-( ...,::. Do e 1

330 i'D '60

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00.

,.:i

/ g'otal SoLl X'ce centerline

/ l 30 700 4

~: ',.' "',, 10" I

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)

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.' ..".,".,: '4:. X 500

~

1 3.3'0 .

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5 ~

~ ~ I on'.figure.represent 'dose'rates (kiloxad/hr) at le'ttex'ed poil1ts when t 1

.'.-Numbers.

source is-located as shownI relaLive to the cables.

~ ~ ~

a'diation was conducted )ly locatkncJ l hc ..OLlrce at I) qLladxant. of the dizLlon cll;lmbcr., with a typical luc'ltio>> how]1 above. Nhe>> equal adj.ati.on times are administered in each of thc source locat'ons, the average dose rate at a point is the average of the sum of the c)ose xa'es rec'eived in each position. Rotation of the vessel and positioning the soux'ce in-two.guadrants each time had the arne effect as four.times. ~ ~

if the ouxce'ere.relocate

~ ~

~ ~ r Average Dose rates at A,C,E and G are:

1/4 <A,C,E,G. = 1/4< 700+330+330+230 =;.1590 = 397 Kza0/hr

. and at B,D,P and H 1/4 ~ BID@ P and Hg 1/4E500+260+260+500 1520 380 Krac>/hr

~ ~ r r

Considering irregularities in the actual contai)lm nt ves el a p absorption factor was applied. 1fence actual dose rates at. A,C,Eandand G wexe .88x397 or 349.0 Krad/hr (maximum close xate) and at B,D,F H,

.88x380 or 334 Krad/hr (minimum dose rate) . I

\

The minimum dose administered over the 7 day period. t:0 positi.ons B,D,P and H from the 153 hour0.00177 days <br />0.0425 hours <br />2.529762e-4 weeks <br />5.82165e-5 months <br /> exposure was l53 hr x .334 Yirzd = 51.1 Nrad hx' the maxi.mum dose, =- to positiolls A,C,L and Gg was hr x 34 9 Nrsd 53;I) Hrad,

/ ~lr n'tlation.'r huilc)up fhoL'orb .io'r L)lc contel1ts of thc chambc.r (mandrel, cable, ctc. ) werc not considered in thc above bccau.'.e of the Ira>>c)oi Inc s of t)le ix locations.

~ ~

Pha' XX 30 days ~ ~

7 Pig 2 I ~

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Dose Hates and Total .D oa e

~

240 i

"-.-- ~ '. ~ 0 ~

g' 16(3 '3~0 .

C r Snuxce-

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'enterline

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. p'].30 370

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' 10 II ',. 2 III 12II

/: +

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p, 160 ':'. r I

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2-i~.0" "..

r Nu&ers on. figuxe repre'sent'dose

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vhan,'rt:he's'ource 'is lochted's sho~in",'elative -t:o the cabl.'es ..-:-...-: '.:.'.':

~ ~

rates (kiloxad/hr) 't ll lettered points

~ i r ~,%i gr'radiation iras conducted by'ocating the source't 4 quadrants of '".:

chamber, irith a typical location sholem above. Nhen equal o

'rradiation isation tines are administered in each of the source locations, average dose rate at a'oint is the average of the sum of the Bose

'rates received in each position. 'ota':ion of .the vessel and posi.tioning "

the. sour'cc.in, t~"or quadrant each time had 'the same effect as

~vere -relocated four times.

if the source '

A.erage Dose xates A,C,E and G are:

fl' ' '

I ~ ~ ~

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~ '-,',"-. 1/4, A C,L' = 1/4 4 370+240+130",2)0=

and.at BfD'tFf and HJ .' ' ',.' ,,'.'.:'"'".'..': .': .-'.s'"  :.  : ~

' " " ~

.-.;."'l.. 1/4 8 D,P H + 1/4+ 320+3.60+160+370= 96P = 24P Brad/hr ':.

, ~ 's Consic~cxing ixxegul.arit'ics in the actual cont:ainmcnt vessel, a 1 absorpti.on fact:ox r as app3.3.cd. Hence actua3. do.".e raCes

.88x2$ 5 or 215.6 6ad/hx (maximum do e rata) and at at0 A,C,E D P and G d

88x240 or..'211 Exad/hx (minimum do c rate) .

I ~ ~, ~ ~

~

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i~inimum do e administered ovex the 30 day (705 hrs. of i,xradi,gati..op) ihe pexLod Was 7P5 hx ~ x ~ 211- 148, 8 and the maximum dose

~ I h ~ ~

'.705 hr. x, .215.6-'-' .152.0 Brad, uat3.qn or biiildup fact:ox" 'ox. the contents c".bios, spi-ay, li.<quid, ctc.) wove not con.".idorcd o fi.>> thc 4, c c.h am ex, (mandrel, t..hc above b'ec use

(

of the xandomnc"s of their locations.

~ ~ ~

Cyprus VVire 8. Caote Company Quality Assurance department Certification H

V Indiana 5 Michigan Power Co.

D.C. Cook Plant Construction Cverornor'e Dory Order 05526-821-5 I

C P.O.Box 458 Bridgeman~ Mi. II9106

~ 'orno e

Cable Order No. EUN 03422 R

r

.. 6/16/76 f- I ~

MILL ORDER NO. 78668 S

H Indiana 80 Michigam Power Co. ,~

78669 D.C. Cook Plant Construction p

5"Miles North of Bridgeman Michigan Item Ho. Quantity Description Applicable Specification 51,790 Ft. C Triolexed A.E.P. DCCEE-171-~":l Sept. 8, 1975 e

~ .., ,/(): >P>  !'.1$-7/.;0305.Tin, Copper, 030" .EzW

.015 'eoprene Jacketed e

PowerCable"'00"Volt.

lI,815 Ft. ~C T~ri lexeme 5

/lgm 10-7 .0385 Tin Copper, .030"

.015 Heoprene Jackceee Power Cable EPR 600 Volt DONALD C. COOK hUCLEAR PLAr;T ACCEPTEO FOR QIA BY ELECTRiC GEt(ERATl0 < SECIIOft A~~F"wt'., h. Y.

ACCEPTED BT:

DATE.

J~~

~ e FjLE. '.=9 6-~ c 5~86"~.~ ili~ir'-

I hereby certify that the material described above was inspected under my general supervision and complies with the test requirerr ents A.E.P. Spec DCCEE-leak-ACN Set3t. 8, 1975 Rome Cable Quality Assurance Procedures prior to beii.g'placed into stock or released for shipment.

Test records will be kept on file Two years from date of test a nd will be made availaole for examination by authorized persons upon request. gA OC. ItlOEX SEIt.s 4'++

DATE KE'ire.'r cPn

, CJJ Zu 2~

se 4,

s.

IIEP.

EXPo

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Cyprus Wire & Cable Company 421 Ridge Street Post Ottice Box 71

/

Rome, New York 13440 TWX 510) 243-9732

~ . Telephone 315) 337-3000

~

~ ~

J~e 16, 1976.

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Indiana & ttichigan Power Co.

D.C. Cook Plant Construction P.O. Box 458 Bridgeman, Mi. 49106 Gen tlemen:

Ve certify that a radiation resistance qualification'test has been perfo~ecI'on cable 'sampl'eh of" sitttilar-construe't:ien.'employing iden-. ~ .".

tical insulating materials to the cables on this order. The test procedure used was that in IEEE Std. 383-1974 Para. 2.3.3 but with a 2 X 10 rd radiation dose rather than 5 X 107 rd. All cable samples passed the test. The radiation qualification test con; ducted was more severe than that required in Para. VI.A.3 of Spec-ification DCCEE-171-QCN.

.L.A. Doyl

'enior An lyst','Q;A; LAD: cs DO'ihLB C CCOK iiUCL i L~ 1 ACCEPTED FOR Q/A B" i E'HiC 0"?""'"'"'i ~'"T!OH r.'..:....,.. Y..;

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DhlE ~

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M.o. 78668 OA -24 Cy prus 'Wt!e REPQRT NO. 3525 DATE 6/16/76

'i at aft<a -:"<UCvt SHEET 1 Of 5 dc<<I<camp<ay QLJEfmis"JF AS:LJrance "~

D:.,:i>t tfT:CTTt cvsTO<<R indiana gc Michigan Power Co.

ORDcR NO. ENN 03422 Tost Data "Pr'oH 05526-821-5 fsc 3/c Triplezed, 12-7/. 0305 Tin. Copper J ~ 030" EPR J . 015 'eoprene sPEc o A.E.P. DCCEE-171-QCN- Sept, 8

.l'"cketed Power Cable 600 Volt .

PHYSICAI PROPERTIES ACCcl RATED VJATER A8SORPTION TESTS IHSVlA ION

< JACKET KLKCTRICAL ShEfttOD< ln<cscrsed ot C ot on overage stress TEST TEST j'JE S Ei:lfl::D ihlH f ST 'LVE  !

PECIFIFD tAIN of volts on<i volta per rnil. cycles VALVK SPEC PEASE IH 'C '-le days. %

ORIG!'IAL se'f 'c<E IN S!C. y-!4 dnys, %

i: L 1156-- ST<S8!LI! I';ACT<mT ArTER ! C DAYS,  %

i lr <H< !

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A f'R AG!."!G 2/0 eyn.cl mod

~ )rrL'.f".! ':I:TstdaDi I<oar rrsion for

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P ~ rr:;I! ~: an ~ at

• Wa 0

IJgd<l!IQQn CAPACITY AND POWKR FACTORS 'fESTS J p.h7~ ~jit.i

neos a<.J 'it o I vct< ~ otter Doy( ~ ) an water ot C

'.. ~ .at C .. J psl SPEClflC!NVVCstVF. CA<PACIT.

T ii'ld E.: 0 el r < ~.~ <<:<<I POWER FAG ION. %o

'0': ! l...l '..  !, iai hhlSCELlANEOVS TESTS Au O'RH TESTI IHSUl'ATION

<<s vt1 81 C

~ f Ha<I! f.; ot o<! .<<ol fit::<IIAftori.": oi or'nol

~

3 llr. 0'ne Resistance I .030[> - No Cracking JACKPl A!R "'lcS>VRK IIL h! IfSfs I ~ ~, cll C oi<d psl

":e ~ <I <i.. ial Vertic:Ll Flame Test Passed Per" Para VI-A-2 of Spec. DCCEE la!.e:LE, 171-QCNI

!LCHGATIOtt. '.<. <<t original DOflALD C. COOK NUCLEAR

~ ~ ~

~e PLAff~

OIL VrL<<IERSION TEST ~

ACCEPTED FOR g/A BY ELECTR/C hrs ot GE CRATED~ ~ECTtO CD lfavltE.!<a ol ci ! ol ~~

CD ACCEPIED BY:

flct<GAIIOH, ' <il a<i!sinai o~ DATE ~ 4- j 7C o >~

~~rn D ' << t<<<<n ~ "< . I ~ a ol the coLl ~ atvac ~ !bed oh<aye.

M.o. 7

\

Q.A. 247 F.'arr~:,"Ca hie Oiv Giorv 0F REPORT SHEET 2 No. 35I25 OP 5

. DATE 6/16/76.

CYPRUS MINLS CORPORATION Indiana &. Michigan Power Co.

Qualify Assurance Department ORDER NO. ENN Q3422 Electrical Test Data c. o. No. Q5526-821<<5 5PEclflcATIQN A.E.P. DCCEE-3.71-QCN Sept. 8~ 1975 DE"RI>>!GN 3 0 Triplexed 12-7/.0305 Tin Copperp ~ Q3Q EPR, .015" NyopreILe J L,".dieted POLIer Cable 600 Volts CONSTRUCTION INSULATION RESISTANCE r A C VOLTAGE D C VOLTAGE REEL NUM3ER LENGTH ICOFI IOQQ'ORONA I.EVEL FEET . MISCELLANEOUS TESTS NO. DIA. me@ohms Lv SIZE STDS.

WALL CTIME TI E STDS. ACTUAL SPEC ACTUAL SPEC 73639 12 7 .0305 . 030 4o4o 0.0 35(3 2617 3/c .015 732yl 2525 17693(3 2065 Api p'g

->r) 1385 5832(3)

.<<r 4 66o

.I DXi 340 7456( 3)

I3-r< 1500 465'. 8o45(3)

Ah i

-I 3:-"~ 42o

='I 3245 450 .

.73305. 8lo 181o8(3

-7325o 1520 I

+7r 0 ~

92Q 18812(3 Ql "+~ 1820 3I Qov 42'10 15300(3) b816(3) CONTINUITY OK

.2vv5- 2085. 47538(3.

D MALO C. COOK NUCLEAR PLANT A CEPTEO FOR QtA gy ELECTRlC G NERATIOH SECT(OH AEpSC g y A CErrIo 8r.Cc .4 0 TE: ~-2i->c, Fl E. Pg' '5'Q I

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M.0.

Q.A. -24 P .-'- Cabf f.'.s ~;:<AN OF RB'oRT'o.

5HEET 3 OF

+25 5

~

DATE 6/16/76 CYPRUS hf INES CORPO RATION cusTGMER Inliana 8o Michigan Power Co, Quality Assurance Department oRDER No. ENN 03422 Electrical .Test Data c. o. No. 05526-821-5 spEcfficATIGN A.E.P. DCCEE-3.71-QCN Sept 8F 1975 DEscRIPTIGN 3/C Triplevecl, 12-7/.0305 Tin Copper, .030" EPH, .015 Neoprene Jacketed, Power Cable 600 Volt, CONSTRUCTION INSULATION RESISTANCE CORONA A C VOlTAGE D C VOLTAGE RE.EL LENGTH (40F) LEVEL NUMBER MISCELLANEOUS TESTS FEET megohms-NO. 0IA. f000'PEC SIZE WALL STDS. STDS. hv TIME kv TIME ACTUAL ACTUAl SPEC 0305 .030 2855 4.o 2617 37)43'3I505 . 015 6182(3) 3545

~

<g<so 4o4o 9332Ii(3)

.37503'375K 174o 28752(3) r;.,0) 54o

,I O

~few/ 1730 3P]<1 161o 2-(311(3)

I 1970

-733K 1260 49140(-3)

) I <-04 2775 3i506 (3:oo) 358o 21588(3 73=4 f 4oo5 CONTINUITY

~

~

OK'ON LD C. COOK NUCLEAR PLANT ACC .PTED FOR QIA BY ELECTRIC

'GEN RATION SECTION AEPSC, N. Y.

ACC PTED BY:

DAT FILE age'4

'<fot< ~ <I<<i.<<<f hF <<!.:<Ii< <bfe sfsecir<<<sho<<.

~

M.Q. 7866 REPORT NO. DATE 6 16 7 s l < ~c'4 Cyprus Wtre ~. Of ui v)i~~~

SHEET lp E Cable Company Indiana Michigan Power Co.

QuEflfiy hs:uran'ce DepurtfTscnt cUsTOMER c Ec OROcR NO. ENN 03422 Test Data c. o. No. 05526-821-5 3/C Triplexed 10-7/.0385 Tin Copperf .Q3Q EPR~ ,Q3Q Neoprene spEclflcAT,oN A. E.P. DCCEE-17 1-QCN Sept. 8, J"cketed Power Cable 600 Volts PHYSICAL PROPERTIES ACCELERATED WATER ABSORPTION TESTS INSULATION JACKET ELECTRICAL METHOD: Imm "Hed at C ot an average stress TEST SPt TES > -LJE,SPECI. I%O rRIN. TEST VALUE SPECIFIKO rAIN of 'olts and voits per mil cycles VALUE I!tCPEr Sc:tf SIC. I-I4 dovs, 'rc OstterlttssL ItiCREASE IN SIC,?-I4 dnys, %

~CIs 3 I sssssssssssrs:. "sss snss s s,sass. C J 350 .. mQ f.ast

..:.""'Sf! .'.'.: LSIOSs I. ~il r ( S 7CS I 1.2ts- TMO-AFT'R ssErINsrs CAPACITY AND POVIER FACTORS TESTS vswsssre'J nt 9l cvclev olt r Oo:.Is) in svater at C

.rs. ot C ond psi SPEt.lf IC:rturyCTIVE CAPACITY S.fssr:sr. ' . POWFfs FA .TOR. %

'.s..f'IS'tot:s.:Aito~.

.rs inol MISCELLANEOUS TESTS sslR CZ*)t I ST INSUL~,TION 1.'. ass otl st 'C

' tsnoi

~ tsSILE. s s ~

3 Hx. Ozone Resistance 8 .03+ No 'Cracking Slot sosn floss. ' ol or:rrinal n JACK!".V AIR IsRLSSUAE IIEAT TEST:

hrs ot C ond psi Vert ical Flame Test Paesed per Para VI-A-2 of Spec. DCCEE TE! I>ILE. ",sL os s sisllnol 171-iLCN

!LONCA'floss, ~ ss ol cls9inol OONALDL C. COOX NUCLEAR PLANT OIL IMMERSION TEST CCEPTED FOR Q/A BY ELECTRlC hrs ot GENERATloN SECnoN AEPSC, N Y.

IEIISILE, "'s . I ssri.snal ACCEPIED BY:C~rs LLONGAfloft... ol orsgsnol ~

DATE g 7d PILE: ~'I: i>

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S88 o1Bo RE+ ~7 DONALD C. COOK NUCLEAR PLANT EQUIPMENT QUALIFICATION FILE UFDATE TRANSHXTTAL FORM Attached Forms checked: 9- ~~r ORIGINATED BY DATE: ~~ ~ cP/

(System Engineer Signature)

APPROVED BY

'ure) DATE: // +@o

( . . F)gv.tz.als)

CEEQF PILE INDEX UPDATED BY: Date XIl1'tl 5 DATA FILED BY: Date Inst'.al.',.

CEEQF PILE NUMBER OF DOCUMENT:

4. COPY OF COMPLETED FORM TO BE RETURN'HD 0 ORIGINATOR 'KiVC.

GENERATION SECTION.

To be incorporated in RFC file at close-out.

gRIE >I ~ 44 gc y.

C AMERICAN ELECTRIC POWER SERVICE CORPORATION WE'R BYgT+

DATE: November 20, 1981 BJECT4 Addend Environmental Qualification for ectrical Cables Outside the Reactor Containment (Ref. 165}

FRpg> L F Ca so TPs NRC IE Bulletin 79-01B Central File In reference to Table I in the. or'iginal document, ge.

have contacted the cable manufacturers therein listed (~acondy,<

Continental, and Essex); our request for in4ormati'on and thei'.Z responses. are attached to this addendum, In summary, Anaconda advised that their cable was qualified under FIRL test report F-C4350-3 (200 Mrads).; Essex advised that their cable was qualified for 100 Mrads; Continental answered that they did not have radiation data on the subject cable.

The Cyprus Company cable listed in Table II is used for applications outside the reactor containment. It has been qualified for radiation to the extent of 200 Nrads and passed an air over test of 250 F for seven days and an it has immersion test for seven days. The arguments developed in the original issue of thi's reference I65 fully applies.

as well to the Cyprus Company cable. Therefore, we conclude that this cable is fully qualified for its application outside the reactor containment.

LFC/jal L. F, Caso '

APPROVED INTRABARTOLA INTRA-SY ST EM

Cable Location in Insulation/ Cable Description Plant Jacket Qualification Outside Containment'able Material'PR/Neoprene Cyprus Cable Cyprus Report 3 1/C 412 N3525 Cyprus Item N324 statement of 600 Volt 6/16/76 Cyprus Cable EPR/Neoprene Cyprus Report 3 1/C ~gl0 I3525 Cyprus Item N325 statement of 600 Volt 6/16/76 Cyprus Cable EPR/CSPE Cyprus Report 3 1/C N2 N3658 Cyprus Item N3102 statement of 5 kV 8/14/76

0 AMERICAN ELECTRIC POVfER Service Corporation 2 Broadway, Hem York, K Y. l0004 (212) 440-9000 Cable for Cook Nuclear Plant September 16, 1981 Mr. J. L. Steiner, Chief Engineer Essex Group Power Conductor Division P.O. Box 1000 Lafayette, Indiana 47902

Dear Mr. Steiner:

Cable which we purchased from Essex some time ago is installed in our D. C. Cook Nuclear Plant. The cable is outside the containment and, thus, was not required to be qualified in accordance with our nuclear environment for containment use.

However, due to recent directives from the NRC, we now must provide additional test or engineering data to confirm qualification of the cable for outside containment service for the following conditions: 250 F for 10 seconds, plus 18.26 megarads of radiation, total accumulated dose.

~

, Ne would be most grateful if you would review your records and'iles, and furnish test or engineering data which..

meets 'or exceeds the above criteria, for the cable listed on the attached sheet..

Your prompt .attention .to this request and. earliest reply would be gxeatly ap'prec'iated.

Very truly yours, T. J. Massar TJM/gal Electrical Engineering Division cc: H. N. Scherer, Jr. Columbus S. H. Horowitz J ~ M. Intrabartola T. E. King L. F. Caso Volk R. F. Kroeger K. Shiu

AEP P0503694-821-3 dated 5/29/73 Essex Order 5114-2548 Essex Certification of Compliance dated 2/13/74, 2/28/74, 5/31/74, 11/18/74, 12/20/74 and 6/ll/75 100,000 ft. 3-1/C twisted 512 AWG stranded copper .030" EPR insulation, .015" Neoprene jacket, 600 V. AEP Item 324.

~ r ~ ( ~

LJIVI I P kJ East Union St. 8 Sagamore Parkway Klf P.O. Box 7000 TECH NQLOGIES Lafayette, Indiana 47903 ESSEX GROUP 317/447-9464 Power Conductor Division October,8, 1981 American Electric Power 2 Broadway

.New York, N.Y. 10004 Attn: Mr. T. J. Massar-EE Div.

Subj: Cable Radiation S Thermal Resistance Ref: Cook Nuclear Plant AEP Ord. 03694-821-3, item 324 Essex Ord. 114-2548

Dear Mr. Massar:

We are in receipt of your letter of 9-16-81 requesting radiation and thermal resistance data on the 3 x 1/C N12 EP insulated/neoprene jacketed subject cable; Attached to and made a part of this letter are data generated on the insulation material and the jacketing material

- used on this cable. These data show suitability for use after 100 Megarads (gamma) radiation plus 7d at 136C (276F) for the EP insulation and 50 Megarads (gamma) radiation plus 7 days at 121C (250F) for the neoprene. These test levels readily en-velope the requirements of 20 Mrads and 10 seconds at 121C(250F).

We"trust this material will be adequate for your present needs.

Ve truly yours,.

seph Lz Steiner hief Engineer JLS/fb cc: E.K. Duffy J.C. Rose A.W. Reczek P. Bernard

TEST DATA ESSEX GROUP ENC DC Cook Plant AEP/EP-Neoprene (non-containment}

EP (T035)

Unaged Tensile Strength (psi) 1200 Elongation (%) 350 Aged 7d at 136C Tensile Strength (psi} 1000 Elongation (%) 350 Aged 100 M Rads Tensile Strength (psi) 900 Elongation (I) 30 Aged 7d at 3.36C and 100 M Rads Tensile Strength (psi) 1100 Elongation (8) 24 Actual data typical values J. L. Steiner

TEST DATA ESSEX GROUP INC DC Cook Plant AEP/EP-Neoprene (non-containment)

Neoprene (T 450)

Unaged Tensile Strength (psi) 1800 Elongation (%) 450 Aged 7d at 121C Tensile Strength (psi) 1500 Elongation (0) 110 Aged 50. M Rads Tensile Strength (psi) 1300 Elongation (%) 120 Aged 7d at 136C and 50 M Rads Tensile Strength (psi) 2000 Elongation (8) 35 Actual dat'a'ypical values J. L. Steiner

$ 6F 4 7o DONALD C. COOK NUCLEAR P <~MT EQUIPMENT QUALIFICATION FILE UPDATE TRANSMITTAL FOR'0 l..TO BE CON>L TED BY COGNIZ 'HT AEPSC S~CT>

SUBJECT fq v J t-c Q Q PQci z4viPAgg i<'< ~

ORIGINATED BY: DATE:

APPROVED BY -

(Si nature)

(

4' "Z gnatu"

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g.)

DATE: ~$ 2 W3 ~

DATE:

(Sag re 2 o'TO BE COMPLETED BY AE SC MS' SEC a IOA

@ACCEPTED-TFMPSMIT TO AEPSC QUALITY ASSURANCE j

@REJECTED- RETURN TO COGNIZANT AEPSC SECTION MANAGER REASON FOR REJ'ECTION:

ZS NRC SUBMITTAL.REQUIRED? @YES @NO ZF YES, GIVE SUBMITTAL LETTER NUMBER AEP:NRC:

APPROVED BY: DATE:

3.TO BE COHPL TED BY AEPSC QUALITY ASSUPA'.0CE TRANSNITTAL FOR'4f AND DATA RECEIVED BY- DATE:

(Inz.tiara.s )

CEEQF FILE INDEX UPDATED BY: Date natura s DATA FILED BY: Date In'teals "Iv 'sDwR Oc vvC 4A'LDNL ~

48 Day Street Seymour, Connecticut 06483 (203) 888-259 t

@he kermit:e company i

April 18, 1980 American Electric Power Service Corporation 2 Broadway New York, New York 10004 Attention: L. F. Caso Re: A.E.P. Purchase Order No. 05601.-821-2 A.E.P. Cable No. 3127 Kerite No. B-3230 Radiation Qualification D .C. Cook Nuclear Generating Station Gentlemen:

Per the re uest of y o ur Mr. W. R. Farguharson and your telephone conversation with our Mr J M P ar ks, we are enclosin g the documentation for the above referenced item Xf we may be of an y furtherr assistance, please do not hesitate to c'all.

Yours truly, THE KERXTE COMPANY y

Robert J.henry Customer Service Representative RJH:sal Enc.

a subsidiary ot HARVEY HUBBELL INCORPORATEO

(/ (

pe kerite company July 27, 1979 4p AMERICAN ELECTRIC POWER SERVICE CORPORATION

,DONALD C. COOK NUCLEAR GENERATING STATION RADIATIONQVALIFICATICN Samples of Kerite unaged and aged 600 volt and 1000 volt HTK, FH jack ted power cables, with and without splices, have been type-tested to 200 megarads at a rate of less than 1. 0 megarads per hour in a Cobalt 60 Gamma Field.

On the*basis=of this testing, it is concluded that the Kerite 1000 volt HTK FR jacketed cables, as supplied for the subject installation, wil) operate after exposure N radiation levels up to the severity of those simulated in the test. The 200 megarad tes.'evel is 1. 33 times the 150 megarad lovel given in the May 30, 1979 letter to the Keriie Company from William H. Farcpiharson, American Electric Power.

R. E. Fleming ~/

Nuclear Developmen~gineer

HEP/ic APPROVED

. Gar((ner, V.. ~o~'(-(((e ring Subscribed and sworn to before me this 47 day of July, 1979.

~((( E'5 ~ (~ ~ ' ~

~ (

MP 1~0405603 -821-2 hl."P Cable  !.'-3127 (Kerite B-3230) Nay 30, 1979 The Kore.te Company

'l 9 Dc,l)'t J;e Conn.'.'l'eymour, 06483 At ten tion: l lr. J . $ 1. Campbell, Jr .

Gentlemen:

Subject power cable, 3-1/C twisted 52 N1G stranded copper with tl.T.K. insulation and PR jacket was qualified to 120 Yir .ds of radiation in your report of April 30, 1970 entitled, "Rcport on the Effects of Gaimna Radiation and 1iuto-claving on Kerite Power and Control Cables".

l'e would very much like to have in our file an which will qualify the subject cable to 1SO blrads of addition:;'eport radiation. Do you have such a report available? If so, please respond by forwarding a copy at your earliest convenience. If not, please advise.

Your prompt. attention to this correspondence will be much appreciated.

Very truly yours, I ~e~% MA" ~~~

hil liam R. Farquharson l:.'ev>trical Engineering Division l ~

A!.'!'.0'v'0 cc: Ii. ".

~ C Qso

AMERICAN ELECTRIC POWER Service Corporation 2 Droadway, How York,/. Y. I000d (818) d40.9000 AEP P0005601-821-2 AEP Cable N3127 (Kerite B-3230) July 23< 1979 The Kerite Company 49 Day Street Seymour, CN 06483 Attention: Mr. C. A. Lund Gentlemen:

On May 30, 1979, I wrote you (copy of that correspondence attached).

On June 19, 1979, you called re my letter and advised "you would get back to me".

I wonder if at this time you are to forward either a report (as requested in attached) or in a position an "offical" Kerite statement (letter) attesting that the cable identified above will, or will not, withstand 150 Mrads of radiation.

Your response one way or the other is critical to a research project being'onducted by us (AEPSC), therefore a prompt reply from you will be very much appreciated, Thanking you in advance, I am, Very truly yours r-William R. Farquhar on lectrical Engineering Divi i'.>:i WRF/jal APPROVED J. . NTRABARTOLA cc: L. a so

~&tA4

~ ~

~ P AMERICAN ELECTRIC PONER Service Corporation 2 Oroadu'ay, Xcu York, S. Y. I ooo.s (zs ) ~co-oooo Previous Correspondence on Kerite Power Cable Environmental Qualifications April 10, 1980 Mr. C. A. Lundy The Kerite Company 49 Day Street Seymour, CT 06483

Dear Mr. Lundy:

Attached for 'your reference, find our communications of 5/30/79 and 7/23/79 that Mr. S. H. Horowitz refers to in his

'recent telephone conversation with you.

Very truly yours, L. F. aso p El ctrical Engineering Division LFC/jal"

'APPROVE J. M., XiuTRABARTOLA

/

cc: 'S.=H. Horowitz T. E. =-King

DONAID C. COOc( NUCL=AR P~~VT EQUIPMENT QUB ~ I~:CWZI'ON " ZI r~ UPDATE TKMVSMZTTAL FORM

' L.TO BE Cpte>>ETED BY C.".G~J:Z .i - .~.EPSC ~"-C>> ~

SUB JECT 97Y7u

)..;--su'Signa@

'RXGZNATM BY: DAT APPROVED BY

( xc71P'i 'e) DATE: 0 f

~ ~

il/pj~s-DATE:

(S -..av de) 2.TO BE COMP~ =D BY .-. PSC NSGL SEC'FZO>J Q ACCEPTED- 'AUS'-lXT TO AZPSC QUALXT ASSUR~~NC REJ CTED- RETURN TO COGNZZAVP AEPSC SECTION Hc4JAGc.R REASON cOR REJ CTZON:

'IS NRC SUBi4Z TAL HEQUZRED7

~

QY S +NO I YES g GXV" SUBMZ~AL LETTER NUPDER AEP: NRC-APPROVED BY: DATE:

3.TO BE COMPLETED 3Y AEPSC QUALITY ASSUM.i~JCE P

TRANSPZTT3~ FOPii AND DATA REC" ZVED BY- DAT (XnitiaLsl

.~QP c.ZLE ~i1CEZ UPDATED BY: Date n'= a s)

DATA "ZLED BY-In> "xa s)

~)CAN El pc~

AMERICAN ELECTRIC POWER SERVICE CORPORATION WKR SYSY September 28, 1982 The Kerite Company Cab}e Environmental Qual!tie;;~~'.On L. F. Caso 79-818 Central File The attached letter ~Fog the Kerite Company dated 9/21/82 should be made part o~ o ~

~,I.Ji ment qualification document reference numbers 63,68, 70 and 72.

L. F. Caso 2.4/LFC:jal APPROVE rg/~pe ~(

J,M ABARTOLA

V 49 Day Street Seymour, Connecticut 06483 (203) 888-2591 Mell All Correspondence To:

the kevite company P.O. Box 452 Seymour, Connecticut 06483 September 21, 1982 Anerican Electric Power Service Corporation 2 Broadway New York, NY 10004 ATTENTlON: T.J. HASSAR-ELECTRICAL ENGlNEERING DIIIIS10N

Dear Sir:

SUBJECT:

DONALD C. COOk NUCLEAR PLANT

REFERENCE:

QUAL l F l CATION UPDATE Me have enclosed LOCA profile (excerpted from "Tests of Electrical Cables Under Simultaneous Exposure to Gamma Radiation, Steam, and Chemical Spray Mhi le Electrical iy Energized" - March,i 1985; Final Report PF"C4020-2; Figure

1) which describes a 100-day test conducted by the Franklin tnstitute Laboratories. This test provided a sodium borate ra e chemical spra c emica spray 'esearch with pH a of 10.5 for 100 days continuously. The attached profile and the following results are offered as documentation of kerite insulatio i e insu a ion an d Jacket materials I. IILong-Term"II. (three months) immersion performance in a sodium borate solution. I The two cable samples (tested in referenced report) are representat ive of each I/C which form the 3/C cable. Both samples (aged and unaged) are described as fo1 1ows:

1/C, g6 AMG, 65 mi 1 HTK (N-98) insulation and 65 mi 1 FR (HC-711) jacket.

Each sample was irradiated to 200 megarads while installed in the autoclave.

ln sugary, both cables maintained their electrical loading (1000v ac, 50 amps) throughout the test. Each cable passed the 5 minute volt.-ge with" stand test of 80 volts ac per mil of conductor insulation. Thi test was performed after completion of the LOCA exposure and prior to di assembly of the test vessel while the cables were stiil on the'andrel.

a subsldlary or HARVEY H'ioOELL INCORPORATED HuaaCt t

American EIectric Power Corp. September 2l, 1982 I

We trust that this is sufficient information to enable you to answer the inquiry of the NRC.

Very truly yours, THE KERlTE COMPANY From the office of: CD A. Lundy Metropolitan Sales Manager S i.gne.e: Nqrma H. Oube Administrative Sales Assistant GALr/NHD/ss Enclosure

PIIASE I COMPINEO THERMAL ANO PHASE JE Ph~

SIMULTANEOUS STEAM/CHEIhlCAL-SPRAY/RADIATIONEXPOSURE STEAM ANL.

RADIATION AGING (!50 MEGARAOS GAMMA RADI'ATION) SPRAY EXP%

. [50 MEGARAOS (NQ GAMMA RAb~

GhhlMA RAOIAT ION) 3 46'F/I I 3 psig WITHIN 3 TO 5MIN.

335'F/95 psig 840 0

320 GR 3)5 F/69psig

4. 265~F/28 psig 6 IN SULATION R ESISTANCE MEASUREMENT

< 250 I-280'Fl 70psig (min)

WITHIN IO SEC. 2)2'F/0 psig 4J

~ 200 DAILY l22iF (50ic) MAXIMUM QoNCE PER WEEK STARTING AT 5 DAYS CABLES AT ROOM CONDITIONS DURING RELOCATION OF TEST l40 VESSEL TO OUTSIDE OF THE 77 DAYS RADIATION HOTCELL.

122 PREHEAT TO l40iF MAXIMUM O i IMMEDIATELYPRIOR TO TEST 3 .5 8 II 23

~

IO 15 IOO 7DAYS SEC HR HR HR HR HR 4 DAYS DAYS DAYS TIME I

Figure 1. Specified Temperature, Pressure and Radiation Test Profile

DONALD C. COOK VUCLEAR ? ~~IT R,~ 4=7~

EQUXP."KVT QUALX"ECAZTON c XL UPON~ ~WNSÃXTT>Z FOB<

1.TO BE CO% ~ ~

ED 3Y CCGVXZAVT AEPSC S C~..nV SUB JECT Cgw ORXGXVATED BY: DATE:

(Si-natu . )

U~ROV" D BY (Sign+,are)

(Si e)

,2.TO BE COMPLETED BY AEPSC NSeL S C'DIXON

+ACCEPTED-TRAVv. SEXT TO AEPSC QVALXTY ASSUR~2lCE

~

QB Z=C H3- RE~JR% TO.CCGNXZANT AEPSC SZCTXON HAiVAGER REASON FOR REJ CTXON:

XS 'HRC .BW T AL REQUXRED. /YES @HO YES, GXV- S'UBMXTTAL LETTER HUPAER AEP: NRC:

APPROVED BY: DAT-:

3'.TO BZ COMP~=-TED BY A"-PSC C,UALX~"ASSUHAVCE TRMS~<TTAL PORN AND DATA'ECOAT D BY: DATE:

( Xnitia3.s )

C-~QP FXLZ ~JDEX UPDATED BY: Date in'-'a s)

DATA PXLED BY: Date Inxcz.a s)

~g(cAN E'4 pc ~

l~

AMERICAN ELECTRIC POWER SERYICE CORPORATION A

~CA Stat<

September 28, 1982

- SUBJECT! The Kerite Company Cable Environmental Qualification FROM<

L. F. Caso Tos79-81B Central File The attached letter from the Kerite Company dated 9/21/82

.should be. made part of our equi nt qualification document xeference numbers 63,68,78 and 72.

I L. P. Caso 2.4/LFC:jal APPROVE J. Mo ABARTOLA 4

49 Day Street Seymour, Connecticut 06483 (203) 888-2591 f

'e. the kerite company Mail All Correspondence To:

P.O. Box 452 Seymour, Connecticut 06483 R \

"~~ in September 21, .1982 I American Electric Power Service Corporation 2 Broadway New York, NY 10004 ATTENTION: T.J. MASSAR-ELECTRICAL ENGINEERING DIVISION

Dear Sir:

~ ~

SUBJECT:

DONALD C.

Q, gA~ ~/-7i~

COOK NUCLEAR PLANT

REFERENCE:

QUAL IF I CAT ION UPDATE We have enclosed LOCA profile (excerpted from "Tests of Electrical Cables Under Simul taneous Exposure to Gamma Radiytion, Steam and Chemical Spray Whi le Electrical ly Energized" - March,i 1985'~ Final Report IIIF-C4020-2, Figure

1) which describes a 100"day test conducted by the Frankl in Institute Research Laboratories. This test provided a sodium borate chemical spray with a pH of 10.5 for 100 days continuously. The 'attached profi le and the following results are offered as documen'tation of Kerite insulation and jacket materials'Long-Term" (three months) immersion performance in a sodium borate solution.

The two cable samples (tested in referenced report) are representative of each 1/C which form the 3/C cable. Both samples (aged and unaged) are described as follows:

1/C, g6 AWG, 65 mil HTK (N-98) insulation and 65 mil FR (HC-71 1) jacket. I Each sample was irradiated to 200 megarads whi le instal led in the autoclave.

In summary, both cables maintained their electrical loading (1000v ac, 50 amps) throughout the test. Each cable passed the 5 minute vol t."ge wi th" stand test of 80 volts ac per mi1 of conductor insulation. Thi test was performed after completion of the LOCA exposure and prior to di assembly of the test vessel whi le the cables were sti I I on the'andrel ~

a subsidiary of HARVEY HUBDELL INCORPORATED HUoocLL

-~~rican Electric Power Corp. "2" September 21, l982 We trust that this is sufficient information to enable. you to answer the inquiry of the NRC.

Very truly yours, THE KERITE COHPANY From the office of: C.A. Lundy Metropohitan Sales Hanager Signee: N Ad rma H. Dube

>L inistrative Sales Assistant CAL/NHD/ss Enclosure

r PHASE I COMBINED THERMAL AND PHASE R SIMULTANEOUS STEAM/CHFMICAI. SPRAY/RADIATION EXPOSURE 'HASE'3K STEAM AND CHEMICAL-RADIATION AGING (l50 MEGARADS GAMMA RADIATION) SPRAY EXPOSURE (50 MEGARADS (NO GAMMA RADIATION)

GAMMA RADIATION) 346 F/II3psig WITHIN 3 TO 5MlN.

335'F/95 psig 340 320 3 I5'F/69 psig QIINSULATION 265 F/2epslg RESISTANCE MEASUREMENT W

< 250 I-280'Fl70psig (min)

W WITHIN IO SEC. 212~F/Opsig

~ 200 -

' DAILY 12VF(50ic) MAXIMUM 60NCE PER t

WEEK STARTING AT 5 DAYS CABLES AT ROOM CONDITIONS DURING RELOCATION OF TEST

- I40 VESSEL TO OUTSIDE OF THE 77 DAYS RADIATION HOTCELL.

I22 PREHEAT TO 140 F MAXIMUM IMMEDIATELY PRIOR TO TEST

.5 8 II l5 23

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IO 3 IOO 70AYS SEC HR HR HR HR 4 DAYS DAYS DAYS TIME I

Figure 1. Specified Temperature, Pressure and Radiation Test Profile

K~o'- EGQ I'9U DONALD C. COOK NUCLEAR PLANT EQUIPMENT QUALIFICATXON FILE UPDATE TRANSMITTAL F

'l..TO BE COMPLETED BY COGNIZANT AEPS SF( >> RFC DC Attached Forms checked: G~

ORIGINATED BY:

'6) DATE: il~s Isa (System ngineer Signature)

APPROVED BY DATE: rg g0

( e igryx re)

DATE:

(EGS Manager Signature) 2.TO BE. COMPLETED BY AEPSC NS&L SECTION

+ACCEPTED-TRANSMIT TO AEPSC QUALITY ASSURANCE

@REJECTED- RETURN TO COGNIZANT AEPSC SECTION MANAGER REASON FOR REJECTION:

, XS NRC SUBMITTAL REQUIRED? @YES @NO IF YES'IVE SUBMITTAL'ETTER NUMBER AEP:NRC:

APPROVED BY: DATE:

3.TO BE COMPLETED BY AEPSC QUALXTY ASSURANCE

.TRANSMITTAL FORM AND DATA RECEIVED BY: DATE:

(Inxtxals)

CEEQF ".FILE;INDEX"UPDATED BY: Date Xnxtxa s DATA FXLED BY'. Date Inxtz.als

4. COPY OF COHPLETED FORM TO BE RETURNED TO ORXGINATOR ELEC.

GENERATION SECTION.

To be incorporated in RFC file at close-out.

p)+AN ce,gc r lp A)IE RICA}( El ECTRIC POYI ER SERVICE CORPO RATiON Ar ~>>

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January 7, 1902 U" 79-Olla Submittal JLCT'~,uipmcnt Qualification Co>>tn.i.ament Spray pH F(,og: P. A ~ Fisher TO: 3.-:- R;--1:":-Dodd--

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Ne have reviewed the attached list of electrical materials with respect to the stated test report pH's vs the postulated 0.5 to 11 pH range for the containment spray following a LOCA. The postulated pH brackets all but three of the thirty five pH values listed; Of the three items, one was tested at a pH range of 7.67 to 10.5. The upper value, falls within the postulated pH xange. The other two items tested at. a stated pH of 7.67, axe listed as "steel or cast Iron enclosure". These materials would definitely not be affected anymore ignificantly at a postulated upper pH limit of the spray solution than at the lowex'.67 pH test value.

Therefore it is I:ho Chemical l',nginecring Section's considered opinion that the differences between the pH's listed for the test reports and that postulated for .the spray are insignificant. Consequently, for all practical purposes, the pH values listed meet the postulated spray pH criteiion.

M. O'Keefe's memo'of November 3, 1901 addressed the ubject of electrical and mechanical materials in mqre detail. This memo, therefore, is to be considered as pertinent reference information on this subject, partic-ularly in regard to instrument component materials'ompatability with the postulated pH range of the containment spray.

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I AMERICAN ELECTRIC POWER SERVICE CORPORATiON E'R eve<~

V November 3, 1981 Equipment Qualification Meeting M. J. O'Keefe z~ i et~~.

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3. S. H. Steinhart

4. S. M. Toth This memo is in response to questions raised during the October 2 Equipment Qualification Meeting. The pH range of 8.5 to 11.0 used to assess the resistance of various materials .to the containment spray is given in both Unit 1 and Unit 2 Technical Specifications. There i:s no need to consider the corrosion effects of demineralized water sihce during and after an accident the water in the containment wi.ll contain chemical additives.

The "alkaline" spray in the containment will be a weakly basic sodium borate (borax) solution formed by the reaction between the boric acid in the reactor coolant and the sodium hydroxide spray additive. The .long term

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ffect of this solution on stainless'teel, copper wire, and polysulfone would be

~

'nimal. Polysulfone, a Union Carbide Corp. product, is used as a sealant for

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containment penetrations. Union Carbide recommends polysulfone for use up to 250 F in a 50% sodium hydroxide solution, which has a pH of approximately 14.

'his solution would be much more aggressive than the containment spray.

The components of the Hydrogen Recombiner specified by Electrical

.,Engineering Division are 300-Seri~ stainless steel, carbon steel, Inconel-600, Incoloy-800, and magnesium oxide. The magnesium oxide is an insulating material sheathed in the Incoloy-800. The spray solution would not adversely affect the stainless steel, Inconel-600 or Incoloy-800. The magnesium oxide because is contained in the Incoloy-800 will not be contacted by the spray and will not be affected. The carbon steel components would rust, unless coated, as they would in any moisture laden atmosphere, such as would exist in the containment after a loca.

Neoprene, crosslinked polyethylene, chlorosulfonated polyethylene, and ethvlene-propylene elastomer which are used inside the containment a cabl:.

insulation, all exhibit long term resistance to basic solutions. Chlorosulfonatod polyethylene and ethylene-propylene whose trade names arc Hypalon and Nordel respectively, along with Neoprene are recommended for use in boric acid, sodium borate, and sodium hydroxide solutions.

~ ~ ~ ~ ~ ' w ( OL M4(

~ lt '4 44l ~ Il'l opylene have corrosion resistance to ba ic solutions. The carbon steel and cast ron components of the instruments aze coated with ~ nercoat 66. This coating is an epoxy-polyamide "esistant to basic . olutions.

IHT RA ~ SY 5T CM

This submittal input was prepared using the sources of information shown on the attached SSDL and is, to the best of my knowledge, technically curate, factual, and complete.

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M. O'Keefe MJO:mm cc: + 1~(@~ra J. Castresana TBN/GWP/File AEC it I have reviewed this document and have verified that is factual. by: review of information sources on SSDL; discussions with preparer; and discussions with

.other parties. To the best of my. knowledge, thi;s submittal input is 'technically

,.'accurate, responsive to the 'Action Item" and complete.

NRC SllHlllTTAL SOURCE DI.)CUBI)ENT LIST IOH ITEM s.P.

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FOR f'llEP APAf I Oh OF 1 HF AI I ACl CO RNC Clif Ill 'I AL ~ \!Or I C S OF 1llCSE Per ..fACi f C Ai>I, Al Al I AliiI l CR etf i l ~ a 4~ 1llF COC AI I O'I SPECI F I FO SUBhIITTAL STATEI!ENT SOURCE DOCUhIEIIT DESCRIPTION TITLE, CURREII'I'OURCE PACE PARA.

NUMOER, Rf VISION, ETC. DOC. I.OCATION go34

/03 7