ML18219D868

Letter Additional Information on Use of Butt Spliced Connections for Electrical Penetrations on the Inside of the Containment

ML18219D868
Person / Time
Site:	Cook
Issue date:	11/29/1977
From:	Hunter R American Electric Power Service Corp, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	Case E Office of Nuclear Reactor Regulation
References
Download: ML18219D868 (29)

Text

(i DISTRIBUTION AFTER ISSUAVICE OF T

LICE ISE I NRC,PoRM

$95

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U.S NUCLEAR REOUI ATORY COMMISSION

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NFtC DISTRIBUTION FoR PART 5D DOCKET MATERIAL 0

ET NUMB I TO:.

i Mr. Edson G. Case FROM:

Indiana Si Michigan Power Company New York, N

Y R

ST Hunter OATE OF OOCUMENT 11/29/77 OATS R ECEI VE 0 11/30/77 gmTTER C'ORIOINAI

~COPY ESCRIPTIQN C3NQTORIZEO RKINCLASSIFIEO PROP INPUT FORM ENCI OSURE NUMBER OF COPIES RECSIVEO eoPy Consists of additional infoi to that sujIIplied-in licensee'4 ll/23/77

1tr, in support of their use of, butt spliced connections for electrical penetrations on the inside of thy containment+

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(2-P)

(1-P)+(11-P)

PLANT NAME:,

Cook RJL 12/1/77 Q~IQ~ ~ QL~~IG~G LV A'b~ I~~

oe ARHAa. Sue,wibc.

PER l&s~W or-MBA

// Ho SAF:"TY BRANCH CHIEF:

7 FOR AC i ION/INFORMATION INTFRNAL0 RlBUTION RIRC FDR ICE (")

OELD HANAUER CHECK IIH~

EISEiVVT SHAO BUTLER GRIMES 0

INS J

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LFDR!

TIC NSIC 1S CYS ACRS SENT CATE 0 EXTERNAL0 ISTR I8UTION CONTROL NUMBFR

/IA.III 773250iS5

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5SIXg8ijjSA'NoIANA a

NIIcHIGAN PowER CowpANY

r. a. BOX >II BOWLIHC CACEN STATION HEW YOAK, I4 ~ Yi )0004 Donald C. Cook Nuc1ear X'lant Units 1 and 2

Docket Nos.

50-315 and 50-316 DPR No.

58 and CPPR No.

61 November 29, 1977 her.

Edson C. Case, Acting Director Office., of Nucleax Reactor Regulation U.S. Nucleax Regulatory Commission Nashington>

D.C.

20555 Dear Mr. Casei Attachment A to this letter provides additional information Co that supplied in our November 23, 1977 letter, in support. of'our use of butt spliced connections for electrical penetrations on the inside of the contain-ment.

The attachment entitled, Addendum Raychem Report No. 71100, Revision 1 Heat Shrinkable Products for Nuclear Powex, documents the Raychem post-accident environment qualification of the butt splices that we are

using, A comparison of. cable materials used in the Raychem test and those used in the Cook Nuclear Plant splice is shown on Table 5 of the Baychem test xeport.

The procehorea used to fabxicate the splices at.

Cook Nuclear Plant are based on the Raychem procedures.

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Edeon C. Case November 29, 1977 Those Raychem Procedures as well as'aychem Report 71100 are to be found in the Raychem Power Distribution Products catalog.

Very truly yours>

RSH kb Mtachment R. 8. Hunter Sr. Vice President

'- Construction American Electric Power Service Corporation Coo R. C. Callen P.

N. Stekett R. Welsh R. J.

Vo11en D. V. Shnller Bridgman R. W..7urgensen G. Charnoff John Tile.inghait

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TELECGt)-QQ-pp p~

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To Mhotn l t Hay Concern!

SubJect:

Addendum Boychctn Ac port P'71100, Revision 1

Hest Shrinkable l'roducte for Nuclear Power ln ordor to clarify certain product testln9 (PCS')

h ol)owing notation to cubJoct report should be bddedgt e A)1 MCSF>>type ports tasted in accordance saith Raycl>om Report tlo. 71100, Revision 1 ~clara coated typo -H adhesive dosignnted by Rnychem type

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Thermo% l t fj hHsterl evalojment Honhger

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.~on Herkat h~>>ager Power Dls<'rlbutton Products

~Por ovr 'fhermofl t Specification f1508 datod Hay, 19Z4, Revision 'l,

Raychem Corporation fs ln the process of evaluating many of its products for use fn nuclear power plant contalnnents.

Using the institute of Kfectrfcal Electronics Engineers "f'roposed Guide for Type Tests of Class f Cab1es and Connections installed Inside the Containment of Nuclear f'ower Generating Stations" as the test bisfs, 5 and 15KV high voltage terminatlons

()IVT's) 1 and 600>>2000 volt in"line spl fees wore found to wi ttistand loss of coolant accident (LOCA) conditions of a design basis event (DDE) ei ther early or fate ln their anticipated use fifo.

llVT's remain usable, f~avfno excellent tensile strengths and efongatfons, even after 200 Mrads (2 x l0 Rods) of gamma radiation fn afr.

properly applied HVT's form an'nvironmental seal around the cable protectfnj ft from high pressure stcam, moisture, and boric acid spray.

Thermofit Report 71100 Revision 1

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'NTRODUCTION The cus rent energy crisis a>>d increased power consumption

}iavu created is demand for more power plants.-

When tfscse factors. are combined with our 4

current ecolojfcal awareness and the need to prevent addft.fonaf damage to the environment, nuclear power plants emerge as viable candidates to satisfy our power needs.

4 of September 30,

1971, 10,060,800 kilowatts of e/ectricfty could be generated fn the Unf ted States by nuclear power plants,f adsff t fnnal capacf ty of 4$,77$,000 ki iowatts were befng buf I t; and 51,571,000 fcf Iowa( ts 4

of nuclear power were being planned., Tfifs growth attests to the 1ncreased attention being given to nuclear power as a source of enercjy.

Mhiie the uftfstote purposes of a nuclear pcmter plant are tl>e sama as those of a foss f f fuel plant, the requtrements and demands placed upon electrfcnl Insulatfng materials are different.

In a foss11 fuel plant, tf>e engineer needs to know the electrical propertfes of the fnsulatfng materials, how these properties chssilgss with t.fme, and tho effects of.moisture and oxygnn upon electrical and physical propertfes.

For nuclear power plant u~e, in addition to the aforementioned properties, the engineer also needs to know how the materials ore affected by nuclear radfation over a AO-year 1ffetfme.

Vli'tually a)I organic materials are known to be affected by radfatfon.

In some cases where the radfsstlon can be controlled, the property proff les of many organic materials are improved by exposure to radiation.

In these

esses, tbe nmtertil ls enposed to genme or e'leotron ennm rndletlon under

> "Nuclear Reactors Built, Oeing Built, or I'Iaiined In the Unf ted States as of pecember 31, l971"; National Technical Information Service; Report Number TID-8200 (25th ftevfsfan).

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carefu) ly controlled condi tiuns for spccl fic )enotlis of time and a material wt th an improved property speclrum resul ts.

These improved material have greater tensl le strength, greater stress crack resistance,

)ower moiturc vapor transmfssfun, greater ela tic memory, ln addi tion to the other improve ments over their non<<frradiatacj counterparts.

In a nuclear power pla i, th exposure of materlalr, to radfatfon cannot bc ful ly controlled, nor can tf~e

)ength of exposure 6e reasonably cohtro) )ed.

The moterfafs fnstal led fn a nuc)ear power plant must have the highest possfh)e rcsfstanco to the long-tirm effects of hLat and lad)ation.

)n addftion to inherent radfatfon resistance, the materials used tn a nuc)ear power plant must also provide assurance t)iat in the event. of an

iccfdent, they wf)l mafntafn theft'ntegri ty so that ttie plant may be safely shutdown.

This ls true tf the accfdcnt were to occur during start<<up or after the p)ant had been operating for many years.

Consequent)y, materials designed for use fn nuclear power plants must bc eva)uated under accfdent conditions before and after their exposure to nuclear md)at)on.

Raychem Corporatfon has extensive experience in thc irradiation of organic materials.

For over

)5 years, our prlncipa1 buslnes has been thc lrradlatlon of organic materia)s to enhance their balance of properties.

Some of the products devk)oped In our laboratarfes and extensively tested ln use are our heat recoverab1e high vo) tage terminations (IIVT) and 600-2000v ln<<)lne splices (MCSF).

This report describes the evaluation of these products for use

) n nuc) oar power p )ants

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PROGRhN OVTLINE HVT and MGSF evaluations were divided into two pleases:

materia)s ava luat ion and sys tems eva lua t Ion

The mater I a I s eva Iuat Ion cons I s tcd of in-depth look at t>ow the materials of constructlan behaved as a resul t of nuc)ear radiation.

Systems evaluation consisted of an ln-depth analysis of how the completely assemb)ed part behaved as a resu) t af nuclear radia-tion and how we I I I t wi thstaod the effects of a loss of coolant accident before and after exposure to nuclear radiation.

Tha ovaluatfon was based upon the institute of K)ectr)ca) and Electronics Engineers "Proposed Guide for Type Tests of. Class I Cab)es and Connections installed Inside the Containment of Nuclear Power Generating Stations".

The test Sequence for materia)s consisted of:

I.

Heat aging the materia)s ln a forced air oven at 12lo 4 2 C 'for

. l68 hours, trradtat)on of the materials ln a cobalt 60 gamma source at N

0.52 Hrads,.per hour to total doses of 100 and 200 Nrads.

The test sequenCe for assemb)ed high, voltage terminattons and tn-I inc

)ow vo) tage (I.e., 600-2000v) splices consisted of: --

Heat aging high voltage terminated cables at 12)

< 3oC for 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> In a forced ai r oven.

Irradlatlon of assemb) les with cobalt 60 gatena radiation at 0,50 tracts pcr hour for.HVT's and,27 Hrads per hour for MCSF to total doses of 100 and 200 Nrads.

SubJectlng irradiated assemblies maintained at maximum rated

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voltage to LOCA tcs ts in a prcssvri wed autoc) ave according to the following *chedule:

a.

5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> at 360 F, 70 psig steam.

b.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at 320oF ~ 70 psig steam.

c.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 250 i', 2l pslg steam, O.N boric acid spray, buffered to pH nf 10.

d, l2 days at 221oF, 2,$ psig steam.

e, 100 days 9212oF 2 0 psig steam, TEST MSULYS Tables 1 and 2 show the results of the materials. evaluation of Aaychem HVT's an MCSF sleeves.

These date show that even after 168 liours at 121oC ln a forced air oven and subsequent irradiatio t

200 1

d o

)ra s co alt 6Q gem@a radiation ln afr, the products have mointained o

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Very g i egrcB of mechoni eel lntegrfty.

As an example the outer high volt t bi 6 d o

age u

ng 6n stress grading material.havo maintained at /cast 804 and 704 elo ti e ongat ons, respectively.

Thfi, coupled with the excel1ent tensi le strengtt 1 di eng is, n

cates that these eaterlals have sufficient toughness end radiatio n res stance to wl ths tand 200 Hrads gamma radiation.

Table 3 shows the electrlca) performance of 15KV HVT's during LOCA tests.

From the data, it is evident that all HVT's, those irradiated tp lOO or 200 Hrade, as well es those not irradiotod at all, are capab1e of performing during a loss of coo)ant accident.

Applied voltages for the 15KV HVT's during LOCA tests varied between 8.7 end l5KV, phiise to ground.

Table 4 yields similar data for 5KV HVT's.

Hire agalnf the IRQychcm

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IIVT's successfully vci thstand LOCA tests before and after Irradiation.

The 5KV HVT's vere subjected to applied voltages bebteen 5 to 8.6KV phase to ground during the LOCA sequence.

Table 5 shceis electrical perfornmnce of a series of In-linc splices made on 600, 1000 and 2000 volt c'lass cable and subjected to continuous marin>un> cable rated voltages.

SUHHARY Oata supplied In this report sheer that +hen properly assembled, Raychem high voltage terelnations and In" ) inc Iev voltage splices may be recommended for use ln nuclear pmcer plants.

The assembled tereinatlons and splices leave successfully withstood OSE and LOCA tests and remain functional during the accident.

They mill perform so as to per+I t'a safe and orderly shut-doc~n of'quiparant in the event of a loss of coolant accident.

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TABLE I

EFFECTS OP Nucl.CAa nAOIATION UPON RAYCllEH llVT HATEAIALS

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ra Initial elonsatLon, X

Elon8ation after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at

-121 C plus 100 dorado, Slongation after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121 C plus 200 Nradsi Initial teasila strength, psi Tensile strength after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121 C plus 100 Nrads, ysi Tensile strength after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> ot 121 C plus 200 Mrads, ysi Xnitial hardness, Shoe'c 9 Outer

~Tub iB 2290

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3025

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~Gradin 236 140 1560 Hardness after 121 C plus 100 llardncms after 121 C plus 200 168 lBnurs at Nx'ads, Shore 9

168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at

1irads, Shore 9 KQFL'CTS OF NUCLEAR l4%DlATION UPOH BAYCI{EH MCSF HATERIALS t ni t) a) e longe t) on, 0 K)ongatlon after

)68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> at l2l C p}us )00 Hrads,

- AE)ongat)o>> after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at

)2loC plus 200 Hrads, lnltlal tens))e strength, psi Tens))e strength after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at l2)

C plus l00 Hrads, qsi Tens I le s treng th a ftcr l68 hours at )2loC plus 200 flrads, psl Inltjal hardness, Shore 0

flardness after

) 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> a t

) 2)oC p) us l00 Hrads, Sfiare 0

ffardness after

}68 hours at l2)oC p)us 200 Hrads, Shore D

WCSF Tubln Samples

)00 2)80 l500 37 MCSF Slab Sample 9.125" Th) ckncss

'70

)600 r

>>4S

) 68%

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46

~Tubing samples pore exposed to simultaneous heat aging and lrradlatlon

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TABLE 3 PERFORIW(CE CHARACTERISTICS (CORONA EXTINCTION VOLTAGE)

OF RAYCIIEH 15KV IllGH VOLTAGE TEAHINATIONS DURING noriLocA TEsTING>

'nitial CEV, KV CEV after )68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> at 12)oC IIVT HVT NVT NVT HVT Hvg k')

42 43 4'4 PS II6 20 17 5 20

)95 2l 5 2) 30 25 25 24 31

)9 BEB af'tor 168 laura at )2)oB plus

)OO llrads CEV after )68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> at 12)oC plus 200 Hrads2 CEV al'ter 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> OOE3 l7

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20. 5

)5.5 2)

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Gros'@linked polyethylene ca'b)e, copper tape shield, extruded semlconductive layer.

2.

Coba)t 60 garan>a radiation, dose rate of 0.50 IIrads per hour.

t 3, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> at 360 F, 70 ps ig steam; 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at 3204F, 70 psig steam, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 250oF,

2) psig steam, 0.24 boric arid spray at pH of 10,

)2 days at 22)oF, 2s5 psig steam,

)00 days at 212oF 2.0 psig staam.

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TABLE 4 PERFoaIIAtIcI: cIIAnA'cTEnisTics (conowA ExTIIIcTIOI< voLTAGE)

OF AAYCHEN 5tiV HIGH VOLTAGE TEWINATIOHS nUIIIwo noEILocn TEsTII<GI nitka1 CI'.Vj Kv CEV after )68 bours at 121 C

CEV after 168 bours at 121 C

p1us

)00 Hrnde~

CEV after 168 bours at 121 C

plujj. 200 Mrads~

1 CEV after 35.hours DSE3 HVf,:.,

81 4.8 4.5 4.5 IIVT II2 4 ~ 2 4.3 4.)

4 '

542 7

BVX 04 5.5 4-0 4.i IIVr 85 5.8 4.8 4.2 4.8 5.8 4,4 5.0 (4) otee 4

l... KPR cable, copper tape shield, tape scmiconductIve layer.

Cobalt 60 gjjnrnn radiation, dose rate of 0.50 Brads per hour.

hours et 360oF, 70 psig stcam; 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at 320oF, 70 pstg steam; 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 2$0oF j 2l psig steam, 0.24 boric acid spray jjt pH of lo, 12 days at 22l4F j 2,5 psig steam~

l00 days at 212 F 2.0 ps ig stcam.

Specimin mechanically damaged before being placed in autoclave.

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PERFORNWCK ClfhhhCTLRI ST I CS OF RAYCIIEII 600"7000 VOLTS Itf"LIIIf.Sf'LICFS TYf'I'. MCSF DVftI HG DOE/LOCA 'f LST It/0 K)cctrical Strength 5 Samplei - Volts/Nfl Hfnfmum Hnxfmvm New Hatcrfnl 312 Per Tnbfe 2

Aged 168 Ilours 912foC 8 200 f)rnds 318 MOll Thfcfcnazs

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.086>>

Volume Resfstivf ty OHH.CNS 2s$ x 1013 1.2 x loll<

Flanrnabf l 1 ty Par A.S.T.M. 0-2063 Oxy9eu Index Rotc Slab Data 0>> ly 35-0 37.0 I

2 s 3e 4.

i Cable types Cor Cook Nuclear P snt splices 600 v Kapton 600 v Hypalon Cobalt 60 gamma radfitfon, dose rote of 0.27 Nrads pcr hour.

$ hours it 360oF, 70 ps fg steam; 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> nt 320 6,'0 pslg stenm; 2~t hours at 250of, 2l psfg steam, 0.2R borfc ne.fd spray at pfl of lp,

}2 days at 22l<F ~ 2.5 ps I g steam, 100 days at 2 l2oF 2sQ ps f g stean>

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All samples passed.

No clcctrfcal or macha>> fcal faf lures.

Cable types for tcs I fng A.

600 volt Flnmtrol~f B.

2000 vol t Kf'R/ffeoprunc I

All samples were contfnuousfy operated at maximum current and voltage pcr cable classs Current levels pcr l.f'.C.E.A.

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