ML18219D866

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

ML18219D866
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: ML18219D866 (18)

Text

U.S. NUCLEAR REGULATORY CO ATION NRC FORM 196 IZ-iSI

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NRC DISTRISUTION FQR PART 50 DOCKET MATERIAL OQG O

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'NATTER IPtQR IQINAI ClcoP Y CESCRIPTIQN I

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~NCLASSIFIEO j TO:

Mr. Edson G>> Case PROP INPUT FORM ENCI OSURE FROM:

Indiana 6i Michigan Power Company New York, N

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S ~ Hunter OATS QI OOCUMENT 11/29/77 OATS RECEIVEO 12/5/77 NUMSER QP COPIES RECEIVED Consists of additional info>> to the supplied info>> in 11/23/77 ltr>> in support of the use of butt spliced connections for electrical penetrations on the inside of the contain-ment>> ~ ~ ~ ~

PLANT ViNE:

Cook 1

RJL 12/6/77 I

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ASSIGiVED AD:

LTR BRANCH CHIEF:

PROJECT i~(ANAGER:

S FOR ACTION/INFORMATION INTERNALOISTRI BUTION ICE P.

COLLINS OUSTON HELTEiiiES IPPOLITO F.

ROSA CAMNILL 2)

VOLLlIIER (LTR)

BUNCH J.

COLLINS CASE (LTR)

MIPC LTR)

IGHT (LTR KREGER CcJCk7 BOSNAK SIHNEIL PAWLICKI ROSS (LTR NOVAK ROSZTOCZY CHECK TEDESCO LTR)

BEViAROYA LPDR:

TIC NSIC ACRS 16 CYS SENT CA i dAr P7-EXTERNALOISTRIBUTION CONTROL NUMBER OOOO

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INDIANA L MIC%lEAII OWER COMPANY P. 0. BOX 18 BO WLIN G G R E EN STAT ION NEW YORK, N. Y. 10004 40+

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Donald C.

Cook Nuclear Plant Units 1 and 2

Docket Nos.

50-315 and 50-316 DPR No.

58 and CPPR No.

61 November 29, 1977 Mr. Edson G. Case, Acting Director Office of Nuclear Rea'ctor Regulation U.S. Nuclea'r Regulatory Commission Washy.'ngton, D.C.

20555

Dear Mr. Case:

Attachment A to this letter provides additional information to 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 Power, 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 Raychem test report.

The procedures used to fabricate the splices at Cook Nuclear Plant are based on the Raychem procedures.

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Mr. Edson G.

Case November 29, 1977 These Raychem procedures as well as Raychem Report 71100.are to be found in the Raychem Power. Distribution Products catalog.

Very truly,yours, R.

S. Hunter Sr. Vice President Construction American Electric Power Service Corporation RSH kb Attachment cc:

R.

C. Callen P.

W. Stekett-R..Walsh R. J. Vollen D. V. Shaller Bridgman R.

W. Jurgensen G. Charnoff John Tillinghast

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To Whom I t May Concern:

Subject:

Addendum Raychem Report P.'71100, Pevision 1

Heat Shrinkable Products for Nuclear Power ln order to clarify certain product testing (WCSF),

the following notation to subject r port should be added:

All WCSF:"type parts tested in accordance with Raychem Report No. 71100, Revision I were coated type

-N adhesive designated by Raychem type S-1024.

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V Canady Thermofit Materi evelopment Manager Al An e.on Market M=..ager Power D*s>'ribution Products

~Per our Thermofit Specification k'1508 dated

May, 1974, Revision 1.

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RAYCHHI~A ABSTRACT Raychem Corporation is in the process of evaluating many of its products for use in nuclear power plant containtttents.

Using the Institute of Electrical 6 Electronics Engineers "Proposed Guide for Type Tests of Class I Cables and Connections Installed Inside the Containm nt of Nuclear Power Generating Stations" as the test basis, 5 and 15KV high voltage terminations (HVT's) and 600-2000 volt in-line splices were found to withstand loss of coolant accident (LOCA) conditions of a design basis event (DBE) either early or late in their anticipated use life.

HVT's remain usable, having excellent tensile strengths and elongations, even after 200 I'rads (2 x 10 Rads) of gamma radiation in air.

Properly applied HVT's form an environmental seal around the cable protecting it from high pressure

steam, moisture, and boric acid spray.

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RAYCHEM I HTRODUCT I OH

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The current energy crisis and increased power consumption have created a demand for more power plants.

When these factors are combined wi th our current ecological awareness and the need to prevent additional damage to the environment, nuclear power plants emerge as viable candidates to satisfy our power needs.

As of September 30,

1971, 10,040,800 kilowatts oF electrici ty could be generated in the United States by nuclear power plants; additional capacity of 45,779,000 ki lowatts were being built; and 51,571,000 kilowatts of nuclear power were being planned This growth attests to the increased attention being given to nuclear power as a source of energy.

Whi le the ultimate purposes of a nuclear power plant are the same as those of a fossil fuel plant, the requirements and demands placed upon electrical insulating materials are different.

In a fossil fuel plant, the engineer needs to know the elcctrica) properties of the insulating materi'als, how these properties char ar with time, and the effects of moIsture and oxygen upon electrical and physical properties.

For n'uclear power plant use, in addi tion to the aforementioned properties, the engineer also needs to knori how the materials

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are affected by nuclear radiation over a 40-year lifetime.

Virtually all organic materials are known to be affected by radiation.

In some cases where the radiation can be control led, the property profi les of many organic materia'ls are improved by exposure to radiation.

In these

cases, the material is exposed to gamma or electron beam radiation under "Huclear Reactors Built, Being Built, or Planned in the United States as of December 31, 1971", Hational Technical Information Service, Report Humber TID-8200 (25th Revision).

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~ l're 9l0 373 l728 RAYCHBd carefully controlled conditions for specific lengths of time and a material with an improved property spectrum results.

These improved materials have greater tensilestrength, greater stress crack resistance, lower moisture

'apor transmission, greater elastic

memory, in addition to the other improve-ments over their non-irradiated counterparts.

In a nuclear power plant, the exposure of materials to radiation cannot be fully controlled, nor can the length of exposure be reasonably controlled.

The materials installed in a nuclear power plant must have the highest possible resistance to the long-term effects of heat and radiation.

In addition to inherent radiation resistance, the materials used in a nuclear power plant must also provide assurance that in the event of an

accident, they will maintain their integrity so that the plant may be safely shutdown.

This is true if the accident were to occur during start-up or after the plant had been operating for many years.

Cottsequently, materials designed for use in nuclear power plants must be evaluated under accident conditions before an 'fter their exposure to nuclear radiation.

Raychem Corporation has extensive experience in the irradiation of organic materials.

For over 15 years, our principal business has been the irradiation of organic materials to enhance their balance of properties.

Some of the products developed in our laboratories and extensively tested in use are our heat recoverable high voltage terminations (HVT) and 600-2000v in"line splices (MCSF).

This report describes the evaluation of these products for use in nuclear power plants.

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RAYCHD0 PROGRAM OUTLINE HVT and WCSF evaluations were divided into two phases:

materials evaluation and systems evaluation.

The materials evaluation cons)sted of an in-depth look at how the materials of construction behaved as a resul t of nuclear radiation.

Systems evaluation consisted of an in-depth analysis of how the completely assembled parts behaved as a resul t of nuclear radia-tion and how well it wi thstood the effects of a loss of coolant accident before and after exposure to'uclear radiation.

The evaluation was based upon the Institute of Electrical and Electronics Engineers "Proposed Gu)de for Type Tests of Class I Cables and Connections Instal led Inside the Containment of Huc)ear Power Generating Stations".

The II test sequence for materials consisted of:

1.

Heat aging the materials in a forced air oven at 121

+ 2 C for 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.

2.

Irradiation of the matet 'a)s in a cobalt 60 garrma source at 0.52 Hrads

~er hour to total doses of 100 and 200 Mrads.

The test sequin e for assembled high voltage terminations and in-line

. )ow voltage

( 1.e.,

600-2000v) splices consisted of:

1.

Heat aging high voltage terminated cables at 121 i 3 C for 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> in a forced air oven.

2.

Irradiation of assemblies with cobalt 60 gatntta radiation at 0.50 Mrads per hour for HVT's and

.27 Hrads per hour for WCSF to total doses of 100 and 200 Hrads.

3.

Subjecting irradiated assemblies maintained at maximum rated Paychem CnlpoMtinn 3GO Cnnslitut ns Oiive tl~enln

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RAYCHEM voltage to LOCA tests in a pressurized autoclave according to the fo 1 1 ow i ng s che du 1 e:

a.

5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> a t 360 F, 70 ps i g s team.

b.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at 320 F, 70 ps i g steam.

c.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 250 F, 21 psig steam, 0.24 boric acid spray, buffered to pH of 10.

d.

12 days at 221oF, 2.5 psig steam, e.

100 days 6212 F

2 0 psig steam.

TEST RESULTS Tables 1 and 2 show the results of the materials evaluation of Raychem HVT's and WCSF sleeves.

These data show that even after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121 C

in a forced air oven and subsequent irradiation to 200 Hrads cobal t 60 gamma radiation in air, the products have maintained a very high degree of mechanical integrity.

As an example the outer high voltage tubing and stress grading material have maintained at least 804 and 70~ elongations, respectively.

This, coupled with the excellent t nsile strengths, indicates that thes materials have sufficrent toughness and radiation resistance to withstand 200 Hrads gamma radiation.

Table 3 shows the electrical performance of 15KV HIT's during LOCA tests.

From. the data, it is evident that all HVT's, those irradiated to i

100 or 200 Hrads, as well as those not irradiated at all, are capable of performing during a loss of coolant accident.

Applied voltages for.the, 15KV HVT's during LOCA tests varied between 8.7 and 15KV, phase to ground.

Table '4 yields simi lar data for 5KV HVT's.

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)IVTts successfully wi thstand LOCA tests before and after irradiation.

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

Table 5 shows electrical performance of a series of in-line splices made on 600, 1000 and 2000 volt class cable and subjected to continuous maximum cable rated voltages.

SUNDRY Data supplied in this report show that when properly assembled, Raychem high voltage terminations and in-line low voltage splices may be recommended for use in nuclear paver plants.

The assembled terminations and splices have successfully withstood DBE and LOCA tests and remain functional during the accident.

They will perform so as to permit a safe and orderly shut-

- down of equipment in the event of a loss of coolant accident.

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RAYCHDI TABLE I

EFFECTS OF NUCLLAR RADIATION UPON RAYCIIEH HVT I'ATERIALS Outer Tab in" Stress

~Grad in Initial elongation, X

260 236 Elongation 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 Hrads, X

126 140 Elongation 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 Hrads, X

80 70 Initial tensile strength, psi E

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 Hrads, psi 2290 3025 1560 2015 Tensile strength after 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121'C plus 200 Hrads, psi Initial hardness, Shore D

3020

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43 1665 37

'lardness after 168 I:ours at 121'C plus 100 Hrads, Shore D

57 50 Hardness 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 Hrads, Shore D

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RAYCHEiVi TABLE 2 E FFE CTS OF NUCLEAR RAO I AT I Otl UPON RAYCHEH WCSF HATERIALS Initial elongation,

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Elongation 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 Hrads,

• Elongation 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 Hrads,

'4 Initial tensile strength, psi Tensile strength after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> a t 121 C

p 1 us 100 Hrads, ps i 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 200 Hrads, ps i Initial hardness, Shore D

Hardness 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 Hrads, Shore D

Hardness 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 Hrads, Shore D

WCSF 565 100 2180 1500 37 MCSF Slab Sample Q.I25" Thickness 440 145 70 1600 1745 1685 43 46

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RAYCl-Ic.("v1 TABLE 3 PERFORHAHCE CHARACTERISTICS (CORONA EXTINCTION VOLTAGE)

OF RAYCHEM I5KV IIIGH VOLTAGE TERMIIIATIONS DURING DBE/LOCA TEST IIIG HVT HVT HVT HVT HVT HVT gl g2 g3

//Il g5 g6 Initial CEV, KV CEV after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121 C

CEV after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121oC p 1 us 100 Hrads 19 14 15.5 20

17. 5 20

19. 5

21. 5 21 s

30 25 25 24 31 CEY after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121oC p lus 200 Hrads CEV after 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> DBE3 17 15 20.5 21

19. 5 16 16 16 Notes 1.

Crosslinked polyethylene cable, copper tape shield, extruded semiconductive layer.

2.

Cobalt 60 gamma radiation, dose rate of 0'.50 Hrads per hour.

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3.

5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> at 360oF, 70 psig steam; 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at 320 F, 70 psig steam, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 250 F, 21 psig steam, 0;2C boric acid spray at pH of 10, 12 days at 221oF, 2.5 ps ig steam, 100 days at 212oF 2.0 ps ig steam.

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RAYCH.M TABLE 4 PERFORHANCE CHAiRACTERI ST I CS (CORO!<r'tt EXTINCT I ON VOLTAGE)

OF RAYCHEH 5KV HIGH VOLTAGE TERNINATIONS DURI tIG OBE/LOCA TEST I tiG HVT Pl HVT ir'2 HVZ 83 HVT 84 HVT l/6 Initial CEV, Kv CEV after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121'C CEV 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 Yirads~

CEV 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 iIrads2 4.8 4.5 4.2 4.3 5.5 4.6 5.2 5.5 4.0 4.3 5.8 4.8 4.2 5.8 4.4 5.0 CEV after'5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> DBE 4,5 4.1 4.7 4.5 4.8 (4)

Notes l..

EPR cable, copper tape shield, tape semiconductive layer.

2.

Cobal t 60 gamma radiation, dose rate of 0.50 Hrads per hour.

3.

hours at 360oF, 70 psig steam; 6',hours at

320oF, 70 psig steami 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 250 F, 21 psig steam, 0.2~~ boric, acid spray at pH of 10, 12 days at 221 F,

2.5 psig steam, 100 days at 212 F 2'.0 psig steam.

4.

Specimen mechanically damaged before being-placed in autoclave.

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~'I RAYCHEIvl TABLE 5 PERFORMANCE CHARACTER I ST I CS OF RAYCHEH 600-2000 VOLTS Ill-LINE S. I.ICES TYPE WCSF'URING DBE/LOCA TFSTING

- New Material Per Table 2

Aged 168 Hours 9121oC 0 200 Mrads Electrical Strength 5 Samples

- Volts/Mi 1 Minimum Maximum X

312 491 380 318 355 334 Wall Thickness 084" 086" Volume Res i s tivi ty OHM-CMS 2.5 x 1013 1.2 x 1014 Flanntabi 1 i ty Per A.S.T.M. D-2863 Oxyge!1 Index Note Slab Data Only 35.0

, 3?.0 Notes l.

Cable types for tes1'!ng A.

600 volt Flamtrol"'.

2000 volt EPR/Neoprene Cable 'types for Cook Nuclear Plant s lices 600 v Kapton 600 v Hypalon 2.

All samples were continuously operated at maximum current and voltage per cable class.

Current levels per I.P.C.E.A.

3.

Cobal t 60 gamma radiation, dose rate of 0.27 Mrads per. hour.

4.

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; 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at 320 F.,

70 psig steam; 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 250 F, 21 psig steam, 0.24 boric acid spray at pH of 10, 12 days at 221oF, 2.5 psig steam 100 days at 212oF 2.0 psig steam.

5.

All samples passed..

No.electrical or mechanical failures.

Roychem Corporotion

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