Text

Submit Additional Information to Supply to Previous Letter of 11/23/1977 in Support of Use of Butt Spliced Connections for Electrical Penetrations on Inside of Containment
	ML18220A502
Person / Time
Site:	Cook
Issue date:	11/29/1977
From:	Hunter R; Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	Case E; Office of Nuclear Reactor Regulation
References
	Download: ML18220A502 (15)
	v • d • e

4 NRCPOAM 195 (Z 7dI UA NUCLEAR RKQULATQRYCCMh.

ION OQCART NUMSe

\\I NRC DtSTRlBUTION PQA PART 50 DOCKET MATER1AL Pl!,s NUMSSA PSAR/PSAR A%)T DIST.

I TO:

1 Mr. Edson Gi Case FROM:

Indiana

& Michigan Power Company New York, Ni Yi Ro ST Hunter OATS QP OOCUMSNT 11/29/77 oAT5 Aecslvao 12/5/77

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~NcLAsslpleo P AOP INPUT POAM NUMseR op copld5 Ascslveo Consists of additional i.nfoo to the supplied info in 11/23/77 ltri in support of the use of butt spliced connections for electrical penetrations on the inside of the contain-menti ~ ~ ~ ~

PLANT ViAME:

Cook RJL 12/6/77 I

(2-P)

C12-P)

ASSIGNED AD!

LTR BRANCH CHI"P'.

PROJECT MANAGER'OR ACTION/INFORMATION INTERNAL0 ISTRlBUTION 4 ~"4 WR i

P.

COLLIVS STON HELTE:.KS CASE (LTR)

INSIGHT LTR)

BOSNAK IPPOLITO F.

ROSA GAMMILL 2 )

VOLLEYER (LTR)

J.

COLLINS URGER C4J44O47 VP PANLICZI ROSS

( LTR)

NOVAK i

I ROSZTOCZY CHECK T-DESCO LTRI BEVAROYA LPDR:

EXTERNAl. OISTRIBUT)ON CONTROL NUMBER NSIC ACRS 1& C.S SENT CATEGQR 69

>g000~

INDIANA II MICHIGAN POWER COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 L IS DPQ 8 19~

W~g~g le 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 Reactor Regulation U.S. Nuclear Regulatory Commission Washington, 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.

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

To Whom It May Concern:

Subject:

Addendum Raychem Report 0'71100, Pevision 1

Heat Shrinkable Products for Nuclear Power

'In 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 1 were coated type -N adhesive designated by Raychem type S-1024.

Or.

Vq Canady

~

[

Thermofit Materi evelopment Manager I

J.'

Al An e'-'on Market M-.ager Power D s>ribution Products Per our Thermofit Specification 4'1508 dated

May, 1974, Revision 1.

ABSTRACT Raychem Corporation is in the process of evaluating many of its products for use in nuclear power plant containntents Using the Institute of Electrical 6, Electronics Engineers "Proposed Guide for Type Tests of Class I Cables and Connections Instalicd 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 wi thstand 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 elongati'ons, even after 200 Hrads (2 x 10 Rads) of gartlta radiation in air.

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

steam, moisture, and boric acid spray.

Thermofit Report 71100 Revision 1

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INTRODUCTION The current energy crisis and increased power consumption hav 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 pover plants; additional capacity of 45,779,000 ki icwatts were being bui I t; 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.

While the ultimate purposes of a nuclear power plant are the same as those of a fossi I

Fuel plant, the requirements and demands placed upon electrical insulating materials are different.

In a fossil fueI plant, the engineer needs to know the electrical properties of the insulating materials, how these properties charac with time, and the effects of moisture and oxygen upon electrical and physical properties.

For nuclear power plant use, in addition to the aforementioned properties, the engineer also needs to know how the materials-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 controlled, the property profiles of many organic materia'ls are irproved by exposure to radiation.

In these

cases, the material is exposed to gamma or electron beam radiation under "Nuclear Reactors Bui It, Being Built, or Planned in the United States as of December 31, 197I", tlational Technical Information Service, Report Number TID-8200 (25th Revision).

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carefully controlled conditions for specific lengths of time and a material wi th an improved property spectrum resul ts.

These improved materials have greater tens i le strength, greater s tress crack res is tance, lower moi s ture vapor transmission, greater elastic r.emory, 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 th plant had been operating for many years.

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

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

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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RAYCHEi'",i PROGRr'M OUTL I tlE.

HVT and WCSF evaluations were divided into two phases:

materials evaluation and systems evaluation.

The materials ev" luation consisted of an in-depth look at how the materials of construction behaved as a result of nucle r radiation.

Systems evaluation consisted of an in-depth analysis of how the corpletely assembled part's behaved as a result of nuclear radia-tion and how well it withstood the effects of a loss of coolant accident before and after exposure to nuclear radiation.

The evaluation was based upon the Institute of Electrical and Electronics Engineers "Proposed Guide for Type Tests of Class I Cables and Connections Installed Ihside the Containment of Nuclear Power Generating Stations".

The 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 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months .

2.

Irradiation of the matet'als in a cobalt 60 gamna source at 0.52 Mrads ~er hour to total doses of 100 and 200 Mrads.

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

. low voltage (I.e., 600-2000v) splices consisted of:

1.

Heat aging high voltage terminated'cables at 121

~

3 C for 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months in a forced air oven.

2.

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

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

3.

Subjecting irradiated assemblies maintained at maximum rated troyes rm Cnr~rzhnn 3tr3 (.r n.t 'r;.".n (pr;~e f)i~l. l~.lid t.'.t'. r ir>t nq",26 4t'.r J~)33)

't't ( 9t03)3 )726 voltage to LOCA tests in a pressurized autoclave according to the following sch dule:

a.

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

b.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months at 320 F, 70 psig steam.

c.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 9212 F 2 0 psig steam.

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

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

in a forced air oven and subsequent irradiation to 200 t<rads cobalt 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 P'aterial have maintained at least 80< and 70~ elongations, respectively.

This, coupled with the excellent t nsile strengths, indi-ates that these materials have suffic,'ent toughness and radiation resistance to withstand 200 Hrads gamma radi ~t i on.

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

From the data, it is evident that all HVT s, those irradiated to 100 or 200 Mrads, as well as those not irradiated at all, are capable of performing during a loss of coolant accident.

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

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

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RAYCHL=,iV'i HN's successfully wi thstand LOCA tests before and after irradiation.

The 5KV HVT's were subjected to applied vol tag s

between 5 to 8.6KV phase to ground during the LOCA sequence.

Table 5 shows electrical performance of a series of in-line splices I

made on 600, 1000 and 2000 volt class cable and subjected to continuous maximum cable rated voltages.

SUHt%RY Oata supplied in this report show that when properly ass'embled, Raychem high vol tage terminations and in-line low voltage splices may be recor'mended 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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EFFECTS OF NUCLEAR RiADIATION UPON RAYCHEM H'iT I"UTERI ALS Outer Tab in Stress GzaBinr Initial elongation, X

260 236 Elongation after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 121 C plus 100 Hrads, X

126 140 Elongation after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 121'C plus 200:lrads, X

80 70 Initial tensile strength, psi 2290 1560 Tensile strength after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 121'C plus 100 Hrads, psi 3025 2015 Tensile strength after 168 hour0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months " at 121'C plus 200 Hrads, psi 3020 1665

,Initial hardness, Shore D

43 37

'lardness after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at

'21'C plus 100 ilrads, Shore D

57 50 Hardness after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 121'C plus 200 ifrads, Shore D

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RAYCI-lE/'V'I TABLE 2 EFFECTS OF NUCLEAR RAD I AT I O'I UPON RAYCHEM WCSF MATERIALS MCSF Tubin Samnles MCSF Slab Sample t.125" Thickness Initial elongation, 0

Elongation after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 121 C p lus 100 Mrads,

-Elongation after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 12l C plus 200 Mrads, Initial tensile strength, psi Tensile strength after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 121 C plus

)00 Mrads, psi Tensile strength after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 121oC plus 200 Mrads, ps i Initial hardness, Shore 0

Hardness after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 121 C plus 100 Mrads, Shore D

Hardness after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 121 C plus 200 Mrads, Shore D

565 100 218o 1500 37 44o i45 70 16oo 1745 1685 43 52 I

Tubing.samples were exposed to simultaneous heat aging and irradiation I

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TABLE 3 PERFORHAHCE CHARACTER I ST I CS (COROHA EXT I hCT I ON VOLTAGE)

OF RAYCHEM 15KV HIGH VOLTAGE TERMIIIATIOlIS DUR I Is 6 DBE/LOCA TEST I H G I HVT HVT HVT HVT HVT HVT gl g2 S3

,4 I5 il6 Initial CEV, KV CEV after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 121 C

30 25 25 24 31 19 20 175 20 19 5

21 5

21 CEV afte'r 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 121oC p 1 us 100 Hrads2 CEV after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 121oC plus 200'Hrads 14 15-5 19.5 16 CEV after 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months DBE3 17 15'0. 5 21 16 Notes l.

Crossl inked polyethyiene

cable, copper tape shield, extrud d

semiconductive layer.

2.

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

3.

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

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TABLE 4 PERFORNAttCE CHARACTEP I ST l CS (CORO!>A EXT l tsCT t Ott VOLTAGE)

OF RAYCHEH 5KV Hl GH VOLTAGE TERHI tJAT I 0!ES DUR I ttG DBE/LOCA TES T I tlG 1

Initial CEV, Kv CEV after 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months at 121'C EEVT dl 4.8 4.5 11VT 82 4 ~ 2 4.3 11VT 83 5.5

5. 5 4.6 4.0 HVT 85 5.8 4.8 11VT II6 5.8 4,4 CEV after 16S hours at 121'C plus 100 Nrads2 CEV after 16S hours at 121'C plus 200 Nrads2 5.2 4.3 4.2 5.0 CEV after 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months DBE

4. 5

4. 1

4. 7

4. 5 4.8 (4)

Nates l...

EPR cable, copper tape shield, tape remi conduct ive layer.

2.

Cabal t 60 garret radiation, dose rate of 0. 50 Hrads per hour.

I 3.

hours at 360oF, 70 ps i g stean; 6 'hours at 320 F, 70 ps i g s teaml 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at 250 F, 2 l ps ig steam,

0. 2~ boric acid spray at pH of 10, 12 days at 221 F,

2 ~ 5 ps ig steam, 100 days at 212 F 2;0 ps i g steam.

4.

Specimen mechanical ly damaged before being ~ laced in autoc1 ave.

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TABLE 5 PERFORMANCE CHARACTERISTICS OF RAYC1IEII 600-2000 VOLTS III-LIIlE SPI.ICES TYPE WCSF'URIIIG DBF. /LOCA TFSTII(G Hew Material Per Table 2

Aged 168 Hours I312 1 C

fr 200 Ml ads Electrical Strength 5 Samples - Volts/Mil Minimum Maximum Mall Thickness 312 491 380

.084!

318 355 334

.086" Volume Resistivity OHM-CMS 2.5 x 1013 1.2 x 1014 Fla!n3:ability Per A.s.T.M. 0-2863 Oxygen Index Note Slab 0"!.a Only 35.0 37.0 Notes Cable types for test.r'ng A.

600 vol t Flamtrol 2000 vol t EPR/Ileoprene Cable types for Cook Nuclear Plant snlices 600 v Eapton 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.

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

4.

5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months at 360 F, 70 psig steam; 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months at 320 F.,

70 psig steam; 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at 250oF, 21 psig steam, 0.2~ 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.

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ML18220A502

Text

Dear Mr. Case:

Subject:

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