ML18037A089

Responds to IE Bulletins 77-05 & 77-05A, Electrical Connector Assemblies. Itt Cannon Connector Types Not Used at Plant.Electrical Connectors Installed on Primary Containment Electrical Penetrations

ML18037A089
Person / Time
Site:	Nine Mile Point
Issue date:	11/28/1977
From:	Schneider R NIAGARA MOHAWK POWER CORP.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-77-05, IEB-77-05A, IEB-77-5, IEB-77-5A, NUDOCS 8103060434
Download: ML18037A089 (38)

Text

7 NIAGARA U M4HAWK NIAGARAMOHAWKPOWER CORPORATIONI300 ERIE 8OUl WARD WEST, SYRACUSE. N.Y. 13202/TElEPHONE (31S) 474-1S11 November 28, 1977 Office of Inspection and Enforcement Region I Attn:

Mx. Boyce H. Grier, Director U.

S. Nucleax Regulatory Commission 631 Paxk Avenue King of Prussia, Pennsylvania 19406 Re:

Docket No. 50-220 I.E.Bulletin 77-05

& 77-05A

Dear Mx. Grier:

I. E.Bulletin 77-05 dated November 8,

1977 described deficiencies in certain electrical pin and socket-type connectors.

These connectors were manufactured by Bendix, ITT Cannon and Gulton Industries.

A review of plant con-struction drawings revealed that these connector types are not used at Nine Mile Point Unit 1.

Electrical connectors of the pin and socket type are used;

however, they were manufactured by D.

G. O'rien Company (see attached drawings}'.

The connectors used at Unit 1 have been reviewed for their application in a loss of coolant accident environment.

The construction of the electrical connection assemblies at Unit 1 is substantial.

For example, a typical 19 pin connector weighs approximately 7 pounds.

The housing is 304 stainless steel.

The electrical socket and pin connectors axe gold-plated copper.

The insulator materials are constructed of one of three materials depending on connector size:

diallyl phthalate, high density polyethylene, ox GMG (glass impregnated melamine).

The sealing function for leak tightness of the penetra-tion is provided in the interior of the connector receptacle by molded.glass.

To assure leak tightness of the connector internals, two areas of ingress are considered.

0

The plug-receptacle interface uses a double viton 0-ring seal.

-The cable-plug interface is sealed with individual viton 0-r'ings around each pin and a viton 0-ring around an insulator.

Each pin passes through 3 insulators within the plug assembly.

Additionally, a polyurethene potting compound and heat shrinkable neoprene boot are used to further protect the assembly.

Table gl provides a listing of cable connector construction and identifies the system it is used in.

The Maine Yankee connectors are manufactured by D.

G. O'rien and are very similar to those used at Nine Mile Point Unit 1.

The attached test report sho~s that typical Maine Yankee connectors will survive a loss of coolant environment of 55

psig, 280oF and 1007. relative humidity for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Figures E31 and E33 in FSAR Volume II show the environmental loss of coolant accident time history for the primary containment.

It can be seen that the qualification testing of the Maine Yankee equipment is directly applicable to that used at iVine Mile Point Unit l.

The differences between the Maine Yankee connectors and those used at Nine Mile Point Unit 1 are as follows:

1)

Nine Mile Point Unit 1 uses 2 viton seals at the plug-receptacle interface versus one at Maine Yankee.

2)

VL ine Mile Point Unit 1 uses a potting compound (polyurethane) inside the neoprene boot.

3)

Whil.e Maine Yankee connectors use diallyl phthalate exclusively for insulators, Nine Mile Point Unit 1 connectors use either GMG, high density polyethylene or diallyl phthalate for insulator materials.

A direct comparison of the other insulating materials based on National Electrical Manufacturers Association values(l)

(tested in accordance with ASTM) indicates:

Insulation Haterial Resistance to Heat Continuous 0 eration Diallyl Phthalate GMG High Density Polyethylene 400 - 450 F

280 F

250 F

Modern Plastics Encyclopedia

The above comparisons show that while the GHG and high density polyethylene insulators do not have the same resistance to heat for continuous operation as those that were tested, the resistance temperature is similar to that expected during a postulated loss of coolant accident.

Considering the short time that these temperatures exist (approximately 60 seconds)(

)

it is unlikely that the insulators would be affected.

Connectors with the high density polyethylene and GHG insulators are used for power connection to core spray valves and isolation valves.

These power circuits are energized'for a short time (approximately 30 seconds) immediately after a loss of coolant initiation and thereafter remain de-energized.

The connectors therefore are expected to perform their function prior to any unlikely insulation failure which might occur during exposure to high temperature.

The radiation effects on components used for the D.

G.

O'rien electrical penetrations.

have been analyzed.

The organic materials would be the most significantly affected by the post-loss of coolant accident environment.

The total combined accident dose (gamma and beta) in the primary containment using Regulatory Guide 1.3 is 1495 megarads (using the inventories from Page E131 Volume XI FSAR).

The neoprene boot and polyurethane filler is expected to see the total dose.

The viton seals and stainless steel housings are expected to be affected by the gamma dose (715 megarads).

The radiation levels inside the electrical connector would be about 36 megarads.

The materials used in the connectors will accept the following radiation levels:

Material Viton "0" rings Neoprene Polye'thylene Resins-Glass Fabric Reinforced (GMG, Diallyl Pthalate)

Polyurethane Exposure for Hoderate Damage to Host Sensitive Pro ert 800 megarads 5 megarads 85 megarads 40 megarads 3000 megarads

FSAR, Volume EE, Page E 130 (2)

'pproximately 25 percent damage (3)

-=

Kirchner J. F.,

and Bowman P. E., Effects of-Radiation on Haterials and Components, New York, ien o

The neoprene boot may fail from the loss of coolant accident.

However, all other materials in the connector would. not be expected to be significantly affected.

There-fore, the electrical connector is expected to perform its design function after exposure to these radiation effects.

Normal. radiation levels are not expected. to exceed 0.4 megarads over the life of the plant.

At this radiation level, no electrical connector materials would be significantly affected.

In regard to I. E. Bulletin 77-05A, electrical connectors installed on the primary cont'ainment electrical penetrations are the only pin and socket type connectors used for safety related interconnecting cable which mitigates accidents.

Both the inside and outside electrical connectors are designed, constructed and installed to the same criteria.

The envizon-ment outside containment during postulated accidents is considerably less severe than that within the containment.

Based on the above, continued operation of Nine Mile Point Unit 1 will not create undue risk to the health and safety of the public.

Additionally a test progzam has been initiated to demonstrate operability of the connectors.

The program will test the two types of pin constructions described in Table 1 in a simulated loss of coolant accident environment without radiation effects and thermal aging.

The test will generally follow the guidelines of IEEE 323 test requirements.

Very truly yours, NIAGARA MOHAWK POWER CORPORATION j(

Vice Pzesident-.Electric Production

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Table 1

ELECTRICAL PENETRATION CONNECTORS REQUIRED TO liITIGA'fEAN ACCIDENT PENETRATION ELECTRICAL CONNECTOR CONSTRUCTION Penetration Number Service Pin Front Construction 'nsulator Mid Rear Insulator Insulai:o X-E178D X-E17BH X-E179A X-E1798 X-E179E X-E179F Core Spray ZV 40-01 Power Core Spray IV 40-01 Control Clean-Up Return IV 33-01 Power Clean-Up Supply IV 33-02 Power Clean-Up Return IV 33-01 Control Clean-Up Supply IV 33-02 Control 4jj8 19 jj'.16 4/8 488 19/16 19jjl6 HDPE DIAL HDPE HDPE DIAL DIAL HDPE DIAL HDPE HDPE DIAL DIAL GMG DIAL

'HQ GMG DIAL DIAL X-E188G X-E188H Electromatic Valves

NR108C, NR108D

$1ectromatic Valve NR108F 19 jp'16 19016 DIAL DIAL DIAL DIAL DIAL DIAL X-E189D X-E189H X-E202-H X-E210-B X-E210-E X-212A X-212E Core Spray IV 40-09 Core Spray IV 40-09 Hain Steam IV 01-02 Core Spray IV 40-10 Core Spray IV 40-10 Power Control I

control Power Control Main Steam IV 01-02 'Power Main Steam IV 01-02i~Control I

4118 19/16 19/16 4/8 19y16 4/8 19/16 I,'f HDPE DIAL DIAL HDPE f

DIAL kk HDPE ) j DIAL~ i f)

HDPE DIAL DIAL HDPE DIAL HDPE DIAL GMG DIAL DIAL GMP DIAL GMG DIAL

Table 1

Continued)

I 1

I ELECTRICAL PENETRATION CONNECTORS RE UIRED TO MITIGATE AN:ACCIDENT I ~ I I

PENETRATION ELECTRICAL CONNECTOR CONSTRUCTION Penetration Number Service Fin Construction Front Hid Rear Insulator Insulator Znsulato:

X-E228F X-K2280 X-E228ti X-E229A X-E229E Electrometry.c Valves NR108A NR1081 Electramatf.c Valve NR108E Main Bl:Oom EV 01-01 Control Main Steam IU 01-01 Power Main Steam IV 01-01 Control 19gl6 19 j/16 19)16 488 19/16 DIAL DIAL DIAL HDPE DIAL DIAL DIAL DIAL HDPE DIAL DIAL DIAL DIAL DIAL X-E231D X-E231H Core Spray IU 40-11 Power Core Spray IV 40-11 Control 4/8 19/16 HDPE DIAL HDPE DIAL GMG DIAL X-E233A X-E2338 X-E233E X-E233F Reactor Shutdown 38-01 Power Reactor Shutdown 38-13 Power Reactor Shutdown 38-01 Control Reactor Shutdown 38-13 Control Cooling System Supply IV Cooling System Supply IV Cooling System Supply IV Cooling Syst)m Supply IV 19/16 19jjl6 HDPE HDPE DIAL DIAL HDPE HDPE DIAL GMG GMG DIAL DIAL D

HDPE DIAL GMG Material Abbreviations High Density Polyethylene Diallyl Phthalate Glass Impregnated Melamine First Number Second Number

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Pin Construction Number of Pins (Contacts Pin Diameter in AWG (American Wire Gauge) i e

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l A CabLe Assembly consisting oZ typicaL cables from the

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.'.'.: ".Maine-Yankee Nuclear Pover Plont installation were assembled to D.G. O'rien, Xnc.'19-pin plugs following

,:..:,.".',"'.:i;the standard recommended termination procedures.

Both V': 'plugs vexe then connected to a splice receptacle which

"'. ';"":: "', duplicates one piessure barrier and electx'ical termx'na>>;

" >',',,:,'.:-.tian in one end of a nozxle.

2 The assembly vcs electrically tested, sub jected to the

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....-:.'nvironmental conditions of a Design Basis Accident

-'.:-:.fax 4S hours and again eLectrically checked..

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1~4 Thex'e are physical indications that the. jacket on one

,',cable split and the primary insulation extxuded thru

':",'the opening.

The shrink tvbing on a second cable in the same bundle split dovn to the boot and appeax's

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'o'continue down into the boot. cavity.

Electxical

's "'. 'characteristics on this plug. were markedly. lowex'

". than the other',plug and the receptacle.

5 'ome extrusion of the cable is evident at points vhere

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'i'"is'ndoubtedly attributed to the tension introduced I

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The 4':extrusion may have contributed to the cable jcicket

.-., failvre that vos mentioned previously.

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4 0 Test Procedures 4.1.

Disassemble plugs from the receptacle and inspect for

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4.2 Neasure and record insulation resistance on each

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They should all be above 5000 megs.'

3 Reassemble plugs to receptacle making sure 0-rings 1

are properly installed.

Repeat ZR measurement.

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4 4 Tape the ends of the cable following MP-EC-122, ateps 7.2 nehru 7.6 modified to suit the cable.

'-';'.Engineering has the supplies for this taping and h

wiles assist techhnicians in the proper application.

'.':.'ake a photograph of completed assembly..

'.. 4.5 Place cable assembly in'he test tank without bending

. the cables.

.The single one inch diameter cable should

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Take a photogra ph.,

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4 9 Disassemble plugs from receptacle and record observations.

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As a minimum, the following information

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. Time at which ev'ents start and finish.

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.. 'Zemperature of'elium environment.

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APP'D DATE VSAOE REVISlOH I

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'"'measurements before and after exposvre.

Data sheets

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'. 5.2 Photographs taken before and after the test are also

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The reproducibility of these photographs

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TEST PROCEDURE gjj/

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,:,t...-'~"'"'by'he Q/A method sheet This atmosphere wall

.-::: '.'::--'.'."','.:--::~~c:- =.+-'",.-'.consist of both pressure and temperature

=:.'.:.:.'.;~".".:-.'-~";'..-cXzaracteristics.

The test will last for a

.'":;-.',.:;..",,:; -',':-',-<<"~periocX:-as specified by. the Q/A method sheet.

=-.;:.'":'....'.,'-;"=:::.Lt'the conclusion of, the test, the steam

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".'-c,~'.-,,-'".'.;. '.~ tratioxx ex'ified. '

'.-.i c.:';::":.:..',"',:;X 2'. The aped.ication of this envixonment is to be

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M the'ina'1 test results must conform to the

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%were lax ge volumes are involved.,

a mixture of t

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"','-....-."-"-.v-'=-.:--".<-."-'..atHZized to reduce excessive background

. '."..."=."'-.'-',:.:=-.:..:co'atamination and to conserve Helium.

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Test chamber

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':: ".'..:;.:;,'-',",:,~.'..:..".namics Mode1'4-1203 with its associated'";;:,-"...'"=~,.2

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, -.".".-':.2.6 Equivalent instrumentation may 'be subs tituted

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APP'O OATE

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':..":.'~"c..-;:.-,".."',.';.,'3 3.'lace tha.e?,ectrical. penetration into the

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~ Nake the necessary connections to the test

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""..; -:.;=,~'",.";<;;,':;...cover fz'om,the electrical penetration for

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',':-'""':.-.~',.-,"'..-,.',.-..-"."-;..-,.-,'-."-.connecMaxg the Helium leak detector.

Close tJxe cover with a sufficient number of'",:.',.".~;:

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."c~'.-:"".=',"latches to contain and seal the pressure,

.:"".-'-,'-=.;,-3'.4 'ozznect the Helium leak detector and the,

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6: Inde'ct helium into the canister and establish.~...

. ". -'",.'-';;;-::;-'::;.,';.'i".-..the leak rate 'of the" eL'ectrical pe'netration.

,'. "-,"",$,';:. "g ~a~Cmc~a OtC~~~r.

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.;.i, '-...~:.'.-',. 3 8 Replace the helium atmosphere 'n the test

.chamber with the steam atmosphere spe cifi'ed i: ";.":.'I -.,: -'.".-.-"':,:;~.':: oa."the appropriate Q/A method sheet.

'~": -..-",,'"<<",.'--,;;:3 9 Maintaizz the environment on the electrical

.':.'";"-.;.',.:.:.,'..::.-'.-:,". calf.ster as specified.

.'-";:3 10 Remove the steam and nitrogen atmosphere and

".-'.;.';- ",::<"-.'.:-.--',=,'""-',."repeat the helium checks by following the r

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'ORIG.

DWII.

APP'D DATE

~CK cv R& ISION RKYoIIO.

APP'D

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~P,S ASGI Wp,0 I

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Docket No. 50-220 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 63I PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 November 28, 1977 Ce+Fp~

gi'(as Niagara Mohawk Power Corporation ATTN:

Mr. R.

R. Schneider Vice President Electric Operations 300 Erie Boulevard liest

Syracuse, New York 13202 Gentlemen:

The enclosed IE Circular 77-14 is forwarded to you for information.

No written response is required.

Should you have any questions related to your understanding of this matter, please contact this office.

Sincerely, Director

Enclosures:

1.

IE Circular 77-14 2.

List of IE Circulars Issued in 1977 cc w/encls:

T.

E. Lempges, General Superintendent, Nuclear Generation T. J. Perkins, Station Superintendent C. L. Stuart, Operations Supervisor E.

B. Thomas, Jr.,

Esquire A. Z. Roisman, Counsel for Citizens Committee for Protection of the Environment

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