ML19309B801

Responds to IE Bulletin 79-28, Possible Malfunction of Namco Model EA180 Limit Switches at Elevated Temps. Supplier Taking Measures to Prevent Use of Defective Switches

ML19309B801
Person / Time
Site:	Vogtle
Issue date:	01/25/1980
From:	Dutton D GEORGIA POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-79-28, NUDOCS 8004070198
Download: ML19309B801 (6)

Text

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? 4To-faf USNRC REGt1

' T' Georgia Power Company **lT!.,e-'

,8 Post Offce Box 4545 Atlanta, Georgia 30302 h

Telephone 404 522-606o 39qg4 p;. 7 Vogtle Project Southern Company Services, Inc, Post Office Box 2625 Birmingham, Alabama 35202 Telephone 205 870-6o11 January 25, 1980 United States Nuclear Regulatory Commission

REFERENCE:

Office of Inspection and Enforcement RII: JP0 Region II - Suite 3100 50-424 101 Marietta Street 50-425 Atlanta, GA 30303 i File: X7BC24 Attention: Mr. James P. O'Reilly Log: GM-559

, Gentlemen:

The following is submitted in response to your letter dated December 7, 1979 concerning I.E. Bulletin 79-28.

One Georgia Power Company supplier will use Namco EA180 limit switches. This supplier was notified of the problem outlined in Bulletin 79-28. The supplier stated that these limit switches have not yet been ordered and that measures are being taken to ensure that the defective r switches are not used.

ry truly p

Doug Dutto n

5 Project General Manager

, CWH:tp xc: U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, DC 20555 ,

j M. D. Hunt - USNRC, Region II g;,

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5 OFFICIAL O(Y f- 8004070(%

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.c Mr. James P. O'Reilly RII: JPO, 50-424. 50-425

-January 25, 1980.

Page 2 xc:- J. H. Miller, .Jr.

-W. E. Ehrensperger F. G. Mitchell, Jr.

C. F. Whitmer .

R. J. Kelly R. E. Conway R. W. Staffa J. T. Beckham, Jr.

K. M.:Gillespie

C.;W. Hayes E. D. Groover D. -L. McCrary R. A. Thorias M. Z. Jeric J. L. Vota-oh s

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ed@,'E.c Bechtel Power Corporation f'fDJ Cili "'.Eli f Engineers - Constructors

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Mr. C. W. Ilayes Project Quality Assurance Manager Georgia Power Company J

. P. O. Box 4545 Atlanta, Georgia 30302

Subject:

Georgia Power Company Alvin W. Vogtle Nuclear Plant

. Bechtel Job 9510-001 NRC IE Bulletin 79-28 File: X7BC24 Loa BG 9049

Reference:

(a) GPC letter GB-2475, dated December 12, 1979

Dear Mr. Ilayes:

In response to reference (a), we have reviewed the subject bulletin.

Westinghouse has advised us that the types of limit switches discussed in IE Bulletin 79-28 are not included in the West-inghouse supplied safety-related equipment for the Vogtle plant.

For Bechtel supplied safety-related equipment, specifications X5AC01 and X5AC03 call for the use of Namco EA180 limit switches on Fisher butterfly valves. Fisher states that

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Bechtel Power Corporation Mr. ' C. W. Ilayas

. Alvin W. Vogtle Nuclear Plant January 24, 1980 Bechtel Job 9510-001 NRC IE Bulletin 79-28 File: X7BC24 Page 2 these-limit switches have not yet been ordered and that measures are being taken to ensure that the defective switches are not used. Fisher will confirm by letter to Bechtel the exact nature of the action taken to ensure the use of the defective limit switches does not occur.

Very truly yours, BECilT SER CORPORATION

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W M. T. Jer.1

' Project En neer Los Angeles Power Division BLK/SAS/pm xc: D. E. Dutton J. A. Bailey  !

J. T. Beckham K. M. Gillespie i

. L. T. Gucwa l J. L. Vota

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Vogtle Project 13 F r rt ,; e  : ,

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_ Plant Vogtle - Units 1 & 2 -: -

flRC Inspection & Enforcement Bulletin 79 '

"Possible Malfunction of Namco flodel EA180 .-

Limit Switches at Elevated Temperatures" File: X7BC24 Log: GB-2475 Dr. M. 2. Jeric

. Bechtel Power Corporation P.O. Box 60860, Terminal Annex Los Angeles, CA 90060

Dear Dr. Jeric:

You are requested to provide my office a draft of the information

~( necessary to answer I.E. Bulletin 79-28. The response should be received no later than February 1,1980.

Please forward a copy of your response to J. A. Bailey.

Very truly yours, C. W. H yes Project Quality Assurance Manager CUH:tp

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Attachment xc: D. E. Dutton (w/o attach.)

J. T. Beckham "

K. M. Gillespie "

E. D. Groover J. A. Bailey b/ attach.)"

J. L. Leamon "

J. L. Vote / .

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December 10, 1979 -

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• : 2 m '3 PLANTS HATCH AND VOCTLE co 'a o Transmittal of IE Bulletin 79-28, 2- p-o "Possible Malfunction of Namco Model .sM EA180 Limit Switches at Elevated '

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MESSRS: D. E. DUTTON ~

W. A. WIDNER You are requested to provide the NRC a response to the attached Bulletin.

The Hatch response is due in 30 days, and the Vogtle response is due in 60 days.

u/R.'W. Staffa

( RCW/bg Attachment xc: (with attachment)

J. H. Miller, Jr.

W. E. Ehrensperger F. G. Mitchell, Jr.

C. F. Whitmer R. J. Kelly ,

, J. H. Boykin J. T. Beckham, Jr.

K. M. Gillespie (w/o attachment)

C. W. Hayes L. T. Gucwa W. M. Johnston, Jr.

M. Manry C. R. Miles, Jr.

• E.,D. Groover (w/o attachment) '

R. A. Glasby O. Batum (SCSI Internal Distribution)

V. C. Valekis Route to SRB Members s

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• i t-s** "I% . UNITED STATES

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'} < I E NUCLEAR REGULATORY COMMISSION

• I f REGION 11 101 MAR.tTTA ST. N.W., SUIT E 3100 cs, ATLANTA, C EoRCIA 30303 /p

'DEC 7 ins Of '<

In Reply Refer To: 4 Rll:JPO 50-321, 50-366 50-424, 50-425

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r Georgia Power Company Attn: . J. H. Miller, Jr.

Executive Vice President 270 Peachtree Street, N.W.

Atlanta, Georgia 30303 Centlemen: -

. Enclosed is IE Bulletin No. 79-28 which requires action by you with regard to your power reactor facility (ies) with an operating license or a construction

. permit. ,

Should you have questions regarding this Bulletin or the actions required of

- ( you, please contact this office.

Sincerely,

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James P. O'Reilly Director ,

Enclosures:

1. 1E Bulletin No. 79-28 w/its Attachment

, 2. List of Recently Issued 1E Bulletins e

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M. Hanry,' Plant Manager Post Office Box 442 Baxley, Georgia 31513-C. E. Belflower .

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Site QA~ Supervisor Post Office Box 442' Baxley, Georgia 31513 K. M. Gillespie

- Construction Project Manager Post Office Box 282 Waynesboro, Georgia 30830 E. D. Groover QA Site Supervisor

• Post Office Box 282 Waynesboro, Georgia 30830 W. A. Widner, General Manager

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Nuclear Generation .

Georgia Power Company Post Office Box 4545

- ( Ktlanta, Georgia 30303 1

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SSINS No.: 6820 T UNITED STATES NUCLEAR REGULATORY COMMISSION Accessicn No.:

. OFFICE OF INSPECTION AND ENFORCEMENT 7910250505 ,

WASilINGTON, D.C. 20555 ,r' , ,

D f3 /IPP December 7, 1979 h gg]

. IE Bulletin No. 79-28  ;

POSSIBLE MALFUNCTION OF NAMCO MODEL EA180 LIMIT SWITCHES A1 ELEVATED TEMPERATURES Description of Circumstances:

The NRC has been recently advised through a 10 CFR 21 report from Namco Controls that a malfunction of a Namco Model EA180 stem mounted limit switch (SMLS) occurred at the Cooper Nuclear Station. Investigation into the switch failure by the licensee revealed yellow and brown " crystal-like" resin deposits on the internal components of the switch. The affected switch is located inside the ,

I drywell containment at this facility and was being used as the replacement

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switch for an unqualified SMLS previously identified in IE Eulletin Nos.

78-04 and 79-01.

According to the manufacturer, the problem was traced to a batch of top cover gaskets of which some were over-impregnated and insufficiently heat cured. It

( h'as been determined that this condition can leave an uncured residue of " Loctite" in the gasket, which vaporizes at sustained temperatures above 175'F. To correct the problem, the manufacturer has revised production techniques beginning September 1979.in order to better control the impregnation process and to properly heat cure the gaskets following impregnation. This problem is unique to all Namco Model E/180 series switches received by licensees after March 1, 1979. According '

to the manufacturer, the suspect switches can be identified by checking the date code which is a 4 digit number stamped on the conduit bost of the switch housing.

Namco recommends that any EA180 series switch with a date code between 02-79 through 08-79 should have its top cover gasket replaced. Also, licensees should request from their suppliers of equipment on which Namco EA150 series switches are used that they check their inventory and replace top cover gaskets on switches date coded between 02-79 through 08-79.

The enclosed letter from Namco further describes the high-temperature environ-mental problem with the top cover gaskets used in their EA180 switches and provides recommendations to correct the problem. According to Namco, this letter has been sent to each customer who was shipped EA180 switches between February 21, 1979, and August 24, 1979.

.. 1 Action to be Taken by Licensees of Power Reactor Operating Tacilities and i

Holders of Construction. Permits: .

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1. Determine if your facility has installed or plans to install Namco EA180 switches in any safety-related equipment loed{e'd inside or outside containment, including valve position indicating circuitry related to

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containment isolation valves.

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• I'E Bulletin No. 79-28

• December 7,1979

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2. If such switches are identified, examine the four digit number stamped on the conduit boss of the switch housing. If this number falls between 02-79 and 08-79, replace the top gasket of the switch in accordance with the manufacturer's recommendations provided in the enclosed letter.

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3 Submit your plans and programs, including schedules for corrective action, regarding your findings in response to Items 1 and 2 above.

4. P.rovide the response in writing within 30 days for facilities holding an operating license and within 60 days for those holders of construction permits. Reports should be submitted to the Director of the appropriate NRC Regional Office and a copy should'be forwarded to the U. S. Nuclear Regulatory. Commission, Office of Inspection and Enforcement, Division of-Reactor Operations Inspection, Washington, D.C. 20555.

Approved by GAO, B180225 (R0072); clearance expires July 31, 1980. Approval was given under a blanket clearance specifically for identified generic problems.

Attachment:

Extract of Namco Controls Letter dated 8/30/79 .

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EXTRACT .

NAMC0 C0NTR0LS August 30, 1979 Attention:

Subject:

Possible malfunction of Namco Model EA180 limit switches at elevated ambient temperatures Gentlemen:

Namco Controls has determined that t'te EA180 series limit switches shipped against your purchase order (s) #___ may have top cover gaskets which will emit a resin vapor at temperatures above 175'F. l This vapor could condense into deposits on the normally open contacts, j possibly causing.a switch malfunction.

We have reported this situation to the NRC, and we are contacting each customer who has received switches with gaskets from the questionable production lot, l with the following recommendations: )

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( a) If the switches have not been put into service, and the ultimate ambient l

' temperatures are unknown, the top cover gasket should be replaced.

b) If the switches are in service and are subjected to a continuous ambient temperature of more than 175*F, they should be inspected for deposits, the contacts cleaned if necessary, and have the top cover gasket replaced.

2 c) If the switches are in service, (or scheduled for service) in a continuous ambient temperature of 175'F or less, no action is necessary. ,

We will provide you with whatever number of new top cover gaskets you may require, free of charge. Or, if you prefer, we will accept switches returned i

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to our Jefferson plant freight collect, for gasket replacement and/or cleaning. 1 l

We sincerely regret any inconvenience this remedy may cause. If you have any questions, please contact either Robert H. Kantner, 216-268-4200 or John R.

'Bendokaitis, 216-576-4070.

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l IE Bulletin No. 79-28 -

Enclosure

- ' December 7, 1979 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.

79-28 Possible Halfunction of 12/07/79 'All power reactor Namco Model EA180 Limit facilities holding ,

Switches at Elevated OL or CP 1 Temperatures i

r9-27 Loss Of Non-Class-1-E 11/30/79 All power reactor l Instrumentation and facilities holding 1 Control Power System Bus OLs and to those During Operation nearing licensing .

79-26 Boron Loss From BWR 11/2b/79 .All BWR power reactor Control Blades ficilities with an

, OL

. 79-25 Failures of Westinghouse 11/2/79 All power reactor BFD Relays In Safety-Related' facilities with an Systems OL or CP a .

' ( 79-17 Pipe Cracks In Stagnant 10/29/79 All PWR's with an (Rev. 1) Borated Water System At OL and for information

.PWR Plants to other power reactors 79-24 ' Frozen Lines 9/27/79 All power reactor facilities which have

. either OLs or cps and are in the late stage of construction "

79-23 Potential Failure of 9/12/79 All Power Reactor Emergency Diesel Facilities with an Generator Field Operating License or Exciter Transformer a construction permit 79-14 Seismic Analyses For 9/7/79 All Power Reactor (Supplement 2) As-Built Safety-Related Facilities with an Piping Systems OL or a CP

, 79-22 ,- 'Possible Leakage of Tubes 9/5/79 To Each Licensee of Tritium Gas in Time- M ho Receive,s Tubes 4

pieces for Luminosity -

of Tritium Gas

' t .) ' Used in Timepieces

'4 for Luminosity 79-13 Cracking in Feedwater 8/30/79 All Designated

, (Rev. 3) System Piping Applicants for OLs t

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