ML19329E349
| ML19329E349 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 01/16/1978 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8006120659 | |
| Download: ML19329E349 (1) | |
Text
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CA p st Fr Les JAN1t,.:8 Docket No. 50-329 Docket No. 50-330 Consumars Power Company ATTN:
Mr. Stephen H. Howell Vice President 1945 West Parnall Road Jackson, HI 49201 Gentlemen:
Enclosed is IE Bulletin No. 78-01 which requires action by you with regard to your power reactor facility having an operating license or a construction permit.
Should you have any questione regarding this Bulletin or the actiot.s requirod, plaase contact this office.
l Sincerely, James C. Keppler Director
Enclosures:
l 1.
IE Bulletin No. 78-01, w/ attachment 2.
List of IE Eulletina issued during last 12 months JHIS DOCUMEllT CONTAINS cc w/enels:
P0OR QUAUTY PAGES Central Files j
Reproduction Unit NRC 20b PDR Local PDR NSIC TIC Ronald Callen,Ilichigan 3
Public Service Comission Dr. llayne E. North Myron M. Cherry, Chicago gA
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NRC PORM 313 (9-76) NRCM 0240 fr u. s. novenmusme eninvie.e arrica inte-ese ea4 8006 120 b @ 7
January 16, 1978 IE Bulletin No. 78-01 FLAMMABLE CONTACT-ARM RETAINERS IN G.E. CR120A RELAYS Description of Circumstances:
On April 18, 1977, a fire was discovered in a relay cabinet in the Peach Bottom Unit 3 facility. The fire damaged eight relays, type CR120A, manufactured by the General Electric Company. The fire was investigated by the licensee, the Philadelphia Electric Company, who concluded that it was caused by an overheated relay coil that ignited the relay's plastic contact-arm retainer. Subsequently, on July 29, 1977, fire damage was discovered in a relay cabinet during surveil-lance testing in the Peach Bottom Unit 2 facility. This fire damaged 18 G.E. type CR120A relays.
Discussion:
The investigation revealed that the relay's contact-arn retainer was made from Celcon M90 Acetal Copolymer which is a flammable material.
In June 1972, this material was changed to Valax 310-SED, which is self extinguishing and flame resistant. Both materials are white and have the same surface appearance. A G.E. Service Information Letter SIL-NO-229 (a copy of the text is attached for information) indicates that there is no generic overheating problem with this type relay.
However, they recommend that BWR owners replace the contact-arm retainer of all relays (including BOP applications) marked with manufacturers date code between E.D. (May 1968) and A.J. (January 1923) with the improved, self extinguishing flame resistant contact aon retainers.
Action To Be Taken By Licensees And Permit Holders:
Licensees of power reactor facilities with an operating license and construction permit holders shall take the following actions:
1.
Determine if you have installed G.E. type CR120A relays in safety-related equipment or in areas wherein fires have the f]
potential for damaging safety equipment. Also determine if 9(k you have such relays in spares inventory or on order.
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I IE Bulletin No. 78-01 January 16, 1978 2.
Identify all of the relays that have Celcon contact-arm retainers.
3.
For those relays which have Celcon retainers, develop a program for their replacement with Valox retainers. The program should include:
Identification of the location of the relays a.
b.
The schedule for the replacement of the Calcon retainers The procedure that will be used to perform the replacement, c.
including the means that you will use to differentiate between the Valox and Calcon retainers.
4.
For facilities with an operating license, a report of t,he above actions, including the date(s) when they will be completed, shall be submitted within 30 days of receipt of this Bulletin.
5.
For facilities with a construction permit, a report of the above actions, including the date(s) when they will be completed, shall be submitted within 60 days of receipt of this Bulletin.
Reports should be submitted to the Director of the appropriate NRC Regional Office. A copy of your report should be sent to the U.S.
Nuclear Regulatory Commission, Office of Inspection and Enforcement, Division of Reactor Operations Inspection, Washington, D.C.
20555.
Approved by GAO, 3-180225 (R0072); clearance expires 7-31-80.
Approval was given under a blanket clearance specifically for identified generic problems.
Attachment:
Copy of Text of General
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Electric Service Instruction Letter (SIL)-SIL-No. 229 l
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(COPY OF TEXT OF GE SIL-No. 229)
FWD. BY LTR MFN 373-77 j
8-10-77 IMPROVED CONTACT ARM RETAINERS FOR TYPE CR120A RELAYS Recently, at an operating BWR a small electrical fire occurred in a relay panel. The purpose of this Service Information Letter is to discuss this occurrence and to recommend an improved contact arm retainer for certain CR120A relays to help avoid or mitigate this type of occurrence.
DISCUSSION In a relay panel at an operating BWR, one relay, Type CR120A, overheated, subsequently ignited, and resulted in seven other similar relays in the proximity being burned. No definite cause could be determined for the relay overheating. Moreover, subsequent investigation concluded that there is no generic overheating problem with relays of this type.
The investigation also noted that the contact arm retainers of these relays, and of relays manufactured between May 1968 and June 1972, were made of Celcon M90 acetal copolymer which is flammable. In June 1972 this material was changed to Valoz 310-SEO which is self extinguishing and flame resistant.
RICOMMENDED ACTION General Electric recommends that BWR owners replace the contact arm retainers of all Type CR120A relays (including those in B.O.P. applica-tions) marked with a manufacturing date code between ED (May 1968) and AJ (January 1973) with the improved, self extinguishing flame resistant i
contact arm retainers, as follows:
1.
For four pole CR120A relays use replacement contact arm retainer Part No. 55650378P3.
2.
For two pole adder CR120A relays use replacement contact arm retainer Part No. 55501383P3.
3.
For two pole CR120A relays use replacement contact arm retainer Part No. 55651401P3.
Attachment Page 1 of 2 (COPY)
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.. (Copy of Text of GE SIL-No. 229 - Continued)
BWR owners should survey CR120A relay applications throughout their plants, in bcth the nuclear steam supply system (NSSS) and balance-of-plant (BOP), tc ascertain the total amount of contact arm retainers required for each type of relay. Upon notification of their require-ments, NEDs' Spare and Renewal Parts service will furnish BWR owners the requested amount of replacement parts.
Contact your local General Electric service representative for additional information and for assistance in obtaining the recommended replacement parts.
JW:caj /70 1
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(COPY)
Attachment Page 2 of 2 i
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IE Bulletin No. 78-01 January 16, 1978 LISTING OF IE BULLETINS ISSUED IN 1977 Bulletin Subject Date Issued Issued To No.
77-08 Assurance of Safety 12/28/77 All Power Reactor and Safeguards During Facilities with an Emergency - Locking an Operating Systems License (OL) or Construction Permit (CP) 77-07 Containment Electrical 12/19/77 All Power Reactor Penetration Assemblies at Facilities with a Nuclear Power Plants under Construction Construction Permit 77-06 Potential Problems with 11/22/77 All Power Reactor Containment Electrical Facilities with Penetration Assemblies an Operating
)
License (OL)77-05A Supplement 77-05A to 11/14/77 All Power Reactor IE Bulletin No. 77 Facilities with Electrical Connector an Operating Assedblies License (OL) or Construction Permit (CP) 77-05 Electrical Connector 11/8/77 All Power Reactor Assemblies Facilities with an Operating License (OL) or Construction Permit (CP) 77-04 Calculational Error 11/4/77 All PWR Power Affecting the Design Reactor Facilities Performance of a System with an Operating for Controlling pH of License (OL) or Containment Sump Water Construction Following a LOCA Permit (CP) 1 of 2 I
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.r IE Bulletin No. 78-01 January 16, 1978 LISTING OF IE BULLETINS ISSUED IN 1977 Bulletin Subj ect Date Issued Issued Io No.
77-03 On-Line Testing of 9/12/77 All W Power the W Solid State Reactor Facilities Protection System with an Operating License (OL) or Construction Permit (CP)
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77-02 Potential Failure 9/12/77 All Holders of Mechanism in Certain Operating Licenses W AR Relays with (OL) or construction Latch Attachments Permits (CP) 77-01 Pneumatic Time 4/29/77 All Holders of Delay Relay Set Operating Licenses Point Drift (OL) or Construction P2rmit (CP) 2 of 2 I
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