ML18283B389

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Transmitting Interim Report of Reportable Deficiency, Defective CAM Followers in General Electric Type Sbm Switches, Letter Advising Final Report Will Be Prepared Once Investigations & Replacements Are Completed
ML18283B389
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 05/19/1976
From: Gilleland J
Tennessee Valley Authority
To: Moseley N
NRC/RGN-II
References
Download: ML18283B389 (12)


Text

830 Pcexer Building TE ESSEE VALLEY AUTHORITY r g CHATTANOOGA. TENNESSEE 37401 b.

'~76-19~~ MAY 1S1976 4/~$loc+p~,

Nr ~ Norman C. Hoseloy, Dixector ~o Office of Xnspection and Enforcemcnt U.ST Nuclaar Regulatory Cmmission:

Region XX Suito 818 230 Peachtxco Street, NWs Atlanta, Georgia 30303

Dear IIr,

Hoaeloyc BROILS PERRY NUCLEAR PLANT UNIT 3 REPORTABLE DEPICIENCY DEPECTIVB,CAN FOLLOWERS XN GENERAL ELECTRIC TYPE SBH SlIXTCHES Initial report of the sub)act reportable deficiency ~as made to G. R. Klinglex, NRC>>IE, Region XX, on April 16> 1976. In compliance vith paragraph 50.55(e) of 10 CFR Part 50'e submit the follotdng interim report of the deficiency.

ale conducting a preoperational test on the unit 1 Reactor Core Isolation Cooling (RCIC) System, a General Electric type,SBH smitch failed; this failure was reported in Licensee Event Report BPA0-50-259(764.

During the investigation of this deficiency> s1dtches of the arne type have been inspected throughout the plant. The inspection revealed a large nuzibex of cam followoxs Mth a crazed appearance similar to the condicion dosccihod in cho onclossd Goo~coo Eiscccic conpnny lndocaacion Letter SXL No. 155. Ue have found crazed conditions azisting on s1dtches which vore manufactured outside the dates of manufacture specQicd in the service letter ~ The condition has been found on s1dtches installed in each of the three Brmms Perry units. The investigation is continuing. Xnterim plans include replacement of all crazed stitches installed $ n safeguards systems and all stCtchos manufactured duxing the poxiod defined in the enclosed GE Information Let/or.

5856 i"'SSR An Equal Opportunity Employer

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Hr. No~n 'C. Hoseley MAY, 19 1976

  • ,k A ffonl,report viX1 be prepared, once the itivestigations and replac~enta at the plant are.completed.

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Very truly youroq r'f J, E. Gflleland Aoofetant Manager of Poker 1

BlcloGure CC t,'Fncloeure):

Dr. E. Volgonau~ Director OfHce of Xnspect$ on and Rnforcment U.S. Nuclear Regulatory Comzdoeion Haehington, DC 20555 kr k

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~GA I March 19, 1976 SIL No. 155 File Tab A Category 1 POSSIBLE'FAILURES OF TYPE SBN'CONTROL SWITCHES Recent failures of General Electric Type SBN Control Switches have been reported by the'origi.nal component manufacturer. The application of these switches is widespread throughout operating fossil and nuclear (both BWR and PWR) plants. The'reported failures, however, have been limited to SBN switches installed at fossil p'lants. It should be noted that, to date, the reported number of failed SBH swi'tches is extremely low, (i.e., approximately 0.03 percent for the quantityof switches manufactured and shipped during the period of concern) and that none of the switch failures have occurred in essential circuits. The purpose of this Service Information Letter (SIL) is to list the affected BWR operating plants, to define the conditions causing the problem and to present corrective action recommendations for nuclear application of SBN, switches.

DISCUSSION

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reported failures of J'he GE Type SBN Control Switches have been diagnosed as fracture of the Lexan cam followers (an integral part of the switch).

The failures have been attributed to exposure of some Lexan cam followers to hydrocarbons. Contamination by hydrocarbons contributes to degradation of the Lexan mater ial. This degradation could eventually progress to a fracture of the cam follower resulting in failur e of the switch assembly in any of the following three modes:

1. Failure of the switch to open.
2. Failure of the switch to close.
3. Jamming of the switch mechanism which would prevent any further action.

Cam followers in question which have been exposed to the hydrocarbon are a part of SBH switches manufactured during the period from July 1972 through May 1975. SBM switches manufactured during this time period may be NUCLEAR ENERGY DIVISION ~ OPERATING PLANT SERVICES SAN JOSE, CALIFORNIA 95125 NO WARRANTY OR REPRESENTATION EXPRESSED OR IMPLIED IS MADE WITH RESPECT TO THE ACCURACY, COMPLETENESS OR USEFULNESS OF THIS INFOR-MATION. GENERAL ELECTRIC COMPANY ASSUMES NO RESPONSIBILITY FOR LIA- 0 EH ERAL ' E t.Et:TB I 0 BILITY OR DAMAGE WHICH MAY RESULT FROM THE USE OF THIS INFORMATION.

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March 19, 1976 'SIL No. 155 identified by a small sticker. label affixed to the back end or side of each switch having a number less than 50 and two letters .in the following series:

-'AJ DJ GJ KJ'K

'AK DK KK AL DL HH. LH BJ BK BL EJ EK EL HJ HK JH

'KLJ MH CJ FJ JJ MJ CK FK JK MK CL GH KH Examples would be: "14GH" and "16HJ" I

Appendix A lists the results of a records search conducted by General Electric-Nuclear Energy Division of the known application of Class 1E SBM switches in operating BWRs, including the specific location of the SBM switches that are identifiable to the A through M series discussed above. The records review'as limited to operating BWRs original equipment hardware as well as hardware in support of Field Disposition. Instructions (FDIs) shipped to BWR operating plants after June 30, 1972.

RECOMMENDED ACTION General Electric reconmends the, following action:

1. Replace any SBM Control Switch currently installed in a BWR plant which is identified in the A through M series listed above and used in Class IE application as indicated in Appendix A.
2. Order'SBM switch replacements by the Panel Parts List General Electric Part Number to assure that such replacements will be to their original configuration requirements.
3. For switches identifiable in the A through M series and having a number less than 50 as described above, and with applications other than Class 1E, the 'cam followers can be .inspected for cracks with an auxiliary light source of adequate intensity through the opening hear the terminals of each switch deck. It is advisable to refrain from switch dissassembly for purposes of this inspection.
4. The switch application and its frequency of use as well as the results of the visual inspection should determine if immediate replacement would be in the best interest.

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March 19, 1976 SIL No. 155 Contact your local GE service representative for additional information and for assistance $n ordering replacement parts.

Prepared by: M.J. Sier ra/L.A. Gonzalez Approved by: Issued by:

D.L. Layt n, Manager D. . La ton, ctlng Manager Product ervice Perfo ance Analysis and Service Conmunications Product Refer ence:

A71 - Plant Recommendations

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APPENDIX A LOCATION AND DATE CODES OF GE TYPE SBM CONTROL Slr!ITCHES IN ESSENTIAL (CLASS IE) APPLICATIONS.

BWR PLANT PANEL TY DEVICE LOCATION DRAWING 8 DATE CODE Fitzpatrick 9-3 1 23A-S20 234A932?P002 9-8 32B, 32E, 32F 248A9615P001 Please check No cert. ayail-abl e 9-21 32, 33, 41, 42 234A932?P002 9-3 9-75 9-075-000 235A1127P002 975, - 2 15-MOV-102 248A9117P001 14JH 15-MOV-103 Peach Bottom II 9-4 16A-18B 234A9329P003 14MH 9-41 16A<<19B 14LH 9-4A 32, 39 234A9327P002 Cert. dated 10/13/75.

No Date Code Could be KL Peach Bottom III 9-4B 32, 39 234A932?P002 Cert. dated 10/13/75.

No Date Code Could be KL 9-4 16A-18B 234A9329P003 9-41 16A-19B 14MH, 14LH Brunswick II (Carolina I) H12-P601 E51AS15 234A9330P002 14MH

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