ML19210A136
| ML19210A136 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/28/1976 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | James O'Reilly, Reid R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19210A137 | List: |
| References | |
| GQL-0634, GQL-634, NUDOCS 7910240856 | |
| Download: ML19210A136 (1) | |
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METHOPOLITAN EDISON COMPANY car.v w er ce. m e. cc o., u,a c ms,. :. /
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TELEPHONE 215 - 023-0501 Po3T OFFICE COX 542 P.EAD tJG, PENNSYLVANIA 10C03 gg g
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Director of Nuclear Reactor Regulation ij
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Attn:
R. V. Reid, Chief
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U. S. Nuclear Regulatory Commission Washington, D. C.
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Mr. J. P. O'Reilly, Directo Office of Inspection & Enforcement, Region 1 U. S. Nuclear Regulatory Ccamission 631 Park Avenue King of Prussia, Pennsylvania 194C6
Dear Sirs:
Docket No. 50-2C9 Operating License DR-50 In our letter CQL 1632, dated November 3, 1975, regarding missinc Inservice Inspection baseline data, we ec:mitted to a liquid penetrant examination of two six-inch by six-inch patches of Reactor Vessel Closure Head cladding to he performed during the present on%ge.
Since that time, the AS!E Code Ccemittee has approved the deletion of all cladding inspection requirements. This change vill be reflected in the Su=er,1976 Addenda to the Code. This information is per telephone conversation between Mr. J. Gorman (MPR Associates) and Mr. O. Hedden, of the ASIG Code Cc=ittee, on April 8,1976.
The deletion of cladding examinaticn frc= code requirerents vill be a basis for incorporation of the same deletion into a future proposed technical specification change for the Inservice Inspection Pregram.
With the anticipated dele +1on of these examinations from the technical specification, we feel there is no justification for recreating a b;seline that vill not te used again, especially when the attendant radiation exposures are considered.
Consequently, we do not plan to perform this inspection.
All other commitments for examinations this refueling outage have been met.
Sincerely, 1490 028
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%L R. C. Arnold C
Vice President RCA:JJM:eg 7910240 g
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METHOPOLITAN EDISON COMPANY - m:vi.w v or cenem pucuc ununes coneonnic :
POST OFFICE BOX 542 READING, PENNSYLVANIA 19603 TELEPHONE 215 - 929-3601 May 7, 1976 GQL 0660 Mr. J. P. O'Reilly Office of Inspection and Enforcement U.S. Nuclear Regulatory Cc==ission 631 Park Avenue King of Prussia, PA 19hC6 U.S. Nuclear Regulatory Cc==ission Office of Inspection and Enforcement Division of Reactor Inspection Progress Washington, D.C.
20555
Dear Sirs:
Three Mile Island Nuclear Station, Unit 1 (D:I-1)
Decket Nc. 50 089 Operating License Lo OPR-50 IE Bulletin 76-05 This letter ant.i the attached enclosure are provided in response to ycur IE Bulletin 76-05, and is being submitted one day late in accordance with the May 7,1976 conversation between our Mr. :/oran and your Mr. Spessard.
With regard to the Westinghcuse Service letter referenced in the bulletin, we had not received it prior to receipt of the bulletin.
Please be advised, hevever, that we have subsequently established cc==unications with Westinghcuse regarding the details of this matter, and will continue working with them, as may be appropriate, until this matter is resolved.
We believe our actions as presented in the attached enclosure are sufficiently responsive to *,he concerns raised by the subject bulletin. Should you, however, have any additional questiens or concerns, please centact me.
Sincerely, f1
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.. C. 6..cld Vice President
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Inclosure File:
61.0016.0003.0053 1490 029
Three Mile Island Iluclear Station Unit 1 (TMI-1)
Docket I;o. 50-289 O
Operating License No. DPR-50 fD Restense to TE Bulletin 76-05 We have found that there are a number of LFD relays in use on safety related syste=s.
The relays are used in two applications:
1.
The "Y" relay located en DHP Westinghouse Circuit Breakers and 2.
The control relays for the 1A and 13 Emergency Diesel Generators.
The relays on the DHP circuit breakers have a =olded coil (Coil number 506C322G02).
We believe these coi]2.re not subject to the failure mentioned in the IE Bulletin and therefor *. aa further action is required. There are 29 breakers en the 1D and lE hKV busses. Each breaker has one relay.
There are 3h BFD relays en each diesel generator (68 total). Each relay is believed to have the coil indicated as " defective" by the IE Eulletin (Coil style 503Ch28G21). Many of the relays are energi:cd for long periods of tice.
Failure of sc=e of the relays could affect the operability of the diesel generator.
Our discussion with Westinghouse indicates that the coils / relays are not subject to failure / sticking at nor=al voltages (125 VDC 1 105). Reliable operation could therefore be expected up to 137 VDC. Cur battery chtrgar ficat (nor :.1) vultcgc is 130 V i IV.
Equalize charge is set at 135 volts i 2 volts. The battery is normally put on equalize when specific gravity readings drift down, or following the refueling interval lead test. The duration of the equalize charge is normally 24 to L8 hours.
Two continuously energized relays on the A Diesel Generator were checked. The/
vere selected because they represent the vorst case regarding aging.
The CF1 coil outside temperature was =easured as 80 C vith an ambient temperature 0
of 220C. The supply voltage was measured as 129.6 VDC.
Relay Designation Physical Condition Droccut Time CF 1 Shoved sc=e signs of heat 19.8 Ms aging. The black speel piece was broken er broke during disassembly.
The nylon sleeve vcs discolored and, brittle.
9 030 CF 2 Shoved some signs of heat 20.1 M aging. Nylor sleeve dis-colored.
.1 functicnal ;cs: va: pu formed sn ul thu IFD rehys in the A Diesel au.e n.c cabinet. All relsyc responced properly to the tea m.
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_ 2-The relay coils chev adverse effects from the heat; however, we believe the degree of degredation does not indicate i=minent failure, even considering the number of relays in the system. We will evaluate ventilation of the cabinet.
We plan to replace all the subject relays during the next refueling.
1490 031