ML19345G139
| ML19345G139 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/07/1976 |
| From: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-76-04, IEB-76-4, NUDOCS 8103060724 | |
| Download: ML19345G139 (5) | |
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>ttir i(~..,.by General officos: 212 West wchigan Avenue. Jackson, Michigan 49201. Area Code S17 788 05S0 June 7, 1976 Mr James G. Keppler US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-155, LICENSE DPR-6 BIG ROCK POINT PIRIT By letter dated March 31, 1976 you transmitted IE Bulletin 76-04 which re-quested information on austenitics stainless steel piping which may have undergone cold bending during fabrication without subsequent solution anneal-ing.
The purpose of this letter and its attachment is to provide the reque'sted I
information for the Big Rock Point Plant, to the' extent that it is available.
Our responses correspond to the item numbers in the IE Bulletin.
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The attached list describes reactor pressure boundary piping which is austenitic stainless steel greater than two inches in nominal size.
Plant records do not indicate whether or not this piping was cold work without full solution annealing following forming. We believe that the records which exist regarding this piping are compatible with the record retention requirements that existed at the time of initial plant con-struction, lb.
The program, including inspection criteria and a general schedule, for nondestructive volumetric examination of the items identified in la above is contained in Section 9 of the Big Rock Point Technical Specifica-tions. A detailed schedule of items to be inspected during the next refueling outage is presently bei.ng prepared and should be available for s
your inspection after August 1976.
It is noted that, while records regarding cold working without solution annealing do not exist, previous volumetric inspections have failed to reveal any defects which could be attributed to cold working.
In addition, the leak detection system backfit into the Big Rock Point Plant during the early 1970s has been ' demonstrated to be very sensitive and would provide an adcquate warning of throuch vall cracking, were it to occur. We have concluded, based on the 13 years' operating experience, the inspection results described above and the sensitive leak detection system, that further inspection in addition to those presently required is not necessary.
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This reply constitutes the 60 day response requested.
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The-reporting requirements'of the existing Technical Specifications
- already cover adverse nondestructive examination findings. We will report any adverse findings in accordance with the requirements of the existing Technical Specifications.
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RalphB.Sewell Nuclear Licensing Administrator 4
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CONSUMERS POWER COMPANY L_
BIG ROCK POINT PLANT DOCKET N0. 50-155 Attached is a copy of licensee's reply dated June 7, 1976, to IE Bulletin 76-04.
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Do NOT use this form as a RECORD of approvals. concunences.
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disapprovals. clearances, and similar actions Faou o -
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y Generat Offices: 212 West Michigan Avenuc. Jackson. Michigsen 49M1. Area Code S17 780 0D00 May 17, 1976 Mr J:unes G. Keppler US Uuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 I
DOCKET 50-155, LICEI;SE DPR l BIG ROCK POI. tit PLA'iT This 1ctter is to provide a final response to IE Bulletin 76-02 regarding certain direct current relays manufactured by the General Electric Company.
A preliminary response was submitted April 19, 1976.
137 relays have been identified at the plant in both safety-re. lated and nonsafety-1 related systems as defined by our "Q-List."
We have had no known failures of any of there relays in direct current applications during the plant operating history. Relays, except CVX-1 and CVX-2 (see below) are physically located in area's vnere humidity and moisture are not likely to cause problems as described in Bulletin 76-02.
In addition, the h2_ relays in safety-related systems which have nylon spools are either energized more than 99% of the time or less than
.1% of the time and thus not deemed susceptible to the failures as described in the bulletin.
Only five relays are in critical applications requiring nonfail-safe operation to cope with accidents as described in the FHSR. The evaluation of these relays is as follows:
Relay SVX-1 is in the containment vacuum relief circuitry associated with the containment ventilation supply valves.
This relay is in the relatively dry control room, energised more than 99% of the time and failure could be identi-l fied by inadvertant closure of the containment ventilation supply valves which are open more than 99% of the time.
Relaya CVX-1 and CVX-2 are located in containment in an area where moisture and
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Proper functioning of the entered into system under:
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