ML20023C698
| ML20023C698 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/11/1983 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8305170558 | |
| Download: ML20023C698 (2) | |
Text
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s GPU Nuclear Q
gf P.O. Box 388 s
Forked River, New Jersey 08731 a
609-693-6000 Writer's Direct Dial Number:
May 11, 1983 Mr. D. G. Eisenhut, Direct or Division of Licensing Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Eisenhut:
Subj ect:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Mark I Containment Torus-to-Drywell Vacuus Breakers
References:
(1) NRC Letter dated February 2,1983 f rom D. G. Eisenhut to P. B. Fiedler.
(2) GE Letter MFN-159-82 and enclosure dated October 28, 1982
Dear Mr. Eisenhut:
This letter provides the status of analysis of the Oyster Creek Torus-to-Drywell vacuum breaker valves for condensation oscillation (CO) and chugging loads and CPUN's proposed schedule for completing this analysis.
The Oyster Creek Mark I containment is equipped with vacuum breaker valves mounted in piping lines connected between the Torus and the Drywell vent lines. These piping lines are external to the Torus. The vacuum breaker valve s are Atwood and Morrill swing check valves. CPUN is performing analysis to ensure the adequacy of these valves for loads induced by condensation oscillation and chugging during postulated loss-of-coolant accidents.
The general methodology to be used to define loads on the Oyster Creek vacuum breaker valves has been submitted to the NRC for review and approval by Reference (2). Based on Reference (2), GPUN has performed a preliminary analysis which indicates the existing Oyster Creek vacuum breaker valves meet the appropriate acceptance criteria. Based on the results of our preliminary analysis, we are presently planning no modifications to the Oyster Creek vacuum breaker valves.
Once the NRC has completed its review of the general methodology for OE defining vacuum breaker valve loads, CPUN plans to finalize the analysis.
l Unless there are substantial differences between the methodology submitted by Reference (2) and the final approved methodology, we expect it will require about 4-1/2 months to incorporate changes, if any, resulting from the NRC's revi e w, finalize our analysis of the adequacy of the vacuum breaker valves, and 8305170558 803511 PDR ADDCK 05000219 P
PDR vrv nuciear is a part of the General Pubhc Utihties System
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, subnit to the NRC this final analysis along with plans for vacuum breaker valve modifications, if they are required. We understand that the NRC was scheduled to complete _ their review of Reference (2) by April 15, 1983. Based on this scheduled review date, we would plan to submit to the NRC our final analysis of the Oyster Creek Torus-to-Drywell vacuum breakers by September 1,1983.
Since the present Oyster Creek refueling outage is planned to extend to January 12, 1983, it appears this schedule would provide the NRC with adequate time for review prior to plant re st ar t.
Very truly yours, 4
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gA f f l/2 - _ A__J Pet r B. Fiedler Vice President and Director Oyster Creek PBF:jal cc: Regional Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 l
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