ML20127E301
| ML20127E301 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/12/1993 |
| From: | Dromerick A Office of Nuclear Reactor Regulation |
| To: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| References | |
| GL-91-08, GL-91-8, TAC-M81902, NUDOCS 9301190242 | |
| Download: ML20127E301 (4) | |
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January 12, 1993 Docket No. 50-219 Mr. John J. Barton Vice President and Director GPU Nuclear Corporation Oyster Creek Nuclear Generating Station Post Office Box 388 forked River, New Jersey 08731
Dear Mr. Barton:
SUBJECT:
RESOLUTION OF MPA B-24, CONTAINMENT PURGE AND VENT ISOLATION VALVES (TAC NO. M81902)
By letters dated October 10, 1991, and September 9,1992, GPU Nuclear i
Corporation submitted additional information regarding the response for the Oyster Creek Nuclear Generating Station (OCNGS) to MPA B-24.
Your October 10, 1991, letter presented your position regarding the inclusion of valve closure times for containment purge and vent valves in the OCNGS Technical Specifications (TSs).
Your September 9, 1992, letter provided information regarding modifications to several purge and vent valves as part of the installation of a hardened wetwell vent.
With respect to your October 10, 1991, letter, the staff agrees that the Updated Final Safety Analysis Report (UFSAR) is an appropriate document in which to identify valve closure times.
This is consistent with guidance provided in Generic Letter (GL) 91-08, " Removal of Component Lists from Technical Specifications." Your letter also stated your position that additional leakage testing of containment purge and vent valves with resilient seals is not necessary.
Your justification for this position was that:
(1) the valves are not exposed to an environment inconsistent with the manufacturer's temperature and radiation limitations, (2) t$ e valves are used infrequently, and (3) the resilient seals are replaced act rding to the manufacturer's recommendations. The staff considers this position to be acceptable, so long as the resilient seals are replaced at least every 5 years.
3 In your September 9, 1992, letter, you stated that you had performed calculations to qualify containment isolation valves V-23-13,14,15, and 16 to close from an initial 75 degree open position in the event of an accident during containment purge and vent activities during plant operation.
You stated that, as part of the qualification of these valves, you will be replacing the taper pins and resilient seals during the upcoming 14R refueling outage. As a result of the increased opening positions, you stated that valve closure times for the above mentioned valves will not exceed 60 seconds, which is consistent with the previously accepted Current Licensing Basis and the closure times of other isolation valves.
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4 Mr. John J. Barton Based upon these proposed modifications, the staff considers containment isolation valves V-23-13,14,15, and 16 to be acceptable for use at opening angles not to exceed 75 degrees, provided the total containment atmosphere release through the containment purge and vent valves remains less than the 2000 lbm assumed in the staff's January 21, 1986, Safety Evaluation.
For purposes of calculating offsite releases, the staff does not consider the non-safety nitrogen inerting system to be an extension of the containment boundary. We request that you calculate the potential mass release through the containment purge and vent valves to ensure that these modifications will remain bounded by the staff's site boundary dose calculations. The maximum opening angles for other valves discussed in the staff's January 21, 1986, and October 10, 1986, Safety Evaluations remain unchanged.
in the course of this review, you provided several documents depicting the design of the OCNGS hardened vent system.
Please note that this letter should not be construed as an implicit staff acceptance of the OCNGS hardened ver,t.
The staff has not yet undertaken efforts to review and approve individual licensees' hardened vent designs, nor do we have plans to do so in the immediate future.
No response to this letter is required if the increased valve closure times for containment isolation valves V-23-13,14,15, and 16 do not result in a combined mass release of greater than 2000 lbm through all containment purge and vent valves during postulated accident conditions.
If you have any questions regarding this issue, please contact me at (301) 504-3473.
Sincerely, Original signed by Alexander Oromerick, Senior Project Manager Project Directorate I-4 Division of Reactor Projects I and II Office of Nuclear Reactor Regulation cc:
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Mr. John J. Barton Oyster Creek Nuclear GPU Nuclear Corporation Generating Station cc:
Ernest L. Blake, Jr., Esquire Resident Inspector Shaw, Pittman, Potts & Trow'oridge c/o U.S.. Nuclear Regulatory Commission -
2300 N Street, NW.
Post Office Box 445 Washington, DC 20037 Forked River,' New Jersey 08731.
Regional Administrator, Region I Kent Tosch, Chief U.S. Nuclear Regulatory Commission New Jersey Department of 475 Allendale Road Environmental Protection King of Prussia, Pennsylvania 19406 Bureau of Nuclear Engineering-CN 415' BWR Licensing Manager Trenton, New Jersey 08625 GPU Nuclear Corporation 1 Upper Pond Road Parsippany, New Jersey 07054 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731-Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop:
Site Emergency Bldg.
Post Office Box 388 Forked River,-New Jersey 08731 4
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4 Distribution:
Docket File NRC & Local PDRs PD-1-4 Plant SVarga
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- ADromerick OGC RBarrett JNorberg ACRS-(10)
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