ML20151Y832
| ML20151Y832 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/29/1988 |
| From: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20151Y767 | List: |
| References | |
| RTR-NUREG-0578, RTR-NUREG-0660, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-660, RTR-NUREG-737 NUDOCS 8805050124 | |
| Download: ML20151Y832 (2) | |
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GPU Nuclear Corporation l
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Post Office Box 388 Route 9 South Forked River.New Jersey 08731-o388 609 971-4000 Wnters Direct DialNumber:
April 29,1988 U.S. Nuclear Regulatory Comission Attention: Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Technical Specification Change Request N;.173 Pursuant to 10CFR50.90, GPU Nuclear Corporation, operator of the Oyster Creek Nuclear Generating Station, Provisional Operating License No. DPR-16, requests e change to Appendiy, A of that license.
The enclosed plant specific Technical Spec ication Change Request proposes to revise the requirements for operability of sosition indicators for the sixteen ASME Code safety valves.
One primary and one backup position indicator was installed in 1980 on each safety valve as a result of NUREG 0578, TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations.
The primary device is an acoustic monitor while the backup device is a thermocouple.
The requirements for relief and safety valve position indication were described in NUREGs 0578, 0660 and 0737.
Currently, Oyster Creek Technical Specifications require a plant shutdown depending on the number of inoperable safety valve position indicators and the location of their associated safety valves.
The sixteen safety vaives are located on the main steam piping inside containment and they discharge directly to the containment atmosphere.
These valves are spring-type Code safety valves with no means of remote control. As of this date four valves have inoperable backup devices and three other valves have inoperable primary devices. The indicators cannot be repaired without a containment entry.
The essence of the proposed change is to permit continued operation with no limitation on the number of inoperable positicn indicators for the safety valves.
Repair of any inoperable devices would still be required prior to startup following each cold shutdown.
The basis for the proposed change is that, at Oyster Creek, procedure-directed operator response to symptoms indicative of a primary system steam or liquid release inside containment hD I 8805050124 880429 i /
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is no different whether the source is an open scfety valve or breach in the reactor coolant pressure boundary. Our evaluation in support of this proposed change concludes that safety valve position indicators provide no benefit as regards operator response to this type of event. Consistent with NUREG 0737, revised operability requirements would still be maintained in the Technical Specifications with no change to current surveillance requirements.
We request that the NRC Staff place a high priority in consideration of the requested change.
This is due to the imminent risk of a plant shutdown should future surveillance on the safety valve position indicators reveal additional failures resulting it, a configuration necessitating entrance into a shutdown action statement.
Therefore, Staff action on this proposed change is requested as soon as possible and, if approved, we would be prepared te implement the change upon issuance of the license amendment.
In the event a shutdown is required due to the subject Technical Specifications prior to amendment issuance, we would give serious consideration to request that this change be considered by the Staff on an exigent basis, if possible, at that time.
This change request has been reviewed in accordance with Section 6.5 of the Oyster Creek Technical Specifications, and using the standards in 10CFR50.92 we have concluded that this proposed change does not constitute a significant hazards consideration.
Pursuant to 10CFR50.91(b)(1), a copy of this change request has been sent to the State of New Jersey Department of Environmental Protection.
In addition, a check for $150.00, pursuant to 10CFR170.12, will be forwarded shortly under separate cover for the application fee.
Very t ruly ours
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s do Barton cting Director, Oyster Creek JB/PC/pa(6732f/0487A) cc: Mr. William T. Russell, Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, N.J.
08731 Mr. Alex Dromerick U.S. Nuclear Regulatory Commission Washington, D.C.
20555
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