ML20198K058
| ML20198K058 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/23/1998 |
| From: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC |
| Shared Package | |
| ML20198K038 | List: |
| References | |
| NUDOCS 9812300330 | |
| Download: ML20198K058 (6) | |
Text
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GPU Nuclear, Inc.
l Oyster Creek Nuclear Generating Station Facility License No. DPR.16 i
Technical Specification Change Request No. 268 l
Docket No. 50 219 I
Applicant hereby submits a change to Appendix A Technical Specification pages 3.8 2 and 4.8-1.
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By:
[bk Michael B. Roche Vice President and Director Oyster Creek Sworn and Subscribed to before me thisi day of M&Mk. /97?
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Notary Public of NJ f
GERM. DINE E.ijiVIN NOTARYPUBUCCFIEWSWEY r--
9812300330 981223 pmEghs_6 N#9 PP ADOCK 05000219 P
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1 United States of America l
Nuclear Regulatory Commission j.
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In the Matter of
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Docket No. 50-219 GPU Nuclear, Inc.
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l Certificate of Service
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2 This is to certify that a copy of Technical Specification Change Request No. 268 for Oyster Creek Nuclear Generating Station Operating License, filed with the U.S. Nuclear Regulatory Commission on 34.. 33,199 3, has this day of /Ac. J3,179 8, been served on the Mayor l
of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:
1 The Honorable Louis A. Amato, Jr.
Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 By: b d
Michael B. Roche
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Vice President and Director Oyster Creek I
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Oyster Creek Nuclear Generating Station Technical Specification Change Request No. 268 I
I 1.
Change Reauested GPU Nuclear requests that Appendix A Technical Specification (TS) pages 3.8-2 and 4.8-1 be revised to reflect a surveillance frequency of once per three months for verifying the operability of Isolation Condenser motor-operated isolation valves and condensate makeup valves.
i II.
Discussion of Proposed Change TS 4.8.A.1 addresses the periodic testing requirements employed to verify the operability of Isolation Condenser motor-operated isolation valves and condensate makeup valves.
Currently, TS 4.8.A.1 specifies a surveillance frequency of once/ month.
Surveillance testing of the Isolation Condenser motor operated valves has been shown to result in wear on the valves which eventually results in leakage past the seat of the valve.
The intent of TSCR No. 268 is to increase the surveillance test interval and thereby reduce both tN wear on the motor operated valves and the potential for valve leakage.
l Accordingly, GPU Nuclear is proposing to change TS 4.8.A.1 such that surveillance testing is performed once per three months.
III.
Safety Assessment The Isolation Condenser System (ICS) is a standby, high pressure system for removal of fission product decay heat when the reactor vessel is isolated from the Main Condenser.
The system prevents overheating of the reactor fuel, controls the reactor pressure rise, and limits the loss of reactor coolant through the relief valves.
The ICS consists of two full capacity isolation condensers, four AC motor-operated isolation valves, four DC motor operated isolation valves, and three vent lines to the atmosphere. The ICS operates by natural circulation without the need for electrical power other than the de electrical system used to place the ICS in operation. The system operates with steam flowing from th6 reactor pressure vessel through the condenser tubes and condensate returning by gravity to the reactor pressure vessel, forming a closed loop.
The valves in the steam inlet lines are normally open so that the tube bundles are at l
reactor pressure.
The DC motor-operated condensate isolation valves, which are l
normally closed, are the only valves that need to be opened in order to place the ICS in operation. The system can be activated manually or automatically.
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1940-98-20674 Page 2 of 3 Surveillances are performed to verify the operability of systems and components, and to verify that variables are within specified limits.
Currently, specification 4.8.A.1 stipulates.a surveillance frequency of once per month for verifying the operability of Isolation Condenser motor-operated isolation valves and condensate makeup valves.
TSCR No. 268 proposes to alter specification 4.8.A.1 such that it specifies a surveillance frequency of once per three months.
The proposed surveillance frequency is consistent with ASME Code Section XI, IWV-3411(1986 Edition with no addenda) which requires in-service testing of the active function valves every three months as well as BWR Standard Technical Specifications, NUREG-l_433 " General Electric Plants, BWR/4", which requires surveillance testing of valves in the ECCS system once every ninety two days. The risk of a plant transient due to surveillance testing, personnel radiation exposure and equipment degradation will be reduceJ as a result of the proposed increase in the surveillance test interval. In addition, a review of the Oyster Creek ICS surveillance test data for the last three years demonstrates that the valves are reliable. The proposed changes are compatible with plant operating experience and sre consistent with the guidance of Generic Letter 93-05, "Line-Item Technical Specifications Improvements To Reduce Surveillance Requirements For Testing During Power Operation".
Based on the above, the proposed change in surveillance frequency will not adversely affect system availability and reliability nor will it adversely affect nuclear safety or safe plant operation.
IV.
Information SuDDortine a Finding of No Significant Hazards Consideration l
GPU Nuclear has concluded that the proposed change to extend the surveillance interval for verifying the operability ofIsolation Condenser motor-operated isolation valves and condensate makeup valves from once per month to once per three months does not l
involve a Significant Hazards Consideration. In support of this determination, an evaluation of each of the three (3) standards set forth in 10 CFR 50.92 is provided below.
1.
The proposed TS chance does not involve a sinnificant increase in the probability l
or conseauences of an accident previously evaluated.
The proposed surveillance interval change does not alter the actual surveillance requirements, nor does it alter the limits and restrictions on plant operations. The reliability of systems and components relied upon to prevent or mitigate the consequences of accidents previously evaluated is not degraded by the proposed change to the surveillance interval. Assurance of system and equipment availability is maintained. The proposed change does not alter any system or equipment configuration.
Based on the above, the proposed change does not significantly increase the probability or consequences of a accident previously evaluated.
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1940-98-20674 Page 3 of 3 l
2.
The proposed TS chance does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed surveillance interval change does not alter the actual surveillance requirements, nor does it alter the limits and restactions on plant operations.
Assurance of system and equipment availability is maintained. The proposed j
change does not alter any system or equipment configuration nor does it introduce any new mechanisms which could contribute to the creation of a new er different i
kind of accident than previously evaluated.
3.
The pronosed TS channes do not involve a sienificant reduction in a marein of safety.
The proposed change extends the surveillance interval for verifying the operability ofIsolation Condenser motor-operated isolation valves and condensate makeup valves from once per month to once per three months. The proposed change does not alter the actual surveillance requirements, the limits and restrie.tms on plant operations nor the design, function or manner of operation of any structures, systems or components. System availability and reliability are maintained. Accordingly, the proposed TS change does not involve a significant reduction in a margin of safety.
i V.
Information Supporting an Environmental Assessment i
An environmental assessment is not required for the proposed change since the proposed change conforms to the criteria for " actions eligible for categorical exclusion" as specified in 10 CFR 51.22(c)(9). The proposed change will have no impact on the environment. The proposed change does not involve a significant hazards consideration as discussed in the preceding section. The proposed change does not involve a significant change in the types or significant increase in the amounts of any effluents that may be released offsite. In addition, the proposed change does not involve a significant increase in individual or cumulative occupational radiation exposure.
VI.
Conclusion The proposed changes have been reviewed in accordance with Section 6.5 of the Oyster Creek Technical Specifications and it has been concluded there are no unreviewed safety questions. As discussed above, using the standards in 10 CFR 50.92, GPU Nuclear has l
determined that there are no Significant Hazards Considerations involved with the l
proposed changes.
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VII.
IMPLEMENTATION i
l It is requested that the amendment authorizing this change become effective upon issuance.
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Revised Technical Specification Pages I
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