ML20117K537
| ML20117K537 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/04/1996 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20117K533 | List: |
| References | |
| NUDOCS 9606110353 | |
| Download: ML20117K537 (2) | |
Text
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'1 54 E8i UNITED STATES f
y y
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20666 0001 d
.....p SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMiNDMENT NO.184 TO FACILITY OPERATING LICENSE NO. DPR-16 l
GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY l
0YSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219
1.0 INTRODUCTION
By letter dated March 28, 1996, the GPU Nuclear Corporation (the licensee) submitted a request for changes to the Oyster Creek Nuclear Generating Station Technical Specifications (TSs). The requested changes would modify TS pages 3.1-5 and 3.1-i6 to indicat: "O percent of rated reactor thermal power as the anticipatory reactor scram bypass setpoint on turbine trip or generator load i
rejection.
The licensee will update its Final Safety Analysis Report for consistency with this change in the TS.
i l
2.0 EVALUATION The Reactor Protection System (RPS) monitors plant parameters and automatically initiates protective actions if established limits are exceeded.
l The RPS acts to protect the core against fuel rod cladding damage and to i
protect the reactor vessel from overpressure. The RPS initiates an anticipatory reactor scram for a turbine trip (turbine stop valve closure) and generator load reject (turbine control valve fast closure).
When reactor rated thermal power is below 40 percent, the TSs allow this anticipatory' scram signal to be bypassed. During power ascension, the bypass is removed and the anticipatory scrams are enabled before reaching 40 percent power. The bypass is accomplished using pressure switches off the high pressure turbine third stage extraction steam line. This pressure relates to rated reactor thermal power.
Previously, a nonconservative setpoint existed t
for the anticipatory scram signal. The conversion from steam pressure to reactor thermal power was not properly correlated for all possible equipment l
configurations during plant operation.
l The licensee has collected data to more accurately correlate turbine steam pressure to reactor power and is revising the TSs to clarify that the setpoint is to be based on rated reactor thermal power, rather than turbine rated steam flow.
9606110353 960604 PDR ADOCK 05000219 P
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' l The proposed ehang.s to the TS would indicate that the bypass for anticipatory I
reactor scram"on turbine trip or generator load reject is based on reactor thermal power, rather than turbine steam flow.
Because the changes are'a clarification to more accurately represent the design basis of the plant and eliminate a nonconservative setpoint, the changes are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Jersey State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no I
public comment on such finding (61 FR 18167). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR i
51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
G. Golub Date: June 4, 1996
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