ML20077F715
| ML20077F715 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/30/1994 |
| From: | Dromerick A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077F698 | List: |
| References | |
| NUDOCS 9412150028 | |
| Download: ML20077F715 (2) | |
Text
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION GPU NUCLEAR CORPORATION DOCKET NO. 50-219 NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U.S. Nuclear Regulatory Commission (Commission) has issued Amendment No. 174 to Facility Operating License No. DPR-16 issued to GPU Nuclear Corporation, which revised the Technical Specifications for operation of the Oyster Creek Nuclear Generating Station located in Ocean County, New Jersey.
The amendment is effective as of the date of issuance.
The amendment revises the Technical Specification Section 2.3.P(2) safety limit to raise the degraded voltage setpoint from 3671 volts to 3840 volts, and to revise the allowable setpoint range from 1% to +20V, -40V.
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Notice of Consideration of Issuance of Anendment and Opportunity for Hearing in connection with this action was published in the FEDERAL REGISTER on July 25, 1994 (59 FR 37787). No request for a hearing or petition for leave to intervene was filed following this notice.
The Commission has prepared an Environmental Assessment related to the action and has determined not to prepare an environmental impact statement.
Based upon the environmental assessment, the Commission has concluded that the issuance of the amendment will not have a significant effect on the quality of the human environment (59 FR 59443).
9412150028 941130 DR ADOCK 0500 9
3 2-For further details with respect to the action see (1) the application for amendment dated July 8, 1994, and supplemented October 10,1994,(2)
Amendment No.174 to License No. DPR-16, (3) the Commission's related Safety Evaluation, and (4) the Commission's Environmental Assessment. All of these items are available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street NW., Washington, DC, and at the local public document room located at the Ocean County Library, Reference Department, 101 Washington Street, Toms River, NJ 08753.
Dated at Rockville, Maryland, this 30th day of November 1994 FOR THE NUCLEAR REGULATORY COMMISS!JN Y/
Alexander W. Dromerick, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation l
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Post Office Box 388 Route 9 South Forked River, New Jersey 08731-0388 609 971 4000 Wnter's Direct Dial Number:
C321-94-2150 October 10, 1994 U. S. Nuclear Regulatory Commission Att: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Facility Operating License No. DPR-16 Response to Request for Additional Information - Technical Specification Change Request No. 219 This letter confirms our discussion via teleconference on September 14, 1994 regarding Technical Specification Change Request (TSCR) No. 219, submitted to NRC on July 8, 1994 (C321-94-2089).
The revised degraded voltage setpoint coupled with interim administrative controle will protect required engineered safety features equipment from the adverse affects of degraded grid voltages. As stated in TSCR No. 219, administrative controls exist to provide adequate protection for 480V and 120V circuits.
These administrative controls will remain until appropriate modifications can be completed.
Modifications to the 480V system components identified in TSCR No. 219 which require a plant shutdown will be completed by the end of the current 15R refueling outage. Other modifications will be completed in conjunction with the implementation of the requested change to the Technical Specifications.
Additional field testing is ongoing during the 1SR outage to verify 120V system voltage drops and current values. Measured voltage and current values will be compared to analysis assumptions. Any modifications to these 120V circuits identified as a result of this reanalysis are planned to be completed no later than the end of the 16R outage consistent with the Long Range Planning Program.
Upon completion of the above noted 480V System modifications and possible 120V System modifications, the revised degraded voltage setpoint will ensure adequate voltage to required engineered safety features eculoment under worst case postulated conditions.
94.10200138 J41010 PDR ADOCK 050002F9' N{
P PDR 1 h h ( ( } GPU Nuclear Corporation is a suosid:ary of General PuDhc UtAttes Corporation
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l A C321-94-2150 Page 2 The postulated worst case bus loading for a single onsite power distribution train was conservatively utilized as the basis for calculating the degraded voltage relay setpoint. This assumption is consistent with the design basis of the OCNGS onsite electrical distribution system as described in OC Final Safety Analysis Report (FSAR) Section 8.3.1, and satisfies the intent of 10 CFR 50, Appendix A, General Design Criteria regarding electrical power systems.
The basis for the worst case loading on each train assumes that only one of the two power trains is available during the accident scenario.
Therefore, the remaining train must carry all the loads necessary for safe shutdown. The electrical distribution system was mathematically modeled using the DAPPER computer program.
Each train was analyzed separately to determine which was more heavily loaded. Considering the worst case loading condition on the 4160V bus, downstream voltages were computed by the DAPPER program to determine the acceptability of supplied voltages. This method provides a conservative approach to ensure that all equipment required for safe shutdown is protected at the selected UV relay setpoint.
If any additional information is required please contact us.
Sincerely,
\\gyf' J. J. Barton
- "' Vice President and Director Oyster Creek DJD/plp c:
Administrator, Region I Oyster Creek NRC Project Manager Sr. Resident Inspector, OC T. J. Hutler - Mayor of Lacey Township K. Tosch - Director, NJ Bureau of Nuclear Engineering i
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