ML20077F695
| ML20077F695 | |
| 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 9412150021 | |
| Download: ML20077F695 (4) | |
Text
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[ na creo,k UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20MSC001
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GPU NUCLEAR CORPORATION MQ JERSEY CENTRAL POWER & LIGHT COMPANY 00CKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATI0B AMENDMENT TO FACILITY OPERATING llCENSE Amendment No.174 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee), dated July 8, 1994, as supplemented October 10, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9412150021 941130 PDR ADOCK 05000219 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph.2.C.(2) of Facility Operating License No. DPR-16 is hereby
. amended to read as follows:
(2)
Technical' Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.174, are hereby incorporated in the license.
GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/Phillip
. McKee, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance:
November 30, 1994 j
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ATTACHMENT TO LICENSE AMENDMENT N0.174 FACILITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
Remove Insert 2.3-3 2.3-3
FUNCTION LIMITING SAFETY SYSTEM SETTINGS K.
Reactor Low-Low Water Level, 17'2" above the top of the active fuel Core Spray Initiation L.
Reactor Low-Low Water Level, 27'2" above the top of the active fuel Isolation Condenser Initiation with time delay 53 seconds M.
Turbine Trip, Scram 10 percent turbine stop valve (s) closure from full open N.
Generator Load Rejection, Initiate upon loss of oil pressure Scram from turbine acceleration relay O.
Recirculation Flow, Scram 571.4 Mlb/hr (117% of rated flow)
P.
Loss of Power
- 1) 4.16 KV Emergency Bus 0 volts with 3 seconds Undervoltage(Lossof 0.5 seconds time delay Voltage)
- 2) 4.16 KV Emergency Bus 3840(+20V,-40V) volts l
Undervoltage(Degraded 10 ! 10% (1,0) second time Voltage) delay Bases:
Safety limits have been established in Specifications 2.1 and 2.2 to protect the integrity of the fuel cladding and reactor coolant system barriers, respectively. Automatic protective devices have been provided in the plant design for corrective actions to prevent the safety limits from being exceeded in normal operation or operational transients caused by reasonably expected single operator error or equipment malfunction. This Specification establishes the trip settings for these automatic protection devices.
W The Average Power Range Monitor, APRM
, trip setting has been established to assure never reaching the fuel cladding integrity safety limit. The APRM system responds to changes in neutron flux. However, ne&r the rated thermal power, the APRM is calibrated using a plant heat balance, so that the neutron flux that is sensed is read out as percent of the rated thermal power. For slow maneuvers, such as those where core thermal power, surface heat flux, and the power transferred to the water follow the neutron flux, the APRM will read reactor thermal power. For fast transients, the neutron flux will lead the power transferred from the cladding to the water due to the effect of the fuel time constant. Therefore, when the neuron flux increases to the scram setting, the percent increase in heat flux and power transferred to the water will be less than the percent increase in neutron flux.
TheAPRMtripsettingwillbevariedautomatica}lywithrecirculationflow,with the trip setting at the rated flow of 61.0 x 10 lb/hr of greater being 115.7%
of rated neutron flux. Based on a complete evaluation of the reactor dynamic performance during normal operation as well as expected maneuvers and the various mechanical failures, it was concluded that sufficient protection OYSTFR CREEK 2.3-3 Amendment No. /I,16, 8d,174
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