ML20204B704
| ML20204B704 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/12/1988 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20204B707 | List: |
| References | |
| DPR-16-A-128 NUDOCS 8810200299 | |
| Download: ML20204B704 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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WASM NGTON, D. C. 20666
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EU N'JCLEAR CORPORATION AND.
JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 O STER CREEK NUCLEAR GENERATING STATf0N J
AMEN 0 MENT TO PROVISIONAL OPERATING LICENSE Amendment No. 128 License No. DPR-16 1.
The Nuclear Regulatory Comission (the Connission) has fcund that:
A.
The application for amendment by GPU Nuclear Corporation, et al.,
(the licensee), dated June 21, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Cornission; 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 ('.i) that such activities will be conducted in compliance with the Comission's regulations; D.
The i;suance of this arrendment will not be inimical to the common oefense 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 Comission's regulations and all applicable recuirements have been satisfied.
8810200299 881012 PDR ALOCK 05000219 P
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attechn;ent to this license amendment, and paragraph 2.C.(2) of Provisional Operating License No. DPR-16 is hereby antended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendnent No.128, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specific,tions.
3.
This license amendment is effective as of the date of issuance.
FM TilE NUCLEAR REG LATORY COMMISSION
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Johh'F. Stolz, Direct r ProjectDirectorate
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Di(1sion of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications Date of Issuance: October 12, 1988 l
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ATTACHMENT TO LICENSE AMENOMENT NO. 128 PROVISIONAL OPERATING LICENSE N0. OPR-16 00CKET NO. 50-219
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Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated.
The revised pages are identified by amendment number and tontain vertical lines indicating the areas of change.
Remove Insert Page 4.5-4 Page 4.5-4 Page 4.5-13 Page 4.5-13 1
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I.
Functional Test of Valves 1.
All containment isolation valves specified in Table 3.5.2 shall be tested for automatic closure by an isolation signal during each refueling outage.
The following valves are required to close in the time specified below:
Main steam line isolation valves
> 3 see and 410 sec.
Isolation condenser isolation valves 2 60 sec.
Cleanup system isolation valves 2 60 sec.
Cleanup auxiliary pumps system isolation valves "I 60 sec.
Shutdown system isolation valves j60sec.
2.
Each containment isolation valve shown in Table 3.5.2 shall be demonstrated operable prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator by cycling the valve through at lear.t one complete cycle of full travel and verifying the specified isolating time.
Following niaintenance, repair or replacement work on the control or power circuit for the valves shown in Table 3.5.2, the affected component shall be tested to assure it will perform its intended function in the circuit.
3.
Quarterly, during periods of sustained power operation, each main steam isolation valve shall be closed (one at a time) and its closure time verified to be within the limits of specification 4.5.I.1 above.
Such testing shall be conducted with reactor power not greater than 50% of rated power.
4.
Reactor Building to Suppression Chamber Vacuum Breakers a.
The reactor building to suppression chamber vacuum breakers and associated instrumentation, including setpoint, shall be checked for proper operation every three months.
b.
During each refueling outage each vacuum breaker shall be tested to determine that the force required to open the vacuum breaker from closed to fully open does not exceed the force specified in Specification 3.5. A.3.a.
The air-operated vacuum breaker instrumentation shall be calibrated during each refueling outage.
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OYSTER CREEX 4.5-4 Amendment No: J4, %, 128
Since the main steam line isolation valves are normally in the open position, more frequent testing is specified.
Per ASME Boiler and Pressure Vessel code, section XI, the quarterly full closure test afil ensure operability and provide assurance that the valves maintain the required closing time.
The minimum time of 3 seconds is based on the transient analysis of the isolation valve closure that shows the pressure peak 76 psig below the lowest safety valve setting.
The maximum time of 10 seconds is based on the value assumed for the main steam line break dose calculations.
Surveillance of the suppression chamber-reactor building vacuum breakers consists of operability checks and leakage tests (conducted as part of the containment leak - tightness tests).
These vacuum breakers are normally in the closed position and open only during tests or an accident condition.
As a result, a testing frequency of three months for operability is censidered justified for this equipme1t.
Inspections and calibrations are performed during the rufueling outages, this frequency being based on equipment quality, experience, and engineering judgment.
The fourteen suppression chamber-drywell vacuum relief valves are designed to open to the full open position (the position that curtain area is equivalent to valve bore) with a force equivalent to a 0.5 psi differential acting on the suppression chamber face of the valve disk.
This opening specification assures that the design limit of 2.0 psid between the drywell and external environment is not exceeded.
Once each refueling outage each vale is tested to ast.ure that it will open fully in response to a force less than that specified. Also 't is inspected to assure that it closes freely and operates properly.
The containment design has been examined to establish the allowable bypass area between the drywell and suppression chamber as 10.5 in.2 (expressed as vacuum breaker open area).
This is equivalent to one vacuum breaker disk off its seat 0.371 inch; this length corresponds to an angular displacement of 1.25*.
A conservative allowance of 0.10 inch has been selected as the maximum permissible valve opening.
Yalve closure within this limit may be determined by light indication from two independent position detection and indication systems.
Either system provides a control room alarm for a non-seated valve.
At the end of each refueling cycle, a leak rate test shall be performed to verify that significant leakage flow paths do not exist between the drywell and suppression chamber.
The drywell pressure will be increased by at least 1 psi with reipect to the suppression chamber pressure.
The pressure transient (if any) will be monitored with a sensitive pressure gauge.
If the drywell pressure cannot be increased by 1 psi over the suppression chamber pressure it would be because a significant leakage path exists; in this event the leakage source will be identified and eliminated before power operation is resumed.
If the drywell pressure can be increased by 1 psi over the suppression chamber the rate of change of the suppression chamber pressure must not exceed a rate equivalent to the rate of air flow from the drywell OYSTER CREEK 4.5-13 Change: 27, Amendment No. 128