ML19344F412
| ML19344F412 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/29/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19344F392 | List: |
| References | |
| NUDOCS 8009150244 | |
| Download: ML19344F412 (4) | |
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UNITED STATES
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. NUCLEAR REGULATORY COMMISSION f
3-E' WASHINGTON, D. C. 20555
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p DUQUESNE LIGHT _ COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET N0. 50-334 BEAVER VALLEY POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 29 License No. DPR-66 1.
The. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated May 14, 1980, 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 Commission; C.
There is reasonable assurance (i) 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; 5
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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.
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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-66 is ~ hereby a, mended to read as follows :
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 29, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b.dtt
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"'s6teven A. Varga, hief Operating Reactors Branch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 29, 1980 L
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ATTACHMENT TO LICENSE AMENDMENT
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AMENDMENT NO. 29 TO FACILITY OPERATING LICENSE NO. OPR-66 5I DOCKET NO. 50-334' b
h Revise Appendix-A as follows:
1:9 Remove Pages Insert Pages B
2-8 B
2-8 3/4 3-4 3/4 3-4
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r LIMITING SAFETY SYSTEM SETTINGS BASES Safety Injection Input from ESF If a reactor trip has not already been generated by the reactor protective instrumentation, the ESF automatic actuation logic channels will initiate a reactor trip upon any signal which initiates a safety injection.
This trip is provided to protect the core in the event of a LOCA. The ESF instrumentation channels which initiate a safety injection signal are shown in Table 3.3-3.
Reactor Coolant Pump Breaker Position Trip The Reactor Coolant Pump Breaker Position Trips are anticipatory trips which provide reactor core protection against DNB resulting from the opening of two or more pump breakers above P-7.
These trips are blocked below P-7.
The open/close position trips assure a reactor trip l
signal is generated before the low flow trip set point is reached.
No credit was taken in the accident analyses for operation of these trips.
Their functional capability at the open/close position settings is required to enhance the overall reliability of the Reactor Protection System.
l BEAVER VALLEY - UNIT 1 B 2-8 Amendment No. 29 l
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[h" TABLE 3.3-1 '(Continued) f!
REACTOR TRIP SYSTEM INSTRUMENTATION E
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MINIMUM APPLICABLE TOTAL N0.
CHANNELS CHANNELS gi-FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE P10 DES ACTION j
18.
Turbina Trip J A.#.A to Stop Oil Pressure 3
2 2
l' 7'
B.,
lurbine-Stop Valve Closure 4
4 4
1 8
- 19..SafetyL Injection Input from ESF 2
1 2
1, 2 1
- 20. -Reactor Coolant Pump Breaker
. u, is Pot? ion Trip Abuve P-7 1/ breaker 2
1/ breaker 1
11 o,
' 1, per oper-ating loop 21.
Reactor Trip Breakers 2
1 2
1, 2*
1
- 22. Automatic Trip Logic 2
1 2
1, 2*
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