ML20116N261
| ML20116N261 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/24/1985 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20116N264 | List: |
| References | |
| NUDOCS 8505070084 | |
| Download: ML20116N261 (5) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
a j
WASMNGTON, D. C. 20555 s.,.....,f DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 92 License No. DPR-66 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.-
-The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated November 14, 1984 and revised by letter dated March 8,1985, 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; 8.
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 (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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
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 amended to read as follows:
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' l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 92, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amendment is effective on issuance, to be implemented within 30 days of issuance.
FOR THE NUC ULATORY COMMISSION P
- hrda, f
ven perating Reactors B anch #1 Division of Licens l
Attachment:
Changes to the Technical Specifications Date of Issuance: April 24, 1985 t
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 92 TO FACILITY OPERATING LICENSE N0. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 4-2b 3/4 4-2b B 3/4 4-1 B 3/4 4-1 t
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1 REACTOR COOLANT SYSTEM HOT STAND 8Y LIMITING CONDITION FOR OPERATION 3.4.1.2 a.
At least two reactor coolant loops and associated steam generators and reactor coolant pumps shall be in operation
- when the rod control system is capable of control bank rod r
withdrawal.
b.
At least two reactor coolant loops and associated steam j
generators and reactor coolant pumps shall be OPERABLE and one reactor coolant loop shall be in operation
- when the rod control system is incapable of control bank rod withdrawal.
i.
i APPLICABILITY:
MODE 3
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ACTION:
a.
With less than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i' "WEth less than two reactor coolant loops in operation, insnediately
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b.
de-energize all control rod drive mechanisms, or align the rod I
control system so that it is incapable of control bank rod i
withdrawal.
'l c.
With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and inunediately initiate corrective action to return the i
j required coolant loop to operation, i
SURVEILLANCFsAEQUIREMENTS j
4.4.1.2.1 With the rod centrol system capable of rod withdrawal, at least two cooling. loops shall be verified to be in operation and circJlating reactor coolant at least.once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4.1.2.2 With the rod control system incapable of rod withcrawal, at least
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two cooling Roops, if not in operation, shall be determined to be OPERABLE j
once per 7 days by verifying correct breaker alignments and indicated power j
availability.
i 4.4.1.2.3 With the rod control system incapable of rod withdrawal, at least one cooling loop shall be verified.to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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All reactor coolant pumps may be de-energized for up to I hour provided (1)
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no operations are permitted that would cause dilution of the reactor coolant system boron concentration and (2) core outlet temperature is maintained at least 10*F below saturation temperature.
This does not preclujie natural circulation cooldown under abnormal cooldown conditions.
BEAVER VALLEY - UNIT 1 3/4 4-2b Amendment No. 92 1
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3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS The plant is designed to operate with all reactor coolant loops-in i
operation and maintain DNBR above 1.30 during all normal operations and anticipated transients.
In Modes 1 and 2, with one reactor coolant loop not in operation, THERMAL POWER is restricted to < 31 percent of RATED THERMAL POWER until the Overtemperature AT trip is reset. Either action ensures that the DNBR will be maintair.ed above 1.30.
A loss of flow in two loops will cause a reactor trip if operating above P-7 (11 percent of RATED THERMAL POWER) while a loss of flow in one loop will cause a reactor trip if operating above P-8 (31 percent of RATED THERMAL POWER).
In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, due to the initial conditions assumed in the analysis for the control rod bank withdrawal from a subcritical condition, two operating coolant loops are required to meet the DNB design basis for this Condition II event.
In h00ES 4 and 5, a single reactor coolant loop or RHR subsystem provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops be OPERABLE.
Thus, if the reactor coolant loops are not OPERABLE, this specification requires two RHR loops to be OPERABLE.
The operation of one Reactor Coolant Pump or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System.
The reactivity change rate associated with boron reduction will, therefore, be within the capability of operator recognition and control.
The restrictions on starting a Reactor Coolant Pump with one or more RCS cold legs less than or equal to 275'F are provided to prevent RCS pre'ssure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to 10 CFR Part 50.
The RCS will be protected against overpressure transients and will not exceed the limits.
BEAVER VALLEY - UNIT 1 B 3/4 4-1 Amendment 30.'92 i
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