ML20029E605
| ML20029E605 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/16/1994 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20029E606 | List: |
| References | |
| NUDOCS 9405190160 | |
| Download: ML20029E605 (5) | |
Text
[p* %q UNITED STATES
[.k/f.,tj NUCLEAR REGULATORY COMMISSION
- Q 2J WASHINGTON. D.C. 20555 0001 4.....-
COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-457 BRAIDWOOL STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. NPF-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated April 21, 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 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; 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.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-77 is hereby amended to read as follows:
l 9403190160 940516 l
DR ADOCK 0500 7
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. (2) Ischnical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 51 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No.
NPF-72, dated July 2,1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date if its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION L2/L $.
' jg James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 16, 1994
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f ATTACHMENT TO LICENSE AMENDMENT N0. 51 FACILITY OPERATING LICENSE NO. NPF-77 DOCKET NOS. STN 50-457 Replace the following page of the Appendix "A" Technical Specifications with the attached page.
The revised page is identified by amendment number and contains a vertical line indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
Remove Paaq Insert Pace 3/4 7-1 3/4 7-1 e
0*
i-3/4.7 PLANT SYSTEMS I-3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line Code safety valves. associated with each steam generator shall be OPERABLE with lift settings as specified in Table 3.7-2.
APPLICABILITY: MODES 1, 2, and 3.
j ACTION:
a.
With four reactor coolant loops and associated steam generators in operation and with one or more main steam line Code safety valves inoperable, operation in MODES 1, 2, and 3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpoint is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE_QUIREMENTS 4.7.1.1 No additional requirements other than those required by Specification 4.0.5.
The provisions of Specification 4.0.4 are not applicable for Braidwood, j
Unit. 1, Cycle 5, until the initial entry into MODE 2.
The provisions of Specification 4.0.4 are not applicable for Braidwood, Unit 2, until the initial entry into Mode 2 following forced outage A2F27.
i BRAIDWOOD - UNITS 1 & 2 3/4 7-1 UNIT 2 - AMENDMENT NO 51
TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGL NEUTRON FLUX HIGH SETPOINT WITH JNOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP OPERATION MAXIMUM NUMBER OF INOPERABLE MAXIMUM ALLOWABLE POWER RANGE SAFETY VALVES ON ANY NEUTRON FLUX HIGH SETPolNT OPERATING STEAM GENERATOR (PERCENT OF RATED THERMAL POWER) 1 87 2
65 3
43
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BRAIDWOOD - UNITS 1 & 2 3/4 7-2