ML20081L454
| ML20081L454 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/03/1983 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Toledo Edison Co, Cleveland Electric Illuminating Co |
| Shared Package | |
| ML20081L456 | List: |
| References | |
| NPF-03-A-064 NUDOCS 8311160270 | |
| Download: ML20081L454 (2) | |
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UNITEC STATES
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NUCLEAR REGULATORY COMMisslON
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?b THE TOLEDO EDISON COMPANY
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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. NPF-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by The Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated July 10,1981, as supplemented March 21, 1983, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assura~nce (1) that the activities authorized by this amendment dan be cond0cted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's Ngulations; 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.
8311160270 831103 PDR ADOCK 05000346 P
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-2 2.
Accordingly Facility Operating License No. NPF-3 is hereby amended as indicated below and by changes to the Technical Specifications as indicated in the attachment to this license amendment:
Revise paragraph 2.C.(2) to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.64. are hereby incorporated in the license.
The Toledo Edison Company 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 J6 n F. Stolz, Chief Op rating Reactors Branch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of issuance:
November 3, 1983 t
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ATTt.CHMENT TO LICENSE AMENDMENT NO. 64 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 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 area of change. The corresponding overleaf page is also provided to maintain document completeness.
Page 3/4 2-13 e
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9 P'0WER DISTRIBUTION LIMITS DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB related parameters shall be maintained within the limits shown on Table 3.2-1.
a.
Reactor Coolant Hot Leg Temperature b.
Reactor Coolant Pressure c.
Reactor Coolant Flow Rate APPLICABILITY: MODE 1 ACTION:
If parameter a or b above exceeds its limit, restore the parameter to within its limit.within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
If parameter c exceeds its limit, either:
1.
Restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or 2.
Limit THERMAL POWER at least 2% below RATED THERMAL POWER for each 1%
parameter c is outside its limit for four pump operation within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or limit THERMAL POWER at least 2% below 75% of RATED THERMAL POWER for each 1% parameter c is outside its limit for 3 pump operation within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.2.5.1 Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.2.5.2.The Reactor Coolant System total flow rat'e shall be determined to be within its -limit by measurement at least once per.18 months.
DAVIS-BESSE, UNIT 1 3/4 2-13 Amendment No. 64 l
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