ML20101M190
| ML20101M190 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/20/1984 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Toledo Edison Co, Cleveland Electric Illuminating Co |
| Shared Package | |
| ML20101M193 | List: |
| References | |
| NPF-03-A-082 NUDOCS 8501020518 | |
| Download: ML20101M190 (5) | |
Text
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UNITED STATES
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TOLED0 EDISON COMPANY g
AND THE CLEVELAND ELECTRIC ILLUPINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. NPF-3
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e 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 December 3, 1984, 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 Comission's regulations; D.
The issuance of triis 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 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. NPF-3 is hereby 0
amended to read as follows:
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Technical Specifications g
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 82
, are hereby incorporated in the license. The Toledo Edison Corpany shall operate the facility in accordance with
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the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
4 FOR THE NUCLEAR REGULATORY COMMISSION j
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lF. Stolz, Chief I
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Att ichment:
Cnr 'es to the Technical Sp! #ications Date of Issuance: December 20, 1984 t
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f ATTACHMENT TO LICENSE AMENDMENT NO.82 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 t
Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and h
contains a vertical line indicating the area of change. The corresponding overleaf page is also provided to maintain document completeniss.
Page
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1.0 DEFINITIONS
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DEFINED TERMS d
1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.
THERMAL POWER f
1.2 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
RATED THERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2772 MWt.
OPERATIONAL MODE
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1.4 An OPERATIONAL MODE shall correspond to any one inclusive combina-tion of core reactivity condition, power level and average reactor l-coolant temperature specified in Table 1.1.
I ACTION r
I 1.5 ACTION shall be those additional requirements specified as corollary statements to each principle specification and shall be part of the i
specifications.
OPERABLE - OPERABILITY 1.6 A system, subsystem, train, component or device shall be OPERABLE or I
have OPERABILITY when it is capable of performing its specified function (s).
Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power I
sources, cooling or seal water, lubrication or other auxiliary equipment, l
that are required for the system, subsystem, train, component or device t
to perform its function (s), are also capable of performing their related support function (s). Prior to entering MODE 1 for Cycle 5, auxiliary feedwater system OPERABILITY shall be determined without consideration i
of the status of the startup feedwater system.
i DAVIS-BESSE, UNIT 1 1-1 Amendment No. 82 p
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DEFINITIONS t
REPORTABLE OCCURRENCE 1.7 A REPORTABLE OCCURRENCE shall be any of those conditions specified in Specifications 6.9.1.8 and 6.9.1.9.
CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:
a.
All penetrations required to be closed during accident con-ditions are either:
1.
Capable of being closed by the Safety Features Actuation System, or 2.
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-2 of Specification 3.6.3.1.
b.
All equipment hatches are closed and sealed, c.
Each airlock is OPERABLE pursuant to Specification 3.6.1.3, d.
The containment leakage rates are within the limits of Specificatlon 3.6.1.2, and The scaling mechanism associated with each penetration (e.g.,
e.
welds, bellows or 0-rings) is OPERABLE.
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CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
CHANNEL CALIBRATION may be performed by any series of sequential, over-lapping or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of chahnel behavior during operation by observation. This determination shall.
include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
DAVIS-BESSE, UNIT 1 1-2
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