ML20148B178
| ML20148B178 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/14/1988 |
| From: | Perkins K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148B182 | List: |
| References | |
| TAC-66006, NUDOCS 8803210369 | |
| Download: ML20148B178 (5) | |
Text
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- p ut:vqk UNITED STATES E
NUCLEAR REGULATORY COMMISSION o-5 E
WASHINGTON, D. C. 20555 TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 110 License No. NPF-3 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated September 29, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amen G d (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 Specifications as indicated in the attachment to this license amendment, and parag aph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
l Technical Specifications l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.110, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
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. 3.
This license amendment is effective as of its date of issuance and shall be implemented not later than the end of the fifth refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
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Kenneth E. Perkins, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V
& Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
March I4, 1988 l
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ATTACHMENT TO LICENSE AMEN 0 MENT NO.110 FACILITY OPERATING LICENSE NO. NPF-3
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DOCKET NO. 50-346 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 Insert 3/4 3-44 3/4 3-44 t
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.o INSTRUMENTATION REMOTE SHUTOOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the control room.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
With the number of OPERABLE remote shutdown monitoring channels a.
less than required by Table 3.3-9, either restore the inoperable channel to OPERABLE status within 30 days, 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 />.
b.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS Each remote shutdown monitoring instrumentation channel snall 4.3.3.5 be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CAllBRATION operations at the frequencies shown in Table 4.3-6.
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l OAVIS-BESSE, UNIT 1 3/4 3-43
TABLE 3.3-9 5
REMOTE SHUTDOWN MONITORING INSTRUMENTATION i
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,~4s MINIMUM READOUT MEASUREMENT c M ELS INSTRUMENT g
LOCATION RANGE OPERABLE 1.
Reactor Trip Breaker Indication (a) 480v F&DC CH. 2 OPEN-CLOSE
.(a) 1 (Trip Breaker A)
Switchgear Room (b) 480v E&DC CH. 1 (b) 1 (Trip Breaker B)
Switchgear Room (c) 480v F6DC CH. 2 (c) 1 (Trip Breaker C)
Switchgear Room u,
(d) CRDC Cabinet Room (d) 1 (Trip Breaker D)
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2.
Reactor Coolant Temperature - Hot Leg Aux. Shutdown Panel 520-620 *F 1
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3.
Reactor Coolant System Pressure Aux. Shutdown Panel 0-3000 psig 1
4.
Pressurizer Level Aux. Shutdown Panel 0-320 inches 1
5.
Steam Generator Outlet Steam Pressure Aux. Shutdown Panel 0-1200 psig 1/ steam generator 6.
Steam Generator Level Startup Range Aux. Shutdown Panel 0-250 inches 1/ steam generator 7.
Control Rod Position Limit Switches Control Rod Drive 0, 25, 50, 75 1/ rod Control Cabinets, and 100%
System Logic si Cabinet #4 Es 5
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