ML20005E375
| ML20005E375 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/29/1989 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20005E376 | List: |
| References | |
| NUDOCS 9001050147 | |
| Download: ML20005E375 (5) | |
Text
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UNITED STATES
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8 NUCLEAR REGULATORY COMMISSION -
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TOLEDO.EDISDN. COMPANY AN_g THE. CLEVELAND. ELECTRIC.1LLUMINATING COMPANY DOCKETNO.50-3%
DAVIS-DESSE.WUCLEAR POWER' STATION d j,T.WO. 1 AMENDNENT.TO FACILITY 0PERATING. LICENSE 4
Amendment No.143 i
i License No. NPF-3 ll' 1.
The Nuclear Regulatory Comission (the Comission) has found that:
l' A.
The application for amendment by the Toledo Edison Company and The Cleveland Electric. Illuminating Company (the licensees) dated January 4, 1988, complies with the standards and requirements of the Atomic Energy. Act of 1954, as amended (the Act), and the Comission's rules 1
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 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 y
conducted in compliance with the Comission's regulations; D.
The issuance of this anendment 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 amenced 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 amended to read as follows:
9001050147 691229 PDR ADOCK 05000346 P
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2 (a)' Technical.Specif.ications The Technical Specifications contained in Appendix A, as revised through Amendment-No.-143, 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 its date of issuance and shall be implemented not later than 45 days after-issuance.
FOR THE NUCt. EAR REGUt.ATORY COMMISSION 4W L John N. Hannon, Director Project Directorate 111-3 Division of Reactor Projects - III, IV, V, & Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: -December 29, 1989
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ATTACHMENT TO LICENSE AMENDMENT NO.143
,F,ACILITY.0PERAT1WG. LICENSE NO. NPF-3 1
J DOCKET WO. 50 346 Replace the followino page of the Appendix 'A" Technical Specifications with the attached page. The revised page is identified by amendment number and contains vertical lines indicating the area of change. The corresponding overleaf page is also provideo to reintain document completeness, temove insert 3/4 9-1 3/491 v
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o 3/4.9 REFUELING OPERATIO!!S, BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 The boron concentration of all filled portions of the Reactor Coolant l
System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:
a.
Either a K conservatifbfof0.95orless,whichincludesa1%ak/k allowance for uncertainties, or b.
A boron concentration of L 1800 ppm, which includes a 50 ppm conservative allowance for uncertainties.
APPLICABILITY: H0DE 6.
l ACTION:
With the. requirements of the above r. pet:lfi:ation not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at 1 10 gpm of 8750 ppm boric acid solution or its equivalent until K ggf is reduced to 1 0.95 cr the boron concentration is restored to 1 1800 ppm, whichever is the more restrictive.
The previsions of Spe;1fice. tion 3.0.3 are not applicable.
SURVEILLANCE _RE')UIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:
a.
Removing or unbolting the reactor vessel head, and b.
Withdrawal of any safety or regulating rod in excess of 3 feet from its fully inserted position within the reactor pressure vessel.
4.9.1.2 The boron concentration of the reactor pressure vessel and the refueling canal shall be detemined by chemical analysis at least once each 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
DAVIS-BESSE, UNIT 1 3/4 9-1 Amendment No. 1C
REFUELING OPERATIONS INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two source range neutron flux monitors shall be operating, each with continuous visual indication in the control room and one with audible indication in the containment and control room.
APPLICABILITY: MODE 6.
i ACTION:
8 With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity l
changes. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREl'ENTS 4.9.2 Each source rangt nrutron flux menitor shall be demonstrated OPERABLE by performance ef:
a.
A CHANNEL FUNCTIONAL TEST at lecst once per 7 days, and b.
A CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of CORE ALTERATIONS, and c.
A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS.
DAVIS-BESSE, UNIT 1 3/4 9-2