ML20114B934
| ML20114B934 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/24/1992 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20114B937 | List: |
| References | |
| NUDOCS 9208310366 | |
| Download: ML20114B934 (9) | |
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UNITED STATES 5
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NUCLEAR REGULATORY COMMISSION o,
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WASHINGTON. D.C. 20556 3
TOLEF0 EDISON COMPANY CENTER 10R SERVICE COMPANY fEQ THE CLEVELAND ELECTRIC ILLUMINATING COMPANY i
DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.172 License No. NPF-3 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Toledo Edison Company, Centarior Service Company, and the Cleveland Electric Illuminating Company (the licensees) dated February 2, 1990, 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 af the Act, and the rules and regulations of the i
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 paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
9208310366 920824 PDR ADOCK 05000346 P
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2 (a) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.172, 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 90 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
Jon B. Hopkins, Sr. Project Manager Project Directorate 111-3 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: August 24, 1992
i ATTACHMENT TO LICENSE AMENDMENT NO.172
((,CILITY OPERATING LICENSE NO. NPF-3 DOCKET N0. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are_ identified by amendment number and contain vertical lines _ indicating the area of change.
The corresponding
~
overleaf pages are also provided to maintain document completeness.
Remove Insert 3/4 3-48 3/4 3-48 3/4 3-48a 3/4 3-50 3/4 3/50 3/4 9-2 3/4 9-2 l
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T_ABL E,.3. 3-10 POST-ACCIDENT MONITORING INSTRUMENTATION Di f,
MINIMUM CHANNELS E
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INSTRUMENT OPERABLE r$
1.
SG Outlet Steam Pressure 1/ Steam Generator Er; 2.
RC Loop 0utlet Tenperature 2/ Loop 3.
RC Loop Pressure 2/ Loop 4.
Pressurizer Level 2
5.
SG Startup Range level 2/ Steam Generator 6.
Containment Vessel Post-Accident Radiation 2
u, 2
i 7.
Pigh Pressure Injection Flow 1/ Channel 9,
5 8.
' Low Pressure Injection (DHR) Flow 1/ Channel 4
9.
Auxiliary Feedwater Flow Rate 2/ Steam Generator
- 10..RC System Subcooling Margin Monitor 1
11.
PORV Position Indicator 1
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12.
PORV Block. Valve Position Indicator 1
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Pressurizer Safety Valve' Position Indicator 1/ Valve f
14.
BWST. Level 3
15.
Containment Normal Sump Level 1
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Containment Wide Range. Water Level 1
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INSTRUMENT OPERABLE C*
17.
Containment Wide Range Pressure 1
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18.
Intere Thermocouples 2 per core quadrant 19.
Reactor Coolant Hot Leg Level (Vide Range) 1 20.
Heutron Flux (Wide Rarge) 1 21.
Neutron Flux (Source Rarige) 1
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3/4.9 REFbELING OPERATIONS BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 The boron concentration of all filled porti0ns of the Reactor Coolant l
System and the refueling canal shall be maintained uniform and sufficient to
! ensure tnat the more restrictive of the following reactivity conditions is met:
Either a K@ allowance for uncertainties, or of 0.95 or less, which includes a 1l.2.k/k a.
conservati b.
A boron concentration of 1 1800 ppm, which includes a 50 ppm conservative allowance for uncertainties.
i APPL _ICABILITY:
MODE 6.
l l ACTION:
- + With the requirements of the above specification not satisfied, i' mediately
'I suspend all operations involving CORE Al.TERATIONS ar positive reactivity I changes and initiate and continue boration at 1 10 gpm of 8/50 ppm boric acid solution or its equivalent until K is reduced to 1 0.95 or the boron eff concentration is restored to t 1800 ppm, whichever is the more restrictive.
ll,TheprovisionsofSpecification3.0.3arenotapolicable.
li I!
! ! S_U3VEILLANCE REQUIRE'4ENTS 1i l
! 4.9.1.1 The more restrictive of the above two reactivity cond;,'ons s%I1 be
, determined prior to:
a.
Removing or unholting the reactor vessel-head, ard b.
Withdrawal of any safety or regulating rod in excess of 3 feet from its fully inserted position within the reactcr pressure vessel.
4.9.1.2 The boron concentration of the reactor pressure vessel and the refuelir.g canal shall be determined 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 />.
I i
DAVIS-BESSE, UNIT 1 3/4 9-1 Amendment No. 143
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l REFUELING OPERATIONS 4
j LNSTRUMENTATION 1
l LIMITING CONDITION FOR OPERATION i
i 3.9.2 As a minimum, two source range neutron flux monitors, one from each siue of the reactor core, shall be operating, each with continuous -visual indication in the control room and one with audible indication in the contain-ment and control room.
3 APPLICABILITY:
MODE 6.
1 f
FACTION:
i
-l Witn the requirements of the above specification ~ not satitfied, immediately t suspend all operations involving CORE ALTERATIONS er positive rcactivity i
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'Ichanges.
The provisions of Specification 3.0.3 are not applicable.
I 1
1 l
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l: SURVEILLANCE REQUIREMENTS
'i l
l 4.9.2 As a minimum, two source range neutron flux monitors, one from each side of the reactor core, shall be demonstrated OPERABLE by performance of:
a.
A CHANNEL FUNCTIONAL TEST at least once per 7 days, and i
l 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, cnd 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.
l c.
A CHANNEL CALIBRATION prior to entry into MODE 6 if not performed I
t within the last 18 month.
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DAVIS-BESSE, UNIT 1 3/4 9-2 Ameadment No.172 I
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