ML19340E858
| ML19340E858 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 01/05/1981 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19340E859 | List: |
| References | |
| NUDOCS 8101160057 | |
| Download: ML19340E858 (5) | |
Text
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umiso:Taras y
NUCt. EAR REGULATORY COMMisslON s
.g wAsmmaron, o.c.aosas eu THE TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET N0. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No.35 License No. NPF 3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A. The request for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated flovember 18, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Com-mission'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 Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's regulations; 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.
B10 3160 C67
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license
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amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF 3 is hereby amended to read as follows:
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(2) Technical Specifications
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The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 35, are hereby incorporated in the license. The Toledo Edison..
Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment was effective November 17, 1980.
l FOR THE NUCl. EAR REGULATORY COMMISS, ION Robert W. Reid, Chief Operating Reactors Branch i4 Division of ticensing
Attachment:
Changes to the Technical l
Specifications I
Date of Issuance:
January 5,1981 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 35 FACILITY OPERATING LICENSE NO. NPF-3 l
DOCKET NO.50-34E f
Replace the following page of tho Appendix "A" Technical Specifi-cations with the enclosed page as indicated. The revised page is identified by Amendment number and contains a vertical line indi-j cating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
Page 3/4 3-22 t
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TARIE 4.3-2 j
4 SAFETY FEATURES ACTUAil0N SY_ STEM INSTRilMfNTATION SURVEILLANCE REQtilREMENTS O.
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CHANNEL MODES IN WHICH CllANNfL CHANilEL FUNC110NAL SURVEILLANCE
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c FUNCTIONAL UNIT 3
CllECK CAllt, RATION TEST REQUIRED a
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1.
INSTRUMENT STRINGS Containment Radiation - liigh S
R H
A11 MODES a.
b.
Containment Pressure - High S
R M(2) 1, 2, 3 Containment Pressure - High-liigh R
M(2) 1, 2, 3 c.
d.
RCS Pressure - Low S
R H
1, 2, 3 e.
RCS Pressure - Low-Low S
R H
1, 2, 3 f.
BWST Level - Low S
R H
1, 2, 3 2.
OUTPUT LOGIC a.
Incident level #1: Containment M
isolation S
R H
All MODES b.
Incident Level #2: High Pressure Y3 Injection and Starting Diesel Genera tors S
R M
1, 2, 3, 4 c.
Incident Level #3: Low Pressure Injection S
R M
1, 2, 3, 4 d.
Incident Level #4: Containment s
Spray S
R M
1, 2, 3, 4 e.
Incident level #5: Containment Sump Recirculation S
R M
1, 2, 3, 4 3.
MANUAL ACTUATION SFAS (Except Containment Spray NA NA M(1)
All MODES a.
i and Emergency Sump Recirculation) b.
Containment Spray NA NA M(1) 1, 2, 3 4.
SEQUENCE LOGIC CHANNELS S
NA M
1, 2, 3, 4
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G TABLE 4.3-2 1
SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS t
CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 5.
INTERLOCK CHANNELS y
a.
Decay Heat Isolation Valve S
R 1,2.3.4,5 y
b.
Pressurizer Heater S
R 3,4,5 I3 i
- See Specification 4.5.2.d.1 TABLE NOTATION N
Eg (1) Manual actuation switches shall be tested at least once per 18 months.during shutdown. All other circuitry associated with manual safeguards actuation shall receive a CHANNEL FUNCTIONAL g
TEST at least once per 31 days.
Q (2) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by apolying either vacuum or pressure to the appropriate side of the transmitter. The. provisions of Sdction 3.0.3 are not g
applicable for the first test of each channel following the first refueling outage.
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