ML20052D543
| ML20052D543 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/12/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Toledo Edison Co, Cleveland Electric Illuminating Co |
| Shared Package | |
| ML20052D547 | List: |
| References | |
| NPF-03-A-044 NUDOCS 8205060573 | |
| Download: ML20052D543 (5) | |
Text
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8 N
UNITED STATES
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NUCLEAR REGULATORY COMMISSION ht WASHINGTON, D. C. 20555
%Y THE TOLEDO EDISON COMPANY
....+
AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. NPF.3 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 March 23, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amende,d (the Act) and the Commission'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 Comission; 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 (ii) that such activities will be conductad 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.
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2.
Accordingly, Facility Operating License No. NPF-3 is hereby amended as indicated below and by changes to the Technical Specifications as indicated in the attachment to this license amendment:
J Revise paragraph 2.C.(2) to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.44,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 the date of its issuance.
FOR THE NUCLEAR REGUL TORY COMMISSION
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]Y, oh
. Stolz, Chief Ope 'ating Reactors Branch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications l
Date of Issuance:
April 12,1982 i
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ATTAC!"4ENT TO LICENSE N4ENDMENT N0. 44
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FACILITY OPERATING LICENSE NO. NPF-3 1
DOCKET NO. 50-346 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by Amendment number and contains vertical lines indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
7 Page 3/4 3-19 i
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TABLE 3.3-5 (Continued)
RAFETY FEATURES SYSTEM RESPOUSE TIMES RESPONSE TIME IN SECONDS _
II:ITIATIt:G SIGi?AL AND FUNCTION _
4.
CCS Pressure-Lou (continued) 1.
Containment Isolation Valves 1.
Vecuum Relief
< 30*
7 25*
2.
Normal Sump 3.
RCS Letdown Delay Coil Outlet i30*
< 30*
4.
RCS Letdown High Tcmperature 7 45*
5.
Pressurizer Sample 6.
Service Water to Cooling Water 7 45*
7 15*
7.
Vent Header 7 15*
8.
Drain Tank 7 15*
9.
Core Flood Tank Vent 7 15*
10.
Core Flood Tank Fill 11.
Steam Generator Sample 7 15*
7 17*
12.
Atmospheric Vent 7 15*
13.
Quench Tank 14.
Emergency Sump NA*
1 15*
15.
Air Systems 16.
N System 1 15*
17.
Quench Tank Sample 1 35*
2 18.
Main Steam Warmup Drain 1 15*
19.
Core Flood Tank Sample 1 15*
20.
RCP Standpipe Demin Water Supply 1 15*
21.
Containment H Dilution Inlet
< 7 5*
22.
Containment H Dilution Outlet i 75*
j.
BWST Outlet Valves NA*
5.
RCS Prassure--Low-Low a.
Low Pressure Injection
< 30*
1.
Decay Heat Pumps 2'.
Low Pressure Injection Valves 7 NA*
3.
Decay Heat Pump Suction Valves 7 NA*
4.
Decay Heat Cooler Outlet Yalves 7 NA*
5.
Decay Heat Cooler Bypass Valves iNA*
b.
Component Cooling Isolation Valves 1.
Auxiliary Equipment Int
< 90*
~
2.
Inlet to Air Compresso, 7 90*
3.
Component Cooling from Decay Heat Cooler 5NA*
c.
Containment Isolation Valves
< 45*
I-RCP Seal Return 2-Makeup 530*
3.
RCP Seal Inlet l 'i7*
DAVIS-BESSE, UNIT 1 3/4 3-19 Amendment No. 44
l TABLE 3.3-5 (Continued)
SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 6.
Containment Radiation - High a.
Emergency Ven.t fans
< 25*
b.
ECCS Room
< 75*
2.
Emergency Ventilation II75*
3.
Containment Air Sample 7 30*
4.
Containment Purge li 15*
5.
Penetration Room Parge
][ 75*
c.
< 10*
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1 TABLE NOTATION Diesel generator starting and sequence loading delays included when applicable.
Response time limit includes movement of valves and attainment of pump or blower discharge pressure.
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l DAVIS-BESSE, UNIT 1 3/4 3-20 Amendment No. 40
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.JUN 1 198I
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