ML20092B933

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Amend 68 to License NPF-3,changing Tech Spec Table 3.3-10, Post-Accident Monitoring Instrumentation, to Specify Two Auxiliary Feedwater Flow Rate Indicators Per Steam Generator
ML20092B933
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 05/30/1984
From: Rivenbark G
Office of Nuclear Reactor Regulation
To:
Cleveland Electric Illuminating Co, Toledo Edison Co
Shared Package
ML20092B937 List:
References
NPF-03-A-068, TAC 53298 NUDOCS 8406200457
Download: ML20092B933 (5)


Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION o

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THE TOLEDO EDISON COMPANY i

i AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE 4

Amendment No.68 License No. NPF-3

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1.

The Nuclear Regulatory Comission (the Comission) has found that:

The application for amendment by The Toledo Edison Company)and A.

The Cleveland Electric Illuminating Company (the licensees dated l

November 21, 1983, 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 of the Act, and the regulations of the Comission; 3

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 conducted in compliance with the Comission's regulations; D.

The issuance of this license amendment will not be inimical to the comon defense and security or_ to the health and safety of the 4

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, 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:

Revise paragraph 2.C.(2) to read as follows:

8406200457 840530 PDR ADOCK 05000346 P

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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 68, 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.

FOR THE NUCLEAR REGULATORY COMMISSION O L/Uftds (th George. Rivenbark, Acting Chief Operating Reactors Branch #4 Division of Licensing

Attachment:

Changes to the Technical Specifications l

Date of Issuance: May 30,1984

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ATTACHMENT TO LICENSE AMENDMENT NO. 68 j

FACILITY OPERATING LICENSE NO. NPF-3 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 a vertical line indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.

Page 3/4 3-48 u_

TABLE 3.3-10 5

Y POST-ACCIDENT 110tilTORING lilSIRlflENTATION m

2N HINIHUN lilSIRLSENT CHANNELS OPERABLE 1.

SG Outlet Steam Pressure 1/ Steam Generator 2.

RC Loop Outlet Temperature 2/ Loop 3.

RC Loop Pressure 2/ Loop 4.

Pressurizer Level 2

5.' SG Startup Range Level 2/ Steam Generator g

6.

Auxiliary Feedwater Status 1/AFW System b

7.

Containment Vessel Hydrogen

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2 8.

Containment Vessel Post-Accident Radiation 2

9.

Containment Vessel Isolation Status 1/ Valve

10. SFAS Status 1/ Channel
11. Safety Features Equipment Status 1/ System
12. RPS Status 1/ Channel
13. SFitCS Status 1/ Channel
14. liigh Pressure injection Flow 1/ Channel

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_1AllLE 3.3-10 (Continued).

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POSI-ACCIDtHT MONil0HillG_lilSIRUNCNlATION IllillHUM lits 1RIMENT CllAllHLi S i

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15. Low Pressure injection (DilR) riow 1/thannel
16. IIPI System Pump and Valve Status 1/ system
17. LPI. System Pump and Valve Status 1/ System Y
18. Containment Spray Pump and Valve Status Y

1/ System

19. Core Flood Valve Status

$5 1/ System

20. BWST Valve Status 1/ System
21. Containment Emergency Sump Valve Status 1/ valve
22. Containment Air Recirculation Fan Status 1/ran
23. Containment Air Cooling Fan Status 1/lan
24. EVS Fan and Damper Status 1/ System 25 Auxiliary Feedwater Flow Rate 2/ Steam Generator 26 RC System S:sbcooling Hargin Monitor j
27. PORV positlon Indicator E

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28. PORV Block Valve Position Indicator j
29. Safety Valve Position Indicator g
30. BWST Level yjy,y9, 3

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