ML20247C386
| ML20247C386 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/01/1989 |
| From: | Thoma J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247C390 | List: |
| References | |
| NUDOCS 8909130346 | |
| Download: ML20247C386 (5) | |
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UNITED STATES 3-g NUCLEAR REGULATORY COMMISSION 5
l WASHINGTON, D. C. 20555 ks....,o$
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DETROIT EDI M4 COMPANY WOLVERINE POWER SUPPLY COOPERATIVE. INCORPORATED DOCKET NO. 50-341 FERMI-2 AMENCMENT TO FACILITY OPERATING LICENSE Amendment No.40 License No. NPF-43 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Detroit Edison Company (the licensee) dated March 10, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission'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 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 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 40, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. DECO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
e90913o346 890901 FDR ADOCK 05000341 p
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This' license amendment is effective as of its date of issuance with full. implementation.within 90 days from the date'of issuance.
FOR THE NUCLEAR REGULATORY C0tEISSION hn 0. Thoma,. Acting Director Project Directorate 111-1 Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Pegulation u
Attachment:
Changes to.the Technical Specifications Date of Issuance: September 1, 1989 I
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ll ATTACHMENT TO LICENSE AMENDHENT NO. an FACILITY OPERATING LICENSE NO. NPF-43 g
DOCKET NO. 50-341 a
Replace the following page of the Appendix "A" Technical Specifications with-the attached page..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.
REMOVE INSERT-3/4 6-43~
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.o T.ABLE 3.6.3-1 (Continued)
PRIMARY-CONTAINMENT ISOLATION VALVES TABLE NOTATIONS (a) The following is a summary of the parameters which will automatically actuate the Primary Containment Isolation Valve Groups.
The instruments-tion associated with these parameters is described in Specification 3.3.2.
1.
Group 1 - Main Steam System Reactor Vessel Low Water Level - Level 1 Main' Steam Line Radiation - High Main Steam Line Flow - High Main Steam Line Tunnel Temperature - High Main Steam.Line Pressure - Low Condenser Pressure - High Turbine Building Area Temperature - High 2.
Group 2 -' Reactor Water Sample System Reactor Vessel Low Water Level - Level 2 Drywell Pressure - High Main Steam Line Radiation - High 3.
Group 3 - Residual Heat Removal (RHR) System Reactor Vessel Low Water Level - Level 1 Drywell Pressure.- High 4.
Group 4 - Residual Heat Removal Shutdown Cooling and Head Spray Reactor Vessel Low Water Level - Level-3 Reactor Vessel Pressure - High, Shutdown Cooling Interlock 5.
Group 5 - Core spray System Reactor Vessel Low Water Level - Level 1 Drywell Pressure - High 6.
Group 6 - High Pressure Coolant Injection (HPCI) System HPCI : team Line Flow - High HPCi Steam Supply Pressure - Low HPCI Turbine Exhaust Diaphragm Pressure - High i
HPCI Equipment Room Temperature - High 7.
Group 7 - High Pressure Coolant Injection (HPCI) Vacuum Breakers j
Drywell Pressure - High with simultaneous HPCI Steam Supply Pressure - Low l
i FERMI - UNIT 2 3/4 6-44 I
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