ML20154B534
| ML20154B534 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/21/1998 |
| From: | Kugler A NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20154B538 | List: |
| References | |
| NUDOCS 9810050239 | |
| Download: ML20154B534 (5) | |
Text
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h UNITED STATES l
j NUCLEAR REGULATORY COMMISSION o.
J WASHINGTON, D.C. 20066 4001 5,
e DETROIT EDISON COMPANY 1
DOCKET NO. 50-341 FERMI 2
)
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.129 License No. NPF-43 1.
The Nuclear Regulatory Commission (the Commission) has foui.d that:
A.
The application for amendment by the Detroit Edison Company (the licensee) dated June 5,1998 (NRC-98-0067), as supplemented August 24,1998, 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 rules and regulations of the 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 (;l) that such activities will be conducted in compliance wdh 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 accordan::e with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9810050239 980921 PDR ADOCK 05000341 P
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. 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-43 is hereby amended to read as follows:
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 129
, and the Environmental Protection Plan confeined 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.
3.
This license amendment is effective as of the date of its issuance with full implementation prior to restart from the sixth refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION dL
/
Andrew J. Kugler, Project Manager Project Directorate ill-1 Division of Reactor Projects -Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: September 21, 1998 i
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4 ATTACFJMENTTO LICENSE AMENDMENT NO.129 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications v<ith the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 2-1 2-1 2-2 2-2*
- Overleaf page provided to maintain document completeness. No changes contained on tii. page.
4 i
2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS THERMAL POWER. Low Pressure or low Flow 2.1.1 THERMAL POWER shall not exceed 25% of RATED THERMAL POWER with the reactor vessel steam dome pressure less than 785 psig or core flow less than 4
10% of rated flow.
4 APPLICABILITY: OPERATIONAL CONDITIONS I and 2.
ACTION:
With THERMAL POWER exceeding 25% of RATED THERMAL POWER and the reactor vessel steam dome pressure less than 785 psig or core flow less than 10% of rated flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with the requirements of Specification 6.7.1.
THERMAL POWEP. Hiah Pressure and Hiah Flow
- j 2.1.2 The MINIMUM CRITICAL POWER RATIO (MCPR) shall not be less than the Safety Limit MCPR of 1.11 for two recirculation loop operation and shall not be less than the Safety Limit MCPR of 1.13 for single loop operation with the reactor vessel steam dome pressure greater than 785 psig and core flow grecter i
than 10% of rated flow.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With MCPR less than the Safety Limit MCPR of 1.11 for two recirculation loop operation or less than the Safety Limit MCPR of 1.13 for single loop operation and with the reactor vessel steam dome pressure greater then 785 psig and core flow greater than 10% of rated flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with the requirements of Specification 6.7.1.
REACTOR COOLANT SYSTEM PRESSURE 2.1.3 The reactor coolant system pressure, as measured in the reactor vessel steam dome, shall not exceed 1325 psig.
APPtICABILITY: OPERATIONAL CONDITIONS 1. 2, 3 and 4.
ACTION:
With the reactor coolant system pressure, as measured in the reactor vessel steam dome, above 1325 psig, be in at least HOT SHUTDOWN with reactor coolant system pressure less than or equal to 1325 psig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with the requirements of Specification 6.7.1.
- MCPR values in Technical Specification 2.1.2 are applicable for Cycle 7 l
operation only.
FERMI - UNIT 2 2-1 Amendment No. /J, EJ, JSS. 129
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SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS l
SAFETY LIMITS (Continued)
REACTOR VESSEL WATER LEVEL 2.1.4 The reactor vessel water level shall be above the top of the active l
irradiated fuel.
APPLICABILITY: OPERATIONAL CONDITIONS 3, 4 and 5 i
EllQ!i:
i With the reactor vessel water level at or below the top of the active irradiated fuel, manually initiate the ECCS to restore the water level, after depressurizing the reactor vessel, if required. Comply with the requirements of Specification 6.7.1.
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FERMI - UNIT 2 2-2
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