ML20237D200
| ML20237D200 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/31/1998 |
| From: | Kugler A NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20237D202 | List: |
| References | |
| NUDOCS 9808250139 | |
| Download: ML20237D200 (5) | |
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- 4 UNITED STATES a
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NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D.C. ma "1 DETROIT EDISON COMPANY DOCKET NO. 50-341 FERMI 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.123 License No. NPF-43 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Detroit Edison Company (the licensee) dated January 28,1998, as supplemented March 12 and June 9,1998, 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 (ii) that such activities will be conducted in compliance with 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 accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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9808250139 980731 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 Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 123, 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.
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 6'
Andrew J. Kugler, Project Manager Project Directorate ill-1 Division of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: July 31, 1998 l
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ATTA.CHMENT TO LICENSE AMENDMENT NO.123 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain verticallines indicating the area of change.
REMOVE INSERT 3/4 4-7 3/4 4-7 B 3/4 4-1a B 3/4 4-ia
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3/4.4.2 SAFETY / RELIEF VALVER SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION l
3.4.2.1 - The safety valve function of at least 11 of the following reactor coolant system safety / relief valves shall be OPERABLE with the specified code safety valve function lift settings:*
5 safety / relief valves 91135 psig i3%
5 safety / relief valves 9 1145 psig 13%
5 safety / relief valves 91155 psig 23%
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
a.
With the safety valve function of less than 11 of the above safety / relief valves OPERABLE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With one or more safety / relief valves stuck open, provided that suppression pool average water temperature is less than 95'F, close the stuck open safety / relief valve (s); if unable to close the stuck open valve (s) within 2 minutes or if suppression pool average water temperature is 95'F or greater, place the reactor mode switch in the Shutdown position.
With one or more safety / relief valve position indicaters inoperable, c.
restore the inoperable indicator (s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN. within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, i
SURVEILLANCE RE0VIREMENTS j
4.4.2.1.1 The valve position indicator for each safety / relief valve shall be demonstrated OPERABLE with the pressure setpoint of each of the tail-pipe pressure switches verified to be 3015 psig by performance of a CHANNEL CALIBRATION at least once per 18 months.
4.4.2.1.2 At least 1/2 of the safety relief valves shall be set pressure tested at least once per 18 months, such that all 15 safety relief valves are j
set pressure tested at least once per 40 months.
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- The lift setting pressure shall correspond to ambient conditions of the 1
valves at nominal operating temperatures and pressures. Although the as-found lift setting tolerance is $3%, the as-left lift settings shall be within 1% of the specified setpoints prior to installation following testing.
FERMI - UNIT 2 3/4 4-7 Amendment No. A7,123 L
3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 RECIRCULATION SYSTEM (Continued)
Sudden equalization of a temperature difference greater than 145'F between the reactor vessel bottom head coolant and the coolant in the upper region of the reactor vessel by increasing core flow rate would cause undue stress in the reactor vessel bottom head.
Requirements are imposed to prohibit idle loop startup above the 77% rod line to minimize the potential for initiating core thermal-hydraulic instability.
3/4.4.2 SAFETY / RELIEF VALVES The safety valve function of the safety / relief valves operate to prevent the reactor coolant system from being pressurized above the Safety Limit of 1325 psig in accordance with the ASME Code. A total of 11 OPERABLE safety / relief valves is required to limit reactor pressure to within ASME III j
allowable values for the worst case upset transient.
Demonstration of the safety / relief valve lift settings will occur only during shutdown and will be performed in accordance with the provisions of Specification 4.0.5.
Although the safety / relief valves are tested to demonstrate that opening pressures are within 23% of the nominal pressure setpoints, they are adjusted to within il% of the nominal pressure setpoints prior to reinstallation.
The low-low set system ensures that a potentially high thrust load (designated as load case C.3.3) on the SRV discharge lines is eliminated during subsequent attuations.
This is achieved by automatically lowering the closing setpoint of two valves and lowering the opening setpoint of two valves following the initial opening.
Sufficient redundancy is provided for the low-low set system such that failure of any one valve to open or close at its reduced setpoint does not violate the design basis.
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l FERMI - UNIT 2 B 3/4 4-la Amendment No. )), 57,123