ML20213A603
| ML20213A603 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 01/28/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20213A605 | List: |
| References | |
| NUDOCS 8702030387 | |
| Download: ML20213A603 (5) | |
Text
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D. C. 20555 q
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DETROIT EDISON COMPANY WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED DOCKET NO. 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 License No. NPF-43 1.
The Nuclear Regulatory Comission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Detroit Edison Company (DECO or the licensee), dated September 30, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's 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 reculations of the Comission; C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endancerino the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFD Chapter I; 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 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 enclosure to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
5, 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.
I 8702030387 87o128 PDR ADOCK 05000341 P
4 3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4g5-
?nW + - -
Elinor G. Adensam, Director BWR Project Directorate No. 3 Division of PWR Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance:
January 28, 1987
O e
ENCLOSURE TO LICENSE AMENDMENT NO. g_
FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicatino the area of change. The corresponding overleaf page is also provided to maintain document completeness.
REMOVE INSERT 3/4 1-9 3/4 1-9 (overleaf pagei 3/4 1-10 3/4 1-10
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4 REACTIVITY CONTROL SYSTEMS CONTROL R0D SCRAM ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.1.3.5 All control rod scram accumulators shall be OPERABLE.
APPLICABILITYf OPERATIONAL CONDITIONS 1, 2, and 5*.
ACTION:
a.
In OPERATIONAL CONDITION 1 or 2:
1.
With one control rod scram accumulator inoperable, within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s:
a)
Restore the inoperable accumulator to OPERABLE status, or b)
Declare the control rod associated with the inoperable accumulator inoperable.
Otherwise, 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 />.
2.
With more than one control rod scram accumulator inoperable, declare the associated control rods inoperable and:
a)
If the control rod associated with any inoperable scram accumulator is withdrawn, immediately verify that at least one control rod drive pump is operating by inserting at least one withdrawn control rod at least one notch.
If no control rod drive pump is operating:
- 1) If react' r pressure o
is > 900 psig, restart at least one control rod drive pump witIiin 20 minutes or place the reactor mode switch in the Shutdown position.
- 2) If reactor pressure is < 900 psig, place the reactor mode switch in the Shutdown position.
b)
Insert the inoperable control rods and disarm the associated control valves either:
1)
Electrically, or 2)
Hydraulically by closing the drive water and exhaust water isolation valves.
Otherwise, 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 />, b.
In OPERATIONAL CONDITION 5*:
1.
With one withdrawn control rod with its associated scram accumulator inoperable, insert the affected control rod and disarm the associated directional control valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, either:
a)
Electrically, or b)
Hydraulically by closing the drive water and exhaust water isolation valves.
2.
With more than one withdrawn control rod with the associated scram accumulator inoperable and no control rod drive pump oper-ating, immediately place the reactor mode switch in the Shutdown position.
i c.
The provisions of Specification 3.0.4 are not applicable.
- At least the accumulator associated with each withdrawn control rod.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
FERMI - UNIT 2 3/4 1-9
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.3.5 Each control rod scram accumulator shall be determined OPERABLE:
a.
At least once per 7 days by verifying that the indicated pressure is greater than or equal to 940 psig unless the control rod is inserted and disarmed or scrammed.
b.
At least once per 13 months by:
1.
Performance of a:
a)
CHANNEL FUNCTIONAL TEST of the leak detectors, and b)
CHANNEL CALIBRATION of the pressure detectors, and verifying an alarm setpoint of greater than or equal to 940 psig on decreasing pressure.
2.
Measuring and recording the time for at least 10 minutes that each individual accumulator check valve maintains the asso-ciated accumulator pressure above the alarm set point with no control rod drive pump operating.
5 FERMI - UNIT 2 3/4 1-10 Amendment No. 5
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