ML20203M573
| ML20203M573 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/25/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20203M576 | List: |
| References | |
| NUDOCS 8605010584 | |
| Download: ML20203M573 (5) | |
Text
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%o, UNITED STATES f' 1
. G.!d [
'n WASHINGTON, D. C. 20555 NUCLEAR REGULATORY COMMISSION j,d.. g i
e
\\f....*f DETROIT EDISON COMPANY WOLVERINE POWER StlPPLY COOPERATIVE, INCORPORATED DOCKET NO. 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 1 License No. NPF-43 1.
The Nuclear Reculatory Comission (the Commission or the NRC) having found that:
A.
The application for amendment filed by the Detroit Edison Company (the licensee), dated December 23, 1985, as supplemented by letters dated February 4, 1986, and April 23, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's regulations set forth in 10 CFR Chapter I; R.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endancerir.g the health and safety of the oublic, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR 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 Commission'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 the Facility Operating License No. NPF-43 is hereby amended to read as follows:
(2) Technical Specifications and Envirorrnental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 1, 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 8605010584 860425 PDR ADOCK 05000341 P
_2 3.
This amendment is effective as of date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
- : =-
Elinor G. Adensam, Director BWR Pro.iect Directorate No. 3 Division of BWR Licensing
Enclosure:
Chances to the Technical Specifications Date of Issuance: April 25,1985 i
P
s ENCLOSURE TO LICENSE AMENDMENT NO. 1 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
(
REMOVE INSERT 3/4 3-44 3/4 3-44 3/4 9-4 3/4 9-4 I
)
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I fr -
TABLE 3.3.6-2 CONTROL R0D BLOCK INSTRUMENTATION SETPOINTS TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE-E 1.
ROD BLOCK MONITOR E
a.
Upscale
< 0.66 W + 40%*
< 0.66 W + 43%*
b.
Inoperative HA HA g
c.
Downscale
> 5% of RATED THERMAL POWER
> 3% of RATED THERMAL POWER Z
2.
APRM a.
Flow Biased Neutron Flux - High
< 0.66 W + 42%*
< 0.66 W + 45%*
b.
Inoperative NA HA c.
Downscale
> 5% of RATED THERMAL POWER
> 3% of RATED THERMAL POWER d.
Neutron Flux - Upscale, Setdown 512%ofRATEDTHERMALPOWER 514%ofRATEDTHERMALPOWER 3.
SOURCE RANGE MONITORS a.
Detector not full in NA NA b.
Upscale
$ 1.0 x 105 cps 5 1.6 x 105 cps c.
Inoperative NA NA d.
Downscale
> 3 cps **
> 2 cps **
4.
a.
Detector not full in NA NA w
b.
Upscale
< 108/125 divisions of
< 110/125 divisions of j
full scale Tull scale c.
Inoperative NA NA d.
Downscale
> 5/125 divisions of
> 3/125 divisions of uH scale Tun scale 5.
Water Level-High
< 589'11 "
< 591'0" b.
Scram Trip Bypass NA NA 6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW Ng a.
Upscale i 108/125% of rated flow
< 111/125% of rated flow g
b.
Inoperative NA NA g
c.
Comparator i 10% flow deviation i 11% flow deviation
[
7.
REACTOR MODE SWITCH SHUTDOWN POSITION NA NA
- The rod block function is varied as a function of recirculation loop drive flow (W).
The trip setting
~
of this function must be maintained in accordance with Specification 3.2.2.
- The downscale rodblock setpoint count rate may be reduced to 0.3 cps prior to achieving a burnup of 2000 MWD /T on the first core provided the signal-to-noise ratio is >2.
After a burnup of 2000 MWD /T on the first core, the count rate may be reduced to 0.7 cps provided the signal-to-noise ratio is >2.
../
REFUELING OPERATIONS SURVEILLANCE REQUIREMENTSt(Continued) b.
Performance of a CHANNEL FUNCTIONAL TEST:
1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the start of CORE ALTERATIONS, and 2.
At least once per 7 days.
c.
Verifying that the channel count rate is at least 0.7* cps:
1.
Prior to control rod withdrawal, 2.
Prior to and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS, and 3.
At least onc.e per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d.
Verifying, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if during, that the RPS circuitry " shorting links" have been removed during the time any control rod is withdrawn ** unless adequate shutdown margin has demonstrated per Specification 3.1.1.
- For only the fuel movements required to replace neutron sources, the count rate may be reduced to 0.3 counts per second prior to achieving a burnup of 2000 MWD /T on the first core provided the signal-to-noise ratio >2.
After a burnup of 2000 MWD /T, the count rate must be at least 0.7 cps provided the signal-to-noise ratio is >2.
Otherwise, 3 cps.
- Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.
e FERMI - UNIT 2 3/4 9-4 Amendment No. 1 322-I