ML20151P040
| ML20151P040 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/05/1988 |
| From: | Virgilio M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151P044 | List: |
| References | |
| NUDOCS 8808090165 | |
| Download: ML20151P040 (5) | |
Text
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quo vy' 'o, UNITED STAT ES
'n NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 205s5
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DETROIT EDISON COMPANY WOLVERINEPOWERSUPPLYCOOPERATIVE,INCORPORATR DOCKET NO. 50-341 FERMI-2
_ AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.2 7 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 January 27, 1988, 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 assuranco (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.
, 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.
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-2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Marti J. Vir ' io, irector Projec Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August 5, 1988 l
4 e
ATTACHMENT TO LICENSE AMENDMENT NO.9y FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 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 3-61 3/4 3-61
TABLE 3.3.7.5-1
~
ACCIDENT MONITORING INSTRUMENTATION e
MINIMUM APPLICABLE e
REQUIRED NUMBER CHANNELS OPERATIONAL
{
INSTRJMENT OF CHANNELS OPERABLE CONDITIONS ACTION 1.
Reactor Vessel Pressure 2
1 1, 2 80 2.
Reactor Vessel Water Level, Fuel Zone 2
1 1, 2 80 3.
Suppression Chamber Water Level 2
1 1, 2 80 4
Suppression Chamber Water Temperature 2
1 1, 2 80 5.
Suppression Chamber Air Temperature 2
1 1, 2 80 6.
Suppression Chamber Pressure 2
1 1, 2 80 7.
Drywell Pressure, Wide Range 2
1 1, 2 80 8.
Drywell Air Temperature 2
1 1, 2 80 9.
Drywall Oxygen Concentration ***
2 1
1, 2 80 10.
Drywell Hydrogen Concentration 2
1 1, 2 80 11.
Safety / Relief Valve Position Indicators 1*/ valve 1*/ valve 1, 2 80 12.
Containment High Range Radiation Monitor 2
2 1,2,3 81 l
13.
Standby Gas Treatment System Radiation Monitors **
2 1
1,2,3 81
- 14. Neutron Flux 2
1 1, 2 80 3
15.
Drywell Sump-Level 2
1 1, 2 80 16.
Primary Containment Isolation Valve Position 1/ valve 1/ valve 1, 2, 3 80
- Pressure switch
- High (accident) range noble gas monitors
- See Special Test Exception 3.10.5
TABLE 3.3.7.5-1 (Continued)
ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 80 -
a.
With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, restore the inoperable channel (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 />.
b.
With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 />.
ACTION 81 -
With the number of OPERABLE accident monitoring instrumentation channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:
a.
Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and b.
Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the sction taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
l l
}
FERMI - UNIT 2 3/4 3-62 i
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