ML20082P635
| ML20082P635 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/28/1991 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082P637 | List: |
| References | |
| NUDOCS 9109100427 | |
| Download: ML20082P635 (2) | |
Text
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.5 NUCLEAR REGULATORY COMMISSION
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DETROIT EDISON COMPANY FERMI-2 DOCKET NO. 50-341 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 74-License No. NPF-43 1.
The Nuclear Regulatory Comission (the Comission) has found that:
l
-A.
The application for amendment by the Detroit Edison Company (the i
licensee) dated August 1,1990, complies with the standards and recuirements of the Atomic Energy Act of 1954 as amended (the Act),
anc the Con.wission's rules and regulations sel forth in 10 CTR l
Chapter I; j
.5 B.
The facility will operate in conformity with the application, the t
provisions of the Act, and the rules and regulations of the Commission; i
C.
There is reasont,ble assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and i
safety of the public, and (ii) that such activities will be conducted
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in compliance with the Commission's regulations;
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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 j
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E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of l
the Commission's regulations and all applicable requirements have been satisfied..
l 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:
l Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 74, and the Environmental Protection Plan contained in j
Appendix B, are hereby incorporated in the license. Deco shall operate i
the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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i 9109100427 910920
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2-1 3.
This license amendment is ef fective as of its date of issuance.
FOR TliE NLK. LEAR REGULATORY COMMISSION M;f L. B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 28, 1991 i
f i
/
t ATTACHMEN1 TO L ICENSE AMENDMENT NO. 74 FACILITY OPERATING LICENSE NO. NPF-43 i
DOCKET NO. 50-341 r
Replace the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by Amendnent number and contains a vertical line indicating the area of change.
7
.REMO_V_E INSERT 3/4 3-29 3/4 3-29 t
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TABlt 3.3.3-3 EMERGENCY CORE COOLING SYSTEM RESPONSE TIMES RESPONSE TIME
. TRIP FUNCT[QN (Seconds) 1.
CORE uPRt.
lILM a.
Reactor Vessel Low Water Level - Level I s 30 b.
Drywell Pressure - High s 30 c.
Reactor Steam Dome Pressure - Low NA*
d, Manual Initiation NA 2.
LOW /RESSURE C00LANT INJECTION H0DE OF RHR SYSTEM a.
Reactor Vessel Low Water level - Level I s 55 b.
Drywell Pressure High s 55 c.
Reactor Steam Deme Pressure - Low NA*
d.
Reactor Vessel Low Water Level - Level 2 NA e.
Reactor Steam Donie Pressure - Low NA f.
Riser Differential Pressure - High NA g.
Recirculation Pump Differential Pressure -
NA High h.
Manual Initiation NA 3.
HIGH PRESSURE COOLANT INJECTION SYSTEM a.
Reactor Vessel Low Water Level - Level 2 s 3P b.
Drywell Pressure - High NA c.
Condensate Storage Tank Level - Low NA d.
Reactor Vessel Water Level - High, Level 8 NA e.
Suppression Pool Water Level - High NA f.
Manual Initiation NA 4.
AUTOMATIC DEPRESSURIZATION SYSTEM a.
Reactor Vessel Low Water Level
- Level 1 NA b.
Drywell Pressure - High NA c.
ADS Timer NA d.
Core Spray Pump Di'. charge Pressure - High NA e.
RHR LPCI Mode Punip Discharge Pressure - High NA f.
Reactor Vessel Low Water Level - Level 3 NA g.
Manual Initiation NA h.
Drywell Fressure - High Bypass Timer NA i.
Manual Inhibit NA 5.
LOSS OF POWER a.
4.16 kV Emergency Bus Undervoltage (Loss of Voltage)
NA b.
4.16 kV Emergency Bus Undervoltage (Degraded Voltage)
NA
- These are permissive signals only.
They do not activate ECCS initiation.
FERMI - UNIT 2 3/4 3-29 Amendment No. JE, /E. 74,
,