ML20062A234
| ML20062A234 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/12/1990 |
| From: | Pierson R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20062A237 | List: |
| References | |
| NUDOCS 9010190247 | |
| Download: ML20062A234 (7) | |
Text
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UNITED $TATES
'g NUCLEAR REGULATORY COMMISSION WASHINGTON, D, C,706ss t
%,.....j DETROIT EDISON COMPANY DOCKET NO. 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 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 February 1, 1989, 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.
l 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 l
l The Technical Specifications contained in Appendix A, as revised through Amendment No. 60, 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.
l-9010190247 901012 PDR ADOCK 05000341 P
l PDC 4
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- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
(~
Robert C. Pierson, Director
)
Project Directorate 111-1 Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation t
Attachment:
I Changes to the Technical Specifications-l Date of Issuance: October 12, 1990
4 i
ATTACHMENT TO LICENSE AMENDMENT NO. 60 j
FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 l
Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
The corresponding j
overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 3-15 3/4 3-15 3/4 3-16 3/4 3-16 3/4 3-17 3/4 3-17 3/4 3-17a 3/4 3-17a
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E TABLE 3.3.2-2 m
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS e
g ALLOWABLE
[
TRIP FUNCTION TRIP SETPOINT VALUE 1.
PRIMARY CONTAINMENT ISOLATION a.
Reactor Vessel tow Water Level 1)
Level.3 1 173.4 inches
- 1 171.9 inches 2)
Level 2 1 110.8 inches
- 1 103.8 inches 3)
Level 1 1 31.8 inches
- 1 24.8 inches b.
'Drywell Pressure - High 5 1.68 psig i 1.88 psig c.
Radiation - High 5 3.0 x full power background 1 3.6 x full power background w
x
{
2)
Pressure - Low 1 756 psig 2 736 psig
_L 3)
Flow - High
< 137.9% of rated flow /109.0 psid 5 139.5% of rated flow /112.0 psid v.
d.
Main Steam Line Tunnel g
Temperature - High 5 200'F 1 206*F l
e.
Condenser Pressure - High 5 6.85 psia i 7.05 psia f.
Turbine B1dg. Area Temperature - High 5 200 F
$ 206*F l
g.
Deleted h.
Manual Initiation NA NA 9
o l
3 I
CL Bm 3
c+
l2 w
O
(
TABLE 3.3.2-2 (Continued) j r,i l
- o z
ISOLATION ACTUATION INSTRUNENTATION SETPOINTS ALLOWA8LE c
TRIP FUNCTION TRIP SET?OINT VALUE i
- c
[
2.
REACTOR WATER CLEANUP SYSTEM ISOLATION ru l
a.
A Flow - High 5 55.1 gpm 1 63.4 gpm b.
Heat Exchanger / Pump /High Energy Piping Area Temperature - High 5 175'F
< 183'F c.
Heat Exchanger / Pump / Phase Separator Area Ventilation A Temperature -
High 1 50*F
~< 53*F d.
SLCS Initiation MA NA e.
Reactor Vessel Low Water Level -
i w
Level 2 1 110.8 inches
- 1 103.8 inches f.
Deleted w
4 i
g.
Manual Initiation NA NA e
i 3.
REACTOR CORE ISOLATION COOLING SYSTEN ISOLATION RCIC Steam Line Flow - High a.
1.
Differential Pressure 1 87.0 inches H O
$ 95.0 inches H O 2
2 2.
Time Delay 3 seconds 312 seconds b,
RCIC Steam Supply Pressure - Low 1 62 psig 1 53 psig c.
RCIC Turbine Exhaust Diaphragm Pressure - High
$ 10 psig i 20 psig
'l
- m o.
d.
RCIC Equipment Room y @a.
Temperature - High
.i 154*F
$ 162*F
- or e.
Manual' Initiation MA NA 1
o
- - - = -
= -
?
TABLE 3.3.2-2 (Continued)
.b ISOLATION ACTUATION INSTRUNENTATION SETPOINTS c.
ALLOWABLE 25 TRIP FUNCTION TRIP SETPOINT VALUE h
4.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION a.
HPCI Steam Line Flow - High 1.
Differential Pressure 1 395.0 inches i 410.0 inches HO HO 2
2 2.
Time Delay 3 seconds 312 seconds b.
HPCI Steam Supply Pressure - Low
> 100 psig 1 90 psig c.
HPCI Turbine Exhaust Diaphragm Pressure - High 1 10 psig i 20 psig d.
HPCI Equipment Room g
Temperature - High 5 154*F
$ 162*F l
wA e.
Manual Initiation MA NA O
5.
RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION a.
Reactor Vessel Low Water Level -
Level 3 3 173.4 inches
- 1 171.9 inches b.
Reactor Vessel (Shutdown Cooling Cut-in Permissive Interlock) Pressure - High i 89.5 psig***
1 05.5 psig***
c.
Manual Initiation MA NA 3m
- Above TAF.
See Bases Figure B 3/4 3-1.
-s tI
- Represents steam done pressure; actual trip setpoint is corrected for cold water head with reactor e
5 vessel flooded.
- o O
.~
jO TABLE 3.3.2-2 (Continued) m 3
ISOLATION ACTUATION INSTRUNENTATION SETPOINTS e
ALLOWABLE 2
TRIP FUNCTION TRIP SETPOINT VALUE
t N
6.
SECONDARY CONTAINNENT ISOLATION a.
Reactor Vessel Low Water Level - Level 2
> 110.8 inches *
> 103.8 inches b.
Drywell Pressure-High 1 1.68 psig i 1.88 psig c.
Fuel Pool Ventilation Exhaust Radiation-High i 5 mR/hr 1 6 mR/hr d.
Manual Initiation MA NA g
xa w
i y
l
- Above TAF. See Bases Figure B 3/4 3-1.
l 5
<D 3
CL 9
to 3r+
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