ML20072C702
| ML20072C702 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/11/1994 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072C699 | List: |
| References | |
| NUDOCS 9408180058 | |
| Download: ML20072C702 (8) | |
Text
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..'S UNITED STATES 7
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NUCLEAR REGULATORY COMMISSION 5,,
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WASHINGTON, D.C. 20555-0001 a....
DETROIT EDIS0N COMPANY DOCKET NO 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 102 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 May 10, 1994, 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 f acility 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 n 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 Cornmission's regulations and all applicable requirements have been satisfied.
9408180058 940811 PDR ADOCK 05000341 P
9 '
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 The Technical Specifications contained in Appendix A, as revised through Amendment No. 102, 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.
3.
This license amendment is effective as of the date of its issuance with full implementation within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION A
he mL Ledyard B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of issuance:
August 1, 1994
ATTACHMENT TO LICENSE AMENDMENT NO.102 FACILITY OPEPATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT xiv xiv xxiv xxiv xxv xxv 1-5 1-5 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 3/4 3-14 3/4 3-14 3/4 3-14a 3/4 3-14a 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-5 3/4 6-5*
3/4 6-6 3/4 6-6 3/4 6-19 3/4 6-19*
3/4 6-20 3/4 6-20 3/4 6-21 3/4 6-21 3/4 6-22 through 3/4 6-22 3/4 6-48 3/4 6-48*
3/4 8-19 3/4 8-19*
3/4 8-20 3/4 8-20 3/4 8-21 through 3/4 8-21 3/4 8-24 B 3/4 6-5
. B 3/4 6-5*
j B 3/4 6-6 B 3/4 6-6 B 3/4 6-6a i
i
- 0verleaf page provided to maintain document completeness. No changes contained on these pages.
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1!$15 BASES SECTION EMil 3/4.4 REACTOR COOLANT SYSTEM (Continued) 3/4.4.10 CORE THERMAL HYDRAULIC STABILITY................ B 3/4 4-8 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1/2 ECCS - OPERATING and SHUTD0WN...................
B 3/4 5-1 3/4.5.3 SUPPRESSION CHAMBER............................. B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity................... B 3/4 6-1 Primary Containment Leakage..................... B 3/4 6-1 Primary Containment Air Locks................... B 3/4 6-la MSIV Leakage control System..................... B 3/4 6-2 Prim:ry Containment Structural Integrity........ B 3/4 6-2 Drywell and Suppression Chamber Internal Pressure...................................... B 3/4 6-2 Drywell Average Air Temperature................. B 3/4 6-2 i
Drywell and Suppression Chamber Purge System.... B 3/4 6-2 3/4.6.2 DEPRESSURIZATION SYSTEMS........................ B 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES............ B 3/4 6-6 3/4.6.4 VACUUM RELIEF................................... B 3/4 6-6 3/4.6.5 SECONDARY C0NTAINHENT........................... B 3/4 6-6a l
3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL.......... B 3/4 6-7 FERMI - UNIT 2 xiv Amendment No. 77, 77 102
INDEX LIST OF TABLES (Continued)
P_AS1 A
TABLE 3.3.7.9-1 DELETED..........................................
3/4 3-68 3.3.7.12-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION.........
3/4 3-77 4.3.7.12-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................
3/4 3-81 3.3.9-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION..................................
3/4 3-87 3.3.9-2 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETP0lNTS........................
3/4 3-88 4.3.9.1-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS........
3/4 3-89 3.3.11-1 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION..
3/4 3-91 4.3.11.1-1 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS........
3/4 3-92 l
3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES...........................................
3/4 4-12 3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE P RE S S URE M0N I TORS................................
3/4 4 3.4.4-1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS..........
3/4 4-15 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND AN A L Y S I S P R0G RAM.................................
3/4 4-18 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM--
WITHDRAWAL SCHEDULE..............................
3/4 4-22 4.6.1.1-1 PRIMARY CONTAINMENT ISOLATION VALVES / FLANGES LOCATED IN LOCKED HIGH RADIATION AREAS...........
3/4 6-lb 3.6.3-1 DELETED..........................................
3/4 6-22 l
3.6.S.2-1 SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION DAMPERS......................
3/4 6-53 4.7.2.1-1 CONTROL ROOM EMERGENCY FILTRATION SYSTEM DUCT LEAK TESTING SURVEILLANCE REQUIREMENTS...........
3/4 7-10b 3.7.3-1 SURVEY P0lNIS FOR SHORE BARRIER..............
3/4 7-12 4.7.5-1 SNUBBER VISUAL INSPECTION INTERVAL...............
2/4 7-20a 3.7.7.5-1 DELETED..........................................
3/4 7-32 3.7.7.6-1 DELETED..........................................
3,4 7-37 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE...................
3/4 8-8 f
FERMI - UNIT 2 xxiv Amendment No. fE,JE,E2,El,E/,EE 102
1N,DE LIST OF TABLES (Continued)
TABLE f111 4.8.2.1-3 BATTERY SURVEILLANCE REQUIREMENTS..............
3/4 8-12 3.8.4.2-1 PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES.................
3/4 8-19 3.8.4.3-1 DELETED........................................
3/4 8-21 l
3.8.4.5-3 STANDBY LIQUID CONTROL SYSTEM ASSOCIATLO ISOLATION DEVICES 480 V MOTOR CONTROL CENTERS..
3/4 8-27 5.7.3-1 COMPONENT CYCLIC OR TRANSIENT LIMITS...........
5-7 i
6.2.2-3 MINIMUM SHIFT CREW COMPOSITION.................
65 i
l FERMI - UNIT 2 xxv Amendment No. J/, //, EJ 102 J
m t
o DEFINITIONS 2.
Closed by at least one manual valve, blank. flange, or deactivated automatic valve secured in its closed position, except for valves that are open under administrative control l
as permitted by Specification 3.6.3.
l b.
All primary containment equipment hatches are closed and sealed.
c.
Each primary containment air lock is in compliance with the requirements of Specification 3.6.1.3.
d.
The primary containment leakage rates are within the limits of Specification 3.6.1.2.
e.
The suppression chamber is in compliance with the requirement of Specification 3.6.2.1.
f.
The sealing mechanism associated with each primary containment penetration, e.g., welds, bellows, or 0-rings, is OPERABLE.
g.
The suppression chamber to reactor building vacuum breakers are in compliance with Specification 3 6.4.2.
THE PROCESS CONTROL PROGRAM 1.30 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
PURGE - PURGING 1.31 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating candition, in such a manner that replacement air or gas is required to purify.he confinement.
RATED THERMAL POWER 1.32 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3430 MWT.
FERMI - UNIT 2 1-5 Amendment No. fl, 52, 57 102
TABLE 3.3.2-1 A
ISOLATION ACTUATION INSTRUMENTATION
- o i5 MINIMUM APPLICABLE E
OPERABLECHANNLR OPERATIONAL U
TRIP FUNCTION PER TRIP SYSTEM as CONDITION ACTION N
1.
PRIMARY CONTAINMENT ISOLATION ReactorVesselgowWaterlevel a.
2 1, 2, 3 20 1) level 3 (d) level 2 2
1,2,3 20 2) 3)
Level 1 2
1, 2, 3 20 88 b.
'Drywell Pressure - High 2
1, 2, 3 20 c.
88 1)
Radiation - High 2
1, 2, 3 21 Y
2)
Pressure - Low 2
1 22 0
3)
Flow - High 2
1, 2, 3 21 d.
Main Steam Line Tunnel Temperature - High 2(C) 1, 2, 3 21 e.
Condenser Pressure - High 2
1, 2**, 3**
21 f.
Turbine Bldg. Area g
Temperature - High 2
1, 2, 3 21 f
g.
Deleted S
h.
Manual Initiation 1/ valve 1, 2, 3 26 5
g.,
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DATED:
Auaust 1. 1994 AMENDMENT NO. 102 TO FACILITY OPERATING LICENSE NO. NPF-43-FERMI-2 Docket File.
'NRC ~
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J. Zwolinski L. Marsh C. Jamerson T. Colburn OGC-WF D. Hagan G. Hill, T-5C2 C. Grimes, 0-ll/f/23 W. Reckley ACRS (10)
OPA OC/LFDCB, T-4A43 L. Miller, R-Ill SEDB cc:
Plant Service list t
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