ML20217A784
| ML20217A784 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/17/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217A790 | List: |
| References | |
| NUDOCS 9803250241 | |
| Download: ML20217A784 (25) | |
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4 UNITED STATES s
,j NUCLEAR REGULATORY COMMISSION
't WASHINGTON, D.C. 20616 0001
...../
g, DETROIT EDISON COMPANY l
l DOCKET NO. 50-341 l
FERMI 2 l
l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 115 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 September 29,1997, as supplemented on March 10,1998, 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 i
Commission's regulations; l
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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the l
Commission's regulations and all applicable requirements have been satisfied.
l
[
9803250241 980317 PDR ADOCK 05000341 P
2.
Accordingly, the license is amended to approve the relocation of the requirements of Technical Specifications 3/4.3.7.2, 3/4.3.7,3, 3/4.3.7.7, 3/4.3.7.8, and 3/4.3.7.10 to the updated final safety analysis report (UFSAR) with modifications as described in the licensee's application dated September 29,1997, as supplemented on March 10,1998, and evaluated in the staffs safety evaluation attached to this amendment.
1 Implementation will be completed within 90 days of the issuance of this amendment.
i With respect to changes to the UFSAR, the action that must be completed within the implementation date is the licensee approval of the UFSAR change documentation.
This license is also hereby 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 Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 115, 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 90 days. Implementation of this amendment shallinclude the relocation of the requirements of Technical Specifications 3/4.3.7.2,3/4.3 7.3,3/4.3.7.7, 3/4.3.7.8, and 3/4.3.7.10 to the updated final safety analysis report (UFSAR) with modifications as described in the licensee's application dated September 29,1997, as supplemented on March 10,1998, and evaluated in the staffs safety evaluation attached to this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION Andrew J. Kugler, Project Manager Project Directorate 111-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: March 17, 1998 Aa
A"ITACHMENT TO LICENSE AMENDMENT NO. 115 FACILITY OPERATING 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 verticallines indicating the area of change.
REMOVE INSERT v
v, vi vi, XI XI xii xii xiii
- xiii, xiv xiv xxiii
- xxiii, xxiv xxiv 3/4 3-51 3/4 3-51 3/4 3-52 3/4 3-52 3/4 3-53 3/4 3-53 3/4 3-54 3/4 3-54 3/4 3-55 3/4 3-55 3/4 3-56 3/4 3-56 3/4 3-65 3/4 3-65 3/4 3-66 3/4 3-66 3/4 3-69 3/4 3-69*
3/4 3-70 3/4 3-70 B 3/4 3-3 B 3/4 3-3*
B 3/4 3-4 8 3/4 3-4 8 3/4 3-5 B 3/4 3-5 B 3/4 3-6 B 3/4 3-6*
- Overleaf page provided to maintain document completeness. No changes contained on these pages.
1.@El l
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION g
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION.......... 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION.................
3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION................................... 3/4 3-23 3/4.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM ACTUATION INSTRUMENTATION.................................... 3/4 3-32 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION................................... 3/4 3-36 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION...................
3/4 3-41 3/4.3.7 HONITORING INSTRUMENTATION l
Radiation Monitoring Instrumentation............. 3/4 3-47 1
Deleted......................
....................... 3/4 3-51 l
Deleted............
.............................. 3/4 3-54 l
Remote Shutdown System Instrumentation and Controls. 3/4 3-57 Accident Monitoring Instrumentation................ 3/4 3-60 Source Range Monitors.............................
3/4 3-64 0eleted.........................
................. 3/4 3-65 l
Deleted.
..... 3/4 3-66 l
Deleted....................
...................... 3/4 3 67 Deleted...........
................................ 3/4 3-70 l
l Explosive Gas Monitoring Instrumentation............ 3/4 3-76 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION i
INSTRUMENTATION..................................... 3/4 3-86 j
3/4.3.10 RESERVED......................
3/4.3.11 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION........ 3/4 3-90 FERMI - UNIT 2 v
Amendment No. 53.59.62.72.82.115
.~m LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
. ~. _
SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM
(
3/4.4.1 RECIRCULATION SYSTEM
{
l Recirculation Loops..................................
3/4 4-1 i
Jet Pumps............................................
3/4 4-4
~
Re c i rcu l a t i o n Pus:p s..................................
3/4 4-5 Idle Recirculation Loop Startup......................
3/4 4-6 3/4.4.2 SAFETY / RELIEF VALVES Sa fety/ Relief Va 1 ves.................................
3/4 4-7 Safety / Relief Yalves Low-Low Set Function............
3/4 4-8 3/4 4.3 REACTOR COOLANT SYSTEK LEAKAGE Lea kage Detection Systems............................
3/4 4-9 O pe rational Lea ka 9e.................................. 3/4 4-10 3/4.4.4 CHEMISTRY............................................
3/4 4-13 3/4.4.5 SPECIFIC ACTIVITY....................................
3/4 4-16 3/4.4.6 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System...............................
3/4 4-19 RE8ctor Steam D0me...................................
3/4 4-23 3 /4.4.7 KAIN STEAM LINE ISOLATION VALVES.....................
3/4 4-24 3/4.4.8 STRUCTURAL INTEGRITY.................................
3/4 4-25 3/4.4.9 RESIDUAL HEAT REH0 VAL Hot Shutdowr..........................................
3/4 4-26 Cold Shutdown........................................
3/4 4-28 3/4.4.10 ' CORE THERMAL HYDRAULIC STABILITY.....................
3/4 4-30 2/.4,5,, EMERG,E!!,C,Y,,00,RE, COOLING SYSTEMS E
3/4.5.1 ECCS - 0PERATING.....................................
3/4 5-1 3/4.5.2 ECCS - SHUTD0WN..................................... 3/4 5-6 3/4.5.3 SUPFRESSION CHAMBER..................................
3/4 5-8 FERMI - UNIT 2 vi Aniendment No. 53-JUL 2 71990
ItiDEK LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUTREMENTS SECTION g
l l
3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS l
l l
Liquid Holdup Tanks........................................
3/4 11-7 3/4.11.2 GASEOUS EFFLUENTS Explosive Gas Mixture......................................
3/4 11-16 Main Condenser.............................................
3/4 11-17 l
i 3/4.12 DELETED I
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FERMI - UNIT 2 xi Amendment No.82 JUN S 1992 1
m Ex BASES SECTION EAGE 3/4.0 AroLICABILITY.........................
B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN...............................
B 3/4 1-1 3/4.1.2 REACTIVITY ANOMALIES.........
B 3/4 1-1 3/4.1.3 CONTROL R005.................
B 3/4 1-2 3/4.1.4 CONTROL ROD PROGRAM CONTROLS................ B 3/4 1-3 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM................ B 3/4 1-4 3/4 2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE....................................... B 3/4 2-1 3/4.2.3 MINIMUM CRITICAL POWER RATIO................. B 3/4 2-3 3/4.2.4 LINEAR HEAT GENERATION RATE................. B 3/4 2-4 3/4 3 INSTRUMEN ATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION..... B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION...........
B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION...............................
B 3/4 3-2 3/4.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM ACTUATION INSTRUMENTATION...............................
B 3/4 3-3 l
l 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION........
B 3/4 3-3 3/4.3.6 CONTROL R0D BLOCK INSTRUMENTATION...................
B 3/4 3-3 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation....... B 3/4 3-3 Deleted..........
B 3/4 3-4 l
FERMI - UNIT 2 x11 Amendment No. 64, 69.115
lhDLE BASES SECTION PXd INSTRUMENTATI0t{(Continued) i MONITORING INSTRUMENTATION (Continued)
Deleted.................
..................... B 3/4 3 4 l
Remote Shutdown System Instrumentation and Controls................................... B 3/4 3-4 Accident Monitoring Instrumentation............. B 3/4 3-4 Source Range Monitors..............
...... B 3/4 3-4 i
Deleted..........
B 3/4 3-4 l
Deleted...
........................ B 3/4 3-5 l
Deleted..
........... B 3/4 3-5 Deleted...
............ B 3/4 3-5 l
Explosive Gas Monitoring Instrumentation........ B 3/4 3-6 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEMS ACTUATION INSTRUMENTATION.............................. B 3/4 3-6 3/4.3.10 RESERVED 3/4 3.11 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION............................... B 3/4 3-6 3/4 4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM....................... B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES........................ B 3/4 4-la 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems............
...... B 3/4 4-2 Operational Leakage........................
... B 3/4 4-2 3/4.4.4 CHEMISTRY..................
............... B 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY.........
B 3/4 4-3 3/4.4.6 PRESSURE / TEMPERATURE LIMITS..
... B 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES....
........ B 3/4 4-5 3/4.'4.B STRUCTURAL INTEGRITY....
B 3/4 4-5 3/4.4.9 RESIDUAL HEAT REMOVAL......
. B 3/4 4-5 FERMI - UNIT 2 xiii Amendment No. 49.E3.59.62.72.82.115
BASES SECTION PEI 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................... R 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 Primary 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 6-2a Drywell and Suppression Chamber Purge System.... B 3/4 6-2a 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 CONTAINMENT........................... B 3/4 6-6a 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL.......... B 3/4 6-7
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FERMI - UNIT 2 xiv Amendment No. #, U, JSJ,108 h% 8 1996
I w
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LIST OF TABLES (Continued)
TABLE
_fAGE 4.3.4-1 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-35 3.3.5-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4 3-37 3.3.5-2 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS 3/4 3-39 4.3.5.1-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-40 3.3.6-1 CONTROL R0D BLOCK INSTRUMENTATION 3/4 3-42 3.3.6-2 CONTROL R0D BLOCK INSTRUMENTATION SETPOINTS 3/4 3-44 4.3.6-1 CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-45 3.3.7.1-1 RADIATION MONITORING INSTRUMENTATION 3/4 3-48 4.3.7.1-1 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-50 3.3.7.2-1 DELETED 3/4 3-52 l
4.3.7.2-1 DELETED 3/4 3-53 l
3.3.7.3-1 DELETED 3/4 3-55 l
4.3.7.3-1 DELETED 3/4 3-56 l
3.3.7.4-1 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION 3/4 3-58 4.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-59 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION 3/4 3-61 4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3 63 FERMI - UNIT 2 xxiii Amendment No. 49,115 j
LIST OF TABLES (Continued)
IABLE f.8fti 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 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 PRESSURE M0NITORS................................
3/4 4-12 3.4.4-1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS..........
3/4 4-15 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.................................
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 LOC ATED IN LOCKED HI GH RADI ATION AREAS...........
3/4 6-lb j
3.6.3-1 DELETED..........................................
3/4 6-22 1
3.6.5.2-1 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 POINTS FOR SHORE BARRIER..................
3/4 7-12 4.7.5-1 SNUBBER VISUAL INSPECTION INTERVAL...............
3/4 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 DELETED..........................................
3/4 8-8 l
FERMI - UNIT 2 xxiv Amendment No. /J.JJ,52,52,5%,pp, 192,107 M 2 01996
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FERMI - UNIT 2 3/4 3-53 Amendment No.115
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I - UNIT 2 3/4 3-69 Amendment No. 62 NOV 141999
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INSTRUMENTATION BASES 3/4.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM ACTUATION INSTRUMENTATION l
The anticipated transient without scram (ATWS) recirculation pump trip system provides a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient. The response of the plant to this postulated event falls within the envelope of study events in General Electric Company Topical Report NEDO-10349, dated March 1971 NE00-24222, dated December 1979, and Appendix 158.8 of the FSAR.
Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the l
difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.
3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without providing actuation of any of the emergency core cooling equipment.
Operation with a trip set less conservative than its Trip 5etpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.
3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION The control rod block functions are provided consistent with the requirements of the specifications in Section 3/4.1.4, Control Rod Program Controls and Section 3/4.2 Power Distribution Limits.
The trip logic is arranged so that a trip in any one of the inputs will result in a control rod block.
Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.
3/4.3.7 MONITORING INSTRUMENTATION 3/4.3.7.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring instrumentation ensures that; (1) the radiation levels are continually measured in the areas served by the individual channels; (2) the alare or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with 10 CFR Par.t 50, Appendix A, General Design Criteria 19, 41, 60, 61, 63, 64.
i FERMI - UNIT 2 B 3/4 3-3 i
INSTRUMENTATION BASES I
MONITORING INSTRUMENTATION (Continued) 3.4.3.7.2 DFlETED l
3/4.3.7.3 DELETED l
3/4.3.7.4 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION AND CONTROLS The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50.
3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97. " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident." December 1975 and NUREG-0737. " Clarification of TMI Action Plan Requirements." November 1980.
The multiple noble gas monitors installed on each division of the Standby Gas Treatment System provide the necessary monitoring capabilities to assure l
that the normal and extended monitoring ranges required by NUREG-0737 and Regulatory Guide 1.97 are met.
3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown. At these power levels, reactivity additions shall not be made without this flux level information available to the operator. When the intermediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.
3/4.3.7.7 DELETED l
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FERMI - UNIT 2 B 3/4 3-4 Amendment No. 28.115 L
INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.7.8 DELETED l
3/4.3.7.9 DELETED 3/4.3.7.10 DELETED
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FERMI - UNIT 2 B 3/4 3-5 Amendment No. 59, 62. 82. 115
i INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.7.12 EXPLOSIVE GAS MONITORING INSTRUMENTATION l
The explosive gas monitoring instrumentation is provided to monitor the 8
concentrations of potentially explosive gas mixtures in the main condenser I
offgas treatment system. The OPERABILITY and use of this instrumentation is I
consistent with the requirements of General Design Criterion 60 of Appendix A l
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to 10 CFR Part 50.
i 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater/ main turbine trip system actuation instrumentation is provided to initiate action of the feedwater system / main turbine trip system in the event of a high reactor vessel water level due to failure of the feedwater controller under maximum demar.d.
3/4.3.11 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION I
The OPERABILITY of the alternative shutdown system ensures that a fire will not preclude achieving safe shutdown. The alternative shutdown system instrumentation is independent of areas where a fire could damage systems normally used to shutdown the reactor. Thus, the system capability is
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consistent with General Design Criterion 3 and Appendix R to 10 CFR 50.
I FERMI - UNIT 2 B 3/4 3-6 Amendment No. #, 7J, 82, JUN 9 1992
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