ML20091C143
| ML20091C143 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/23/1991 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20091C144 | List: |
| References | |
| NUDOCS 9108050348 | |
| Download: ML20091C143 (7) | |
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NUG.cAA REGULATORY COMMISSION UNITED STATES D,
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WASHINGTON. D C. 20f/4
%,.....J DETROIT E01 SON COMPANY FERMI-2 DOCKET NO. 50-341 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 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)datedAugust 17, 1990, 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 (1) that the activities authorited 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.
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. 71, 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.
9108050340 910723 PDR ADOCK 05000341 P
-2 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h 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: July 23, 1991
ATTACHMENT TO LICENSE AMENDMENT NO. 71 FAClllTY 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 Anendment number and contain a vertical line indicating the area of change.
REMOVE INSERT v
v xiii xiii 3/4 3-85 3/4 3-85 B3/4 3-6 B3/4 3-6 l
i
INDEX llMITING CONDITIONS FOR OPERATION AND SURVEltlANCE REQUIREMENTS SECTION f.AJ[
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 R0D BLOCK INS 1RUMENTAT10N...................
3/4 3 41 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation...............
3/4 3-47 Seismic Monitoring instrumentation..................
3/4 3-51 Meteorological Monitoring Instrumentation...........
3/4 3-54 Remote Shutdown System Instrumentation and Controls.
3/4 3-57 Accident Monitoring Instrumentation.................
3/4 3-60 Source Range Monitors...............................
3/4 3-64 Traversing In-Core Probe System.....................
3/4 3-65 Chlorine Detection System...........................
3/4 3-66 Deleted.............................................
3/4 3-67 Loose-Part Detection System.........................
3/4 3 70 Radioactive Liquid Effluent Monitoring Instrumentation.....................................
3/4 3-71 j
Radioactive Gaseous Effluent Monitoring Instrumentation.....................................
3/4 3-76 l
3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION........................................
3/4 3-86 3/4.3.10 RESERVED................................................
3/4.3.11 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION.......
3/4 3-90 FERMI - UNIT 2 v
Amendment No. E3, E9, A2, 71
I!l9.El BASES SECTION PAG [
INSTRUMENTATION (Continued)
MONITORING INSTRUMENTATION (Continued)
Meteorological Monitoring Instrumentation....... B 3/4 3-4 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 Traversing In-Core Probe System................. B 3/4 3-4 Chlorine Detection System....................... B 3/4 3-5 Deleted......................................... B 3/4 3-5 Loose-Part Detection System..................... B 3/4 3-5 Rcdioactive Liquid Effluent Monitoring Instrumentation................................. B 3/4 3-5 Radioactive Gaseous Effluent Monitoring Instrumentation.................................
B 3/4 3-6 l
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 TAFETY/ RELIEF VALVES............................ B 3/4 4-la 3/4 4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems....................... B 3/4 4-2 Operat ional Lea kage............................. 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 3/4.4.8 STRUCTURAL INTEGRITY............................ B 3/4 4 5 3/4.4.9 RESIDUAL HEAT REM 0 VAL............................ B 3/4 4-5 FERMI - UNIT 2 xiii Amendment No. f9, E3, E9, EJ, 71 l
INSTRUMENTATION 3/4.3,8 TURBlf4E OVERSPEED PROTECTION SYST[t]
THIS PAGE INTENTIONALLY DELETED FERM1 - UNIT 2 3/4?,-85 Amendment No. E, 71
INSTRUMENTATION BASES SQNITORING INSTRUMENTATION (Continued) 3/4.3.7.12 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The alarm / trip setpoints for these instruments shall be calculated and i
adjusted in accordance with the methodology and parameters in the ODCM utilizing the system design flow rates as specified in the ODCM.
This 1
conservative method is used because the Fermi 2 design does not include flow rate measurement devices. This will ensure the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
This instrumentation also includes provisions for monitoring and controlling the concentrations of potentially explosive gas mixtures in the main condenser offgas treatment system.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
I I
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 vess.1 water level due to failure of the feedwater controller under maximum demand.
3/4.3,11 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION 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 consistent with General Design Criterion 3 and Appendix R to 10 CFR 50.
FERMI - UNIT 2 B 3/4 3-6 Amendment No. E9, 71
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