ML20094L470
| ML20094L470 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/14/1995 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20094L474 | List: |
| References | |
| NUDOCS 9511200260 | |
| Download: ML20094L470 (10) | |
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n RE:
y UNITED STATES l
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NUCLEAR RECULATORY COMMISSION f
WASHINGTON, D.C. 3086H001 l-
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TOLED0 EDIS0N COMPANY CENTERIOR SERVICE COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.201 License No. NPF-3 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland Electric Illuminating Company (the licensees) dated June 23, 1995, and facsimile transmission dated October 31, 1995, 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 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.
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-3 is hereby l
amended to read as follows:
i 9511200260 951114 PDR ADOCK 05000346 P
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.201, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented not later than 90 days after issuance.
FOR THE NUCLEAR REGULATORY COPMISSION Linda L. Gundrum, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications l
Date of issuance:
November 14, 1995 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 201 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 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 IV IV V
V IX IX 3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-39 3/4 3-40 3/4 3-41 3/4 3-42 3/4 4-32 B 3/4 3-2 B 3/4 3-2 B 3/4 4-13 B 3/4 4-13 6-18 6-18 1
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INDEX LIMITING C0fEITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION EAK 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL POWER IMBALANCE................
3/4 2-1 3/4.2.2 NUCLEAR HEAT FLUX HOT CHANNEL FACTOR - F......
3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F"a...3/4 2-7 3/4.2.4 QUADRANT POWER TILT.................
3/4 2-9 3/4.2.5 DNB PARAMETERS...................
3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION.....
3/4 3-1 3/4.3.2 SAFETY SYSTEM INSTRUMENTATION Safety Features Actuation System..........
3/4 3-9 Steam and Feed Rupture Control System.......
3/4 3-23 Anticipatory Reactor Trip System..........
3/4 3-30a 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation........
3/4 3-31 Incore Detectors..................
3/4 3-35 Deleted......................
3/4 3-37 l
Deleted......................
3/4 3-40 l
Remote Shutdown Instrumentation..........
3/4 3-43 Post-Accident Monitoring Instrumentation......
3/4 3-46 Deleted Waste Gas System Oxygen Monitor..........
3/4 3-57 j
3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation............
3/4 4-1 Shutdown and Hot Standby..............
3/4 4-2 3/4.4.2 SAFETY VALVES - SHUTDOWN..............
3/4 4-3 3/4.4.3 SAFETY VALVES AND PILOT OPERATED RELIEF VALVE -
OPERATING.....................
3/4 4-4 DAVIS-BESSE, UNIT I IV Amendment No. 30,35,134,135, 107,170,174,201
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INDEX I
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PME 3/4.4.4 PRESSURIZER....................
3/4 4-5 3/4.4.5 STEAM GENERATORS...................
3/4 4-6
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3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.............
3/4 4-13 i
Operational Leakage.................
3/4 4 15 3/4.4.7 CHEMISTRY.....................
3/4 4-17 3/4.4.8 SPECIFIC ACTIVITY.................
3/4 4-20 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System...............
3/4 4-24 Pressurizer....................
3/4 4-29 3/4.4.10 STRUCTURAL INTEGRITY................
3/4 4-30 3/4.4.11 Deleted......................
3/4 4-32 l
3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 CORE FLOODING TANKS................
3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T, 2 280 F...........
3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T,, < 280 F...........
3/4 5-6 3/4.5.4 BORATED WATER STORAGE TANK.............
3/4 5-7
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DAVIS-BESSE, UNIT 1 V
Amendment No. -lMr 201
INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY B 3/4 0-1 3 /4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL..................
B 3/4 1-1 3/4.1.2 B0 RATION SYSTEMS..................
B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES.............
B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS B 3/4 2-1 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR PROTECTION SYSTEM AND SAFETY SYSTEMS INSTRUMENTATION B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION.............
B 3/4 3-2 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS...............
B 3/4 4-1 3/4.4.2 and 3/4.4.3 SAFETY VALVES..............
B 3/4 4-1 3/4.4.4 PRESSURIZER....................
B 3/4 4-2 3/4.4.5 STEAM GENERATORS..................
B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE...........
B 3/4 4-4
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3/4.4.7 CHEMISTRY.....................
B 3/4 4-5 3/4.4.B SPECIFIC ACTIVITY..................
B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS............
B 3/4 4-6 3/4.4.10 STRUCTURAL INTEGRITY B 3/4 4-13 3/4.4.11 Deleted......................
B 3/4 4-13 l
DAVIS-BESSE, UNIT 1 IX Amendment No. 44,201
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DELETED l
1 (Pages 3/4 3-37 through 3/4 3-42 have been deleted.)-
The next page is page 3/4 3-43.
DAVIS-BESSE, UNIT I 3/4 3-37 Amendment No.201
3/4.3 INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION j
The OPERABILITY of the radiatier. monitoring channels ensures that 1) the
)
radiation levels are continually measured in the areas served by the i
individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. See Bases Figures 3-1 and 3-2 for examples of acceptable minimum incore detector arrangements.
3/4.3.3.3 SEISMIC INSTRUMENTATION Deleted l
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION Deleted l
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of DAVIS-BESSE, UNIT 1 B 3/4 3-2 Amendment No. 201
REACTOR COOLANT SYSTEM BASES 3/4.4.10 STRUCTURAL INTEGRITY 1
The inspection programs for ASME Code Class 1, 2 and 3 components, except steam generator tubes, ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant. To the extent applicable, the inspection program for these components is in compliance with Section XI of the ASME Boiler and Pressure Vessel Code.
The internals vent valves are provided to relieve the pressure generated by steaming in the core following a LOCA so that the core remains sufficiently covered.
Inspection and manual actuation of the internals vent valves 1) ensure OPERABILITY, 2) ensure that the valves are not stuck open during normal i
operation, and 3) demonstrate that the valves are fully open at the forces i
equivalent to the differential pressures assumed in the safety analysis.
3.4.4.11 HIGH POINT VENTS Deleted l
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l DAVIS-BESSE, UNIT I B 3/4 4-13 Amendment No.-6,201
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f ADMINISTRATIVE CONTROLS l
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission in accordance with 10 CFR 50.4 within the time period specified for i
each report. These reports shall be submitted covering the activities I
identified below pursuant to the requirements of the applicable reference specifications:
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a.
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
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b.
Deleted l
f c.
Deleted l
i d.
Deleted l
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e.
Deleted f.
Deleted g.
Inoperable Remote Shutdown System control circuit (s) or transfer i
switch (es) required for a serious control room or cable spreading i
room fire, Specification 3.3.3.5.2.
6.10 RECORD RETENTIDH 6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of facility operation covering time interval at i
each power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
All REPORTABLE EVENTS.
d.
Records of surveillance activities, inspections and calibrations i
required by these Technical Specifications.
e.
Records of changes made to Operating Procedures.
f.
Records of radioactive shipments.
g.
Records of sealed source and fission detector leak tests and results.
h.
Records of annual physical inventory of all sealed source material of record.
DAVIS-BESSE, UNIT 1 6-18 Amendment 0,12,05,05,105,
-130,170,174,107, 201
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