ML20086Q242
| ML20086Q242 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/21/1995 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20086Q246 | List: |
| References | |
| NUDOCS 9507270360 | |
| Download: ML20086Q242 (9) | |
Text
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x jprerg At UNITED STATES
.p NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20666-0001
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SA. LEA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE t
Amendment No.131 License No. NPF-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, l
Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company, acting for itself, North Carolina Electric Nembership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated April 12, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations as 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 Comission; 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 Comission's regulations set l
forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
9507270360 950721 PDR ADDCK 05000413 p
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2.
Accordingly, the license is hereby amended by page 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-35 is hereby amended to read as follows:
i Technical Specifications I
The Technical Specifications contained in Appendix A, as revised through Amendment No.131, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Duke Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION j
(
M H r ert 1. Ber ow, Director Project Directorate 11-2 e
Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation
Attachment:
Technical Specification i
Changes Date of Issuance: July 21,1995 O
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NUCLEAR REGULATORY COMMISSION t
WASHINGTON. D.C. 20066 4001 j.,
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY l
DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 125 License No. NPF-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company, acting for itself, North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency (licensees), dated April 12, 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 as 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 Comission; e
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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is hereby amended by page 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-52 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.125
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Duke Power Company sht.11 operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
F THE NUCLEAR REGULATORY COMMISSION vt.Y w
l H rbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes l
Date of Issuance: July 21, 1995
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ATTACMENT TO LICENSE AMENDMENT NO.131 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 8HQ TO LICENSE AMENDMENT NO. 125 FACILITY OPERATING LICENSE NO. NPF-52 3
DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaes Insert Paaes VI VI XII XII 3/4 3-87 3/4 3-87 B 3/4 3-7 8 3/4 3-7 T
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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS L
SECTION EA_GE 1
. TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION............ 3/4 3-60 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......................................... 3/4 3-61 Remote Shutdown System............................... 3/4 3-62 TABLE 3.3-9 REMOTE SHUTDOWN MONITORING INSTRUMENTATION........... 3/4 3-63 i
TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................ 3/4 3-64 Accident Monitoring Instrumentation.................. 3/4 3-65 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION.................. 3/4 3-66 i
TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......................................... 3/4 3-68 Chl orine Detection Systems........................... 3/4 3-70 TABLE 3.3-11 (Deleted)
Loose-Part Detection System.......................... 3/4'3-79 Explosive Gas Monitoring Instrumentation............. 3/4 3-80 TABLE 3.3-12 EXPLOSIVE GAS MONITORING INSTRUMENTATION............. 3/4 3-81 TABLE 4.3-8 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................ 3/4 3-83 l
Boron Dilution Mitigation System..................... 3/4 3-85 3/4.3.4
( Del et ed )............................................ 3 / 4 3 -8 7 3/4.4 REACTOR COOLANT SYSTEM l
3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation............................... 3/4 4-1 Hot Standby............................................... 3/4 4-2 Hot Shutdown.............................................. 3/4 4-3
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Col d Shutdown - Loops Fi11 ed.............................. 3/4 4-5 Cold Shutdown - Loops Not Fi11ed.......................... 3/4 4-6
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i CATAWBA - UNITS 1 & 2 VI Amendment No.131 (Unit 1)
Amendment No.125 (Unit 2)
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' 3/4.0' APPLICABILITY..............................................B 3/4 0-1 j
-j 3/4.1 REACTIVITY CONTROL SYSTEMS-
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. 3/4.1.1 B0 RATION CONTR0L..........................................B 3/4 1-l' l
3/4.1.2 BORATION SYSTEMS.....................
....................B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES................................B 3/4 1 l 1
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' 3/4.2 POWER DISTRIBUTION LIMITS (Unit 1)........................B 3/4 2-1 1
t 3/4.2.1 AXIAL FLUX DIFFERENCE (Unit 1)............................B 3/4 2-1
-l 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Unit 1).................B 3/4 2-l' 3/4.2.4 QUADRANT POWER TILT RATIO (Unit 1)........................B 3/4 2-3 3/4.2.5 DNB PARAMETERS (Unit 1)...................................B 3/4 2-3
_ 1/4.2 POWER DISTRIBUTION LIMITS (UNIT 21.......................B 3/4 2-5 3/4.2.1 AXIAL FLUX DIFFERENCE (Unit 2)............................B 3/4 2-5 j
3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR, and REACTOR COOLANT SYSTEM FLOW. RATE AND NUCLEAR ENTHALPY j
RISE HOT CHANNEL FACTOR (Unit.2)..........................B 3/4.2-7 j
3/4.2.4 QUADRANT POWER TILT RATIO (Unit 2)........................B 3/4 2-9 j
3/4.2.5 DNB PARAMETERS.(Unit 2)...................................B 3/4 2-10
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3/4.3 INSTRUMENTATION 3/4.3.1 and'3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.................B 3/4 3-1 j
3/4.3.3 MONITORING INSTRUMENTATION................................B 3/4 3-3 3/4.3.4 ( Del e t ed )................................................. B 3 /4 3-7 l
CATAWBA - UNITS 1 & 2 XII Amendment No.131 (Unit 1) l Amendment No.125 (Unit 2)
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INSTRUMENTATION 3/4.3.4 (Deleted)-
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CATAWEA - UNITS 1 & 2 3/4 3-87 Amendment No.131 (Unit 1)-
I Amendment No.125 (Unit 2) l
1 INSTRUMENTATION BASES 3/4.3.3.11 BORON DILUTION MITIGATION SYSTEM The operability of the Boron Dilution Mitigation System ensures that pro-tection against a loss of shutdown margin from a boron dilution event is pre-sent. This system uses two source range detectors to monitor the subcritical multiplication of the reactor core. An alarm setpoint is continually calculated as 4 times the lowest measured count re e, including compensation for background and the statistical variation in the count rate. Once the alarm setpoint is exceeded, each train of the Boron Dilution Mitigation System will automatically shut off both Reactor Makeup Water Pumps, isolate flow to the charging pumps from the Volume Control Tank, and align the suction of the charging pumps to highly borated water from the RWST. These actions automatically isolate the potential sources of diluted water and allow injection of highly borated water into the Reactor Coolant System.
In the event that the Boron Dilution Mitigation System is inoperable or not operating, the Source Range Neutron Flux Monitors may be used to provide protection against a loss of shutdown margin from a boron dilution event.
If the Source Range Neutron Flux Monitors are used to monitor the subcritical multiplication of the reactor core, the alarm setpoint must be calibrated and periodically checked to ensure that it is less than or equal to one-half decade above the steady-state count rate.
In addition, the flow from the Reactor Make-up Water Pumps must be verified as below specified limits. These actions ensure that adequate time is available for the operator to recognize and terminate a dilution event prior to a loss of shutdown margin.
3/4.3.4 Deleted CATAWBA - UNITS 1 & 2 B 3/4 3-7 Amendment No.131(Unit 1)
Amendment No.125(Unit 2)