ML20205N206
| ML20205N206 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/08/1999 |
| From: | Emch R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205N210 | List: |
| References | |
| NUDOCS 9904160183 | |
| Download: ML20205N206 (7) | |
Text
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 0001
%,.....,o DUKE ENERGY CORPORATION NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 CATAWBA NUQLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 177 License No. NPF-35
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility)
Facility Operating License No. NPF-35 filed by the Duke Energy Corporation, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated March 15,1999, and supplemented by letter dated March 17,1999, complies with the standards and requirements of the Atomic Energy i
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 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 Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amenoi6ent will not be inimical to the common defense and security or to the health and safety of the public; and E. The :ssuance of this amendment is in accordance with 10 CFR Part 51 of the
- > :imission's regulations and all applicable requirements have been satisfied.
9904160183 990408 PDR ADOCK 05000413 P
, 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:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 177, which are attached hereto, are hereby incorporated into this license. Duke Energy Corporation 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 withia 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b
Richard L. Emch, Jr., Chief, Section 1 Project Directorate ll Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance: April 8, 1999 i
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t UNITED STATES
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 206 6 0001
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PUKE ENERGY CORPORATION NORTH CAROLINA MUNICIPAL POWER AGENCY NO.1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 169 License No. NPF-52
- 1. The Nuclear Regulatory Commission (the Commission) 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 Energy Corporation, acting for itself, North Carclina Municipal Power Agency No.1 and Piedmont Municipal Power Agency (licensees), dated March 15,1999, and supplemented by letter dated March 17, 1999, 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 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 Commission's regulations set forth in 10 CFR Chapter I; 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 ir, accordance with 10 CFR Part 51 cf the Commission's regulations and all applicable requirements have been satisfied.
, 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:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.169, which are attached hereto, are hereby incorporated into this license. Duke Energy Corporation 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 within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
Richard L. Emch, Jr., Chief, Section 1 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance: April 8,1999
1 ATTACHMENT TO LICENSE AMENDMENT NO. 177 TO FACILITY OPERATING LICENSE NO. NPF-35 AND LICENSE AMENDMENT NO.169 TO FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NOS. 50-413 AND 50-414 Replace the following page of the joint Technical Specifications (Appendix A of the Operating Licenses) with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the areas of charge.
BALn.gyg 10,gtil 1
i i
3.3.7-1 3.3.7-2 3.3.7-3 3.3.7-4 3.3.8-1 3.3.8-2 3.3.8-3 Replace the following pages of the Technical Specifications Bases with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove irggi i
i B 3.3.7-1 B 3.3.7-2 B 3.3.3-3 B 3.3.3-4 B 3.3.7-5 B 3.3.8-1 B 3.3.8-2 B 3.3.8-3 B 3.3.8-4
TABLE OF CONTENTS 1.0 U S E AND APPLICATION......................................................................... 1.1 -1 1.1 Definitions............................................................................................. 1.1 - 1 1.2 Logical Connectors............................................................................... 1.2-1 1.3 Completion Times............................................................................... 1.3-1 1.4 Frequency............................................................................................. 1.4-1 2.0 SAFETY LIMITS (SLs)............................................................................. 2.0-1 2.1 SLs........................................................................................................2.0-1 2.2 S L Viola tions....................................................................................... 2.0- 1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.............. 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY............................ 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS..................................................... 3.1.1 -1 3.1.1 SMUTOOWN MARGIN (SDM)..................................................... 3.1.1 -1 3.1.2 Core Reactivity............................................................................ 3.1.2-1 3.1.3 Moderator Temperature Ccofficient (MTC).................................... 3.1.3-1 f
3.1.4 Rod Group A!ignment Limits.......................................................... 3.1.4-1 3.1.5 Shutdown Bank insertion Limits.................................................... 3.1.5-1 3.1.6 Control Bank Insertion Limits......................................................... 3.1.6-1 3.1.7 Rod Position Indication.................................................................. 3.1.7-1 3.1.8 PHYSICS TESTS Exceptions....................................................... 3.1.8-1 3.2 POWER DISTRIBUTION LIMITS.......................................................... 3.2.1 -1 3.2.1 Heat Flux Hot Channel Factor (Fo(X,Y,Z))..................................... 3.2.1-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (Fm(X,Y))................... 3.2.21 3.2.3 AXI AL FLUX DIFFERENCE (AFD)................................................ 3.2.3-1 3.2.4 OUADRANT POWER TILT RATIO (OPTR)................................... 3.2.4-1 3.3 i N STR U M ENTATION............................................................................ 3.3.1 -1 I
3.3.1 Reactor Trip System (RTS) instrumentation.................................. 3.3.1-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)
I n stru mentation........................................................................ 3.3.2-1 3.3.3 Post Accident Monitoring (PAM) Instrumentation........................... 3.3.3-1 3.3.4
' Remote Shutdown System............................................................ 3.3.4-1 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start i nstrumentation...................................................................... 3.3.5-1 3.3.6 Containment Purge and Exhaust isolation L
I nstrumentation........................................................................ 3.3. 6-1 3.3.7 Not Used 3.3.8 Not Used 3.3.9 Boron Dilution Mitigation System (BDMS)..................................... 3.3.9-1 v
Catawba Units 1 and 2 i
Amendment Nos.177 (Unit i 169 (Unit 2
TABLE OF CONTENTS B 2.0 SAFETY LIMITS (SLs)
B 2.1.1 R ea ctor Core S Ls........................................................................... B 2.1.1 - 1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL................................. B 2.1.2-1 B3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY....... B 3.0-1 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY...................... B 3.0-9 B 3.1 REACTIVITY CONTROL SYSTEMS B 3.1.1 SH UTDOWN MARG I N (SDM).........-............................................. B 3.1.1 -1 B 3.1.2 Core R ea ctivity................................................................................ B 3.1.2-1 B 3.1.3 Moderator Temperature Coefficient (MTC)..................................... B 3.1.3-1 B 3.1.4 Rod G roup Alignment Limits.......................................................... B 3.1.4-1 B 3.1.5 Shutdown Bank insertion Limits...................................................... B 3.1.5-1 B 3.1.6 Control Bank Insertion Limits.......................................................... B 3.1.6-1 B 3.1.7 Rod Position Indication................................................................... B 3.1.7-1 B 3.1.8 PHYSICS TESTS Exceptions........................................................ B 3.1.8-1 B 3.2 POWER DISTRIBUTION LIMITS B 3.2.1 Heat Flux Hot Channel Factor (FO(X,Y,Z))..................................... B 3.2.1-1 B 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FAH(X,Y))................... B 3.2.2-1 B 3.2.3 AX1/.L FLUX DI FFERENCE (AFD)................................................ B 3.2.3-1 B 3.2.4 OUADRANT POWER TILT RATIO (OPTR).................................... B 3.2.4-1 B 3.3 INSTRUMENTATION B 3.3.1 Reactor Trip System (RTS) Instrumentation................................... B 3.3.1-1 B 3.3.2 Engineered Safety Feature Actuation System (ESFAS)
I n stru m entation....................................................................... B 3.3.2-1 B 3.3.3 Post Accident Monitoring (PAM) Instrumentation............................ B 3.3.3-1 B 3.3.4 Remote Shutfown System.............................................................. B 3.3.4-1 B 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation B 3.3.5-1 B 3.3.6 Containment Purge and Exhaust isolation Instrumentation............. B 3.3.6-1 B 3.3.7 Not Used B 3.3.8 Not Used B 3.3.9 Boron Dilution Mitigation System (BDMS)....................................... B 3.3.9-1 B 3.4 REACTOR COOLANT SYSTEM (RCS)
B 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits................................................. B 3.4.1-1 B 3.4.2 RCS Minimum Temperature for Criticality....................................... B 3.4.2-1 B 3.4.3 RCS Pressure and Temperature (P/T) Limits.................................. B 3.4.3-1 B 3.4.4 RCS Loops-MODES 1 and 2........................................................ B 3.4.4-1 3 3.4.5 R C S Loops-MO D E 3..................................................................... B 3.4.5-1 8 3.4.6 R CS Loops-M OD E 4..................................................................... B 3.4.6-1 B 3.4.7 RCS Loops-MODE 5, Loops Filled................................................ B 3.4.7-1 B 3.4.8 RCS Loops-MODE 5, Loops Not Filled......................................... B 3.4.8-1 Catawba Units 1 and 2 i
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