ML20129F836
| ML20129F836 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/24/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20129F841 | List: |
| References | |
| NUDOCS 9610290221 | |
| Download: ML20129F836 (10) | |
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4 UNITED STATES j
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20565 4001
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
3 DOCKET N0. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.154 License No. NPF-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
4 A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated August 8, 1996, 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 (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 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; 4
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.
9610290221 961024 PDR ADOCK 05000413 PDR 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.
NPC-35 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
154, which are attached hereto, are hereby incorporated into this license. Duke Power 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 within 30 days from the date of issuance.
FOR I E NUCLEAR REGULATORY COMMISSION b
R) n i
//
He'e$t
. Berk w, Director P ject Directorate 11-2 vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
October 24, 1996
u ATTACHMENT TO LICENSE AMENDMENT NO. 154 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 Replace the following pages of the Appendix "A" Technical Specifications with j
the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
i i
Remove Insert i
6-21 6-21 6-22 6-22 i
i
.f l
J
3
' ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) i j
- 11. Reactor Coolant System and refueling canal boron concentration limits for i
Specification 3/4.9.1.
i
- 12. Standby Makeup Pump water supply boron concentration limit of j
Specification 4.7.13.3.
- 13. Spent Fuel Pool boron concentration limit of Specification 3/4.9.12.
i The analytical methods used to determine the core operating limits shall be j
those previously reviewed and approved by NRC in:
)
1.
WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"
l July 1985 (W Proprietary).
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux
{
Hot Channel Factor, and 3.2.3 -Nuclear Enthalpy Rise Hot Channel Factor.)
l 2.
WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION," June 1983 (W Proprietary).
1 i
(Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z) j surveillance requirements for F, Methodology.)
1 3.
WCAP-10266-P-A Rev. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL j
USING BASH CODE," March 1987, (W Proprietary).
j (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
4.
BAW-10168P, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," Rev.1, SER dated January 1991; j
Rev. 2, SER Dated August 22, 1996; Rev. 3, SER Dated June 15, 1994 (B&W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
5.
DPC-NE-2011P-A, " Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," March, 1990 (DPC Proprietary).
(Methodology for Specifications 2.2.1 - Reactor Trip System 4
f Instrumentation Setpoints, 3.1.3.5 - Shutdown Rod Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 4
I 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)
4 I
6.
DPC-NE-300lP-A, " Multidimensional Reactor Transients and Safety Analysis l
Physics Parameter Methodology," November 1991 (DPC Proprietary).
1 CATAWBA - UNIT 1 6-21 Amendment No. 154 i
i
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coeffi-cient, 3.1.3.5 - Shutdown Rod Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)
7.
DPC-NF-2010A, " Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design," June 1985 (Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, Specification 4.7.13.3 - Standby Makeup Pump Water Supply Baron Concentration, and Specification 3.9.1 - RCS and Refueling Canal Boron Concentration, and Specification 3.9.12 - Spent Fuel Pool Boron Concentration.)
I 8.
DPC-NE-3002A, Through Rev. 2, "FSAR Chapter 15 System Transient Analysis d
Methodology," SER Dated April 26, 1996.
l l
(Methodology used in the system thermal-hydraulic analyses which i
determine the core operating limits) 9.
DPC-NE-3000P-A, Rev. 1, " Thermal-Hydraulic Transient Analysis Methodology," SER Dated December 27,-1995.
(Modeling used in the system thermal-hydraulic analyses)
- 10. DPC-NE-1004A, Rev.1, " Design Methodology Using CASMO-3/ Simulate-3P," SER Dated April 26, 1996.
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient.)
- 11. DPC-NE-2004P-A, " Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," December 1991 (DPC Proprietary).
(Methodology for Specifications 2.2.1 - Reactor Trip System Instrumentation Setpoints, 3.2.1 - Axial Flux Difference (AFD), and 3.2.3
- Nuclear Enthalpy Rise Hot Channel Factor Fu (X,Y).)
- 12. DPC-NE-2001P-A, Rev.1, " Fuel Mechanical Reload Analysis Methodology for Mark-BW Fuel," October 1990 (DPC Proprietary).
l (Methodology for Specification 2.2.1 - Reactor Trip System Instrumentation Setpoints.)
- 13. DPC-NE-2005P-A, " Thermal Hydraulic Statistical Core Design Methodology,"
February 1995 (DPC Proprietary).
(Methodology for Specification 2.2.1 - Reactor Trip System Instrumentation Setpoints, Specification 3.2.1 - Axial Flux Difference, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor)
CATAWBA - UNIT 1 6-22 Amendment No.154
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93 RER p
k UNITED STATES s
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2064 6 4001
\\...../
DUKE POWER COMPANY l
NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 1
PIEDMONT MUNICIPAL POWER AGENCY j
DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 146 License No. NPF-52 j
1.
The Nuclear Regulatory Commission (the Commission) has found that:
i 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 August 8, 1996, 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; j
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 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; t
and 3
1 E.
The issuance of this amendment is in accordance with 10 CFR l
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
i
)
5 1
... =
. 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. 146, which are attached hereto, are hereby incorporated into this license.
Duke Power 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 within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ll j
/
H bert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II 1
Office of Nuclear Reactor Regulation j
Attachment:
Technical Specification Changes Date of Issuance: October 24, 1996 l
- = _.- -
=. -.. -.
ATTACHMENT TO LICENSE AMENDMENT NO.146 FACILITY OPERATING LICENSE N0. NPF-52 DOCKET NO. 50-414 l
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 Insert i
6-21 6-21 6-22 6-22 i
1 4-i 4
r i
s i
s J
i f
4
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) i
- 11. Reactor Coolant System and refueling canal boron concentration limits for Specification 3/4.9.1.
- 12. Standby Makeup Pump water supply boron concentration limit of Specification 4.7.13.3.
- 13. Spent Fuel Pool boron concentration limit of Specification 3/4.9.12.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by NRC in:
1.
WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"
July 1985 (W Proprietary).
t (Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux
)
Hot Channel Factor, and 3.2.3 -Nuclear Enthalpy Rise Hot Channel Factor.)
1 2.
WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION," June 1983 (M Proprietary).
i (Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z) i surveillance requirements for F. Methodology.)
3.
WCAP-10266-P-A Rev. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE," March 1987, (W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
4.
BAW-10168P, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," Rev.1, SER dated January 1991; Rev. 2, SER Dated August 22, 1996; Rev. 3, SER Dated June 15, 1994 (B&W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
5.
DPC-NE-2011P-A, " Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," March, 1990 (DPC Proprietary).
4 (Methodology for Specifications 2.2.1 - Reactor Trip System Instrumentation Setpoints, 3.1.3.5 - Shutdown Rod Insertion Limits, 1
3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)
6.
DPC-NE-3001P-A, " Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," November 1991 (DPC Proprietary).
CATAWBA - UNIT 2 6-21 Amendment No. 146
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coeffi-cient, 3.1.3.5 - Shutdown Rod Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)
4 7.
DPC-NF-2010A, " Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design," June 1985 (Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, Specification 4.7.13.3 - Standby Makeup Pump Water Supply Boron Concentration, and Specification 3.9.1 - RCS and Refueling Canal 4
Boron Concentration, and Specification 3.9.12 - Spent Fuel Pool Boron Concentration.)
8.
DPC-NE-3002A, Through Rev. 2, "FSAR Chapter 15 System Transient Analysis Methodology," SER Dated April 26, 1996.
(Methodology used in the system thermal-hydraulic analyses which determine the core operating limits) 9.
DPC-NE-3000P-A, Rev. 1," Thermal-Hydraulic Transient Analysis Methodology," SER Dated December 27, 1995.
'1 (Modeling used in the system thermal-hydraulic analyses)
- 10. DPC-NE-1004A, Rev.1, " Design Methodology Using CASM0-3/ Simulate-3P," SER l
Dated April 26, 1996.
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient.)
i i
- 11. DPC-NE-2004P-A, " Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," December 1991 (DPC Proprietary).
(Methodology for Specifications 2.2.1 - Reactor Trip System Instrumentation Setpoints, 3.2.1 - Axial Flux Difference (AFD), and 3.2.3
- Nuclear Enthalpy Rise Hot Channel Factor Fu (X,Y).)
4
- 12. DPC-NE-2001P-A, Rev.1, " Fuel Mechanical Reload Analysis Methodology for Mark-BW Fuel," October 1990 (DPC Proprietary).
(Methodology for Specification 2.2.1 - Reactor Trip System Instrumentation Setpoints.)
- 13. DPC-NE-2005P-A, " Thermal Hydraulic Statistical Core Design Methodology,"
February 1995 (DPC Proprietary).
(Methodology for Specification 2.2.1 - Reactor Trip System Instrumentation Setpoints, Specification 3.2.1 - Axial Flux Difference, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor)
CATAWBA - UNIT 2 6-22 Amendment No.146