ML20197A626
| ML20197A626 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/02/1998 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20197A630 | List: |
| References | |
| NUDOCS 9803090322 | |
| Download: ML20197A626 (10) | |
Text
__ __ _ _. _
- $30'00y9 a
UNITED STATES g
,j NUCLEAR REGULATORY COMMISSION WASHINGTON, o.C. SoulWoot 9.....,8
'4 DUKE ENERGY CORPORATION NORTH CAROLINA ELECTRIC MEMBERSHIF,f,ORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 ALENDMENT TO FACILITY OPERATING LICENSE Amendment No. 163 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 Enargy Corporation, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperativo, Inc. (licensees), dated December 17, 1997, 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 f"Hity will operate in confarmity 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 helth 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.
9803090322 980302 PDR ADOCK 05000413 P
s 2-2.
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 fol'ows:
(2) Technical Soecifications The Technical Specificatkns contained in Appendix A, as revised through Amendment No.163 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 impiamented within 30 days from the date of is6uance.
FOR THE NUCLEAR REGULATORY COMMISSION 1) f l
A-H rbert N. Berkow, Director jf oject Directorate ll 2 Division of Reactor Projects 1/II Office of Nuclear Reactor ReDulation
Attachment:
Technical Specification Changes Date of lasuance:
March 2, 1998 i
- 4 I
i ATTACHMENT TO LICENSE AMENDMENT NO.163 FACILITY OPERATING LICENSE NO. NPF.35 DOCKET NO. 50-413 Replace the following pages of the Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain verticallines indicating the areas of change.
Remove jnand 6 22 6 22 i
6 23 6-23 a
ADMINISTRATIVE CONTROLS.
CORE OPERATING LIM 11S REPORT (Continued)
(Methodology for 5)ecification 3.1.1.3 - Moderator Temperature Coeffi-cient, 3.1.3.5 - Slutdown Rod Insertion Limits, 3.1.3.6 - Control Btnk Insertion Limits, 3.2.1 - Axial Flux Dif ference, 3.2.2 - Heat
~.ux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)
7.
DPC-NF-2010A, " Duke Power Company McGuire Nuclear Staticn 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 Soron Concentration, and Specification 3.9.1 - RCS and Refueling Canal Boron Concentration, and Specification 3.9.12 - Spent Fuel Pool Boron Concentration.)
8.
DPC-NE-3002A, lic ough Rev. 2, "FSAR Cnapter 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.
i (Modeling used in the system thermal-hydraulic analyses)
- 10. DPC-NE-1004A, Rev.1
" Design Methodology Using CASM0-3/ Simulate-3P." SER Dated April 26, 1996.
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient.)
- 11. DPC-NE-2004P-A, Rev.1, " Duke Power Company McGuire and Catawba Nuclear Stations Co' e Thermal-Hydraulic Methodology using VIPRE-01," SER dated February 20, 1997 (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 Fa (X,Y).)
- 12. DPC-NE-2001P-A, Rev.1, ' Fuel Mechanical Reload Analysis Methodology for Ma-k-BW Fuel," October 1990 (DPC Proprietary).
(Methodology for Specification 2.2.1 - Reactor Trip System Instrumentation Setpoints.)
- 13. DFC-NE-2005P-A, Rev.1. " Thermal Hydraulic Statistical Core Design Methodology " SER dated November 7, 1996 (DOC Proprietary).
(Methodology for Specification 2.2.1 - Reactor Trip System Instrum- 'ation Setpoints, Specification 3.2.1 - Axial Flux Difference, and 3.2.., - Nuclear Enthalpy Rise Hot Channel Factor)
CATAWBA - UNIT 1 6-22 Amendment No.163
~
M tTRATIVE CONTROLS CORE OPEpATING LIMITS REPORT (Continued)
- 14. DPC-NE-2008P-A, " Fuel Mechanical Reload Analysis Methodology Using TACO 3, "
SER dated April 3, 1995 (DPC Proprietary).
(Methodology used for Specification 2.2.1 - Reactor Trip System Instiun,entation Setpoints)
- 15. BAW-10183P-A, " Fuel Rod cias Pressure Criterion," B&W Fuel Company, July, 1995.
(Used for Specification 2.2.1, Reactor Trip System Instrumentation Setpoints)
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic lirits, ECCS limits, nuclear limits such as shutdown margin, and transient ano accident analysis limits) of the safety analysis are met.
The CORE OPERATING LIlilTS REPORT, including any mid-cycle revisions or supple-ments thereto, shall be provided upon issuance, for each reload cy:le, to the NRC in accordance with 10 CFR 50.4.
SPECIAL REPORTS 6.9.2 3)ecial reports shall be submitted to the NRC in accordance with 10 CFR 50.4 wit 11n the time period specified for each report.
6.10 RECORD RETENTION 6.10.1 In additica to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
The following records shall be retained for at least 5 years:
a.
Records and logs of unit operation covering time interval at each power level; b.
Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nucicar safety; All REPORTABLE EVENTS; d.
Records of surveillance activities, inspections, and calibrations required by these Technical Specifications; e.
Records of changes made to the procedures required by Specification 6.8.1; f.
Records of radioactive shipments; g.
Records of sealed source and-fission detector leak tests and results; and CATAWBA - UNIT 1 6-23 Amendment No.163
a sse g$%
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UNITED STATES g
.g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C P.46W1
\\...+/
r DUKE ENERGY CORPORATION NORTH CAROLINA MUNICIPALPOWER AGENCY NO.1 PIEDMONT MUNICIP/)LEQWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.155 License No. NPF 52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
1 S
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 Carolina Municipal Power Agency No.1 and Piedmont Municipa; Powc-Agency (licensees), dated December 17,1997, K
Complies With the standh v., and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rutus and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity witn the application, the p ovisions of the g
Act, and the rules and regulctions of the Commission; C.
There is reasonable assurance (i) that the activities autnorized 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 irtuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2-2.
Accordingly, the !; cense is hereby amended by page changes to the Technical Specifications w 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 Soecific.ations The Technical Specifications contained in Appendix A, as revised through Ambndment No.155, which are attached nereto, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license air,andment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEA!; REGULATORY COMMISSION l
/
~
erbert N. Berkow, Director Pro,iect Directorate 112 Div,sion of Reactor Projects -l/ll Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: March 2, 1998 4
1 m
ATTACHMENT TO LICENSE AMENDMENTRM FACILITY OPERATING LICENSE NO. NPF 52 DOCKET NO. 50-414 Replace the following pages of the Technical Specifications with the enclosed pages The revised pages are dentified by Amendment number and contain vertical lines indicating the areas of change.
Remove lnsert 6-22 6-22 6-23 6-23
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Rod Insertion Limits, 3.1.3.f, - 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 Nucisar 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 Chnal Boron Concentration, and Specification 3.9.12 - Spent Fuel Pool Boron Concentration.)
8.
P C-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 P7, 1995.
l (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. Rev.1, " Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," SER dated February 20, 1997 (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-200lP-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, Rev.1, " Thermal Hydraulic Statistical Core Design Methodology," SER dated Novtmber 7, 1996 (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.155 m
ADMINISTRATIVE CONTROLS f&BE OPERATING LIMITS REPORT (Continued)
- 14. DPC-NE-2008P-A, " Fuel Mechanical Reload Analysis Methodology Using TAC 03, "
j SER dated April 3, 1995 (DPC Proprietary).
(Methadalogy used for Specification 2.2.1 - Reactor Trip System Instrumentation Setpoints)
- 15. PAW-10183P-A, " Fuel Rod Gas Pressure Criterion," B&W Fual Company, July, 1995.
(Used for Specification 2.2.1, Reactor Trip System Instrumentation Setpoints)
The core operating limits shall be determiaed so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supple-ments thereto, shall be provided upon issuance, for each reload cycle, to the NRC in accordance with 10 CFR 50.4.
SPECIAL REPORTS 6.9.2 S)ecial reports shall be submitted to the NRC in accordance with 10 CFR l
50.4 wit 11n the time period specified for each report.
6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
The following records shall be retained for at least 5 years:
Records and logs of unit operation covering time interval at each pover a.
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 required by these Technical Specifications; Records of changes made to the procedures required by Specification e.
6.8.1; f.
Records of radioactive shipments; g.
Records of sealed source and fission detector leak tests and results; and CATAWBA - UNIT 2 6-23 Amendment No.155
-