ML20076G343
| ML20076G343 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/07/1994 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076G346 | List: |
| References | |
| NUDOCS 9410190256 | |
| Download: ML20076G343 (12) | |
Text
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UNITED STATES w
i ci NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY NORTH CAPAINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 125 License No. NPF-35 1.
The Nucleac 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 Power Company, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated May 24, 1994, as supplemented on August 4 and September 8, 1994, 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 w;11 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.
9410190256 941007 DR ADOCK 05000413 PDR
. '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:
Technical Soecifications f
The Technical Specifications cor tained 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 i
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 i
rtN. Berk,kLG j
v ow, Director
," Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
t Technical Specification Changes i
Date of Issuance: October 7,1994 1
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'S UNITED STATES t,
NUCLEAR REGULATORY COMMISSION "g
WASHINGTON, D.C. 20555-4001
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DUKE POWER COMPANY 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. 119 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 i
by the Duke Power Company, acting for itself, North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency (licensees), dated May 24, 1994, as supplemented August 4 and September 8,1994, 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 in accordance with 10 CFR Part 51 of 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 l
amendment, and Paragraph 2.C.(2) of Facility Operating License No.
NPF-52 is hereby amended to read as follows:
~
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.119
, 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 i
Specifications and the Environmental Protection Plan.
i 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 fn 9aN Ee~rb r
. Berkow, Director f
j Project Directorate II ;
Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: October 7,1994 l
5
t ATTACHMENT TO LICENSE AMENDMENT NO.125 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 119 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 l
Replace the following pages of the Appendix "A" Technical Specifications with 1
the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaes Insert Paaes 3/4 7-41 3/4 7-41 3/4 7-42 3/4 7-42 3/4 9-1 3/4 9-1 6-19 6-19 6-19a 6-19a l
6-19b B 3/4 9-1 B 3/4 9-1 4
1 3
-=
PLANT SYSTEMS SVRVEILLANCE RE0VIREMENTS (Continued) b.
At least once per 92 days by verifying.that the individual cell voltage -is greater than or equal to 1.36 volts on float charge, and c.
At least once per 18 months by verifying that:
~
1)
The batteries, cell plates, and battery racks'show no visual indication of physical damage or abnormal deterioration, and 2)
The battery-to-battery and terminal connections are clean, tight, and free of corrosion.
4.7.13.3 The Standby Makeup Pump water supply shall be demonstrated OPERABLE by:
+
a.
Verifying at least once per 7 days:
1)
That the requirements of Specification 3.9.10 are met and the boron concentration in the storage pool is greater than or equal to the minimum specified in the Core Operating Limits Report, or 2)
That a contained borated water volume of at least 112,320 gallons with a boron concentration of greater than or equal to the minimum specified in the Core Operating Limits i
Report is available and capable of being aligned to the Standby 1
Makeup Pump.
j i
b.
Verifying at least once per 92 days that the Standby Makeup Pump.
develops a flow of greater than or equal to 26 gpm at a pressure greater than or equal to 2488 psig.
4.7.13.4 The Standby Shutdown System 250/125-Volt Battery Bank and its associated charger shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying:
1)
That the electrolyte _ level of-each battery is above the plate.,
and i
2)-
The total battery terminal voltage is greater than or equal to 258/129 volts on float charge.
i b.
At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the battery, and i
i i
CATAWBA - UNITS 1 & 2 3/4 7-41 Amendment No.125 (Unit 1)
Amendment No.119 (Unit 2)
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
At least once per 18 months by verifying that:
1)
The batteries, cell plates, and battery racks show no visual indications of physical damage or abnormal deterioration, and 2)
The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.
4.7.13.5 The Steam Turbine Driven Auxiliary Feedwater Pump and associated components shall be demonstrated OPERABLE at least once per 18 months by veri-fying that the system functions as designed from the Standby Shutdown System.
4.7.13.6 Each Standby Shut fown System instrumentation device shall be demonstrated OPERABLE by performance of a CHANNEL CHECK at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.*
- The CHANNEL CALIBRATION requirement of this surveillance need not be performed for level transmitter 1 CFLT5632 until prior to entering HOT STANDBY following the Unit I first refueling.
(This applies to Unit 1 only.)
CATAWBA - UNITS 1 & 2 3/4 7-42 Amendment No. 125 (Unit 1)
Amendment No. 119 (Unit 2)
i 3/4,9 REFUELING OPERATIONS i
I 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met either:
a.
A K,,, of 0.95 or less, or b.
A boron concentration of greater than or equal to the minimum
[
specified in the Core Operating Limits Report.
APPLICABILITY: MODE 6.*
ACTION:
With the requirements of the above specification not satisfied, immediately l
suspend all operations involving CORE ALTERATIONS or positive reactivity.
changes and initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or its equi-l valent until K,,, is reduced to less than or equal to 0.95 or the boron con-centration is restored to greater than or equal to the minimum specified in 5
the Core Operating Limits Report, whichever is the more restrictive.
SURVEILLANCE RE0VIREMENTS l
4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:
i a.
Removing or unbolting the reactor vessel head, and b.
Withdrawal of any full-length control rod in excess of 3 feet from its fully inserted position within the reactor vessel.
4.9.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
l 1
i
- The reactor shall be maintained in MODE 6 whenever fuel is in the reactor i
vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
CATAWBA - UNITS 1 & 2 3/4 9-1 Amendment No. 125 (Unit 1)
Amendment No.119 (Unit 2)
L ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)
P
- 10. Accumulator and Refueling Water Storage Tank boron concentration limits for Specifications 3/4.5.1 and 3/4.5.4.
- 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.
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 (H Proprietary).
(Methodology for Specifications 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.)
2.
WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION," June 1983 (H Proprietary).
(Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z) surveillance requirements for Fo Methodology.)
3.
WCAP-10266-P-A Rev. 2, "THE 1981 VERSION OF WESTINGHOUSE EVAL'JATION MODEL USING BASH CODE," March 1987, (H Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
4.
BAW-10168PA, Rev.1, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," January 1991 (B&W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
f CATAWBA - UNITS 1 & 2 6-19 Amendment No.125 (Unit 1)
Amendment No.119 (Unit 2)
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) i 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 Instrumentation Setpoints, 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.)
i 6.
DPC-NE-3001P-A, " Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," November 1991 (DPC Proprietary).
(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-2010P-A, " Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design," June 1985 (DPC Proprietary).
(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 Boron Concentration.)
8.
DPC-NE-3002A, "FSAR Chapter 15 System Transient Analysis Methodology,"
November 1991.
(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," November 1991.
(Modeling used in the system thermal-hydraulic analyses) i 1
CATAWBA - UNITS 1 & 2 6-19a Amendment No.125 (Unit 1)
Amendment No.119 (Unit 2)
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)
- 10. DPC-NE-1004A, " Design Methodology Using CASMO-3/ Simulate-3P," November 1992.
(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 FAH (X,Y).)
- 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.)
The core operating limits shall be determined 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.
l 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.
j i
CATAWBA - UNITS 1 & 2 6-19b Amendment No.125 (Unit 1)
Amendment No.119 (Unit 2)
I
3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:
(1) the reactor will remain subcritic:11 during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel.
These limitations are consistent with the initial conditions assumed for the boron dilution incident in the safety analyses.
The value of 0.95 or less for K,# includes a 1% Ak/k conservative allowance for uncertainties.
Similarly, the boron concentration value equal to that specified in the Core Operating Limits Report or greater includes a conservative uncertainty allowance of 50 ppm boron.
3/4.9.2 INSTRUMENTATION The OPERABILITY of the Boron Dilution Mitigation System ensures that monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products. This decay time is consistent with the assumptions used in the safety analyses.
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY of the Reactor Building Containment Purge System ensure that a release of radioactive material within containment will be restricted from leakage to the environment or filtered through the HEPA filters and activated carbon adsorbers prior to release to the atmosphere.
The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE. Operation of the Reactor Building Con-tainment Purge System and the resulting iodine removal capacity are consistent with the assumption of the safety analysis. Operation of the system with the heaters operating to maintain low humidity using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. ANSI N510-1980 will be used as a procedural guide for surveillance testing.
CATAWBA - UNITS 1 & 2 B 3/4 9-1 Amendment No.125 (Unit 1)
Amendment No.119 (Unit 2)
.