ML20073M249
| ML20073M249 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  (NPF-87-A-028, NPF-87-A-28, NPF-89-A-014, NPF-89-A-14) |
| Issue date: | 10/05/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073M252 | List: |
| References | |
| NUDOCS 9410140216 | |
| Download: ML20073M249 (7) | |
Text
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t UNITED STATES j g&f j NUCLEAR REGULATORY COMMISSION y
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\\...;.. y TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 28 License No. NPF-87 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Texas Utilities Electric Company (TV Electric, the licensee) dated March 28, 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 set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, as amended, 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; D.
The issuance of this license 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 amended by 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-87 is hereby amended to read as follows:
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2.
Technical Soecifications and Environmental Protection Plan The -Technical Specifications contained in Appendix A, as revised through Amendment No. 28, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance, to be implemented within 30 days of issurance.
FOR THE NUCLEAR REGULATORY COMMISSION Q
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William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 5, 1994 i
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NUCLEAR REGULATORY COMMISSION
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gi nr TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 2 DOCKET NO. 50-446-AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.14 License No. NPF-89 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Texas Utilities Electric Company (TU Electric, the licensee) dated March 28, 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 set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, 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; D.
The issuance of this license 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 th'is 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 amended by 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-89_ is hereby.
amended to read as follows.
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4 9 1 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.14, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
TV Electric 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, to be implemented within 30 days of issuance.
4 FOR THE NUCLEAR REGULATORY COMMISSION fu'N :- D. U
^
William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 5, 1994 l
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ATTACHMENT TO LICENSE AMENDMENT NOS, 28 AND 14 FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 DOCKET NOS. 50-445 AND 50-446 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by Amendment number and contains a marginal line indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
FEMOVE INSERT 6-21 6-21 l
i l
i 1
J
ADMINISTRATIVE CONTROLS v
CORE OPERATING LlHITS REPORT (Continued) 5).
WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL F o
i SURVEILLANCE TECHNICAL SPECIFICATION," June 1983 (W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor (W(z) surveillance requirements for F Methodology).)
6).
WCAP-10079-P-A, "NOTRUMP, A N0DAL TRANSIENT SMALL BREAK AND GENERAL NETWORK CODE," August 1985, (W Proprietary).
7).
WCAP-10054-P-A, " WESTINGHOUSE SMALL BREAK ECCS EVALUATION MODEL USING THE NOTRUMP CODE", August 1985, H Proprietary).
8).
WCAP-lll45-P-A, " WESTINGHOUSE SMALL BREAK LOCA ECCS EVALUATION MODEL GENERIC STUDY WITH THE NOTRUMP CODE", October 1986, H Proprietary).
9).
RXE-90-006-P, " Power Distribution Control Analysis and Overtemperature N-16 and Overpower N-16 Trip Setpoint Methodology," February 1991.
(Methodology for Specification 3.2.1 - Axial Flux. Difference, 3.2.2 -
Heat Flux Hot Channel Factor.)
l 10). RXE-88-102-P, "TUE-1 Departure from Nucleate Boiling Correlation",
January 1989, i
11). RXE-88-102-P. Sup. 1, "TUE-1 DNB Correlation - Supplement 1",
December 1990.
l 12). RXE-89-002, "VIPRE-01 Core Thermal-Hydraulic Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications", June 1989.
13). RXE-91-001, " Transient Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications", February 1991.
t 14). RXE-91-002, " Reactivity Anomaly Events Methodology", May 1991.
(Methodology for Specification 3.1.1.3 - Moderator Temperature 1
Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 -
Control Cank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 -
i Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)
15). RXE-90-007, "Large Break Loss of Coolant Accident Analysis Methodology", December 1990.
16). TXX-88306, " Steam Generator Tube Rupture Analysis", March 15, 1988.
17). RXE-91-005, " Methodology for Reactor Core Response to Steamline Break Events," May, 1991.
COMANCHE PEAK - UNITS 1 AND 2 6-21 Unit 1 - Amendment No. 1,6,14,18,21,28 Unit 2 - Amendment No. 49,14
4 ADMINISTRATIVE CONTROLS g
CORE OPERATING LIMITS REPORT (Continued)
Reference 18) is for Unit 2 only:
18).'WCAP-9220-P-A, Rev. 1, " WESTINGHOUSE ECCS EVALUATION MODEL-1981 Version", February 1982 (W Proprietary).
6.9.1.6c 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.
6.9.1.6d The CORE OPERATING LidITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
COMANCHE PEAK - UNITS 1 AND 2 6-21a Unit 1 - Amendment No. 21 Unit 2 - Amendment No. 7