ML20081C402
| ML20081C402 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 03/14/1995 |
| From: | Beckner W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081C404 | List: |
| References | |
| NUDOCS 9503170239 | |
| Download: ML20081C402 (7) | |
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- UNITED STATES 3
U;%i NUCLEAR REGULATORY COMMISSION f
o WASHINGTON, D.C. 20565
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HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET NO. 50-498 SOUTH TEXAS PROJECT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE
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Amendment No. 72 License No. NPF-76
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1.
The Nuclear Regulatory Commission (the Cemission) has found that:
A.
The application for amendment by Houston Lighting & Power Company *
(HL&P) acting on behalf of itself and for the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL),
and City of Austin, Texas (C0A) (the licensees), dated March 9, 1995, 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:
(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
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E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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- Houston Lighting & Power Company is authorized to act for the City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
9503170239 950314 PDR ADOCK 05000498 P
j 2.
Accordingly, the license is amended by changes'to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 1.C.(2) of Facility Operating License No. NPF-76 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 72, and the Environmental Protection Plan i
contained in Appendix B, 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 prior to the end of the Unit I fifth refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION I
i ypC8- ). /W 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: March 14. 1995 i
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UNITED STATES 3.. ~
- E NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20066 '
HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY
[ITY OF AUSTIN. TEXAS DOCKET NO. 50-499 10UTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 61 License No. NPF-80 3.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Houston Lighting & Power Company *
(HL&P) acting on behalf af it* elf and for the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL),
and City of Austin, Texas (COA) (the licensees), dated March 9, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulation:. est 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; i
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; i
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 i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 4
of the Commission's regulations and all applicable requirements have been satisfied.
- Houston Lighting & Power Company is authorized to act for the City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
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,.1 a
, d 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the at.achment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-80 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised i
through Amendment No. 61, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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3.
The license amendment is effective as of its date of issuance to be implemented prior to the end of the Unit I fifth refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION Q
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/.,Y William D. Beckner, Director Project Directorate IV-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 14, 1995 i
i
A1TACHMENT TO LICENSE AMENDMENT N05. 72 AND 61 FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 l
DOCKET N05. 50-498 AND 50-499 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by Amendment number and contains marginal lines indicating the areas of change. The corresponding overleaf page is also provided to maintain document completeness.
1 REMOVE INSERT 6-22 6-22 t
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, _ g'MISTRATIVE CONTROLS l
M0hTHLY OPERATING REPORTS i
L 6.9.1.5 Routine reports of operating statistics and shutdown experience, i
including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Manage-
[
ment, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.-
CORE OPERATING LIMITS REPORT 6.9.1.6.a Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle, or any part of a reload cycle for the following:
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1.
Moderator Temperature Coefficient BOL and EOL limits, and 300 ppm surveillance limit for Specification 3/4.1.1.3, 2.
Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, 3.
Control Bank Insertion Limits for Specification 3/C.I.3.6, i
4.
Axial Flux Difference limits and target band for Specification 3/4.2.1, Heat Fg) Hot Channel Factor, K(Z), Power Factor Multiplier, 5.
and (F for Specification 3/4.2.2, and-y 6.
Nuclear Enthalpy Rise Hot Channel Factor, and Power Factor Multiplier for Specification 3/4.2.3.
j The CORE OPERATING LIMITS REPORT shall-be maintained available in the Control Room.
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6.9.1.6.b The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in 1.
WCAP 9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY", July, 1985 (){ Proprietary).
i (Methodology for Specification 3.1.1.3 - Moderator Temperature i
Coefficient, 3.1.3.5 + Shutdown Rod Insertion Limit, 3.1.3.6 -
1 Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy
.i Rise Hot Channel Factor.)
1.A.
WCAP 12942-P-A, " SAFETY EVALUATION SUPPORTING A MORE NEGATIVE EOL MODERATOR TEMPERATURE COEFFICIENT TECHNICAL SPECIFICATION FOR THE SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION UNITS 1 AND 2."
SOUTH TEXAS - UNITS 1 & 2 6-21 Unit 1 - Amendment No. 9, N, 46, 47 Unit 2 - Amendment No. 4, M, 46, 36
d-l
-' ADMINISTRATIVE CONTROLS-v
- [0RE OPERATING LIMITS REPORT (Continuedl (Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient) j i
2.
WCAP 8385, " POWER DISTRIBUTION AND LOAD FOLLOWING PROCEDURES 1
TOPICAL REPORT", September,1974 (W Proprietary).
(Methodology for Specification 3.2.1 - Axial Flux Difference j
(Constant Axial Offset Control).)
l 3.
Westinghouse letter NS-TMA-2198, T.M. Anderson (Westinghouse)_
j to K. Kniel (Chief _of Core Performance Branch, NRC)
J January 31, 1980 -
Attachment:
- 0. tation and Safety Analysis i
5 Aspects of an Improved Load Follow Package.
(Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control). Approved by NRC. Supplement No.' 4 to NUREG-0422, January, 1981 Docket Nos. 50-369 and 50-370.)
i 4.
NUREG-0800, Standard Review Plan, U.S. Nuclear Regulatory Commission Section 4.3, Nuclear Design, July, 1981. Branch Technical Pos' tion CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev. 2, July 1981.
(Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control).)
l S.
WCAP-10266-P-A, Rev. 2, WCAP-11524-NP-A, Rev. 2, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code", Kabadi, J.N., et al., March 1987; including t
Addendum 1-A, " Power Shape Sensitivity Studies," December 1987
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and Addendum 2-A, " BASH Methodology improvements and Reliability Enhancements" May 19r,8.
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(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
l 6.9.1.6.c The core operat.ng limits shall be determined so that all applicable limits (e.g., fuel thermal-oechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as' shutdown margin, and transient and accident analysis limits) of the j
safety analysis are met.
6.9.1.6.d The CORE OPERATING LIMITS 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.
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i SOUTH TEXAS - UNITS 1 & 2 6-22 Unit 1 - Amendment No. 27,35,47,72 Unit 2 - Amendment No. 17,25,35,61 1
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