ML20064A286
| ML20064A286 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/24/1990 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064A287 | List: |
| References | |
| NUDOCS 9008310051 | |
| Download: ML20064A286 (6) | |
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l UNITED STATES NUCLF.AR REGULATORY COMMISSION a
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6 VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 YERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 126 License No. DPR-?8 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Vennont Yankee Nuclear Power Corporation (the licensee) dated June 11, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations 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 Comission; 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and caf M of the public; and 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.126, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
J'g831oos! 900824 ADock 03o00273 p
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August 24, 1990 l
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Victor.Nerses. Acting Director Project Directorate I-3 Division of Reactor Projects I/11 Office of Nuclear Reactor Regulation 1.ttachment
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Changes to the Technical Specifications Date of Issuance: August 24, 1990 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 126 FACILITY OPERATING LICENS: N0. DPR-28 DOCKET NO. 50-271 Replace the following pages of the Appendix A Technical Specifications with
.the attached pages. The revised pages are identified by Amendment number and contain vertical lines. indicating the area of change.
Remove Insert 4,
674 67a c.
209a 209a s.
209b*
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VYMPS Report, J. M. Molzer, " Methods for the Analysis of Boiling Water Reactors Transient Core Physics "
YAEC-1239P, August 1981 (Approved by NRC SER, dated September 15, 1982).
Report, S. P. Schultz and K. E. St. John, " Methods for the Analysis of Guide Fuel Rod Steady-State Thermal Effects (FROSSTEY): Code /Model Description Manual," YAEC-1249P, April 1981 (Approved by NRC SER, dated September 27, 1985).
t Report. A. A. F. Ansari, " Methods for the Analysis of Bolling Water Reactors: Steady-State Core Flow l
Distribution Code (FIBWR) " YAEC-1234, December 1980 (Approved by NRC SER, dated September 15, 1982).
Report, S. P. Schultz and K. E. St. John, " Methods for the Analysis of Oxide Fuel Rod Steady-State Thermal Effects (FROSSTEY): Code Qualification and Application," YAEC-1265P, June 1981 (Approved by NRC SER, dated September 27, 1985).
Report, A. A. F. Ansari and J. T. Cronin, " Methods for the Analysis of Boiling Water Reactors: A System l
Transient Analysis Model (RETRAN)," YAEC-1233 April 1981.
(Approved by NRC SENs, dated November 27, 1981 and September 4, 1984).
Report, A. A. F. Ansari, K. J. Burns and D. K. Beller, " Methods for the Analysis of Bolling Water Reactors: Transient Critical Power Ratio Analysis (RETRAN-TCPYA01)," YAEC-1299P, March 1982 (Approved by NRC SER, dated September 15, 1982).
Report, A. S. Diciovine, et al., "CASMO-3C Validation," YAEC-1363-A, April 1988.
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Report, A. S. Diclovine, J. P. Corski, and M. A. Tremblay, " SIMULATE-3 Validation and Verification,"
YAEC-1659-A, September 1988.
Report, R. A. Wochlke, et al., "MICBURN-3/CASMO-3/ TABLES-3/ SIMULATE-3 Benchmarking of Vermont Yankee Cycles 9 through 13 " YAEC-1683-A, March 1989.
i Report, J. T. Cronin, " Method for Generation of One-Dimensional Kinetics Data for RETRAN-02," YAEC-1694-A, June 1989.
Report, V. Chandola, M. P. LeFrancois, and J. D. Robichaud, " Application of One-Dimensional Kinetics to i
Boiling Water Reactor Transient Analysis Methods," YAEC-1693-A, Revision 1. November 1989.
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f Amendment No. Il6 126 209a y
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VYNFS Report. "Iase-cf-Coolant Accident Analysis for Vermont Yankee helear Power Station," NEBO-21697, Aangest 1977, as aseended (Approved by twC SER, dated hvember 30, 1977).
l Report, " General Electric Standard Applicatloa for Reactor Fuel ' (CESTARII)," NEDE-240ll-F-A-9, CE C _ ;:ny.
Proprietary, September 1988, as amended.
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermel-eechenlcal' limits, core thermel-hydraulic limits, ECCS limits,. nuclear limits such as shutdown mergin, and transient and accident analysis limits) of the safety analysis are met.
The COIA, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Docusent Control i Desk with copies to the Regional Administrator and Resident Inspector.
I B.
Reportable Occurrences This section deleted.
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