ML20043G486

Proposed Tech Specs Re Administrative Controls

ML20043G486
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	06/11/1990
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20043G482	List: BVY-90-069, Application for Amend to License DPR-28,consisting of Tech Spec Change 158,updating Section 6.0 to Add NRC Reviewed & Approved Methodologies Being Used to Generate cycle-specific Limits in Plant Core Operating Limits Rept for Cycle 15 ML20043G486
References
NUDOCS 9006200355
Download: ML20043G486 (3)

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ATTACHMENT 3 Revised Technical Specification Pages l

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, WPP90/13 9006200353 900611

{DR ADOCK 05000271 PDC

VYNPS Report, J. M. Holzer,' " 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 Red Steady-State Thermal Effects (FROSSTEY): Code /Model Description Manual," YAEC-1249P, April 1981 (Approved by NRC SER, dated September 27, 1985).

Report, A. A. F. Ansari, '9MethGds for ' the Analysis of Boiling Water Reactors: Steady-State Core Flow 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 Transient Analysis Model (RETRAN)," YAEC-1233, April 1981.

(Approved by NRC SERs, dated November 27, 1981 and September 4, 1984).

l Report, A. A. F. Ansari, K. J. Burns and D. K. Beller, " Methods for the Analysis of Boiling 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-3G Validation," YAEC-1363-A, April 1988.

Report, A. S. Diciovine, J. P. Gorski, and M. A. Tremblay, " SIMULATE-3 Validation and Verification,"

YAEC-1659-A, September 1988.

Report, R. A. Woehlke, et al., "MICBURN-3/CASMO-3/ TABLES-3/ SIMULATE-3 Benchmarking of Vermont Yankee Cycles 9 through 13," YAEC-1683-A, March 1989.

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 Boiling Water Reactor Transient Analysis Methods," YAEC-1693-A, Revision 1, November 1989.

Amendment No. IIg

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VYMPS Report, " Loss-of-Coolant' Accident. Analysis for Verment Yankee Nuclear Power Station " NEDO-21697,~ August: d' 1977, as amended (Approved by NRC SER, dated November 30, 1977).

Report, " General Electric Standard' Application for Reactor Fuel (CESTARII)," NEDE-240ll-P-A-9, CE' Company Proprietary, September 1988,~as amended.

'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.

The COLR, 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.

I B.

Reportable Occurrences This section deleted.

l Amendment No. IJg 209b

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