ML20217N411

Proposed Tech Specs Pages 270 & 270a,updating Section 6 in Order to Add & Revise Ref to NRC Approved Methodologies Which Will Be Used to Generate cycle-specific Thermal Operating Limits to COLR

ML20217N411
Person / Time
Site:	Vermont Yankee
Issue date:	08/20/1997
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20217N407	List: BVY-97-107, Application for Amend to License DPR-28,modifying TS to Update Section 6 in Order to Add & Revise Ref to NRC Approved Methodologies Which Will Be Used to Generate cycle- Specific Thermal Operating Limits in COLR ML20217N411
References
NUDOCS 9708260157
Download: ML20217N411 (3)

Text

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~ Vermont Yankee Nucleet Power Corporation

. Docket No. 50-271

. %VY 97407 -

ATTACHMENT 3

- REVISED TECHNICAL SPECIFICATION f' AGES s~

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i 9708260157 97G820 PDR ADOCK 05000271 P PDR ,

b-VYNPS Letter.from L. A. Tremblay, Jr. (VYNPC) to USNRC,

" Supplemental Information to VYNPC April 19, 1990 Response Regarding FROFSTEY-2 Fuel Performance Code,"

BVY 90-054, dated May 10, 1990 (Approved by NRC SER, dated September 24, 1992).

Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC,

" Responses to Request for Additional Information on FROSSTEY-2 Fuel Performance Code,' BVY 91-024, dated March 6, 1991 (Approved by NRC SER, dated September 24, 1992).

Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, 'LOCA-Related Responses to Open Issues on FROSSTEY-2 Fuel Performance Code," BVY P2-39, dated March 27, 1992 (Approved by NRC SER, dated September 24, 1992).

l Letter from L. A. Tremblay, Jr. (VrNRC) to USNRC,

'FROSSTEY-2 Fuel Performance Code - Vermont Yankee Response to Remaining Concerns," BVY 92-54, dated May 15, 1992 (Approved by NRC SER, dated September 24, 1992).

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

Report, ' General Electric Standard Application for Reactor Fuel (GESTARII) , " NEDE- 24011-P-A, GE Company Proprietary (the latest NRC pproved version will be listed in the COLR).

Report, General Electric Nu ar Energy, 'BWR Owner's Group Long-Term Solutions I nsing Methodology "

NEDO-31960, June 1991 ( App: rd by NRC SER, dated July 12, 1993).

Report, General Electric F. clear Energy, "BWR Owner's Group Long-Term Solutions Licensing Methodology,'

NEDO-31960, Supplement 1, March 1992 (Approved by NRC SER, dated July 12, 1993).

Report, Yankee Atomic Electric Company, " Application of the FIBWR2 Core Hydraulics Code to BWR Reload Analysis,"

YAEC-1339-A, January 31, 1997.

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 rev.4sions 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.

B. Renortable Occurrences This section deleted.

Amendment No. M, M, M, 4%, M6, H5, 444, 446, 270

VYNPS

• C. Unique Reportina Requirements

1. Annual Radioactive Effluent Release Report

a. Within 90 days after January 1 of each year, a report shall be submitted covering the radioactive content of effluents released to unrestricted areas during the previous calendar year of operation.

Amendment No. 270a

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