ML20247E567

Proposed Tech Specs Page 270,containing Wording Inadvertently Deleted from TS Proposed Change 202

ML20247E567
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	05/08/1998
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20247E555	List: ML20247E553 ML20247E567
References
NUDOCS 9805180385
Download: ML20247E567 (2)

Text

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

" Supplemental Information to WNPC April 19, 1990 Response Regarding FROSSTEY-2 Fuel Performance Code,*

BW 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, " BW 91-024, dated March 6, 1991 (Approved by NRC SER, dated September 24, 1992).

Letter from L. A. Tremblay, Jr. (WNPC) to USNRC, "LOCA-Related Responses to Open Issues on FROSSTEY-2 Fuel Performance Code, " BW 92-39, dated March 27, 1992 (Approved by NRC SER, dated September 24, 1992).

P Letter from L. A. Tremblay, Jr. (

) to USNRC, "FROSSTEY-2 Fuel Performance Code - ermont Yankee Response to Remaining Concerns, " BW 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-approved version will be listed in the COLR).

Report, General Electric Nuclear Energy, "BWR Owner's Group Long-Term Solutions Licensino Methodology,"

("The.IedeS4 d

S l

t4tc.-app M

1. Mon d Report, General Electric Nuclear Energy, "BWR Owner's g tr34ed M Group Long-Term Solutions Licensing Methodology,"

l NEDO-31960-A Supplement 1 (Wc3 Qf,Rr-ddge51 Jerly lu e

e Report, N. Fujita, et al.,

" Method for Power / Flow Exclusion Region Calculation Using the LAPURS Computer Code," YAEC-1926-A (Approved by NRC SER, dated November 5, 1996).

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.

B.

Reportable Occurrences This section deleted.

9805180385 980508 '

PDR ADOCK 05000271 P

pm Amendment No. M, 83, 96, &M, 4M, 4-M, 144, M6, 157 270 i

l t

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

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

l 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 92-39, dated March 27, 1992 (Approved by NRC SER, dated September 24, 1992).

l Letter from L. A. Tremblay, Jr. (VYNPC) 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 l

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-approved version will be listed in the COLR).

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

NEDO-31960-A (the latest NRC-approved version will be listed in the COLR),

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

NEDO-31960-A, Supplement 1 (the latest NRC-approved version will be listed in the COLR).

q

Report, N.

Fujita, et al.,

" Method for Power / Flow Exclusion Region Calculation Using the LAPURS Computer Code," YAEC-1926-A (Approved by NRC SER, dated November 5, 1996).

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.

B.

Reportable Occurrences This section deleted.

Amendment No. 35, 83, 95, 1-16, 126, 135, 144, 146, 157, 270

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