ML20148J186

Proposed Tech Specs Change 191,updating Section 6.0 Administrative Controls

ML20148J186
Person / Time
Site:	Vermont Yankee
Issue date:	06/09/1997
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20148J182	List: ML20148J177 ML20148J186
References
NUDOCS 9706170021
Download: ML20148J186 (5)

Text

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I Vermont Yankee Proposed Change No.191 Marked-up Tecimical Specification page 1

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4 9706170021 970609 PDR ADOCK 05000271 P PDR I

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

" Supplemental Information to VYNPC April 19, 1990 Response Regarding FROSSTEY-2 Fuel Performance Code,* BVY 90-054, dated May 10, 1990 (Approved by NRC SER, dated September 24, ,

1992).

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

• Responses 7J to Request for Additional Information on PROSSTEY-2 Fuel Performance Code,

• BVY 91-024, dated March 6, 1991 (Approved i

j s; 4 { I by NRC SER, dated September 24 1992). l to c $ en.

, .! E h Letter frosa L. A. Tremblay, Jr. (VYNPC) to USNRC, *LOCA- i e .s Related Responses to Open Issues on FROSSTEY-2 Fuel '

") d Performance Code,* BVY 92-39, dated Narch 27, 1992 (Approved y j 'll by NRC SER, dated September 24, 1992).

v. 7 '

U Letter from L. A. Tremblay, Jr. (VYNRC) to USNRC, "FROSSTEY-

• q i ac. j 1 Fuel Performance Code - Vermont Yankee Response to  ;

I j .! d d Remaining Concerns,* BVY 92-54, dated May 15, 1992 (Approved C "9 by NRC SER, dated September 24, 1992).

9 Mu Report,

• Loss-of-Coolant Accident Analysis for Vermont dd di s*j of Yankee Nuclear Power Station.

• NEDO-21697, August 1977, as amended (Approved by NRC SER, dated November 30, 1977).

i s) h3

u. ul

$ Report,

• General Electric Standard Application for Reactor Fuel (CESTARII),* NEDE-24011-P-A, GE Company Proprietary

. p (the latest NRC-approved version will be listed in the "I ,e 4 COLR).

• Es I

te Q.66 Report, General Electric Nuclear Energy, *BWR Owner's Group Long-Term Solutions Licensing Methodology,* NEDO-31960, O- I 8 4h June 1991 (Approved by NRC SER, dated July 12, 1993),

fd td i V Report, General Electric Nuclear Energy, *BWR Owner's Group Long-Term Solutions Licensing Methodology,* NEDO-31960, supplement 1, March 1992 (Approved by NRC SER, dated July 12, 1993).

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 l

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. Reoortable Occurrences j This section deleted.  !

C. Unicue Reportina Recuirements

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 4 previous calendar year of operation.

Amendment No. M, 44, M, M4, MG, 4M, M4, N 270

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Vermont Yankee Proposed Change No.191 I l

1 New Technical Specification page i

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

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

BVY 90-054, dated May 10, 1990 (Approvad 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 i Performance Code," BVY 92-39, dated March 27, 1992 l (Approved by NRC SER, dated September 24, 1992).

l Letter from L. A. Tremblay, Jr. (VYNRC) 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 j September 24, 1992).

Report, " Loss-of-Coolant Accident Analysis for Vermont Yankee Nuclear Power Station," NEDO-21697, August 1977, l as amended (Approved by NRC SER, dated l

November 30, 1977).

Report, " General Electric Standard Application for Reactor Fuel (GESTARII)," NEDE-240ll-P-A, GE Company Proprietary (the latest NRC-approved version will be

(

listed in the COLR).

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

NEDO-31960, June 1991 (Approved by NRC SER, dated l

July 12, 1993).

l Report, General Electric Nuclear 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, N. Fujita, et al., " Method for Power / Flow Exclusion Region Calculation Using the LAPURS Computer l Code," YAEC-1926-A (Approved by NRC SER, dated I 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, M, M, %, H4, H6, MG, H4, H4, 270

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• VYNPS C. Unicue Reportina Recuirements

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 unrastricted areas during the previous calendar year of operation, l

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Amendment No. 270a

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