ML20216C251
| ML20216C251 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 04/10/1998 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216C255 | List: |
| References | |
| NUDOCS 9804140372 | |
| Download: ML20216C251 (4) | |
Text
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p-k UNITED STATES g
j NUCLEAR REGULATORY COMMISSION I
i WASHINGTON, D.C. 20666 0001
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I VERMONT YANKEE NUCLEAR POWER CORPORATION 1
DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.159 License No. DPR-28 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Vermont Yankee Nuclear Power Corporation (the licensee) dated December 11,1997, as supplemented by letter dated March 3,1998, complies with the standards and requirements of the i
Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations, B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission, l
C.
There is reasonable assurance: (i) 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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I 9804140372 980410 7
i PDR ADOCK 05000271
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Accordingly, the license is amended by changes to the Technical Specifications as I
indicated in the attachment to this license e ^
iment, and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:
(B)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.159, are hereby incorporated in the license. The licensee shall
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l operate the facility in accordance with the Technical Specifications.
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S.
This license amendment is effective as of its date of issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION gicY Cecil O Thomas, Director Project Directorate 1-3 j
Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofIssuance: April 10, 1998 i
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e ATTACHMENT TO LICENSE AMENDMENT NO.159 FACILITY OPERATING LICENSE NO. DPR-28 QQCKET NO. 50 271 Replace the following pages of Appendix A Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 6
6-
- f VYNPS 1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING 1.1-FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGPITY Aeolicability:
Aeolicability
(
Applies to the interrelated Applies to trip setting of the variable associated with fuel instruments and devices which i
thermal behavior, are provided to prevent the nuclear system safety limits from being exceeded.
Obiectives obioetive:
To establish limits below which To define the level of the the integrity of the fuel process variable at which cladding is preserved.
automatic protective action is initiated.
Specification:
Specification:
A.
Bundle Safety Limit (Reactor A.
Trio Settinos Pressure >800 osia and Core Flow >10% of Rated)
The limiting safety system trip settings shall be as When the reactor pressure is specified below:
>800 psia and the core flow is greater than 10% of 1.
Neutron Flux Trio rated:
Settinos l
1.
For the Cycle 20 core a.
APRM Flux Scram Trio loading, the existence Settino (Run Mode) of a Minimum Critical Power Ratio (MCPR) of When the mode switch l
1ess than 1.11 (1.13 for is in the RUN Single Loop Oper% tion) position, the APRM
]
shall constitute flux scram trip violation of the Fuel setting shall be as Cladding Integrity shown on Safety Limit (FCISL).
Figure 2.1.1 and 1
Core loadings subsequent shall be:
]
to Cycle 20 will require recalculation of the S10.66(W-AW)+54%
MCPR.
l-where:
S = setting in percent of rated i
thermal power i
(1593 MWt)
I i
W = percent l
rated two loop drive flow where 100% rated drive flow is that flow l
equivalent 6
to 48 x 10 t
lbs/hr core f
flow Amendment No. H, G, H, M, H, H 9, H e,159 6