ML20212H133
| ML20212H133 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 09/21/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212H136 | List: |
| References | |
| NUDOCS 9909300219 | |
| Download: ML20212H133 (4) | |
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION
'2 WASHINGTON, D.C. 20555-0001
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VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.176 License No. DPR-28 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 July 12,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the
. Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the I
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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9909300219 990921 i
PDR ADOCK 05000271 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.176, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days.
j FOR THE NUCLEAR REGULATORY COMMISSION
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Jarbes W. Clifford, Chief, Section 2 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: September 21,1999
a ATTACHMENT TO LICENSE AMENDMENT NO.176 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change, l
Remove Insert 6
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VYNPS 1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING j
1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY Applicability:
Applicability:
Applies to the interrelated Applies to trip setting of the variable associated with fuel instruments and devices which are thermal behavior.
provided to prevent the nuclear system safety limits from being exceeded.
Objective:
Objective:
To establish limits below which To define the level of the process the integrity of the fuel cladding variable at which automatic l
is preserved, protective action is initiated.
Specification:
Specification:
A.
Trip Settings A.
Bundle Safety Limit (Reactor Pressure >800 psia and Core The limiting safety system Flow >10% of Rated) trip settings shall be as specified below:
When the reactor pressure is
>800 psia and the core flow is 1.
Neutron Flux Trip Settings greater than 10% of rated:
a.
- 1. A Minimum Critical Power Setting (Run Mode)
Ratio (MCPR) of less than 1.10 (1,12 for Single Loop When the mode switch l
Operation) shall constitute is in the RUN violation of the Fuel position, the APRM Cladding Integrity Safety flux scram trip Limit (FCISL).
setting shall be as l
shown on Figure 2.1.1 and shall bet S<0.66(W-AW)+54%
where:
S = setting in percent of rated thermal power (1593 MWt)
W = percent rated two loop drive flow where 100%
rated drive flow is-that flow equivalent to 48 x 10' lbs/hr core
+
flow Amendment No M, 44, 4, M, M, M9, MO, M9, 176 6
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