ML20072J061

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Amend 140 to License DPR-28,removing CS High Sparger Instrumentation from Plant TSs for ECCS Actuation Instrumentation
ML20072J061
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 08/22/1994
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20072J065 List:
References
NUDOCS 9408260188
Download: ML20072J061 (5)


Text

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E NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 0001

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VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET N0. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.140 License No. DPR-28 1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Vermont Yankee Nuclear Power Corporation (the licensee) dated May 20, 1994, 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 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

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of the Commission's regulations and all applicable requirements have been satisfied.

I 2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-28 is hereby amended to read as follows:

j 9408260188 940822 PDR ADOCK 05000271 P

PDR:

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Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.140, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

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Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects

_I/II Office of Nuclear Reactor Regulation

Attachment:

Changes t6 the Technical Specifications Date of Issuance: August 22, 1994

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ATTACHMENT TO LICENSE AMENDMENT NO. 140 FACILITY OPERATING LICENSE N0, DPR-28 DOCKET NO. 50-271 Replace the following pages of the Appendix A Technical Specifications with the attached page::.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 38 38 59 59

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e VYNPS TABLE 3.2.1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION Core Spray - A & B (Note 1)

Minimum Number of Required Action When Operable Instrument Minimum Conditions Channels per Trip for Operation S_ystem Trio Function Trio Level Setting are Not Satisfied 2

High Drywell Pressure 12.5 psig Note 2 2

Low-Low Reactor Vessel Water

>82.5" above top of Note 2 Level enriched fuel 1

Low Reactor Pressure 300 < P < 350 psig Note 2 (PT-2-3-56C/D(SI))

2 Low Reactor Pressure 300 < P < 350 psig Note 2 (PT-2-3-56A/B(S1) & 52C/0(M))

1 Time Delay (14A-K16A & B) 110 seconds Note 2 1

2 Pump (P-46-1A/B) Discharge 1100 psig Note 5 Pressure 1

Auxiliary Power Monitor Note 5 1

Pump Bus Power Monitor Note 5 1

1 Trip System Logic Note 5 l

Amendment No. 44, 60, 4-16, 131,140 38 i

4 VYNPS TABLE 4.2.1 MINIMUM TEST AND CALIBRATION FREQUENCIES EMERGENCY CORE COOLING ACTUATION INSTRUMENTATION Core Spray System Trio Function Functional Test (8)

Calibration (8)

Instrument Check High Drywell Pressure (Note 1)

Once/ Operating Cycle Once Each Day Low-Low Reactor Vessel (Note 1)

Once/ Operating Cycle Once Each Day Water Level Low Reactor Pressure (Note 1)

Once/ Operating Cycle (PT-2-3-56C/D(51))

Low Reactor Pressure (Note 1)

Once/ Operating Cycle (PT-2-3-56A/B(SI) &

52C/D(M))

Pump (P-46-1A/B)

(Note 1)

Every Three Months l Discharge Pressure Auxiliary Power Monitor (Note 1)

Every Refueling Once Each Day Pump Bus Power Monitor (Note 1)

None Once Each Day Trip System logic Once/ Operating Cycle Once/ Operating Cycle (Note 3)

Amendment No. 50, M,106. -He,140 59

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