ML20080Q595

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Amend 142 to License DPR-28,revising Identification of Low Reactor Pressure Instrument Trip Card from Slave to Master Trip Card Designation
ML20080Q595
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 03/03/1995
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20080Q598 List:
References
NUDOCS 9503080417
Download: ML20080Q595 (8)
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. UNITED STATES

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. NUCLEAR REGULATORY COMMISSION f

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WASHINGTON,. D.C. 20066 4 001-J

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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.142:

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 December 14, 1994, complies with the standards and requirementsLof 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: '(1) 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.

2.

Accordingly, the license is amended by changes to the Technical Specifica-j tions 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:

t 9503080417 950303 PDR ADOCK 05000271 P

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,,. ' Technical Specifications

.The Technical Specifications contained in Appendix A, as revised through. Amendment No.142,' 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 Walter l R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II.

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications

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Date of Issuance: March 3, 1995

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.t ATTACHMENT TO LICENSE AMENDMENT NO.142-FACILITY OPERATING LICENSE NO. DPR-28

.QQCKET NO.'50-271 Replace the following sages of the Appendix A Technica1 ' Specifications with.

the. attached pages.- Tie revised pages are identified by Amendment' number and contain vertical lines-indicating the area of change.

Remove Insert 38 38 39 39 40 40-59 59 60 60 r

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VYMPS j

TABLE 3.2.1 EMERGENCY CORE COOLING SYSTEM AC11JATION INSTRUMENTATION 1

Core Spray - A & B-(Note 1)

Minimusa Number of Required Action When Operable Instrussent Minimusa conditions -

Channels per Trip for Operation Systeen Trip Punction Trio Level Settino

'are Not Satisfied 2

High Drywell Pressure

$.5 psig Note 2 2

2 Low-Low Reactor Vessel Water 182.5* above top of

-Note 2 Level enriched fuel 1

Low Reactor Pressure 300 $P5 350 psig Note 2 l

(PT-2-3-56C/D(M)).

2 Low Reactor Pressure 300 s P 5 350 psig Note 2-l (PT-2-3-56A/B(M) & 52C/D(M))

1 Tinne Delay (14A-K16A & B) 110 seconds Note 2 2-Pump-(P-46-1A/B) Discharge-1 00 psig Note 5.

1 Pressure 4

1 Auxiliary Power Monitor Note 5 1

Pussp Bus Power Monitor Note 5 1

Trip Systems Logic Note 5 t

1

. Asnendsnent No. 44, '68, 444,. 4M, 444,".W 38-

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1 VYNPS TABLE:3.2.1 (Cont'd)

EMERGENCY CORE COOLING SYSTEM AC113ATION INS 1RGeaiinTION Low Pressure Coolant Injection-System A E B'(Note-1)

Minismun Number of Operable Instrument Required Action When-Miniansa conditions Channels per Trip for. Operation.

System Trio Function Trio Level Settino

'are Not Satisfied-1 Low Reactor Pressure 300 $p5 350 peig Note 2

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l (PT-2-3-56C/D(H))

2 High Drywell Pressure 1 5 psig

-Hote 2-2

~

(PT-10-101A-D(N))

2 Low-Low Reactor Vessel Water

.182.5* above top of-Note'2 Level enriched fuel 1

Time Delay (10A-K51A & B) 0 seconds Note 5-1 Reactor Vessel Shroud-Level-12/3 core height-Note 5 1

Time Delay'(10A-K72A (i B) 160 seconds Note 5--

1 Time Delay (10A-K50A & B)-

15 seconds Note,5 1

Low Reactor Pressure-100's p g 150 psig~

Note 2 (PS-2-128A & B)'

2 per pump RHR Pump A & C Discharge 1100.psig.-

Note 5

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Pressure 2

lHigh Drywell Pressure ~

$.5 psig.

Note 2:

2 (PT-10-101A-D(SI))

. Amendment No. 44,'44, 48, 444

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VYMPS TABLE'3.2.1 (Cont'd)'

ENERGENCY CORE COOLING SYSTEM AC1UATION Ihasnwns.TATION

~

Low Pressure Coolant Injecticn Systemt A & B (Note 1)-

Minimum Number of Required' Action Nhen-Oper=*;le Instrustent Minimaan Conditions Channels per Trip for Operation' System Trio Punction' Trio Level Settina are Not Setistled -

1 Time Delay (10A-K45A ti B) 16 minutes Note 5L i

2 Low Reactor Pressure' 300 g p g 350 psig Note 2 l

(PT-2-3-56A/B(M) & 52C/D(M)) -

1 Auxiliary Power Monitor Note 5-1 Pump Bus Power Monitor Note 5 1

Trip Systesa Logic

. Note.5 f

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Amendme'nt No. H, 4M,142 :

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VYNPS TABLE 4.2.1 HINIMUM TEST AW CALIBRATION FREQUENCIES EMERGENCY CORE COOLING ACTUATION INSTRUMElfrATION Core Spray Systesa Trip Function Functional Test (8).

Calibration (S)

Instrunnent 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 l

(PT-2-3-56C/D(M))

Low Reactor Pressure (Note 1)

Once/ Operating Cycle l

(PT-2-3-56A/B(M) &

52C/D(M))

Pump (P-46-1A/B)

(Note 1)

Every hree Months Discharge Pressure Auxiliary Power Monitor (Note 1)

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

None once Each Day Trip Systesa Logic Once/ Operating Cycle Once/ Operating Cycle l

.(Note 3) l-l Amendsnent No. 54, M, M6, 4M, Me, 142 59.

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.cl VYNPS TABLE 4.2.1 (Cont'd)

HININUM TEST AND CALIBRATION FREQUENCIES ENERGENCY CORE COOLING AC11JATION INSTRLMENTATION Low Pressure Coolant Injection Systesa Trip Function Functiona1 Test (8)

Ca1ibration(8)

Instrussent Check Low Reactor Pressure (Note.1)

Once/ Operating Cycle l

(PT-2-3-56C/D(M))

High Drywell Pressure (Note 1)

Once/ Operating Cycle Once Each Day.

(PT-10-101A-D(M))

Low-Low Reactor Vessel (Note 1)

Once/ Operating Cycle Once Each Day Water Level

'i Reactor Vessel Shroud (Note 1)

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

Every Three Months l

_ PS-2-128A/B)

(

RHR Pump Discharge (Note 1)'

Every three Months Pressure High Drywell Pressure (Note 1)

Once/ Operating Cycle (PT-10-101A-D(SI))

Low Reactor Pressure (Note 1)

Once/ Operating Cycle l

(PT-2-3-56A/B)(M) &

52C/D(M))

Auxiliary Power Monitor (Note 1)

Every Refueling Outage.

-Once Each Day Pump Bus Power Monitor

.(Note 1)

None Once Bach Day Trip Systesa Logic Once/ Operating Cycle Once/ Operating cycle

,(Note 3) l Amendment No. 4+,

ES, 94, 94,'446, 444,' 449,'

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