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. .< - _ ,, _ 1 * . . , - *e UNITED STATES * ' ATOMIC ENERGY COMMISSION 5 . '_.J 1* WASHINGTON, D.C. 20545 - '. | *I ' 1!L >p 7 YANKEE ATOMIC POWER COMPANY # - f ! DOCKET No. 50-29 YANKEE-ROWE ATOMIC POWER PLANT - AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 7 License No. DPR-3 1. The Atomic Energy Commission ("the Commission") has found that: A. The application for amendment by Yankee Atomic Power Company ("the licensee") dated September 21, 1973, and supplements dated November 26, 1973, and February 20, 1974, comply 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 issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; C. The facility will operate in conformity with the license, the provisions of the Act, and the rules and regulations of the Commission; D. 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; and E. Prior public notice of this amendment is not requie d since the amendment does not involve a significant hazards consideration. 2. Accordingly, Paragraph 3.A.(2) of Facility License No. DPR-3 is hereby amended to read as follows: "(2) Technical Specifications The Technical Specifications contained in Appendix A, attached to Facility Operating License No. DPR-3 are i revised as indicated in the attachment to this license amendment. The Technical Specifications, as revised, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, as revised." ! | 80111zo D 5 j _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ .__ ._-

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Page 1: in 10 CFR Chapter I;

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*e UNITED STATES*

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ATOMIC ENERGY COMMISSION5 .

'_.J 1* WASHINGTON, D.C. 20545 -

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1!L >p 7

YANKEE ATOMIC POWER COMPANY# -

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!DOCKET No. 50-29

YANKEE-ROWE ATOMIC POWER PLANT-

AMENDMENT TO FACILITY OPERATING LICENSE

Amendment No. 7License No. DPR-3

1. The Atomic Energy Commission ("the Commission") has found that:

A. The application for amendment by Yankee Atomic Power Company("the licensee") dated September 21, 1973, and supplements datedNovember 26, 1973, and February 20, 1974, comply with the standardsand requirements of the Atomic Energy Act of 1954, as amended("the Act"), and the Commission's rules and regulations set forthin 10 CFR Chapter I;

B. The issuance of this amendment will not be inimical to the commondefense and security or to the health and safety of the public;

C. The facility will operate in conformity with the license, theprovisions of the Act, and the rules and regulations of theCommission;

D. There is reasonable assurance (i) that the activities authorizedby this amendment can be conducted without endangering the healthand safety of the public, and (ii) that such activities will beconducted in compliance with the Commission's regulations; and

E. Prior public notice of this amendment is not requie d since theamendment does not involve a significant hazards consideration.

2. Accordingly, Paragraph 3.A.(2) of Facility License No. DPR-3 is herebyamended to read as follows:

"(2) Technical Specifications

The Technical Specifications contained in Appendix A,attached to Facility Operating License No. DPR-3 are

i revised as indicated in the attachment to this licenseamendment. The Technical Specifications, as revised,are hereby incorporated in the license. The licenseeshall operate the facility in accordance with theTechnical Specifications, as revised."

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Page 2: in 10 CFR Chapter I;

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3. This ikcense amendment is effective 'as of the date of its issuance.

FOR THE ATOMIC ENERGY COMMISSION

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Karl R. Goller, Assistant Directorfor Operating Reactors

Directorate of Licensing

Attachment:-Change No. 112 to Appendix ATechnical Specifications

Date of Issuance: July 10, 1974

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ATTACHMENT TO LICENSE AMENDMENT NO. 7

CHANGE NO. 112 TO TECHNICAL SPECIFICATIONS

FACILITY OPERATING LICENSE NO. DPR-3

DOCKET NO. 50-29

Replace pages 214:5, 214:6 and 214:7 and Table 1 in the TechnicalSpecifications with the attached revised pages and the revisedTable I.

Change specification D.2.d. (1) of Appendix A to read as follows:1

(1) The reactor shall be scrammed automatically by a low primarypressure trip signal at 1800 psig whenever the reactor iscritical.

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Page 4: in 10 CFR Chapter I;

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214 5- . .

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cain control. board. The source range and intemediate range signals actuatethe 1.1 decade per minute circuit, but only _the intermediate range signals

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operate the 1.5 decades per minute circuit.,

The startup rate scram is nomally set to trip at 5.2 decades perminute and is adjustabic from 3 to 10 decades per minute. The sourco rangeand intermediate range signals can actuate individual channel bistable mag-netic cmplifiers to initiate the scram. -

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In addition to these signals, there exists from each one of thelog microammeter units in the intermediate range channels an automatic sig- '

nal, which disconnects the high voltage from the BF3 Proportionalgounterswhen the reactor neutron flux is increasing between 5 x 10' and 10 nv andccecc::3 cts the high voltage on decreasing flux at approxi=stely the samelevel. The infomation that this signal is initiated is obtained by thesource range high voltage light mounted on the nuclear section of the maincontrol board. The light is off when the high voltage is off. A manual,

switch disconnecting the BF3 source range high voltage is also available atthe nuclear instrumentation cabinets.

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The coincidence feature makes it secessary for two out of six powerrange channels to initiate high neutron flux level signals in order to cause

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the scram amplifiers to trip. The high neutron flux level trip set point isadjustable for various reactor operation conditions. For reactor 100% fullpowerloperation, (i.e. , 600 buit), with four loops in service, the level trip

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set point is set at 108%. For rea'ctor operation between 0 and 15% of fullpower, the IcVel trip set point is manually adjusted to 35% of full power.A power range coincidence single switch is provided to allow for coincidencescram or any singic channel scram. The low power scram set switch is locatedon the nuclear section of the main control board.

Signals not fed through the coincidence circuit but operating onthe scram amplifiers through the alarm and scram panel are those initiatedfrom low main coolant pressure, low pressurizer pressure, low steam generator

Provision is made inIcvel, high pressurizer level, and high startup rate.the alarm and scram panel to accommodate additional signals for memory light

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indication only. .,

A praissive relay circuit, shown on page 214:6, is provided whichis operated cy two pressure switches activated from the turbine No. I nozzle

Operation of the circuit occurs at a turbine steam pressurepressure.equivalent to 15bufe output. This circuitry provides for an optional manualby-pass for the low steam generator level scram, low flow scram and turbine-At 15 MNe and above,generator scram signals when the power is below 15 MNe.the scram bypass is automatically removed and the system is available forautomatic rods-in motion of the control rods. The high startup rate scram-

signal is automatically connected at 15 MWe and below and automaticallybypassed above 15 MWe.

A second pcmissive relay circuit is activated at the 30 MWe powerIcVel, which provides for automatic cut-in of a manual rods out reset circuit.At power levels of 30 MWe and above, the reset circuit requires the controlswitch to be returned to the neutral or reset position before making eachadditional rods out step. Selow 30 MWe output, the reset circuit becomes

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Page 5: in 10 CFR Chapter I;

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Page 6: in 10 CFR Chapter I;

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ineffective and thus a controlled but continuous rods out motion may be ;,uffected. .

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Alarm and Scram Panci,

The six scram signals, low pressurizer pressure, low main coolantpressure, lov steam generator icvel, high pressurizer, high startup rate,and hig!. neutron flux levels are connected to the magnetic amplifier alarmand scram panel that acts as the control center for indicating the individualsignals that may have caused the scram and for operating the scram amplifiersdirectly. Low main coolant flow and Turbine Trip signals are connected to g,r, -the alarm and scram panel for indication only. ~

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Scram Amplifiers.;-

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The two magnetic scram amplifiers operate individual scram relays **

whose contacts are connected to the trip coil circuitry of the rod scram cir- '3

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cuit breakers. The scram relays are energized at all times except when a scram.signal is sent to the scram amplifiers. When the scram amplifier outpats arezero, the scram relays are de-energized and the contacts in the trip coil cir-cuits close causing both breakers to operr. *The circuit is such that any onescram relay actuates both circuit. breakers.

Meter and Test Panel,

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Two meter and tes' panels provide local indication at the nuclearinstrumentation cabinets and the necessary calibratini; signals to completelyand accurately check out all the channels for normal operation and energizingconditions.

Auxiliary Meter Panel

The auxiliary meter panel contains three meters which were us3dduring early plant life to measure the uncompensated signal from the threeintermediate range ion chambers. They have been short circuited becauseintermediate power range channels now measure this signal with greateraccuracy.

' Recorder .

The recorder used with the nuclear instrumentation is a large, 2-pen,multi-speed instrument with two decade switching circuits. The speeds of thepaper are 4 and 240 inches per hour. The decade switching allows for fullscale deficction for one decade change in reactor flux. This recorder ismounted on the front of the nuclear section of the main control board. 7*

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