ML20151W502

Amend 24 to License R-81,amending Tech Specs to Account for Substitution of Keithley Log-N Amplifier

ML20151W502
Person / Time
Site:	05000054
Issue date:	08/16/1988
From:	Chris Miller Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151W498	List: ML20151W494 ML20151W502 ML20151W505
References
R-081-A-024, R-81-A-24, NUDOCS 8808250006
Download: ML20151W502 (6)

Text

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UNJTED STATES

, [( - 9, E

NUCLEAR REGULATORY COMMISS10N WASHINGTON, D. C. 20666

. D CINTICHEM, INC.

DOCKET NO. 50-54 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 24 License No. R-81

1. The Nuclear Regulatory Comission (the Commission) has found that:

A. The application for amendment to Facility Operating 1.icense No. R-81, filed by Cintichem, Inc. (the licensee), dated July 21, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (ths Act), and the Comission's regulations as set forth in 10 CFR Chapter I; B. The facility will o)erate in conformity with the application, the provisions of t1e Act, and the regulations of the Comission; C. There is reasonable assurance: (1) that the activities authorized by this amendment car 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 set forth in 10 CFR Chapter I; 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; E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable re'quirements have been satisfied; and F. Publication of notice of this amendment is not required since it does not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).

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2. Accordingly, the license is amer.ded by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C(2) of License No. R-01 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 24, are herehy incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendnent is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

&fY Charles L. Miller, Acting Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

Appendix A Technical Specifications Changes Date of Issuance: August 16, 1988 S

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4 ENCLOSURE TO LICENSE AMENDMENT NO. 24 FACILITY OPERATING LICENSE NO. R-81  ;

DOCKET NO. 50-54 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a 'ertical line indicating the area of changes.

Remove Pages Insert Pages 8 8 11 11 27 27 4

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3.3.2 Regulating Rod .

This The integrai worth.of the regulating rod shall not exceed 0.6%

critical.

3.3.3 Scram Time The scram time shall not exceed 0.75 In second and the controlgiven rod magnet in Sec-release the transient analysis time shall not exceed 0.05 second.

tion B3 of Appendix 2 of the SAR, these values were assumed.

3.3.4 Measuring c u.nis The minimum number and type of measuring channels opera

' Tab' e 3.1.

Table 3.1 Minimum number and operating mode of measuring channels Operating Minimum no. mode operable required Channel .

2 All Power level (normal) 1 All Power level (intermediate)

I 1 All l

Period channel la Startup Count rate 1 Forced cooling Coolant flow 1

Forced cooling Core AT Rod position 1/ rod All Pool temperature 1 All l All -

1 Pool level

• 0perable below M W.

Basis: The normal power lovel instruments (level safeties) provide redundant TiFrmation on reactor power in the range 25% - 150% of the normal operating power level of 5 MW.

1 1 Theintermediatepowerirstrument(logN)provjdesusablereactorpowerinfor-mation with a minimum le,garithmic range of 10~ 5 - 200% of the normal power of 5 MW, .

The count rate channel covers the neutron fluxIt range enables from theoperator the source level to start (El cps) to 10' cps on a iogarithmic scale.

the reactor sr.?ely from a shutdown condition, and to bring the power to a level that can te measured by the log N instrument.

• knendrrent flo. 24

Table 3.3 Radiation monitoring systens .

c -

No. - Max. alarm

( Type operable. setpoint Function 1

Exi:ursion monitor .1 5 R/hr

• Detect high radiation:  !

. . Alarm and iso', ate at >5 R/hr

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Exhaust duct monitor 1

• Detect particulate, gas, and'

("stack monitor") iodine activities; slarm in

. control room Building continuous 1 * ** Detect particulate activity .

'. ' air monitor (CAM) -

in reactor building; alarm

. in control room -

Fixed area monitor 3 50 mr/hr Detect radiation ('t) in' key locations; alarm in cdntrol i *= % room Evacuation switch 1 --

Alarm and initiate' evacuation

. sequence (manual)  ;

Note: For maintenance or repair, required radiation monitors (except for ,

excursinn monitor) may be replaced by portable or substitute

. s instruments for periods up to ,24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided the functi'on will still .

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. be ac~complished. Interruption for br'inf periods to permit checkin'g or calibration is permissible. - ,

"The alarm setpoint for the stack gas monitor shall not be set above a value that would result in an exposure g. eater than 2 mrem per hour assuming a dilution factor of 2000 and the isotope mixture determined by the annual ..

environ.' rental report or most recent analysis. The alarm setpoint for the .

stack I-131 and stack particulate monitor shall not be set above a value corresponding to that listed in' Appendix B, Table II, Column I of 10 CFR Part 20, assuming a dilution factor of 2000 and averaging over one week.

• • 25%'of the. maximum permissible concentration at restricted areas according to Appendix B of 10 CFR Part 20. .

Scecifications: The specifications a,re as follows:

'3. 5.1 Excursion Monitor .

Soecification: See Section 3,4 Besis: This monitor senses excessive radiation at tt'ie reactor' bridge and auto-7.T.311/ initiates the "evacuation sequence," which* consists of a distinctive alarm, closure,of damper valves in the building ventilation sya., tem and ho M up .

tank vent, and starting of the emergency exhaust fan (see Section 5.5.2).

11 knendment No. 24 l

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meter allowing channel checks to be done during reactor operation. Each chamber can be changed in position, over a limited range, so as to allow the I channel reading to be standardized against reactor thermal power.

5.2.2 Power Level (Intermediate) Channel For this function, a single channel is provided, covering reliably the range 10~35 to 2005 (of 5 MW) with a logarithmic output indication on both a panel meter and a chart recorder. To cover the range under all core conditions, a pamma-compensated boron-ion chamber is used to supply a logarithmic amplifier.

he chamber can be changed in position, over a limited range, so as to allow the channel reading to be standardized against reactor thermal power. Rate of change of power information is also derived, in the fo"a of a period, that can produce a fast scram (and backup slow scram) in the same way as in Section 5.2.1.

Control of inhibit accions (viz., bypassing of count rate channel funccions, bypassing of flow and flapper scrams) are also derivad from this channel. To negate the effect of certain conditions, overcompensation even in the ion chanber, in an initially undercompensated whichprovision chamber ",n occurmay under '

bemadeti0 supply an adjustable small current to the channel amplifier (up to 1.5 x 10- amps) so as to facilitate startup.

5.2.3 Count Rate Channel

A fission chamber is used to supply pulses to a linear amplifier and loga-

! rithmic count rate circuitry. Pulse height discrimination selects pulse ampli-i tudes that correspond to fission events and rejects those from alpha particles. -

a Count rate on a logarithmic scale is displayed on a panel meter and a chart recorder. In addition, count rate period information is derived and similarly l displayed. The channel covers a range of 1 to 104 cps, corresponding roughly to a range of 0.25 MW to 2.5 W, but the upper limit can be increased many decades by repositioning the chamber. The motor-operated chamber drive is I

operated from the control room, the drive position being indicated on a meter. ,

I To prevent control-rod withdrawal when the neutron count rate information may not be reliably indicated, inhibits are provided on count rate and period, and when the fission chamber is being repositioned. All except the latter are ,

by?assed at a power of >50 W. A' scaler is also provided for obtaining accurate values at low ceunt rates if needed (e.g., approach to critical with new fuel or new core configuration). ,

5.2.4 Neutron Source For obtaining the reliable neutron information necessary for startup from a cold shutdown condition, an antimony-beryllium neutron source is provided for insertion into tt core as needed. This source, nominally 50 Ci of Sb-124, is renewed by neutron activation in the core. Its presence in the core is not l essential except after extended shutdowns. Integrity of the source is checked ,

by periodic sampling of pool water (see Section 4.8).

5.3 Rod Control System 5.3.1 Control Rods The number of control rods shall be determined by the required shutdown margin l and flux uniformity requirements. Up to five control rods are provided for j I

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• Amendment No. 24 I

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