ML20195H055

Amend 14 to License R-73,allowing Certain Surveillance Requirements Associated W/Operation of Reactor to Be Suspended

ML20195H055
Person / Time
Site:	05000139
Issue date:	11/18/1988
From:	Chris Miller Office of Nuclear Reactor Regulation
To:
Shared Package
ML20195H051	List: ML20195H045 ML20195H055 ML20195H069
References
R-073-A-014, R-73-A-14, NUDOCS 8811300202
Download: ML20195H055 (7)

Text

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1. $ 'o,, UNITED STATES

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t w AsHINGTON. D, C. 20666 r.

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UNIVERSITY OF WASHINGTON DOCKET NO. 50-139 AMEN 0 MENT TO FACILITY LICENSE Amendment No. 14 License No. R-73

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

A. The ap>1tcation for amendment to Facility License No. R-73

filed >y the University of Washington (the licensee), dated October 6,1988, as supplemented by telecon on October 17, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C. There is reasonable assurance: (1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be 1 conducted in compliance with the Comission's regulations set forth i

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 requirements have been satisfied; and F. Publication of notice of this amendrent 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 amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 4.B of License No. R-73 is hereby amended to read as follows:

B. Technical Specifications .

The Technical Specifications contained in Appendix A, as revised through Amendment No. 14, 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 the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION cAJ,1 mdb~

Charles t. Miller, Director Standardization and Non-Power i

Reactor Project Directorate Division of Reactor Projects III, !Y, (

Y and Special Projects i Office of Nuclear Reactor Regulation l

Enclosure:

, Appendix A Technical Specifications Changes Date of Issuance: November 18, 1988 1

ENCLOSURE TO LICENSE AMENDMENT N0. 14 FACILITY LICENSE NO. R-73 DOCKET N0. 50-139 i

4 Replace the following gages of the Appendix A Technical Specifications with the enclosed pages. Tae revised pages are identified by Amea dment nus6er and contain a vertical line indicating the area of change.

Remove Pages Insert Pages i

1 1 4 4 5 5 9 9 i

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APPENDIX A TECHNICAL SPECIFICATIONS FOR THE UNIVERSITY OF WASHINGTON NUCLEAR REACTOR FACILITY LICENSE NO. R-73 DATE: APRIL 12. 1972 The dimensions, measurements, and other numerical values given in these specifications may differ from measured values owing to normal construction and manufacturing tolerances or normal accuracy of instrumentation.

I. Definitions A. Reactor Shutdown The reactor shall be considered shutdown whenever:

1. All control blades are fully inserted and the reactor is subcritical by a margin equal to or greater than 1.9% delta k/k at 85'F. When calculating the subcritical margin, no credit shall be taken for xenon poisonirg and experi-ments, and

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2. The reactor console key switch is in the "Off' position, and the key is removed from the console and under the l control of a licensed operator.

3. There is no fuel in the core.

4. Technical Specification I.A.1 and I.A.2 apply only if there is fuel loaded in the core.

B. Reactor Operation i Reactor operation shall mean any condition whersin the reactor is not shutdown.

l C. Operable A system or component shall be considered operable when it is capable of performing its intended function in a normal manner.

D. Operating A system or corponent shall be considered operating when it i

is performing its intended function in a normal manner.

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Ainendment No.14 i

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4 III. Reactor System A. Reactor Core

1. The core shall consist of a maximum of 24 fuel assedlies of up to 11 plates each. These asseelies are contained in six aluminum boxes surrounded by reactor-grade graphite.

The boxes are arranged in two parallel rows of three boxes each, separated by about 30 centimeters of reactor-grade graphite.

2. A fuel plate shall be enriched uranium-aluminum alloy fuel clad with aluminum. There shall be nominally 14.5 grams of uranium per fuel plate.

3. A neutron source shall be provided during reactor startup.

4. The maximum power level shall be 100 kW (thermal).

B. Primary Coolant System

1. The primary coolant shall be demineralized light water.

l 2. The primary coolant flow rate shall be 0.2 gpm, or greater, {

per kilowatt of reactor power.

3. The primary coolant inlet temperature shall be greater than 85'F.

4. The average primary coolant outlet temperature shall not exceed 160'F.

5. The resistivity of the primary coolant shall be measured wee kly. The resistivity shall not be less than 0.2 megohm-centimeters. These determinations may be suspended if there is no fuel in the core.

6. The primary coolant quick-dump valve shall be activated manually and upon receipt of an automatic shutdown signal prior to each reactor startup to assure proper operation.

C. Reactor Coolant System

1. Four cadmium-tipped van-type blades shall be used for reactor control. The control blades shall be protected by shrouds to assure freedom of motion.

Amendment No. 14 1

2. The reactor shall not be made critical unless all control blades and control blade drives are operable.

3. The reactor shall not be made critical unless the inter-locks in Table I are operable.

4. Tests, limits and frequencies of tests for the control system shall be as listed in Table II. The tests, limits, and frequencies of tests can be suspended if there is no fuel in the core. If fuel is to be leaded into the core the times in Table II would be verified prior to loading and the reactivity worths determined after fuel loading.

5. Following maintenance or modification to the reactor control system, an operability test of the affected portion of the system, including verification of control blade drive speed, shall be performed before the system is considered operable.

D. Reactor Safety System

1. The reactor shall not be made critical unless the reactor safety system is operable in accordance with Table III.

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2. Tests for operability shall be made in accordance with Table IV.

3. The following neutron channels shall be calibrated against an independent measure of core power at intervals not exceeding 12 montles, and any time a change in channel performance is noted:

a. log N-period channel

b. power level safety channels

c. linear power level channel These calibrations can be suspended if there is no fuel in the core. If fuel is to be loaded into the core the calibrationsina,b,andcshallbeperformedafterfuel loading.

4. Following r.aintenance or modifications to the reactor safety system, an operability test and calibration of the affected channel shall be performed before the reactor safety systen is considered operable.

Amendment No. 14

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E. Pneumatic Sample Transfer Systems

1. Two pneumatic sample transfer systems may be installed; one shall terminate in the west vertical experimental port of the graphite center island and the other shall terminate in the graphite pedestal at the east end.

2. All operations of the pneumatic sample transfer systems  !

shall be in accordance with approved written procedures. t

3. No sample shall be pneumatically removed from or inserted into a critical reactor if the resultant stable period will be less than 20 seconds.

i IV. Reactivity A. The core excess reactivity at cold critical (85'F) without xenon poisoning or negative reactivity experiments, but including positive reactivity experiments shall not exceed 1.9% delta k/k.

B. The primary coolant void and temperature coefficients of reactivity shall be negative.

C. The minimum shutdown margin, with the most reactive control blade fully withdrawn, shall be 0.75% delta k/k.

D. The reactivity insertion rate for a single control blade shall not exceed 0.051 delta k/k/sec. l E. Items C and D shall be verified in accordance with Table !!, ,

Test 5. This verification need not be performed if there is no fuel in the core. l 4

Y. Radiation Monitoring System l A. The reactor room shall be continuously monitored by at least  :

two arcia radiation monitors. The monitors shall be capable l of audibly warning personnel of high radiation levels. The  ;

output of these monitors shall be continuously indicated in i the control room.

B. Exhaust air drawn from the reactor room shall be continuously monitored for gross concentration of radioactive gases.

i Amendrent No.14