ML20149M360
| ML20149M360 | |
| Person / Time | |
|---|---|
| Site: | 05000139 |
| Issue date: | 02/24/1988 |
| From: | Michaels T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149M359 | List: |
| References | |
| R-073-A-013, R-73-A-13, NUDOCS 8802250510 | |
| Download: ML20149M360 (5) | |
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1 UNIVERSITY OF WASHINGTON DOCKET NO. 50-139 AMENDMENT TO FACILITY LICENSE Amendment No. 13 License No. R-73
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment to Facility License No. R-73 filed by the University of Washington (the licensee), dated February 4, 1988, as supplemented by telecen on February 16, 1988, complier with the standards and reauirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 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 l conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; j D. The issuance of this amendment will not be inimical to the comon 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 l been satisfied; and F. Publication of notice of this emendment 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 Facility License No. R-73 is hereby anended to read as follows:
B. Tec'hnical Specific:eions Th[ Technical Specifications contained in Appendix A, as revised through Amendment No. 13, 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 rm -
ts Su AJ Lester S. Rubenstein, Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Fuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Changes Date of Issuance:
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ENCLOSURE TO LICENSE #1ENDMENT NO.13 FACILITY LICENSE NO. 73 DOCKET NO. 50-139 l
1 Replace the following pages of the Appendix A Technical Specifications with the enclosed paaes. The revised pages are identified by Amendment number and contain a vertidal line indicating the area of change.
Remove Pages Insert Pages 6 6 9 9 iha_ eM,
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E. Pneumatic Sample Transf er Systems .
- 1. fTwo pneumatic sample transfer systema may be installed; one shall terminate in the west vertical experimental port of the graphite center island and the other shall terminate in. the graphice pedestal at the east end.
- 2. All operations of the pneumatic sa=ple transfer syste=s shall be in accordance with approved written procedures.
[ 3. No sample shall be pneumatically removed from or inserted into a critical reactor if the resultant stable period.will ch9,.1b e4*13 be less than 2,0 seconds. .L IV. Reactivity _
~ 1~' . The core excess reactivity at cold critical (85'F) without ghg.J xenon poisoning or negative reactivity experiments, but '
a g.,, q 13 including positive reactivity experiments shall not exceed 3,j, 1 1 9% delta k/k. f5 B. The primary coolant void and temperature coefficients of reactivity shall be negative.
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C. The minimum shutdown margin, with the most reactive control '
blade fully withdrawn, shall be 0.75% A k/P.
D. The reactivity insertion rate for a cingle control blade shall not exceed 0.05% A k/k/sec.
. E. Items C ar ' D shall be verified in accordance with Table II, Test 2.
- V. Radiation Monitoring System A. The reactor room shall be continuously monitored by at least two area radiation monitors. The monitors shall be capable of audibly warning personnel of high radiation levels. The output of these monitors shall be continuously indicated in j the control room. ;
l B. Exhaust air drawn from the reactor room shall be continuously j monitored for cross concentration of radioactive gases, i l
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Amendment No.13 ,
.o TABLE I Control Blade Withdrawal Inhibit Interlocks
- 1. Startup.chann21 count rate less than 1 count per second.
25 Primary foolant temperature less than 85F.
- 3. Reactor period less than 6 seconds.
TABLE II Test Limit Frequt..sy
- 1. Drop time of shim 1 second from monthly (5 week rod No. 1 initiation of maximum interval) blade drop to full insertion
- 2. Drop time of shim 1 second from monthly (5 week rod No. 2 ir,itiation of me"imum interval) blade drop to full insertion
- 3. Drop time of shim 3 seconds from before each rod No. 3 initiation of reactor operation blade drop to as part of the full insertion checkout procedure
- 4. Drop time of 1 second fron, monthly (5 week regulating rod initiation of maximum interval)
. blade drop to _.
full insertion
- 5. Reactivity worth of annual (14 mo,th each control blade, maximum inter.all shutdown margin, and reactivity insertion rate of each control blade
- 6. Operabil'ty test of operable prior to each interlocks listed in reactor startup Tsble I.
l Amendment No. 13