ML20055J479
| ML20055J479 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 07/23/1990 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20055J478 | List: |
| References | |
| R-084-A-019, R-84-A-19, NUDOCS 9008030028 | |
| Download: ML20055J479 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
- E .t. WASHINGTON, D. C. 20555
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- 5. . . .. y ARMED FORCES RAD 10B10 LOGY RESEARCH INSTITUTE DOCKET NO. 50-170 AMENNIENT 'TO FACILITY OPERATING LICENSE Amendment No. 19 License No. R-84
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
S A. volication for amendment ^.o Facility Operating License No. R-84 f.h tv the Armed Forces Radiobiology Research Institute (the
'. W a e), dated April 30, 1990 as supplemented on June 19, 1990, and .uiy 13, 1990 complier with the standards and requirements 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 Comission; C.- Thereis reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and safoty of the public, and (ii) that such activities will be conducted in ecmpliance with the Contrission's regulations set forth in'10 CFR Chapter I; 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 been 9tisfied; and F. Prior notice of this amendment was not required by 10 CFR 2.105(a)(4) and publication of notice for this amendment is not required by 10CFR2.106(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 2.C.(2) of License No. R-84 is hereby amended to read as
'f0110ws:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 19, 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.
FOR THE NUCLEAR REGULATORY COMMISSION i
<A e d Seym ur H. Weiss, Director Non-Power Reactor,. Decommissioning and Environmental Project Directorate Division of Reactor Projects - III, l- IV, Y and Special Projects L Office of Nuclear Reactor Regulation
Enclosure:
Appendix A-Technical Specifications Changes Date of Issuanco: July 23, 1990-l l
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. ENCLOSURE TO LICENSE AMENDMENT NO.19
~ 1 FACILITY' OPERATING LICENSE NO. R-84 l-DOCKET NO. 50-170
' Replace the following ) ages of the Appendix A Technical Specifications with I. the attached pages. . Tie revised pages are identified by amendment number and l contain vertical lines indicating the areas of change. l 1
i; Remove Insert I l
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tions sa reactor' power. level 1:diceti:n are included in this Section, since the -
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- . X power level lo related to the fuel temperotsn.-
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' 2.2 : REACTOR SAFETY SYSTEM -
, - Anoticability This speelfication applies to the reactor safety system.
Objective The objective is to specify the minimum number of nactor safety system channels that must be operable for safe operation.
So cification The reactor shall not be operated unless the safety systems descriW in Tables 2-and- 8 an operable.
TABLE 2. MINIMUM REACTOR SAFETY- SYSTEM SCRAMS Maximum Minimum Number in Mode Channel Set Point Steady State Pulse ,
Fuel Temperature 600'C 2 2 Percent Power, High Flux 1.1 MW 2 0 Console Manual Scram Bar Closure switches 1 1 High Voltage Loss to 20% loss 2 1 Safety Channels Pulse Time is seconds 0- 1 Emergency Stop (1 each exposure room, 1 on console) Closun switch 1 1 Pool Water Level 14 feet from top of core 1 1 Watchdog (DAC to CSC) On digital console 1 1 Entit The fuel temperatun and power level scrams provide protection to assure that the reactor can be shut down before the safety limit on the fuel element temperature will be exceeded. The manud scram allows the operator to shut down the system at any time if an unsafe t.r abnormal condition occurs. In the l .- event of failure of the power supply for the safety channels, operation of the reactor without adegate lastrumentation is prevented. The preset timer insures that the reactor-power level will reduce to a low level after pulsing. The emergency stop allows personnel trapped in a potentially hasardous exposure 10 Amendment No. 19
room or the reactor. operator to stop teti:as throtsh the interlock syst:m.-The-
' " -" - pool wct:r level 1:stres thct a loss of bl:1:gical shielding'wssld res:lt in a reacter ehutd:wn. The wctchdos scram will lasure adeqtete c:mmunicatiw
. between the Data Acquisition Lomputer (DAC) and the Control System
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Computer (CSC) anits.
TABLE 8, MINIMUM REACTOR SAFETY SYSTEM INTERLOCKS
- Effective Mode Action' Prevented Steady State Pub Puk initiatlon at power levels greater X than 1 kilowatt
' Withdrawal of any control rod expect transient X m
Any rod ' withdrawal'with count rate in X X operational channel below 0.5 cpe Simultaneous manual withdrawal of two X standard rods Bath The Interlock preventing the initiation of a pub at a_ critical level above 1 kilowatt assures that the pulse magnitude will not allow the fuel element-temperature to approach the sa.fety limit. The interlock that prevents movement of standard control rods la pulse mode will prevent the inadvertent placing of the reactor on a positive period while in pulse mode. Requiring a count rate to be seen by the operational channels insures sufficient source neutrons to bring the reactor critical under controlled conditions. The interlock that prevents the simultaneous manual withdrawal of two standard control rode limits the amount of reactivity added per unit time.
8.2.8 FACILITY INTERLOCK SYSTEM Anolicability This specification applies to ti.e interlocks that prevent the accidental exposure of an individual in either exposure room.
Oblective The objective is to provide suffielent warning and interlocks to prevent movement of the reactor core to the exposure room in which someone may be working, or prevent the inadvertent movement of the core into the lead shald doors.
11 Amendment Ho.19
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