ML20055G035
| ML20055G035 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 07/13/1990 |
| From: | Irving G ARMED FORCES RADIOBIOLOGICAL RESEARCH INSTITUTE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20055G036 | List: |
| References | |
| NUDOCS 9007200077 | |
| Download: ML20055G035 (3) | |
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DEFENSE NUCLEAR AGENCY bd N
- ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE BETHESDA, M ARYLAND 20814 5145
SUBJECT:
Addendum to Request for Changes to AFRRI - July 13,1990 Facility License 110. R 84, Paragraph 2.C.(1)
'i and the Technical Specifications for License No.
R 84 dated April 30,1990.
Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. -20555 Gentlemen:
This addendum to our request for changes to the AFRRI Facility License No. R-84 and Technical Specifications for license No R-84 is the result of a telephone conversation between Mr. Al Adams of the NRC and 1st Lt Matt Forsbacka, Reactor Executive Officer,
. on July 10,1990. Attachment 1 clarifies a typographical error in the correction of Section 3.2,2 of the Technical Specifications. Attachme::t 2 provides replacement pages for pages 10 and 11 of the Technical Specifications, if you have any questions or comments, please contact the Reactor Facility Director, Mr.
Mark Moore, or the Reactor Executive Officer,1st Lt Matt Forsbacka, at (301) 295-1290.
Thank you for your cooperation.
Sincere .
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GEORGE RVING, III Colonel, ', USAF Director
Enclosures:
as stated cc: USNRC- Region 1 - Project Eng'meer Division of Reactor Projects USNRC- Headquarters Project Manager Nuclear Reactor Regulation 9007200077 900713 PDR P
ADOCK 05000170 PDC i
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-.'s, ATTACHMENT 1 CORREtTION TO PROPOSED CHANGE TO TECHNICAL SPECIFICATION 12.2
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Bethesda, MD 20889-5145 t
.;f July 1990 ; .
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e The original submission has been corrected to read as follows:
- 9. Pane 10/11 section 3.2.2: Replace the Basis in its entiret) where ' safety channels
- replaces " safety chambers" to clarify requirement and to in:lude the basis for the watchdog scram requiremeut.
The fuel temperature and power level scrams provide protection to assure that the i reactor can be shut down before the safety limit on the fuel element temperature will be exceeded. The manual scram allows the operator to shut down the system at any time if an unsafe or abnormal condition occurs. In the event of failure of the power supply for the safety channels, operation of the reactor without adequate instrumentation is prevented. The preset timer insures that the reactor power level will reduce to a low level af ter pulsing. The emergency stop allows personnel trapped in : potentially harardous exposure room or the reactor operator to stop actions through the interlock system. The pool water level insures that a loss of biological shielding would result in a reactor shutdown. The watchdog scram willinsure adequate communication between the Data Acquisition and Control (DAC) and Control System Computer (CSC) units."
Safety Analysis: This change is to reflect USNRC's request to add requirement for new reactor instrumentation, i
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