ML20212P003

Forwards Rev to Section 4.4.1 of Emergency Plan,Reflecting Upgrade of Denver Federal Ctr Fire Alarm Sys

ML20212P003
Person / Time
Site:	U.S. Geological Survey
Issue date:	08/22/1986
From:	Rusling D INTERIOR, DEPT. OF, GEOLOGICAL SURVEY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
NUDOCS 8609020134
Download: ML20212P003 (3)

Text

_

. < uj, f

y ^^^j United States Department of the Interior GEOLOGICAL SI'RVEY BOX 25016 M.S..

424__

DENVER FEDERAL CENTER DENVER, COI.ORADO 80225 n men s..... n, August 22, 1986 License No. R-113 Docket No. 50-274 Administrator Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011

Dear Sir:

In accordance with 10CFR 50.54(q), enclosed is a revision to Section 4.4.1 of the U. S. Geological Survey TRIGA Reactor Facility Emergency Plan.

This change resulted from the upgrade of the Denver Federal Center fire alarm system.

The change does not reduce the effectiveness of the Emergency Plan.

If you have any questions, please call me on FTS 776-4726.

h bb Donald H. Rusling Reactor Supervisor

/cc: Document Control Desk (2) l l

i f

StrSBMA BISS$P g#

k

o o

4.2.2.3 Radiation levels at the site boundary of 20 mrem /hr for 1-hour whole body or 100 mrem thyroid dose.

4.2.2.4 Imminent or existing hazards, e.g.,

(1) missiles impacting on the reactor

facility, (2) explosion that affects facility operation, (3) uncontrolled release of toxic or flammable gases into the facility environs.

4.2.2.5 Radiation dose rates in the reactor building requ i ring evacuation of all mrem /hr for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> throughout the building. personnel, e.g., 100 4.2.2.6 Abnormal loss of core coolant at a rate which exceeds makeup capacity.

4.2.3 Site Area Emergency 4.2.3.1 Actual or projected ef fluent s at the site boundary radiological unrestricted areas when averaged over 24 exceeding 250 MPC for whole body accumulated in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or 375 mrem hours.

4.2.3.2 Actual or projected radiation level s at the site boundary of 100 mrem /hr for 1 or five times this level to the thyroid.

hour whole body 4.2.3.3 Imminent loss of physical control of the reactor.

4.2.3.4 Abnormal continuing loss of core coolant at a rate that exceeds makeup capacity.

4.2.2.5 Severe natural events being experienced that reactor systems. are causing observable damage to critical 4.3 Emergency Planning Zone The EPZ shall consist of the area within the operation's boundary.

4.4 Emergency Response 4.4.1 Communications P rima ry communication will be by telephone or intercom.

An evacuation ho rn is located in the reactor room, and it can be activated manually from the reactor console or from within the reactor room.

Building evacuation horns are located at several points in the building, and these horns are activated automatically by the fire alarms or a high radi ation al arm f rom the reactor facility.

There is a

radiation alarm system connected di rectly to the Fire Department which is activated automatically in the event of high radiation level s.

F i re Department and F ede ral Protective Service units are equipped with 2-way radios and will provide a communication link in the event the telephone system is unavailable.

4.4.2 Attivation of Emergency Organization The Reactor Supervisor, or the Senior Operator-in-

Charge, will be responsible for activation of those portions of the emergency organization requi red for the class of emergency existing.

Emergency notification lists are posted within the operation's boundary and at several other locations on site.

Notification lists are al so available at the Federal Protective Service control center and at the Fi re Dep'artment di spatch center.

The person 'in charge would also be responsible for requesting radiological control assistance from Rockwell International or medical treatment of contaminated personnel at the University of Colorado Health Sciences Center.

4.4.3 Assessment Actions Assessment of the emergency situation would be a continuing process based on visual ob se rva ti on s and information from reactor instrumentation; remote readout from radiological monitoring instruments; and po rt ab l e radiation monitoring instruments.

Multichannel analyzer systems are available on site for use in the identification of radionuclides.

Alpha and beta counting systems are avail able on site to evaluate air samples and contamination wipes.

4 '. 4. 4 Corrective Actions The declaration of any class of emergency shall be cause for the shutdown of the reactor.