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)

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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.

hDonald bbH. Rusling Reactor Supervisor

/cc: Document Control Desk (2) l l

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4.2.2.3 of 20 mrem /hr for Radiation levels at the site boundary dose. 1-hour whole body or 100 mrem thyroid 4.2.2.4 (1) missiles impacting Imminent or existing hazards, explosion on the reactor facility, e.g.,

that affects facility operation, (2) uncontrolled facility release of toxic or flammable gases into the environs. (3) 4.2.2.5 Radiationofdose building requ i ring evacuation all rates in the reactor 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 rate which exceeds makeup capacity. loss of core coolant at a 4.2.3 Site Area Emergency 4.2.3.1 Actual or ef fluent s at the site boundary projected 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 />. hours or 375 mrem 4.2.3.2 at the site boundary ofActual or projected 100 mrem /hr for 1 radiation level s 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 coolant at a rate that exceeds makeup capacity.

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

consist of the area within the 4.4 Emergency Response 4.4.1 Communications P rima ry communication intercom. will be by telephone or room, and itAn can evacuation ho rn be activated is located manually fromin the the reactor 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.