ML14064A369

University of Maryland, College Park Request for Additional Information Review of the Emergency Plan for License Renewal for the University of Maryland Training Reactor

ML14064A369
Person / Time
Site:	University of Maryland
Issue date:	03/11/2014
From:	Lising A Research and Test Reactors Licensing Branch
To:	Koeth T Univ of Maryland - College Park
Lising A
References
TAC ME1592
Download: ML14064A369 (6)

Text

March 11, 2014 Dr. Timothy W. Koeth, Director University of Maryland Nuclear Reactor and Radiation Facilities Department of Materials Science and Engineering 2309D Chemical and Nuclear Engineering Building Building 090, Stadium Drive College Park, MD 20742-2115

SUBJECT:

UNIVERSITY OF MARYLAND - REQUEST FOR ADDITIONAL INFORMATION RE: REVIEW OF THE EMERGENCY PLAN FOR THE LICENSE RENEWAL FOR THE UNIVERSITY OF MARYLAND TRAINING REACTOR (TAC NO.

ME1592)

Dear Dr. Koeth:

The U.S. Nuclear Regulatory Commission (NRC) is continuing its review of your application for the renewal of Facility Operating License No. R-70 for the University of Maryland Training Reactor dated May 12, 2000 (a redacted version of the application is available on the NRCs public Web site at www.nrc.gov under Agencywide Documents Access and Management System Accession No. ML072210862), as supplemented.

The NRC staffs review of your license renewal application includes a review of your current emergency plan, titled Emergency Preparedness Plan for the Maryland University Training Reactor, Revision 12, dated December 1999, submitted to the NRC via letter dated January 5, 2000. Our review identified two questions, which are provided in the enclosed request for additional information (RAI). Please provide your response to the enclosed RAI within 30 days from the date of this letter.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.30(b), you must execute your response in a signed original document under oath or affirmation. Your response must be submitted in accordance with 10 CFR 50.4, Written communications.

Information included in your response that is considered sensitive, or proprietary, that you seek to have withheld from the public, must be marked in accordance with 10 CFR 2.390, Public inspections, exemptions, requests for withholding. Any information related to security should be submitted in accordance with 10 CFR 73.21, Protection of Safeguards Information:

Performance requirements. Following receipt of the additional information, we will continue our evaluation of your license renewal request.

T. Koeth If you have any questions about this review, or if you need additional time to respond to this request; please contact me by telephone at 301-415-3841 or by electronic mail at Jason.Lising@nrc.gov.

Sincerely,

/RA/

A. Jason Lising, Project Manager Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-166 License No. R-70

Enclosure:

RAI cc: See next page

University of Maryland at College Park Docket No. 50-166 cc:

Director, Dept. of Natural Resources Power Plant Siting Program Energy & Coastal Zone Administration Tawes State Office Building Annapolis, MD 21401 Mr. Roland G. Fletcher, Program Manager IV Radiological Health Program Maryland Department of Environment 1800 Washington Blvd., Suite 750 Baltimore, MD 21230-1718 Mr. Vincent G. Adams Facility Coordinator Chemical and Nuclear Engineering Building 090 University of Maryland College Park, MD 20742 Mary J. Dorman Radiation Safety Officer Department of Environmental Safety 3115 Chesapeake Building 338 University of Maryland College Park, MD 20742 Professor Robert Briber Department of Materials Science and Engineering University of Maryland College Park, MD 20742-2115 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

ML14064A369; *concurred via e-mail NRR-088 OFFICE DPR/PRLB/PM* DPR/PRLB/LA NSIR/DPR/DDEP/ORLOB/BC* DPR/PRLB/BC DPR/PRLB/PM NAME JLising PBlechman JAnderson AAdams JLising DATE 03/05/2014 03/06/2014 03/07/2014 03/10/2014 03/11/2014

OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REVIEW OF THE EMERGENCY PLAN FOR THE RENEWAL OF THE FACILITY OPERATING LICENSE FOR THE UNIVERSITY OF MARYLAND TRAINING REACTOR LICENSE NO. R-70; DOCKET NO. 50-166 The U.S. Nuclear Regulatory Commission (NRC) is continuing its review of your application for the renewal of Facility Operating License No. R-70 for the University of Maryland Training Reactor dated May 12, 2000 (a redacted version of the application is available on the NRCs public Web site at www.nrc.gov under Agencywide Documents Access and Management System Accession No. ML072210862), as supplemented.

The NRC staffs review of your current emergency plan, Emergency Preparedness Plan for the Maryland University Training Reactor, Revision 12, dated December 1999, submitted to the NRC via letter dated January 5, 2000, identified two questions. Please provide responses to the following requests for additional information (RAIs) within 30 days from the date of this letter.

Title 10 of the Code of Federal Regulations, Part 50, Appendix E,Section IV.B.1 states, in part:

[t]he means to be used for determining the magnitude of, and for continually assessing the impact of, the release of radioactive materials shall be described, including emergency action levels that are to be used as criteria for determining the need for notification and participation of local and State agencies, the Commission, and other Federal agencies, and the emergency action levels that are to be used for determining when and what type of protective measures should be considered within and outside the site boundary to protect health and safety. The emergency action levels [EALs] shall be based on in-plant conditions and instrumentation in addition to onsite and offsite monitoring.

RAI 1

Section 4.3 of the Emergency Preparedness Plan contains examples of what type of emergency may be included in each classification: specifically, Alert EALs for fires, loss of pool water, and fuel clad damage. However, Table 5.1, Emergency Classification Codes, only has one Alert EAL for a high radiation event.

It is not clear what (if any) procedures are direct actions for emergency classifications. Please provide the applicable procedures that are used by the acting and designated Emergency Directors for classifying events.

Enclosure

RAI 2

Table 5.1 contains the following information:

Unusual Event (Class 1): Any event that causes or likely causes radiation levels as indicated on any radiation area monitors to be above 100 mrem/hr.

Alert (Class 2): Any event that causes or likely causes radiation levels as indicated on any radiation area monitors to be above 100 mrem/hr.

It appears that these EALs are identical. Is the information provided in Table 5.1 accurate with respect to these two EALs?