ML19339C399
| ML19339C399 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 11/06/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | MICHIGAN, UNIV. OF, ANN ARBOR, MI |
| References | |
| GL-80-93, NUDOCS 8011180291 | |
| Download: ML19339C399 (3) | |
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NUCLEAR REGUt el-RY COMMISSION 2
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N ro N
ro To All Nonpower Reactor Licensees SUBJECl: EMERGENCY PREPAREDNESS l
l The Nuclear Regulatory Commission has upgraded its Emergency Preparedness Regulations to ensure that adequate protective measures can and will be taken in the event of a radiological emergency. The final rule consists of amendments to 10 CFR Parts 50 and 70, was published in the Federal Register on August 19, 1980, and became effective November 3,1980.
In addition, the requirements in 10 CFR 50, Appendix E, are clarified and upgraded. These amendments apply to both Power and Nonpower Reactor 1'
Licensees. The rule establishes the requirement for submission of new upgradea emergency plans and associated implementing procedures for NRC review and approval.
A summary of the final rule is as follows:
1.
10 CFR S 50.54 (Conditions of Licenses) is amended by adding two new paragraphs (q) and tr) which affect nonpower reactors, a.
Section 50.54(q) requires that each licensee authorized to possess and/or operate a research reactor or a fuel facility shall follow and maintain in effect emergency plans which meet the requirements in Appenaix E of 10 CFR 50.
b.
Section 50.54(r) requires each licensee who is autnorized to possess and/or operate a research reactor facility with 2
an authorized power level greater than or equal to 500 Kw thermal, shall submit emergency plans complying with 10 CFR 50, Appendix E, to the Director of Nuclear Reactor,
Regulation for approval within one year of the effective date of tnis rule, and all other research or test reactor facilities shall submit emergency plans within two years of the effective date of this rule. All licensees tnat are in the license renewal process will be required to upgrade their plans to the revised criteria as a condition P
of the renewal.
2.
10 CFR 50, Appendix E, " Emergency Planning ano Preparedness for Production and Utilization Facilities", establishes minimum requirements for emergency plans for use in attaining an accep-table state of emergency preparedness, and recognizes that:
8011180 N
4 NOV 6 1980 a.
The potential radiological hazards to the public associated with the operation of research and test reactors and fuel facilities licensed under 10 CFR Parts 50 and 70 involve consideration different than those associated with nuclear o
power reactors.
b.
Consequently, the size of any required Emergency Planning Zones for facilities other than power reactors and the degree to which compliance with the requirements of Sections I through V of Appendix E will be determined on a case-by-l case basis.
3.
Regulatory Guide 2.6 (For Comment) " Emergency Planning for Research Reactors", will be used as guidance for the acceptability of research j
and test reactor emergency plans.
A copy of the Federal Register Notice Volume 45, Number 162 dated August 19, 1980, is enclosed for your information.
Any questions regarding Emergency Planning can be addressed to the Emergency Preparedness Development Branch (Steve L. Ramos (301) 492-8119 or Eugene Bates (301) 492-8639). Further, it would be helpful if you would submit the name(s) of personnel in your organization responsible for emergency planning to:
Steve L. Ramos, Chief Emergency Preparedness Development Branch Emergency Preparedness Program Office U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Sincerely, hE Robert L. Tedesco, Assistant Director 4
for Licensing
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Division of Licensing 1
Enclosure:
Federal Register Notice dtd. August 19, 1980
l ATTACHMENT TO GENERIC LETTER'TO ALL NONPOWER REACTOR LICENSEES I
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DOCKET NO._
DOCKET NO.
DOCKET NO.
50-70 50-113 50-186 50-184 50-224 50-123 50-13 50-326 50-396 50-360 50-357 50-62 50-225 50-151 50-139 50-394 50-166 50-124 4
50-77 50-192 50-87 50-276 50-407 50-134 i'
50-284 50-156
~
50-538 50-131 50-27 50-59 50-99 50-598 50-262 50-406 50-97 50-98 5C-73 50-252 50-160 l
50-112 50-116 5 0-72 50-199 50-228 50-20 i
50-170 50-297 l
50-208 50-375 501E7 50-150 50-.,4 50-182' 50-162 50-193 50-89 50-57 50-274 50-54 50-188 50-142 50-294 50-433 50-187 50-83 50-243 50-356 50-5 E0-148 50-288 50-223 50-128 50-2 7
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