ML19254E680

From kanterella
Jump to navigation Jump to search
Notifies of Commission 790809 Approval to Publish Proposed Amends to 10CFR50 & 70 in Fr,Re Emergency Plans for Nonpower Reactor Licensees.Forwards Transcript of 790827 Meeting Re Impact of Proposed Safeguards Upgrade Rule
ML19254E680
Person / Time
Site: U.S. Geological Survey, Texas A&M University, Pennsylvania State University, Idaho State University, University of Iowa, Kansas State University, Washington State University, Reed College, North Carolina State University, Dow Chemical Company, General Atomics, Ohio State University, Oregon State University, University of Virginia, Rensselaer Polytechnic Institute, University of Lowell, Rhode Island Atomic Energy Commission, University of California - Irvine, Vallecitos Nuclear Center, 05000128, Purdue University, 05000131, 05000375, 05000134, 05000113, 05000262, 05000360, 05000157, 05000054, 05000294, 05000433, 05000406, 05000077, 05000097, Neely Research Reactor, 05000142, 05000199, 05000192, 05000148, 05000538, Vallecitos, 05000139, 05000087, 05000124, Lynchburg Research Center, 05000072, 05000356, MIT Nuclear Research Reactor, 05000394, 05000187, University of Michigan, University of Missouri-Rolla, Aerotest, University of Wisconsin, University of Missouri-Columbia, University of Illinois, 05000129, 05000276, 05000208, 05000112, 05000106, Armed Forces Radiobiology Research Institute, University of Buffalo, 05000098, University of New Mexico, 05000357, National Bureau of Standards Reactor, University of Maryland, Berkeley Research Reactor, University of Utah, 05000083
Issue date: 10/19/1979
From: Reid R
Office of Nuclear Reactor Regulation
To: Alger D, Burn R, Cashwell R, Lisa Clark, Curtner A, Marlone Davis, Dimeglio A, Doran J, Denise Edwards, Elliott A, Feltz D, Foster R, Furr A, George K, Andrea Johnson, Kachel P, Light R, Mcmaster I, Mowry W, Ostrander N, Raby T, Roth J, Ruzich R, Shoptaugh J, Swannack C, Williamson T, Wilson W
BABCOCK & WILCOX CO., CALIFORNIA, UNIV. OF, LOS ANGELES, CA, ESGRIAC, GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER, GENERAL ELECTRIC CO., Neely Research Reactor, ATLANTA, GA, LOS ALAMOS NATIONAL LABORATORY, MASSACHUSETTS INSTITUTE OF TECHNOLOGY, CAMBRIDGE, MICHIGAN, UNIV. OF, ANN ARBOR, MI, MISSOURI, UNIV. OF, COLUMBIA, MO, MISSOURI, UNIV. OF, ROLLA, MO, NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL, Oregon State University, CORVALLIS, OR, PENNSYLVANIA STATE UNIV., UNIVERSITY PARK, PA, TEXAS A&M UNIV., COLLEGE STATION, TX, UNION CARBIDE CORP., VIRGINIA POLYTECHNIC INSTITUTE & STATE UNIV., BLACKSB, VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA, WASHINGTON STATE UNIV., PULLMAN, WA, WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP., WISCONSIN, UNIV. OF, MADISON, WI
Shared Package
ML19254E681 List:
References
NUDOCS 7911020154
Download: ML19254E680 (8)


Text

72/l4 s

4 pR Rig

/

g UNITED STATES NUCLEAR REGULATORY COMMISSION yy p,

7..g

. g WASHINGTON. D. C. 20555 8

October 19, 1979

- j ALL NONP0WER REACTOR LICENSEES

Background

On August 9, 1979, the Commission approved Ba publishing of proposed amendments to 10 CFR Parts 50 and 70 on Emergency Plans for comments in the Federal Register.

On September 19, 1979, the Commission published in the Federal Register (FR 54303) the aforementioned amendments. These amendments apply to both power and nonpower reactor licensees and makes the legal requirement for NRC review and approval of emergency plans and maintenance of these plans up to date. The following specific requirement applies to nonpower reactors:

1.

Research reactors with an authorized power level greater than 500 KW thermal, an emergency plan shall be submitted within one year from the effective date of the rule; 2.

For all other research reactors, emergency plans shall be submitted within two years from the effective date of the rule; 3.

For all research reactor facilities applying for license renewal, an energency plan shall be submitted in accordance with 550.34(a)(6)(v), 150.90, and Appendix E to Part 50.

Regulatory Guide 2.6, " Emergency Planning for Research Reactors", provides the current guidance to licensees in complying with the proposed rule changes.

All nonpower reacter licensees currently undergoing renewal and who have submitted emergency plans were previously provided Regulatory Guide 2.6 to use in preparation of their renewal application.

If these plans meet the R.G. 2.6 criteria, a new plan need not be submitted.

A copy of Federal Register Notice 54303 is attached for your information.

Also attached is a copy of the transcript for a neeting held August 27, 1979, at NRC Reg. ion III Office, to discus ; the impact of the proposed Safeguards Upgrade Rule on certain nonpower reictor licensees.

There were 22 facilities so affected.

A copy of the list of attendees is also attached.

1260 353

'6V 7911020 el T

s

_ 2_

In addition, as promised by Mr. J. R. Miller, Acting Director for Site and Safeguards, DOR, NRR, NRC, a copy of the September 13,1979 letter to all operating nuclear power plants, " Followup Actions Resulting From the NRC Staff Reviews Regarding the Three Mile Island Unit 2 Accident",

also is provided to apprise you of current actions being undertaken as a result of the Three Mile Island Accident.

Sincerely,

,2d Mw z--e Robert W. Reid, Chief Operating Reactors Branch #4 Division of Ooer..t.ng Reactors Attachments:

1.

Federal Register Notice 54303 2.

Impact of the Safeguard Rule on Nonpower Reactor Licensees 3.

List of attendees 4.

Letter to all operating nuclear power plants dated 09/13/79.

t 1260 354

ATTACHMENT TO GENERIC LETTER TO ALL NONPOWER REACTOR LICENSEES October 18, 1979

SUBJECT:

EMERGENCY PREPAREDNESS 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 50-77 50-192 50-87 50-276 50-407 50-134 50-284 50-156 50-129 50-538 50-111 50-106 50-27 50-59 50-99 50-111 50-262 50-406 50-97 50-98 50-73 50-252 50-160 50-112 50-116 5 0-72 50-199 5~u-228 50-20 50-170 50-297 50-208 50-375 50-157 50-150 50-264 50-182 50-163 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 50-148 50-288 50-223 50-128 50-2 i260 355