ML19253A532

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Forwards 790724 Fr Notice of Amends to 10CFR70 & 73 to Provide Physical Protection Measures to Detect Theft of Snm. All Affected Licensees Must Submit New Physical Security Plans Following Reg Guide 5.XX Format
ML19253A532
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, 05000598, University of Buffalo, 05000098, 05000357, National Bureau of Standards Reactor, University of Maryland, Berkeley Research Reactor, University of Utah, 05000083
Issue date: 07/30/1979
From: Reid R
Office of Nuclear Reactor Regulation
To:
AFFILIATION NOT ASSIGNED, MEMPHIS STATE UNIV., MEMPHIS, TN
References
GL-79-34, NUDOCS 7909100225
Download: ML19253A532 (2)


Text

UNITED STATES y

[g NUCLEAR REGULATORY COMMISSION E

WASHINGTON. D. C. 20555

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I.d o% vt/

July 30, 1979 ALL NONPOWER REACTOR LICENSEES

Background

On July 24, 1979, the Commission published in the Federal Register (FR 43280-285) amendments to 10 CFR Parts 70 and 73 that will provide for physical protection measures to detect theft of special nuclear material (SNM) of moderate and low strategic significance.

These arendments apply to nonpower reactor licensees and have been promulgated to apply the international standards of physical protection as outlined in Information Circular 225 (Revision 1) and recomended by the International Atomic Energy Agency. As noted in the notice issued February 28, 1979, the Office of Muclear Reactor Regulation Safeguards planned visits at all affected nonpower reactor facilities to assist in the review and assessment of site specific characteristics. Most of the sites have nos been visited. The new rule (10 CFR 73.47) is provided at Enclosure

'-A" as excerpted frcm the Federal Register Notice.

As noted in 10 CFR 73.47, all affected licensees must submit new physical security plans by 120 days from November 21, 1979 following the content and format of Regulatory Guide 5.XX, which was previously provided to you. Along with this submission and to insure licensing conditions reflect the category of physical protection to be maintained, each license must be changed to include the implementation and maintenance of the physical security plan as a license condition. As the new regulation defines the categories by quantity and enrichment of SNM and exempts SNM that can be maintained continuously at self protection levels of 100 rem / hour at three feet, the maximum limits of SNM authorized by the licanse also must contain these values.

Therefore, submit within 30 days of receipt of this notice, the total anrount of SNM required to be possessed, the to'.al amount required in the core, the total amount required in storage, and the amounts of each of the foregoing to be exempt and nonexempt.

It should be noted that with the implementation of the Safeguards Upgrade Rule, all fuel previously exempted that was in the core and had been irradiated is no longer exempt.

The only exemption criteria is the self-protection criterion.

If SNM is to be exempt an amendment to the Technical Specifications also must be made establishing surveillance re-quirenents for measuring the radiation levels of the, exempted fuel.

Sincerely, t

{ } [p Odj Qj/[-4 b

F Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors

Enclosure:

Federal Register Notice 7909100 22 S P (FR 43280-285)

s ATTACHMENT TO GENERIC LETTER TO ALL NONPOWER REACTOR LICENSEES DATED JULY 30, 1979

SUBJECT:

Transmitting FR 43280-285 DOCKET NO.

DOCKET NO.

DOCKET NO.

50-70 50-113 50-186, 50-184 50-224 50-123:

50-13 E0-326 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 50-156-50-538 50-131.

ADD ADDITIONAL 50-105 50-27 DOCKET N0. FOR 50-59 50-99 DECOMMISSIONED 50-598 50-262

& NON0PERATING 50-406 50-97 FACILITIES 50-96 50-73 50-50-160-50-111-50-112 50-116-50-129' 5 0-72 50-199 50-228 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 50-274 50-54 50-188 50-142-50-294 50-433s 50-187 50-83 50-243 50-356 50-5 50-148 50-288 50-223 '

50-128 50-2 00.2 0

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