ML20149K191

Generic Ltr 80-38 to All Nonpower Reactor Licensees Re NPR Physical Protection Requirements.Summary of Certain NPR Physical Protection Requirements Encl & Should Aid in Determining Safeguards Requirements Applicable to Facility

ML20149K191
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, 05000276, 05000208, 05000112, 05000106, Armed Forces Radiobiology Research Institute, 05000598, University of Buffalo, 05000098, 05000119, 05000357, National Bureau of Standards Reactor, University of Maryland, Berkeley Research Reactor, University of Utah, 05000083
Issue date:	05/07/1980
From:	John Miller Office of Nuclear Reactor Regulation
To:	AEROTEST OPERATIONS, INC., ARIZONA, UNIV. OF, TUCSON, AZ, BABCOCK & WILCOX CO., Battelle Memorial Institute, Brigham Young University, PROVO, UT, CALIFORNIA, UNIV. OF, BERKELEY, CA, CALIFORNIA, UNIV. OF, IRVINE, CA, CALIFORNIA, UNIV. OF, LOS ANGELES, CA, CALIFORNIA, UNIV. OF, SANTA BARBARA, CA, CATHOLIC UNIV. OF AMERICA, WASHINGTON, DC, COLUMBIA UNIV., NEW YORK, NY, CORNELL UNIV., ITHACA, NY, DELAWARE, UNIV. OF, NEWARK, DE, DEPT. OF VETERANS AFFAIRS MEDICAL CENTER, OMAHA, DOW CHEMICAL CO., FLORIDA, UNIV. OF, GAINESVILLE, FL, GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER, GENERAL ELECTRIC CO., Neely Research Reactor, ATLANTA, GA, IDAHO STATE UNIV., POCATELLO, ID, ILLINOIS, UNIV. OF, URBANA, IL, INTERIOR, DEPT. OF, GEOLOGICAL SURVEY, IOWA STATE UNIV., AMES, IA, KANSAS STATE UNIV., MANHATTAN, KS, KANSAS, UNIV. OF, LAWRENCE, KS, MANHATTAN COLLEGE, RIVERDALE, NY, MARYLAND, UNIV. OF, COLLEGE PARK, MD, MASSACHUSETTS INSTITUTE OF TECHNOLOGY, CAMBRIDGE, MASSACHUSETTS, UNIV. OF, LOWELL, MA (FORMERLY LOWELL, MEMPHIS STATE UNIV., MEMPHIS, TN, MICHIGAN STATE UNIV., EAST LANSING, MI, MICHIGAN, UNIV. OF, ANN ARBOR, MI, MISSOURI, UNIV. OF, COLUMBIA, MO, MISSOURI, UNIV. OF, ROLLA, MO, NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL, NAVY, DEPT. OF, NEW YORK, STATE UNIV. OF, BUFFALO, NY, North Carolina State University, RALEIGH, NC, NORTHROP CORP., NORTHWESTERN UNIV., EVANSTON, IL, OHIO STATE UNIV., COLUMBUS, OH, OKLAHOMA, UNIV. OF, NORMAN, OK, Oregon State University, CORVALLIS, OR, PENNSYLVANIA STATE UNIV., UNIVERSITY PARK, PA, PURDUE UNIV., WEST LAFAYETTE, IN, REED COLLEGE, PORTLAND, OR, RENSSELAER POLYTECHNIC INSTITUTE, TROY, NY, RHODE ISLAND, STATE OF, ROCKWELL INTERNATIONAL CORP., TEXAS A&M UNIV., COLLEGE STATION, TX, TEXAS, UNIV. OF, AUSTIN, TX, TUSKEGEE INSTITUTE, TUSKEGEE, AL, UNION CARBIDE CORP., UTAH, UNIV. OF, SALT LAKE CITY, UT, VIRGINIA POLYTECHNIC INSTITUTE & STATE UNIV., BLACKSB, VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA, WASHINGTON STATE UNIV., PULLMAN, WA, WASHINGTON, UNIV. OF, SEATTLE, WA, WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP., WISCONSIN, UNIV. OF, MADISON, WI, WORCESTER POLYTECHNIC INSTITUTE, WORCESTER, MA
References
GL-80-38, NUDOCS 9707300046
Download: ML20149K191 (4)

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SSPB Filec MTl b 2cptPAts ALL NONG3tER REACTOR LICENSEES On January 7,1980, you were sent a letter describing certain nonpower reactor (NPR) physical protection requirements. Recent discussions between personnel frca the NRC's Division of Safeguards and staff menbers of several licensees have identified what appears to be a mis-understanding of regulatory requirements relatigg to the protection of fomula quantities of strategic special nuclear material; special nuclear material (SNM) of moderate strategic significance; and SNM of low strate 9f e significance. As a result of this, the NRC has pre-pared a sumary of certain NPR physical protection requirements.

The str. mary, which is enclosed, supplements the January letter and should aid you ip determining the safeguards (security) requirements applicable to your facility.

If you have any questions regarding this letter, please contact your O

appropriate project manager.

I Sincerely, ORIC!."AL SIO!C Sy:

JA?LES R. n:Lra,

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James R. Miller, Chief t

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ALL NCNPOWER REACTOR LICENSEES i

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DOCKET NO.

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50-184 50-224 50-123 50-13 50-326 50-396 I

50-360 50-357 50-62 l

50-225 50-151 50-139

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50-77 50-192 50-87 j

50-276 50-407 50-134 i

50-284 50-156 i

50-538 50-131 i

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50-98 50-73 1

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50-228 50-20 50-170 50-297 i

50-208 50-375 50-157 50-150 i

50-264 50-182' l

50-163 50-193 i

50-89 50-57 50-274 50-54 i

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 4

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ENCLOSURE

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NONPOWER REACTOR PHYSICA'. PROTECTION REQUIREMENTS 1.

Presently NPR licensees are not required to meet the provisions of the "Pnysical Protection Upgrade Rule" (Federal Register Notices 65184-68199) as it pertains to the possession or use of formula cuantities of strategic special nuclear material (SSNM) at any fixed site or contiguous sites (173.20, $73.45 and 573.46). NPR licensees who possess or use such mat-erial at this time have been temporarily exerepted f om implementing these requirements while certain NPR safeguards studies are being completed.

These studies are intended to determine whether or not safeguards credit can be given fer unique features associated with NPR's.

2.

In the interim, licensees who possess or use formula cuantities of SSNM 4

(not exempt pursuant to 573.6(b)) are required to implement tne require-ments identified in 573.60, 573.70 and 573.40(b). These regulations gen-

'l erally require additional physical protection measures at facilities where formula quantities of SNM are possessed; require certain records to be maintained; and requires that a safeguards contingency plan be pre-pared in accordance with critieria set forth in Appendix C to 10 CFR Part 73.

In addition, licensees are required to implement the require-ments identified in 573.67(a), (b), (c) and (d). A security plan or an a ended securit/ plan must be prepared which describes how you plan to ccmoly with these requirements and must be submitted to the NRC by August 25, 1950.

The security plan must then be fully implemented on March 25, 1981 or 90 days after the plan is approved, whichever is later. The only exception which may be granted to the full implementation schedule is for odification of structui es and/or installation of major equipment.

In

nese cases the date for full implementation may be extended to August 25, 1981.

If you possess, store, use, transport, export or deliver to a carrier for

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transport SNM of moderate strategic significa'nce, as specified in !73.2(x)(1) 3.

and/or (2), you are required to implement $/3.67 (a), (b), (c), (d) and (e),

A security plan must be prepared which describes how you as appropriate.

plan to comply with these requirements and must be submitted to the NRC by The security plan must then be fully implemented on September "ay 18, 1980.

Please 21,1930 or 20 days af ter the plan is approved, whichever is later.

oc:e that the date for the submittal of the security plan and the date for Me full implementation of the plan have been changed.

This change was pub-lished in Federal Register March 25,1980 (45 FR 19215).

If you possess, store, use, transport, export or deliver to a carrier fcr 4

transport SNM of low strategic significance, as specified in 573.2 (y)(1),

(2) and/or (3), you are required to implement 573.67 (a), (b), (c), (f)

If you possess or transport 10 kilograms or rrore ar.d (g), as appropriate.

af :he above material, you must submit a security plan to tne hRC by May 18,

'923.

The security plan must be fully implemented on September 21, 1983 or 23 days af ter the plan is approved, whichever is later,

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'a'ith regard to paragraphs 1 through 4 above, the application of the 5.

exemptions alloned by 573.6(b) and 173.67(b)(1)(i) will normally be used by licensees when determining physical protection requirements for their facilities.

If these exemptions are applied, and the radioactive SNM or SSNM subsequently falls below the criteria estab-lished by the exemptions, for any reason, licensees will have to initiate measures to increase the physical protection to a level consistant with curient rules and regulations. On the basis of i

the above, it is necessary for the licensees to describe in their f

security plan submittals measures to be taken should such an ever,t occur or describe why such an event is not possible at your facility.

6.

In addition to the above, other sections of Part 73 also apply to NPR licensees (e.g.173.24, Prohibitions; 173.37, Protection of Spent Fuel Shipments; 173.71, Reports of Unaccounted Shipments; 573.72, Advance Notice of Shipment of SNM).

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