NRC Generic Letter 79-34, New Physical Security Plans (FR 43280-285)
text
July 30, 1979
TO 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 amendments apply to nonpower reactor licensees and have been promulgated to apply the international standards of physical protection as outlined in Information Circular 225 (Rev
- 1) and recommended by the International Atomic Energy Agency. As noted in the notice issued Feb 28, 1979, the Office of Nuclear 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 now been visited. The new rule (10 CFR 73.47) is provided at Enclosure "A" as excerpted from the Federal Register Notice.
As noted in 10 CFR 73.47, all affected licensees must submit new physical security plans by 120 days from Nov 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 authorized by the license also must contain these values. Therefore, submit within 30 days of receipt of this notice, the total amount of SNM required to be possessed, the total 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 requirements for measuring the radiation levels of the exempted fuel.
Sincerely,
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enc: Federal Register Notice (FR 43280-285)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 50-336 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 50-106 50-27 DOCKET NO FOR 50-59 50-99 DECOMMISSIONED 50-598 50-262 & NONOPERATING 50-406 50-97 FACILITIES 50-98 50-73 50- 50-160 50-111 50-112 50-116 50-129 50-72 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 50-57 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