ML19325F154
| ML19325F154 | |
| Person / Time | |
|---|---|
| Issue date: | 11/15/1985 |
| From: | Burnett R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Brown R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19325C113 | List:
|
| References | |
| CON-FIN-A-7153-5, FOIA-88-451 NUDOCS 8911140310 | |
| Download: ML19325F154 (9) | |
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19I55 r/f NOV 15 m SGRT r/f SGRT s/f CWithee MEMORANDUM FOR:
R. S. Brown, Jr.
Director rd-Jacobs Planning and Program Analysis Staff, MSS EleniDavge"c\\ts Geer FROM:
Robert F. Burnett, Director gg-
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SUBJECT:
EVALUATION OF PROPOSAL FROM LOS ALAMOS NATIONAL l
LABORATORY (LANL) (FIN A7153-5)
We find the enclosed LANL proposal transmitted by letter of September 27, 1985 acceptable. Accordingly, please provide the currently available $211.K of FY86 funds for this project to the Department of Energy.
Full funding to $225K i
is expected this year. If additional funds do not become available, then the-task ' final report" will be funded in FY87.
b Robert F. Burnett, Director Division of Safeguards, NMSS '
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Enclosure:
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t 1.
Obiettive of Prenesed Work i
4.
Backtrount In 1979, the Los Alamos Scientific Laboratory conducted a study of f
the consequences of sabotage of nonpower reactors (NPRs).
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reca9se di letr.vitt activities in other parts of the world, concerns of the Advisory Connittee on Reactor Safeguards about manipulation of reactor control systems, and concerns of a public interest group about the effects of incendiary devices on reactor components, it was decided that this
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information should be supplemented with further technical information, j
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b.
Objective i
The objective of this work is to provide the Nuclear Regulatory Connission (NRC) with technical information on the ef fects of f
malicious manipulation of reactor controls, blast eff;tts from j
various quantities and types of explosives, and the use of incendiary l
' devices on NPR$ to confirm an acequate margin of public safety.
l 2.
Summary of Prior Efforts l
Existing information in available sources, such as the NRC docket files, j
augmented by site-specific information provided by NRC staff and site visits has been gathered to provide the basis for r41culating the radiological f
consequences for the NPts listed in Table 1.
l TABLE I I
l REACTORS YlS11[0 IN FY 1985 t
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l Facility Docket No. Power level Reactor Twee National Bureau of Standards 50-184 20 W Tank University of Missouri 50-186 10 W Tank l
l-Georgia Institute of Technology 50-160 5W Tank l
Massachusetts Institute of Technology (MITR) 50-20 5W Tank l
Rhode Island Atomic Energy Connission (RIAEC) 50-193 2W Pool,
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It Mathemattcal models have been developed and used to perform the following.
4.
Calculate the radiological release resulting from a total core meltdown, partial core meltdown, core disintegration and/or crushing, or other means that could damage the fuel in the reactor core severely, lecause the key consideration is the fission product release associated with such incidents, the effects of using l
low-enriched uranium vs high-enriched uranium on the fission product release has been evaluated.
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l b.
Determine, as a function of distance from the reactor, the total f
radiation dose (rem) to the whole body and the radiation dose (res) l to the thyroid and indentify any facility for which these could
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exceed regulatory standards.
The list of assunstions used in the
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calculations has been submitted to and reviewed by the NAC Division of Nuclear Material Safety and Safeguards (WMSS).
Analyses of the first three reactors in Table I will be completed, and the report on these will be delivered before the end of FY 1985. These three j
i reactors were used as lead reactors to develop the methodology to be used for a11 remaining reactors.
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The analyses established the doses expected for a worst-case sabotage l
event and developed a set of scenarios that bracket the possible range of f
sabotage actions, idsntifying the equipment and systems that must be attacked r
to cause the release. These scenarios oulined the quantity and placement of tuplosives and all other discrete actions required to achieve the release, f
The analyses included models for internal building transport phenomena i
and atmospheric dispersion so that the entire sequence of events, from initial attack to dose reception, is described clearly.
l 3.
Work to be Performed and EnDetted Resuits During FY 1986 Los Alamos will perform the following:
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a.
Work renuired Task 1.
Complete analyses for the last two reactors in Table 1.
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Task 2.4 Issue an addendum report covering the analyses of these two j
reactors. The form of this report will be similar to and l
compatible with the report covering the first three reactors.
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Task 3.
Make site visits to the reactors in Table !! to gather information necessary for analysis.
I Task 4.
Complete analyses and prepare reports as in item 2 abovJ for the reactors in Table !!.
l Task 5.
Issue a final report incorporating analyses for all nine l
reactors in Table I and !!.
t The tentative schedule for these is as follows.
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IALL Tarnet Completion Data f
4.
Analyses of MITR and RIAEC December 1985
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b.
Report on MITR and RIAEC December 1985 i
c.
Site Visits (Table !!)
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(1) Union Carbide and Michigan December 1985 (2) $UNY Buffalo and UVAR March 1986 d.
Reactor Analyses and Reports (1) Union Carbide and Michigan March 1986 l
(2) SUNY Buffalo and UVAR June 1986 l
(3) Final Report August 1996 I
l I
TABLE !!
LIST OF REACTORS TO BE V!51TED IN FY 1986 l
l i
Facility Docket No.
M r Level Reactor Troe Union Carbide 50-54 5W Pool i
i Buffalo Materials Research Center 50-57 2W Pool l
University of Michigan Ford Reactor 50-2 i; pad Pool l
l Univ. of Virginia Reactor (UVAR) 50-62 2W Pool l
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s b.
Meetinas and Travel site visits for two analysts to the four reactors in Table !! will be required. Two meetings with NRC sponsors in Washington, DC, for two people also will be required in FY 1986. Los Alamos representatives will neet with the NMS$ project manager (PM) two to four times a year. These meetings may be held during Washington visits or during site visits.
c.
NRC Furnished Natglia),
'NRC will furnish only reactor documentation that cannot be obtained by los Alamos from the open literature or f rom the Los Alamos files accumulated during license renewal activities.
4.
Descrintion of follow 0n Efforts, There are no follow on efforts anticipated as a result of this study.
However, the ability to extend the analysis technique to additional teactors at the request of NMS$ will be retained by Los Alamos.
5.
Relationship to other Proietti None 6.
ReDort Schedule 4.
Monthiv Letter Status Report Los Alamos will submit a letter status report each month that summarires the work performed during the previous month, personnel time expenditures during the previous month, and costs generated against the work effort. Any changes to cost projections or schedul,es will be indicated. The letter report will be prepared by the 20th of each month.
In all monthly reports there will be a breakdown of (1) manpower costs; (2) costr incurred for direct salaries, meterial and services, ADP support, subcontracts, travel, general, and administrative and other related items; and (3) current obligation status inforpation for the project..
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The r port shall be distributed as follows.
f T. Sweitrer, 54, NM55 - one copy l
Office of Director, NM55 (Attn: Program Support) - one copy b.
Interim tenorts i
Three draf t iteria reports shall be furnished to the NM55 PM, one for each of the analyses required in Sec. 3.
After review by appropriate l
NRC personnel, the PM wi11 provide consnents on the draf t report to Los Alamos National Laboratory within 60 days of receipt of each l
report. A revised interim report shall be submitted if deemed
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necessary by the NM55 PM.
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Final Kenort Los Alamos shall furnish two copies of a draf t final report to the NM55 FM by June 30, 1986. The format of these focuments shall be as specified for formal technical reports in NRC Manual Chapter 1102 and will provide i
1.
the on-site and off-site fission product release and dosage calculations associated with the sabotage scenarios identified by the analyses, 2.
the quantities of explosives or a description of acts necessary to cause a limiting case incident, 3.
the placement of explosives in relation to the reactor, 4.
a description of unauthorized manipulation of reactor controls and fuel to cause a limiting case incident, j
5.
the resulting consequences, and i
i 6.
cppropriate alternative measures that can be implemented to mitigate a significant event (for example, reactor facility modifications, administrative procedures, and so on).
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I Af ter review by appropriate NRC personnel, the PM will provide comments on the draft report to Los Alamos within 60 days or receipt of the report, f
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l The performing organization shall revise the draft report based on the l
PM's comments and sbbmit one camera-ready copy of the final report to the j
Document Managment tranch. Technical Information and Documeat Control, NRC, to be published 45 4 NURE6/CR series report and a duplicate to the NM55 PM.
P All draft reports, as well as final reports, shall be screened for j
Classified Information and appropriately marked in accordance with 'NRC I
Classification Guide for Information Dealing with the Release and Dispersion of Radioactive Material (NRC RDRM-1)* (September 1982) and NRC Manual Chapter 1102.
7.
Subcor. tractor Inf ormation Los Alamos will use Intermountain Technologies Inc. (ITI) to assist in 4
performing thermal hydraulic analysis in Tasks 1 and 4.
!T! personnel j
are vcry familiar with using the TRAC (Transient Reactor Analysis Code) computer code and have provided this service for us on other NRC l
contracts.
j 8.
New Canital Ecutoment Reauired j
kone 9.
Snecial Facilities Reevired None
- 10. Conflict of Interest Information None i
- 11. Quality Assurance l
All reports, plans, charts, graphs, schedules, and so on furnished under the terms of this statement of work are to be subject to internal review and shall reflect acceptance by an authorized management individual i
before submittel to NRC.
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