ML19325F103
| ML19325F103 | |
| Person / Time | |
|---|---|
| Issue date: | 08/27/1984 |
| 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 | |
| FOIA-88-451 NUDOCS 8911140106 | |
| Download: ML19325F103 (9) | |
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AUS$7 g MEMORANDUM FOR:
R. S. Brown. Jr., Assistant to the Director and Chief Progree, Support Branch,'NMSS FROM:
R. F. Burnett. Direr. tor I
Division of Safeguards, NMSS
SUBJECT:
STATEMENT OF WORK FOR CONSEQUENCES OF SABOTAGE'AT NONPOWER
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REACTORS The attached Staternent of Work (50W) reflects task descriptions for work to be initiated by Los Alates National Laboratory (LAlu.) during FYB4. LMiL personnel are aware of the details of the project and they are preparea to initiate work upon receipt of necessary funding. Because of the current high level of interest in the nonpower reactor area, it is irrportant that the project l
be startec as soon as possible. Consequently, we request that you cocait 93K for this project concurrent with the transmittal of the attached 50W.
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R. F. Burnett, Director Division of Safeguards, NMSS Attachnents:
J S0W NRC Form 187 j
NRC Fors 367 DISTRIBUTION:
SGFF r/f & s/f CRON0 Carlson RRR Burnett 8911140106 891101 hER
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CON $t00tNCES OF SA80TAGE AT N0NPOWER REACTORS' j
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l FIN N0s. A7153 88R N0: 50-19 02-00 1.0 BackgrouF In 1979 Los Alamos scientific Laboratory conducted a study on the con-sequences of sabotage at nonpower reactors. It was concluded that, within the constraints of this study, only one nonpower evactor had any potential L
for the release of significant amounts of fission product materials in i
the event of sabotage. Because of terrorist activities in other parts of the world, concerns by the ACRS about manipulation of reactor control systems, and concerns by a public interest group about.the effects of incendiary devices on reactor components, staff believes that it would j
be prudent to supolement this study with further technical information to assure that the margin of safety provided to the public is maintained.
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2.0 Work Required 4
J Los Alamos National Laboratory shall detemine and evaluate the' risks and potential consequences of both a loss of coolant incident and the direct fuel damage which would be produced by:
(a) blast effects from various quantities and types of explosives, (b) the production of heat from incendiary devices, and (c) the unauthorized manipulation of reactor.
controls and fuels at no.1 power (NPRs) operating at 20 MW,10 MW, 5 MW and 2 MW; and, for (a) and (b), at NPRs operating below 2 MW. Speci fically designed mathematical models or other appropriate methods shall be used to determine the potential consequences of the events associated with (a),
(b), and (c) above. Assessments shall include the consequences associated with core meltdown, partial core meltdown, and disintegration and/or crushing of the core and shall be compared against 10 CFR Parts 20 and 100 standards. Where applicable, the extent of fission product release shall be based upon NRC's re-evaluation of source tem assumptions.and L
l findings.
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Facilities shall be grouped by comon design feature and analysis of a l
representative from each group shall be performed in the sequence of descending power.
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Licensee Docket No. Power Level Reactor Type National Bureau of Standards 50-184 20 MW Tank I
University of Missouri 50-186 10 W Tank Georgia Institute of Technolegy 50-160 5 MW Tank Massachusetts Institute of Tachnology 50-20 5 MW Tank Union Carbide 50-54 5 MW Pool Rhode Island Atomic Energy Comission 50-193 2 MW Pool State University of New York 50-57 2 MW Pool University of' Michigan 50-2 2 MW Pool University o'f Virginia 50-62 2 MW Pool 1
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., j e-Los Alamos Na,tional Laboratory shall perform the following taskst 2.1 Task No.ht-1 i
A review of existing information in available sources such as the NRC docket files augmented by site-specific information provided by NRC staff and on site inspection visits shall be conducted to:
(a) familiarine task personnel with characteristics peculiar to each reactor, and (b) obtain information necessary to aid in the calculation of the radiological i
consequences for each of the NPRs listed above, as appropriate.
2.2 Task No. 2 Mathematical models and/or other appropriate methods, such as a master logic diagram fault-tree approach similar to those used in other safety studies by LANL, shall be developed and/or used to:
a.
calculate the radiological release resulting from a total core melt-down, partial core meltdown core, disintegration and/or crushing, or other means which could severely damage the fuel in the reactor core.
Since the key consideration is the fission product release associated with such incidents, the effects of using low enriched uranium versus high enriched uranium on the fission product release shall be evaluated, b.
determine, as a function of distance from the reactor, the total radiation dose (rem) to the whole body and the radiation dose (rem) to the thyroid from iodine exposure, and identify any facility which could exceed 10 CFR Parts 20 and 100 standards, and l
c.
Determine the characteristics of the event that would limit it to less than Parts 20 and 100 standards.
Certain other parameters and assumptions thould be considered when per-forming this task. These include, and are limited to the following except as may be approved by the NMSS Project Manager (PM) in the future:
a.
The models or methods used to calculate the damage and the releases shali assume that the reactor has been operating at the maximum power level authorized by NRC license and that equilibrium of fission products was attained prior to the incident. Note:
If significant damage to the core or subsequent release is calculated to occur after a period of reactor shutdown, this shall also be evaluated, b.
In those cases in which the fission product inventory of the NPR l
is determined to be insufficient to create a risk to the public health and safety, or those in which the fuel configuration or composition, and/or the reactor construction or other factors is such as to limit the fuel damage and fission product release to a level that is insuf-ficient to create a risk to the public health and safety, the study for that facility shall be terminated, and the basis for the conclusion documented, j
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- c. 'No assumptions are made regarding the saboteurs' capabilities nor is tipre avy design basis threat associated with this task, d.
For baseline considerations, it should be assumed that all reactor safety features fail upon initiation of the incident, and l
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The mean meteorological conditions at the site and the surrounding area should be considered when calculating the atmospheric dispersion of a release.
2.3 Task No. 3 I
After Tasks No. I and 2 have been accomplished, mathematical models or other appropriate methods shall be developed to calculate the amount of explosives and the amount of incendiary material needed to cause the maximum and the limiting events described in' Task No. 2 above. Calcula-tions shall be made for the placement of explosives and incendiary devices attached to reactor components and outside the structure containing the rea ctor.
Certain parameters and assumptions should be considered in those calcula-tions. These include, and are limited to the following except as may be approved by the NMSS PM in the future a.
The type of explosives and incendiary devices used to cause an event are assumed to be easily obtainable.
i b.
Two opposing conditions shall be considered in performing Task 3:
1.
Tre adversary shall have access to all reactor components in carrying out the sabotage event.
- 11. Safeguards credit shall be given for all physical barriers interposed b.etween the explosives / incendiaries and the reactor fuel, and 2.4 Task No. 4 Upon completion of Task No. 3, for those cases in which the fission product release and estimated doses exceed 10 CFR Parts 20 and 100 stan-dards, calculate the amount of explosives and the amount of incendiary material needed to cause the release. The t,alculations shall be made for placement of explosives and incendiary devices attached to reactor compo-nents and outside the structure containing the reactor.
The paraIEters and assumptions employed in Task No. 3 shall be utilized in this task.
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e 2.5 Task No. 5_
Upon compistion of Task No. 3, a review and evaluation of reactor control systems and fuels shall be made to detemine whether en unauthorized manipulation of such controls could cause any detrimental effects that may t
be identified in Task No. 2.
Only credible scenarios and analytical assumptions shall be used and shall be reviewed and approved by the NMS$ PM
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before the analyses are made.
2.6 Task No. 6 Upon completion of Task No. 3, calculate the mitigating effects of full and partial operation of existing safety features associated with the creration of the reactor (these features are ignored under Task 3 to determine maximum consequences). Identify additional safety measures and modifications as well as administrative procedures and practices which could be adopted and determine the degree to which these additional considera-tions would mitigate the consequences. Exclude specific safeguards I
measures from consideration in this task.
I 3.0 Reportino Requirements I
3.1 Monthly Letter Status Report A monthly report shall be given which sumarizes the progress of the tasks being performed including' o The work performed during the previous month.
o Personnel time expenditures during the previous month, o Problems encountered and the proposed solutions'.
o Activities planned for the ensuing two months.
o Costs generated against the work effort during the previous month (including direct salaries, materials and services, ADP support.
subcontracts, travel, general or other related items).
o Current obligation status information The first monthly report shall provide the initial projections or indicate
'no change in the cost and uncosted obligation projection." The report shall be due by the 15th of each month with distribution as follows:
J Donald M, Carlson, SG, NMSS - one copy Office 9f the Director, NMSS (ATTN: Program Support) - one copy l
3.2 Interim Reoorts A draft interim report shall be furnished to the NMSS PM upon completion of each major task (i.e., Tasks Nos. 2, 3, 4 and 5). After review by appropriate NRC personnel, the PM will provide coments on the draft report to LANL within sixty (60) days of receipt of each report. A revised interim report shall be submitted if deemed necessary by the NMS$ PM.
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8 3.3 Final Resorts L
LANL shall furnish two copies of draft final reports to the MSS PM-by June 3th,1906. The format of these documents shall be as specified for formal technical reports in NRC Manual Chapter 1102 and will provides i
a.
The on-site and off site fi sion product release and dosage calcula-tions associated with a total loss of coolant, b.
The quantities of explosives and incendiary material or description of acts necessary to cause a limiting case incident, c.
The placement of explosives and incendiary materials in relation to the reactor.
d.
The descriptior, of unauthorized manipulation of reactor controls and fuel to cause a limiting case incident, e.
The resulting consequences, and f.
Apprcpriate alternative measures which can be implemented to mitigate a 'significant event (e.g., reactor facility modifications, administrative procedures, etc.).
After review by appropriate NRC personnel, the PM will provide coments on the draft reports to LANL within 60 days of receipt of each report.
The perfonning organization shall revise the draft reports based on the PM's comments and' submit the camera-ready copy of each final report to the Document Management Branch. Techr.ical Infomation and Document Control. NRC' to be published as NUREG/CR series reports, and a duplicate to the NMSS PM.
All draft reports, as well as final reports, shall be screened for Clas.
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sified Information and appropriately marked in accordance with "NRC Classification Guide for Information Dealing with the Release and Dis-i persion of Radioactive Material (NRC-RDRM-1)," dated September 1982 and NRC Manual Chapter 1102.
3.4 Prog, ram Plan Within one month after initiation of task orders, LANL shall provide j
a detailed work plan which identifies study milestones and their projected date of accomplishment. Upon NRC review and approval of this plan, it will then became the operating schedule for the overall task.
4.0 Meetines l-LANL representative (s) shal. seet with the letSS Project Manager two to four times a year. Upon completion of the draft final report, LANL representa-tives, upon request of the HMSS PM, shall brief MS$ staff in Washington, DC.
All travel requires approval of the NMSS Project Manager.
5.0,NRC Furnished Material 1
L None, except information in available sources such as NRC docket files.
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6.0 Level Efffert
.c It is expected that approximately three and one half staff years of tech-r nical support will be required to satisfy the provisions of the Statement of Work.
7.0 Period of Performance Performance for the overall task shall commence on the effective date of this agreement and continue through September 30, 1986.
8.0 Quality Assurance For all draft and final technical reports delivered under this agreement, the LANL shall assure that an independent review and verification of all numerical computations and mathematical equations and deviations are performed by qualified contractor personnel other than the original author (s) of the reports. If the LANL proposes to verify / check less than 100 percent of all computations and mathematical equations and
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derivations in the report (s), (such as might be the case when there are a large number of routine, repetitive calculations), the LANL must first J
obtain written approval from the NMSS PM,.
Computer-generated calculations will not recuire verification where the computer program has stready been verifled.
In addition, for all reports, including those which do not contain numeri-cal analyses, a management review shall be conducted prior to submission to the NRC.
l 9.0 Technical Direction Mr. Donald M. Carlson (FTS 427-4712) is designated the NMSS Project Manager i
for the purpose of assuring that the services required under this Statement of Work are delivered in accordance herewith. All technical instructions to the performing organization shall be issued through the NMSS PM. As used herein, technical-instructions are those which provide details, suggest possible lines of inquiry, or otherwise comolete the general scope of work set forth herein. Technical instructions shall not constitute new assignments or work or changes of such nature as to justify an adjustment in cost or peiod of performance. Directions for changes in cost or period of performance will be provided after receipt of an appropriate Stancard Order for Work (S0W) (NRC Form 173) from the Director of the Office of Nuclear Material Safety and Safeguards (NMSS).
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10.0 01sossal of property Prior to ' lose $ut of this-project, a reconciled report shall. be developed c
by DOE to record available equipment and material purchased with mc i
funds. This report should be developed at soon as possible after project completion or termination decision has been made, but not later than 60 days after the termination date. The report should be submitted to the MC Division of Facilities and Operations Support, ACM, and the MS$
Project Manager.
11.0 00E Acevired Material j
The performing organization must notify the MS$ Project Ma' nager prior to acquisition of any capital. ADP, or word processing equipment.
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J u.a.iiWMAR RE99W OnY coMMSaloN t, me seem genser 00E SOURCE SELECTION JUSTIFICATION gg s.~,dans Consequences of sanotage at s es6ssumeewas Los Alamos National Laboratory i
Nonpower Reactorsk.-
auna,ei.same NMSS. Division of Safeguards. Tuel Facility Safeguards Licensing Branch 6 _ O_ a A M A k..
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m ea, 7/t /M, Donald M. Carlson -
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weo In 1979. Los Alamos National Laboratory (then Los Alamos Scientific Laboratory) conducted a :tudy on the consequences of sabotage at nonpower reactors. NURES/CR 0843 was published reporting the results of the study. Los Alamos National Laboratory (LANL) personnel have extensive experience in detemining releases of radioactive fission product materials as well as the effects of explosives and incendiaries on reactor components. The further 1
evaluation of the potential consequences of sabotage at nonpower reactors represents a logical extension of LANL's prior work in this area.
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Robert F. Burnett. Director, Division of Safeguar I**
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' R. S. Brotm Jr.. Assistant to the Director and Chief. Program Support Branch l
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