ML19325F108
| ML19325F108 | |
| Person / Time | |
|---|---|
| Issue date: | 09/06/1984 |
| From: | Brown R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Romatowski R ENERGY, DEPT. OF |
| Shared Package | |
| ML19325C113 | List:
|
| References | |
| CON-FIN-A-7153, FOIA-88-451 NUDOCS 8911140125 | |
| Download: ML19325F108 (11) | |
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NMS$ r/f MP6 1984 DCarlsen, SG v i
HB1ack, SG Plaker, SG Mr. Raymond G. Romatowski,iceManager K0twell, RM/BP Albuquerque Operations Off 00andois, RM/AF0 U.S. Department of Eneriy E0 avis, (2 copies)
P.O. Box 5400 Albuquerque, New Mexico 87115 i
Dear Mr. Romatowski:
i The enclosed NRC Form 173. Standard Order for 00E Work (SOEW), for 493,000 is submitted in accordance with Section !!!.B.2. of the DOE /NRC Memorandum of Understanding of February 24, 1978.
This work is urgently required to support our Safeguards program, and the 50EW is forwarded without prior proposal.
The work authorization provioes for proposal preparation as part of the work scope. The enclosed statenant of work details the required work ar.d should be used as tne basis for preparing a i
proposal. NRC Form 189 contains the minimum information needed and will be used for the proposal. Standard terms and conditions for NHC work, as approved by Headquarters DOE, apply to this effort. A copy of these terns ano condi-tions has been furnished your office separately. The proposal should be submitted within 30 days in five copies to:
U.S. Nuclear Regulatory Comission Office of Nuclear Material Safety and Safeguards i
ATTN: Prngram Support Washington, DC 205b5 Work under this task will require access to and/or origination of classifiec information as indicated on the enclosed NRC Form 187.
Please inoicate DOE acceptance by signing and returning the enclosed NRC j
Form 173 to the NRC Office of Resource Management. Division of Accounting and Finance, with a copy to this office.
i If you have any questions please contact Mrs. Eleni Davis (FTS 427-4072).
l Thank you for your assistance.
l 8911140125 891101 Sincerely, PDR FOIA KUPERMAB9-451 PDR l
(This letter comits.593K of FY64 funds to FIN A7153, B&R 59-19-02-00) p,.**8""I '1 med br 8
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R. S. Brown, Jr., Assistant to tne
( N6.J, /., J/myd Director and Chief, Program Support Branen, hhSS Ifif ~30
Enclosures:
- 1. SOEW 50-84-116 J
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STANDARD ORDER FOR DOE WORK O5.06 gt l'
ietuSD 70: (DOE OWico) se8USD BY: (NRC ONico)
AcoOUNTast olf ATION Albuquerque Operations Office Office of Nuclear Material eenomarc= svue0L i
Safety and Safeguards 31X0200.504 esa Nvueen 50-19-02-00 i
Pshponismes Onsain ATion Asso LOCATION Los Alamos National Laboratory (LANL) n Nvueen i
Los Alamos, New Mexico 87545 A 7153-4 WORK PeRIOC - Twee ORDEA PIN TITLE FtxED :1 ESTIMATED C t
Consequences of Sabotage at Non-Power Reactors Fg tg 00UGATl00f AVAILASluTY PROVIDED SY:
s 93.000 A THis Omosa 0 70tAL OF OADERS PLACED PmCR to THIS Daft wiTH THE PthF0muiNO OAGANilATh0N UND(N THE 8
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FINANCat FLDut4UTY:
E FVNDS WILL Not tf AEP40384Wut0 DETWEEN FINS UNE D CONSTITUTES A UulTATION ON 04LGATONS AU 0 FUN 06 MAY DE MEPm004AuutD Not 70 DCEED 3 0% OF FIN LivfL VP to $60K UNE C CONSilTVTE$ A uuttATION 1
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$f ANDAAD Timut AND COND(TONS (.e. Nhc Warwei Chapier 1102. Appews Part 4) ARE PARt OF THis omDER UNtt$$ OTHERw.SE NOTED ATTACHutets THE FOLLowWG Att ACHutNTS Amt Htmtly uADE A PART OF THis SECVAffY' K3 woAN ON THis ORDim INVOLVES CLASSihED ORDER WFomuaTON wnc FomN is7 iS ATTACHED XX St AttutNT OF wong O pu ON THis ORDER INVOLVES UNCLASSIFifD ADDITCNAL Timus AND CON 0iTCNS SArE0VA408. Pm0P46EtAmy, Om OTHER SENSITivt OTHga INFOAuATION womK O womE ON THis ORDER IS UNCLASSihED AND Not SENSitivt
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This order provides FY84 funding for initiation of this project as delineated in the attached statement of work. An NRC Fonn 189 based on the attached statement of work should be submitted in 5 copies to: Office of Nuclear Material Safety and Safeguards l
(Attn: Program Support Branch) within 30 days of the date of this order,
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%, issunch AUTHORITY ACCEPTING ORGANIZAT60N ScNAT ScNATunt iTt Assistant to the firector and chief tiTL l
Program Support BPanch NMSS DATE NRC FORW 173 (1 44) 1 s
CONS (WINC($ Of $ASOTAGE AT NONPOWER REACTOR $
FIN EJ: A7153~4 B&R CJ:
50-19-02-00 1.0 Backgrouni In 1979. Los Alamos $cientific* Laboratory conducted a study on the con-sequences of sabotage at nonpower reactors.
It was concluded that, within the constraints of this study, only one nonpower reactor had any potential j
for the release of significant amounts of fission product materials in j
the event of sabotage. Because of terrorist activities in other parts of 4
the world, concerns by the ACR$ about manipulation of reactor control systems, and concerns by 4 public interest group about the effects of incendiary devices on reactor components, staff believes that it would be prudent to supplement this study with further technical infomation to l
assure that the margin of safety provided to the public is maintained.
I 2.0 Work Recuired 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 l
Quantities and types of explosives, (b) the production of heat from i
incenciary devices, and (c) the unauthorized manipulation of reactor
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controls and fuels at nonpower (NPRs) eperating at 20 MW,10 MW, 5 MW and j
2 MW; and, for (a) and (b), at NPRs operating below 2 PW.
Specifically l
designed rtthematical models or other appropriate methods shall be used to ceterrine the potential consequences of the events associated with (a),
(b), and (c) above.
Assessments shall include the consequences associateo with core reltdown, partial core meltdown, and disintegration and/or i
crushing of the core and shall be compared against 10 CFR Parts 20 and l
100 standards. Where applicable, the extent of fission product release shall be based upon NRC's re-evaluation of soune term assumptions and findings.
Facilities shall be grouped by cormnon design feature and analysis of a representative from each group snall be performed in the sequence i
of descending power.
l licensee Docket No. Power level Reactor Type National Bureau of Standards 50-184
~ F MW Tank I
University of Missouri 50-186 10 MW Tank i
Georgia Institute of Technology 50-160 5 MW Tank Massachusetts Institute of Technology 50-20 5 MW Tank l
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 i
University of Virginia 50-62 2 MW Pool i
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Los Alamos National Laboratory shall perform the following tasks 2.1 Task No. 1 A review of existing information in available sources such as the NRC l
docket files augmented by site-specific information provided by NRC staff and on site inspection visits shall be conducteo to:
(a) familiarize task i
personnel with characteristics peculiar to each reactor, 3nd (b) obtain information necessary to aid in the calculation of the radiological 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
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diagram fault tree approach sirilar to those used in other safety studies i
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 I
other means which could severely damage the fuel in the reactor core.
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Since the key consideration is the fission prodect release associated with such incidents, the effects of using low enriched uranium versus high enriched uraniun on the fission proouct release shall be evaluated, b
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 fron ioriine exposure, and identify any facility which could i
exceed 10 CFR Parts 20 and 100 standards, and c.
Detennine the characteristics of the event that would limit it to less than Parts 20 and 100 standards.
Certain other parameters and assumptions should be considered when per.
I forming this task.
These include, and are limited to the following except as fray be approved by the NMSS Project Panager (PM) in the future:
a.
The models or methods used to calculate t.5e damage and the releases shall assume that the reactor has been operating at the maximum power level authorized by NRC license and that equilibrium of fission i
products was attained prior to the incident. Note:
If significant I
I damage to the core or subsequent release is calculated to occur after a period of reactor shutdown, this shall also be evaluated, l
b.
In those cases in which the fission product inventory of the NPR 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 conctruction 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 tersnineted, and the basis for the conclusion documented, r
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o c.
No assumptions are made regarding the saboteurs' capabilities nor is there any design basis threat associated with this task, I'
d.
For b seline considerations, it should be assumed that all reactor L
safety features fail upon initiation of the incident, and I
e.
The mean meteorological conditions at the site and the surrounding area should be considered when calculating the atmospheric dispersion of a release.
l 2.3 Task No. 3 j
After Tasks No.1 and 2 have been accomplished, mathematical models t
or other appropriate methods shall be developed to calculate the amount of f
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 ct or.
Certain parameters and assumptions should be considered in those calcula-tions. These include, and are limited to the following except as nay be approved by the NMSS PM in the future:
i a.
The type of explosives and incendiary devices used to cause an event are assumed to be easily obtainable.
b.
Two opposing conditions shall be considered in performing Task 3:
1.
The adversary shall have access to all reactor components in carrying out the sabotage event.
ii.
Safeguards credit shall be given for all physical barriers irterposed between 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 l
product release and estimated doses exceed 10 CFR Parts 20 and 100 stan-dards, calculate the' amount of explosives and the amount of incendiary peterial needed to cause the release.
The calculations shall be made for placement of explosives and ir.;.endiary devices attached to reactor compo-nents and outside the structure containing the reactor.
The parameters'and assumptions employed in Task No. 3 shall be utilized l'
in this task.
i
l 2.5 Task No. 5 i
Upon completion of Task No. 3, a review and evaluation of reactor control systems and fuels shall be made to detemine whether an unauthorized i
manipulation of such controls could cause any detrimental effects that may be identified in Task No.'t.
Only credible scenarios and analytical assumptions shall be used and shall be reviewed and approved by the NMS$ PM l
before the analyses are made.
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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 i
operation of the reactor (these features are ignored under Task 3 to e
detemine maximum consequences).
Mentify additional safety reasures and modifications as well as administrative procedures and practi:es which could be adopted and determine the degree to which these additional considera-tions would mitigate the consequences.
Exclude specific safeguards measures from consideration in this task.
i 3.0 Reportino Reouirements l
3.1 Monthly letter Status Reporf A monthly report shall be given which summarizes the progress of the tasks being perforced including-o The work perforned during the previous month.
l o Personnel time expenditures during the previous month.
i o Problems encountered and the proposed solutions, o Activities planned for the ensuing two months.
o Costs generated agiinst the work effort during the previous month (including direct salaries, materials and s,ervices, ADP support, i
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:
Donald M. Carlson, SG, NMSS - one copy i
Office of the Director, NMSS ( ATTN:
Program Support) - one copy 3.2 Interim Reports j
A draft interim report shall be furnished to the NMSS PM upon complet' ion of 3
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 HMSS PM.
.s.
j 3.3 Final Report l
LAHL shall furnish two copies of a draft final report to the NMSS PM by June 302, 1986. The format of these documents shall be as specified for formal technical reports in NRC Manual Chapter 1102 and will provide:
s.
The on site and off-site fis'sfon product release and dosage calcula-l tions associated with a total loss of coolant, b.
The quantities of explosives and incendiary material or description of i
acts necessary to cause a limiting case incident.
l c.
The placement of explosives and incendiary materials in relation
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to the reactor, d.
The description of unauthorized manipulation of reactor controls and i
fuel to cause a limiting case incident, e.
The resulting consequences, and t
f.
Appropriate alternative measures which can be implemented to mitigate a significant event (e.g., reactor facility modifications, administrative procedures, etc.).
l After review by appropriate NRC personnel, the Pfi will provide coments on
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the draft report to LANL within 60 days of receipt of the report.
l The perfoming organization shall revise the draft report based on the i
PM's comments and submit two camera-ready copies of the final report to the Document Management Branch, Technical Infomation and Document Control, fGC l
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-sified Infomation and appropriately marked in accordance with "NRC Classification Guide for Infomation Dealing with the Release and Dis-persion of Radioactive ttaterial (NRC-RDRM-1) " dated September 1982 and NRC Manual Chapter 1102.
3.4 Program Plan Within one month after initiation of task orders, LANL shall provide 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 become the operating schedule for the overall task.
i 4.0.Meeti ng s LANL representative (s) shall meet with the NMSS Project Manager two to four times a year. Upon completion of the draft final report, LANL representa-
)
tives, upon request of the NMSS PM, shall brief NMSS staff in Washington, DC.
)
i All travel requires approval of the NMSS Project Manager.
5.0 NRC Furnished Material, j
None, except infomation in available sources such as NRC docket files.
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e 6.0 Level of Effort It is expected that approximately three and one half staff years of tech-i nical support will be required to satisfy the provisions of the Statement of Work.
7.0 Period of Performance i
i Perfomance for the overall task shall comence on the effective date of this agreement and continue through September 30, 1986.
F 8.0 Quality Assurance For all draft and final technical reports delivered under this agreement, i
the LANL shall assure that an independeat review and verification of l
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 c.athematical equations and derivations in the report (s), (such as might be the case when there are a large number of routine, repetitive calculations), the LtML nust first obtain written approval from the NMS$ PM.
Conputer-generated calculations will not require verification where the computer program has already been verified.
In addition, for all reports, including those which do not contein numeri.
cal analyses, a management review shall be conducted prior to submission to the NRC.
l 9.0 Technical Direction i
Mr. Donald M. Carlson (FTS 427-4712) is designated the NMSS Project Manager 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 threugh the hMSS PM.
As used herein, technical instructions are those which provide details, i
suggest possible lines of inquiry, or otherwise complete the general scope j
of work set forth herein.
Technical instructions shall not constitute new 3
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 Standard Order for Work (50W) (NRC Form 173) from the Director of the Office of Nuclear Materi,a1 Safety and Safeguards (NMSS).
1 4
i 1000 Disposal of Property l
Prior to close out of this project, a reconciled report shall be developed by DOE to record available equipment and material purchased with NRC funds. - This report should be developed as soon as possible after project completion or temination decision has been made, but rot later than 60 days after the temination date. The report should be submitted to the NRC Division of Facilities and Operations Support, ADM, and the NMSS Project Manager.
11.0 DOE Acquired Materia 1 i
The perfoming orpnization must notify the NMSS Project Manager prior to acquisition of any capital ADP, or word processing equipment.
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CITY STATE 2iP CODE CIT Y STATE ZIP CODE PRostCT TITLE ANo OTHER ietNTiPYiNG iNPoRM ATiON Consequences of Sabotage at Nonpower Reactors LANL shall determine and evaluate the consequences of both a loss of coolant incident
& fuel damage produced by:) u(a) blast effects from explosives, (b) prod. of he incendiary devices, &
(c nauthorized manipulation of reactor controls.
- 7. PERPoma4ANCE IWILL REQUIRE YES NO TS S
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- s. INFORMATION PERTAINING TO THESE REQUIREMENTS OMg S P JECT, EVEN THOUGH SUCH INFORMA.
TlON IS CONSIDERED UNCLASSIFIED, SHALL NOT BE R EA D' FO DISSEMINA"joN EXCEPT AS APPROVED A d/
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Classification wil'i be according to LANL's findings and classified in accordance with "NRC Classification Guide for Information Dealing With the.
Release and Dispersion of Radioactive Material (NRC-RDRM-1)," dated September,1982.
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- 10. CLASSIFICATION REVIEW OF CONTRACTOR /SUSCONTRACTOR REPORT (S) AND OTHER DOCUMENTS WILL BE CONOUCTED 0Y NAME OF AND TITLE OF POSITION OF AUTHORIZED CLASSIFIER C
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SECURITY /CLAS$1FICATION REQUIREMENTS FOR SUBCONTRACTS RESULTING FROM THIS CONTRACT WILL BE APPROVED BY THE OFFICIALS NAMED IN ITEMS 12b AND 12c SELOW.
- 11. THE SECURITY / CLASSIFICATION REQUIREMENTS AND ATTACHMENTS REFERENCED HEREIN HAVE BEEN
' APPROVED BY THE OFFICIALS NAMED IN 120 AND b eELOW. FINAL CONTRACTING APPROVAL SY THE DIRECTOR, OlVISION OF CONTRACTS OR HIS REPRESENTATIVE 18 TO at INCLUDED IN 12e eF. LOW l NAMe' SIGNATURE DATE
- a. DIRECTOR OFFICE OR OlvillON Robert F. Burnett, Director
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