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Tc: Richard Hartfield ( RM ) 12105 MNBB WJ111am Dorie (ADM) 2100 MNBR
&#obert Brown (N".55) 396 $$ '
Eernard Greater (NRR) P-433 **
A. P. Muir (I AE) EW-359 Bill Forehand . P.csources Management Branch, RES From:
Phone: 427-4250 l6
Subject:
CONTRACT REVIEW BOARD REVIEW 0F: hPAf RES -e?Mr!N [$ %9 9 Titie: f'rsio A) hec lact Re{ pas 2 :
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Statement of Hork
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To: Richard Hartfiele ( RM ) 12105 MNBB Wilitam Dorte (ADM) 2100 MNB8 RobertBrown(N".55)39655 ernard Grenier (HRR) P-433 A. P. Muir (!&E) EW-359 P.csources Management Branch, RES From: Bill Forehand _.
Phone: 427-4250 I69
Subject:
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Attachment:
Statement of Work#
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- a ,.' 4 DATE:{3 g To: hard Hartfield ( RN ) 12105 MNBB William Dorie ( ADM) 2100 MNBR Robert Brown (N'tSS) 396 55 Bernard Grenier (NRR) P-433 -
A. P. Muir (!&E) EW-159 Bill Forehand __. Pesources Management Branch, RES From:
Phone: 427-4250 M
Subject:
CONTRACT REVIEW BOARD REVIEW DF: RfPu RES -P2,.ovfrIn T319 4 7 Titie: 5s3 iou hec lati RP(PAse :
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SA$e$A* /c e contraetor: _S^++elle %meriAl .TDJY) fait P,ES
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O i have reviewee the sud3.ct project ene fine no objection to i,ts issuance.
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Return to Mail Stop 1130-55
Attachment:
Statement of Work
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STATEMENT OF WORK MAR 2 5 1983 ,
l FISSION PRODUCT RELEASE:
TRANSPORT SAB0TAGE B&R 60190102 FIN: 8 syn RFPA R es-6.9-M lbf CONTRACTOR: Battelle Columbus Laboratories (BCL)
PRINCIPAL INVESTIGATOR: Ms. Audeen Walters SITE: BCL STATE: Ohio
1.0 BACKGROUND
The Office of Nuclear Materials Safety and Safeguards has a technical assistance study underway to provide a detailed analysis of the potential need to safeguard high level waste during transport. According to the completed portion of the study, sabotage of casks containing vitrified-high level waste during transport could result in a release that would be comparable to that frca sabotage of a spent fuel shipment. The next task in the NMSS study is to estimate the consequences of radiological release as a result of sabotage of vitrified high level waste during transport. This requires that an experimental determination of a source term likely to result from sabotage of vitrified high level waste during transport be made. The Office of Nuclear Regulatory Research has an on-going study which has provided a source term characterization for sabotage of spent fuel casks during transport. 'Q mu,os.z-em yndelgdntoy 3
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- 2. 0 WORK REQUIRED
[ 2.1 The contractor shall provide the personnel, facilities, materials, equipment, and services necessary to perform the following tasks:
2.1.1 Obtain or make up borosilicate glass samples containing appropriate concentrations of fission products and actinides which are representative of high level waste.
2.1.2 Apply the same attack scenarios defined in the study of the source term for sabotage of spent fuel shipping casks to sabotage of high level waste shipping casks.
2.1.3 Assess the physical / chemical form of high level waste which might be available for ejection through cask containment violations. For any experimental subtasks the ability to successfully model the necessary internal cask structures, closure designs, and the structural and geometric properties of the high level waste shall be evaluated.
2.1.4 _ Experimentally and analytically assess the potential radio-logical source term as it leaves the containment boundary.
This assessment shall define the chemical / physical properties and the dynamic behavior associated with any release. As in task 2.1.3, for any experimental subtasks, the ability to model the necessary cask and high level waste structure shall be evaluated.
2.1.5 Assess quantitatively and qualitatively the uncertainties associated with the evaluations of the chemical / physical form of the source term and its dynamic behavior as it leaves the containment boundary.
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' .2 -The contractor shall submit an interim report after completion of the e -
periments and preliminary analysis of the' data. The interim report shall be submitted by Octobe_r 1983.
~ After NRC review and comment, the contractor shall submit a camera-ready copy and two additional copies of a final report to the NRC project manager. The final report shall be submitted no later than May 1984.
2.3 The contractor may be required to participate in up to two meetings to be held at the NRC offices. No other travel is anticipated.
- 3. 0 REPORTING REQUIREMENTS 3.1 Monthly Letter Status Report By the 20th of each month, three copies of a brief letter status report shall be submitted to the NRC project manager which summarizes: the work performed during the previous month, personnel time expenditures durindRh the previous month, and costs generated against the work effort. The first monthly letter status report after project authorization shall include the planned monthly rate of expenditures for the fiscal year, if not provided with the Form 189, and include any changes to prior schedules
-or estimated costs. Also contained in each monthly report will be a breakout of (1) manpower utilized, (2) costs incurred for direct salaries, material and services, ADP support, subcontracts, travel, general and administrative and other related items, and (3) current obligation status information for the project.
3.2 Technical Reports Technical reports will be provided as specified in paragraph 2, Work Required.
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, 4.0 MEETINGS AND TRAVEL .
, 4.1 All travel requires prior. approval of the NRC project manager.
4.2 Annual Light Water Safety Research Meeting If requested by the NRC project manager, by August 15, 1983, a draft report summarizing the current year research results will be prepared and submitted to the NRCeproject manager for review and possible presentation at the NRC's Annual Light Water Reactor Safety Research meeting. If accepted, a final versior,of the report will be presented at the October 1983 meeting in Gaithersburg, Maryland, by either the project's principal investigator or a mutually satisfactory alternate.
5.0 NRC FURNISHED MATERIAL None.
6.0 CAPITAL EQUIPMENT All capital equipment expenditures require the prior written approval of the NRC project manager.
7.0 ' SUBCONTRACTOR Subcontracts require the prior written approval of the NRC project manager.
. 8.0 PERIOD OF PERFORMANCE The period of performance for the work described in this Statement of Work is April 1983 to May 1984.
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9.0 TECHNICAL DIRECTION t
.The NRC Project Manager is.Andrea K. Barnold, FTS 443-5976, Human Factors and Safeguards Research Branch, Division of Facility Operations, RES.
10.0 CONTACTS WITH NRC LICENS ES Any contacts with NRC licensees require prior written approval of the NRC project manager.
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60190102'is - $85' DD0 (FF83') BJ997 '
I $85 000 (FY 83T-I is *=osicr oencu s =*ue j u*it svor lna,,osi~uusu NL5650 i e a ,xova o o, o m cre . o. oc s.G , e a,,, ~ .,, ,,,,, .- ~ ..,~, ,,, ,,,,, .. ,,,,, .,,,,,, i o.n RobgrtM Bernero l arl'R oIGANIZAboh II!r % d h (d _, Director 4/p/p;f_
Division of Facility Onerations 17 f EnAAnns (1) This cancels Mod #4 of RFPA RES-80-180 (dated 2/23/83).
(2) Contract NRC-04-80-180 with the Battelle Memorial Institute (BMI) has been satisfactorily completed, and the Division of Contracts has been requested to arrange for the close out and deobligation of any FY 1981 funds not required by BMI. (No FY 1982 funds were obligated.)
- (3) eThe workscope (Attachment 1) for this new RFPA (Rg is essentially the same as that forward _ed with RFPA-RES-80-180 (Mod #4) ilDrcep earva FDiM~eldidh
,_Jt5.Tgt.anQ_ will'2E'adixnp1 fe h ed 't.h fold hghMf,qggesle@_cT1 Cgh t is estimated that themm-----@ tne work requested underj 'e new RFPA will be ES is certif ing the availability o# fmdE"KNG8 ' $-
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-emui urina-ra 6=iitwih13 #Et ANF= c.r net g e Attachment 2 to this new RFPA provides justification for having BMI do this work.
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{. APR 2 6 1983
- q i JUSTIFICATION FOR PLACEMENT OF WORK WITH BATTELLE COLUMBUS The Office of Nuclear Materials Safety and Safeguards has a technical as-sistance study underway to prbvide a detailed analysis of the potential need to safeguard high level waste during transport. According to the completed portion of the study, sabotage of casks' containing vitrified high level waste during transport could result in a release that would be comparable to that from sabotage of a spent fuel shipment. The next task in the NMSS study is to estimate the consequences of radiological release as a result of sabotage of vitri-fied high level waste during transport. This requires that an experi-mental determination of a source term (i.e. the magnitude and chemical /
physical form of any released radioactive material) likely to result -
from sabotage of vitrified high level waste during transport be made.
Battelle Columbus Laboratories (BCL) recently completed a study for the Office of Nuclear Regulatory Research that resulted in a source term characterization for sabotage of spent fuel casks during transport.
The study was conducted in three phases: (1) Definition of the refer-ence basis threat, design of the experiments, and design of equipment; (2) construction and testing of the system; and (3) conduct of the ex-periments and data analysis. The proposed work on high level waste will require the same equipment, expertise, and experimental setup as the spent fuel sabotage source term. BCL has the unique capability to con-duct the proposed study in that it is the only organization that has the required equipment, expertise, and experimental design already available.*
Any organization other than BCL would have to duplicate the existing equipment and experimental setup and possibly acquire the expertise, all at a considerable additional cost.
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, This would also require more time than is available. /the NMSS study re-quires development of the source term no later than October 1983** Because BCL has the necessary system readily available, they could meet this mile-stone. Any other organization could not.
Finally, BCL has easy access to the borosilicate glass samples that will be experimented with, through Battelle's Pacific Northwest Laboratories.
Any other organization would have difficulty acquiring or fabricating the samples, which would affect the timeliness and cost of conducting the study.
The equipment was designed and fabricated by BCL specifically for the experiments to determine the spent fuel sabotage source term. The equipment is still in place and is readily availat,le for use in the
, experiments on high level waste. It would be extremely cost inefficient to duplicate the equipment, in terms' of both material and personnel resources.
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