ML20207A563

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Forwards Std Order for DOE Work for FINs A-1019,A-1030, A-1198,A-1218,A-1227,A-1246,A-1258,A-1335,A-1342,A-1389, A-1405 & A-1406
ML20207A563
Person / Time
Issue date: 02/21/1986
From: Gillespie F
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To: Romatowski R
ENERGY, DEPT. OF
Shared Package
ML20207A169 List:
References
CON-FIN-A-1019-6, CON-FIN-A-1030-6, CON-FIN-A-1198-6, CON-FIN-A-1218-6, CON-FIN-A-1227-6, CON-FIN-A-1246-1, CON-FIN-A-1258-6, CON-FIN-A-1335-6, CON-FIN-A-1342-6, CON-FIN-A-1389-6, CON-FIN-A-1405-6, CON-FIN-A-1406-6, FOIA-86-678 NUDOCS 8611110008
Download: ML20207A563 (3)
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FEB 211986 5 V # j l .

(-1 f I I l'r. R. G. konatowski, fia. nager

' Albuquerque Operations Office U. S. Cepartment of Energy j P. O. Box 5400 Albuquerque, f:sw tmxico c7115 l

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Dear I.r. Retratewski:

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FY 1986 fiUCLEf.R REGULATOI.Y R: SEARCH ORCEF !<0. 60-26-134 FOR 5% CIA .i.TRWAL L A6t.RATvhlts ,

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e NRC FORM 173 u 5 NUCLEAR REGULATORY COMMSSON ORDER NUMSER ma') 60-86-134

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STANDARD ORDER FOR DOE WORK FEB 211986 issued TO: (DOE Omce) ISSUED BY: (NRC Off ce) ACCOUNTING CITATION Albuquerque Operations Office Division of Accident " *"'**"

Evaluation 31X0200.606

. SSR NUMGER PERFOmMNG ORGANIZATION ANO LOCATION See Attached FIN NUMSER Sandia National Laboratories See Attached WORK PEfh00 - THis ORDEpl FIN TITLE FIXED C ESTilAATED U See Attached FROM TO:

10/1/85 9/30/86 OSLIGATION AVAILASILITY PROVIDED BY:

^ "'S ORDER $ 6,314.000 8 TOTAL OF ORDERS PLACED PRIOR TO THIS DATE WITH THE PERFORMING ORGANIZATCN UNDER THE 8 SAME "APPROPRIATON SYMSOL" AND THE FsRST FOUR DIGITS OF THE "B4R NUMSER" CITED ASOVE 14.497.000 C TOTAL ORDERS TO DATE <TOTAtA a e) : 20,811,000 D AMOUNT INCLUDED IN ' C" APPUCABLE TO THE " FIN NUM8ER' CITED IN THIS ORDER S g

FINANCIAL FLExtBluTY Z FUNDS WILL NOT BE REPROGRAMMED BETWEEN FINS UNE D CONSTITUTES A UMITATON ON OtuGATONS AUTHORIZED 3 FUNDS MAY SE REPROGRAMMED NOT TO EXCEED 2 10% OF FIN LEVEL UP TO 860K. UNE C CONSTITUTES A UMiTATON ON OSUGATCNS AUTHORIZED STANDARD TERMS AND CONDITIONS (see NRC Manuel Chapter 1102. Appenais Part a) ARE PART OF THIS ORDER UNLESS OTHERWISE NOTED ATTACHMENTS THE FOLLOWING ATTACHMENTS ARE HEREBY MADE A PART OF THl$ SECURITY-OADER C WORK ON THIS ORDER INVOLVES CLASSIFIED C STATEMENT OF WORg INFORMATON NRC FORM 147 IS ATTACHED C ADDITIONAL YERMS AND CONDITCNS C pk ON THIS ORDER INVOLVES UNCLAS$6FIED

! OTHER SAFEGUARDS. PROPRIETARY, OR OTHER SENSITIVE INFORMATION

"' ' u w Rx = mrS OaDER iS UNCtASSiriED AND NOT SENSimE E b'O'"$ESE RECYv'EIAE*WORx REMARKS <Rownee une o.meer or meer one aere ena na.cere ,o une eneenn areMment or ore moees une oOe oropoeno REF: SOEW *60-86-007 dated 11/22/85 for previous FY 1986 funds and work scope. )

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ISSUING AUTHORITY ACCEPTING ORGANIZATION S8GNATURE gi /// SIGNATURE Frank P. dfflespie, Director f. j TiTt E Division of Accident Evaluation TirtE Office of Nuclear Regulatory Research NRC FORM 173 (1-44, DATE 1

. ($ - c . ..

FEB 21 1996 '

SOEW #60-86-134 SANDIA NATIONAL LABORATORIES FY 1986

~(DOLLARS IN THOUSANDS)

PREY. TOTAL-FY 86 THIS FY 86 B&R NO. FIN NO. TITLE OBLIG ORDER ORLIG 601930 A1019-6 Molten Fuel-Concrete Interactions (CORCON/VANESA) $ 81 $ 244 $ 325

-)*601930 A1030-6 Corium-Coolant Interactions 146 (279i r[425 )

601930 A1198-6 Containment Analysis - CONTAIN Code Development and Application 200 600 800~

601930 A1218-6 Core Melt Technology 363 1087 1450 601930 A1227-6 High Temperature Fission Product Chemistry 100 350 450 601930 A1246-6 Hydrogen Behavior Program 300 900 1200 601930 A1258-6 PWR Severe Accident Sequence Analysis-SNL 150 150 300 601930 A1335-6 ACRR Melt Progression Experiments 250 480 730 601930 A1342-6 Melt Progression Analysis (MELPROG) 200 600 800 601930 A1389-6 ACRR Source Term Experiments 375 875 1250 601930 A1405-6 MELPROG Validation Experiments and Analysis 88 262 350 601930 A1406-6 Direct Containment Heating 163 487- 650 TOTAL $2416 $6314 $8730 b

.e UNITED STATES

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e WASHINGTDN, D. C. 20555

,y - ,/ FEB 211986

, t;r. R. G. Romatowski,fianager Albuquerque Operations Office U. S. Department of Energy P. O. Box 5400 Albuquerque, New flexico 87115 Dear I/r.

i Romatowski:

, FY 1986 NUCLEAR REGULATORY RESEARCH ORDER N0. 60-86-134 FOR SANDIA NATIONAL LABORATORIES Please authorize Sandia flational Laboratories to execute the program described in the enclosed f;RC Order.

If this meets with your approval, it is requested that acceptance be indicated on the enclosed form ano the original be sent to the NRC Office of Resource f*.anagement and one copy returned to this office.

Sincerely,

' /

..i Frank P. Gillespie, Director Division of Accident Evaluation Office of Nuclear Regulatory Research

Enclosures:

1. NRC Order
2. Program Brief cc w/ enclosures:

R. W. Barber, DOE /EP J. L. Kenoyer, Pfil

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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REGULATORY RESEARCH REVISED FY 1986 PROGRAM BRIEF TITLE: ACRR SOURCE TERM EXPERIMENTS FIN: A1389

- CONTRACTOR: Sandia National Laboratories PRINCIPAL INVESTIGATORS: P. S. Pickard, D. A. Powers, and W. J. Camp NRC PROJECT MANAGERS: R. W. Wright and L. K. Chan -

DIVISION: Accident Evaluation BRANCH: Fuel Systems Research Prev. FY 86 Oblig.: $ 375K BUDGET ACTIVITY: 601930 This Order: $ 875K Total FY 86 Oblig.: $1,250K OBJECTIVE: To perform a series of separate-effects Source-Term (ST) experiments in ACRR on fission-product and aerosol release rates from reactor fuel and the fission-product and aerosol chemical form under core-uncovery accident conditions and at temperatures up to fuel melt.

The results are to be used in fission-product release codes, including the VICTORIA fission product and aerosol module in the MELPROG mechanistic core-melt progression code, ard to benchmark laboratory fission-product and aerosol release experiments. This program is part of the international integrated Severe Fuel Damage (SFD) and Source Term (ST) research program of the Fuel Systems Research Branch. It is anticipated that additional funding of

$1000K for this program will be provided by foreton partners in the SFD and ST research program under a separate FIN.

FY 1986 SCOPE OF WORK:

1. Perform the first two Source Term experiments, ST-1 and ST-2. These experiments are to investigate the effects of low and high pressure in a reducing hydrogen environment on fuel liquifaction and fission-product release and chemical form and on aerosol generation up to peak temperatures of about 2500K.
2. Issue a quick-look report on the results of experiments ST-1 and ST-2.

Analyze the ST-1 and ST-2 results and apply them to the CORSOR fission-product release correlation, the FASTGRASS mechanistic fission product l O

release code, and the MELPROG fission-product module VICTORIA.

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FIN: A1389 3. Make inital preparations for experiments ST-3 and ST-4. These are to be in particulate debris-bed geometry, a high-pressure steam environment, and to be taken to 2,800K for data on non-volatile release.

4. Coordinate the ACRR Source Term experimental program with the laboratory fission-product and aerosol release experiments in the RES source term research program and with the RES code assessment activities.
5. Provide RES with fast-response technical consultation on fission-product and aerosol release under LWR Severe Accident conditions for the RES Source Term reassessment and other Severe-Accident activities.

DELIVERABLES AND MAJOR MILESTONES:

1. Perform ST-1 Experiment (June 1986).
2. Perform ST-2 Experiment (August 1986).
3. Quick Look Report on Experiments ST-1 and ST-2 (September 1986).

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1 U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REGULATORY RESEARCH REVISED FY 1986 PROGRAM BRIEF TITLE: ACRR MELT PROGRESSION EXPERIMENTS FIN: A1335 CONTRACTOR: Sandia National Laboratories PRINCIPAL INVESTIGATORS: P. S. Pickard and W. J. Camp NRC PROJECT MANAGER: R. W. Wright DIVISION: Accident Evaluation BRANCH: Fuel Systems Research Prev. FY 86 Oblig.: $250K BUDGET ACTIVITY: 601930 'This-Order: $480K Total FY 86 Oblig.: $730K OBJECTIVE: To develop a data base and validated analytical redels on the development.of severe fuel damage (including the oxidation process and hydrogen generation), core-melt progression, and in-vessel aerosol release for the range of LWR severe-accident conditions by performing small-scale integral experiments in the ACRR test reactor.

- The results are used to assess severe-accident codes, in particular the mechanistic MELPROG and SCDAP codes. These experiments include four Debris Formation and Relocation (DFR) experiments, to be completed early in FY 1986,and follow-on Melt Progression (MP) experiments on the key processes involved in the later stages of in-vessel core-melt progression. This international Severe Fuel Damage (SFD) program and Source is (ST)

Term part of the research progran of the Fuel Systems Research Branch. It is anticipated that additional funding $1.5M for this program will be provided by foreign partrers in the SFD and ST research program under a separate FIN.

FY 1986 SCOPE OF WORK:

1. Issue a quick-look report on the results of the PWR DF-3 experiment with a Ag-In-Cd control rod performed in September 1985. Analyze the results, perform Post-Irradiation Examination (PIE) on the DF-3 experiment capsule, and issue a final experiment report.
2. Perform the BWR DF-4 experiment with a B,C control blade. Issue a quick-look report on the results of DF-4. AnaTyze the results and perfonn PIE on the DF-4 experiment capsule.
3. Complete analysis of results and PIE on experiment DF-2 and issue the final experiment report.
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FIN: A1335 4 Perform experiment planning and begin construction of apparatus for two small integral Melt Progression (MP) experiments that are to be performed in FY 1987.

5. Coordinate the ACRR MPST experimental program with the other elements in the RES experimental program and with the RES code assessment activities.
6. Provide RES with fast-response technical consultation on melt-progression and source term phenomena under LWR severe accident conditions for the RES source-term reassessment and other severe-accident activities.

DELIVERABLES AND MAJOR MILESTONES:

, 1. DF-3 Quick Look Report (November 1985).

2. DF-2 Final Experiment Report (November 1985).
3. Perform Experimental DF-4 (May 1986).
4. DF-3 Final Experiment Report (March 1986).
5. DF-4 Quick Look Report (July 1986).

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0 February 19, 1986 FY 1986 Program Brief Program: DAE '

Title:

PWR Severe Accident Sequence Analysis-SNL Fin No.: A1258 Contractor: SNL Site: Albuquerque State: New Mexico NRC Technical Monitor: B. Agrawal Principal Investigator: A. Peterson Objective: Improve the understanding of containment loading by severe reactor accidents and by events beyond the design basis. Provide interactive analyses with damaged fuel research, accident management developments and containment response.

Budget Activity: 601930 Previously Committed $150K This Order $150K -

Total Obligation 3703R FY 1986 Scope:

(10/01/85-9/30/86)

1. Identify, collect and store information on the design and operation of specific reactors for use in accident response calculations.
2. Develop logic models (such as event trees, operator action event trees, cause-consequence diagrams) to illustrate variations of the basic accident sequence being analyzed.
3. Use best-estimate, state-of-the-art techr.iques to analyze the physical response of the plant accident sequences approved by NRC. The analyses should emphasize the information available to the operator during the accident, the potential interpretations of that information, the options available for altering an accident sequence, and the probabilities and consequences of those options.

4 Issue the final report on the investigation of the potential for hydrogen detonation in local regions in large dry containments for PWRs. Include potentially severe environmental conditions, due to local detonations, that could cause damage to safety equipment. Make recommendations, if necessary, of safety equipment that may be damaged.

5. Resolve the hydrogen stratification issue. Provide simplified models, if necessary, to enable HECTR/CONTAIN to simulate the diffusion kinetics now under investigation with HMS.

-6. Complete the analysis of station blackout with loss of turbine-driven auxiliary feedwater and issue the final report.

6-Januarv 16, 1986 U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REGULATODY RESEARCH REVISED FY 1986 PROGDAM BRIEF TITLE: HIGH TEMPERATURE FISSION PRODUCT CHEMISTRY FIN: Al??7 CONTRACTOR: Sandia National Laboratory PRINCIPAL INVESTIGATORS: D. Powers, R. M. Elrick and R. A. Sallach NRC PROJECT MANAGERS: L. Chan and C. Ryder DIVISION: Accident Evaluation BRANCH: Fuel Systems Research BUDGET ACTIVITY: 601930 MODIFIED 1986 SCOPE OF WORK: PREV. FY 86 OBLIG:- $100K THIS ORDER: 350K TOTAL FY 86 OBLIG: 12l TOR The 1986 Scope of Work for this program is modified to include the following:

7. Conduct experiments to can'irm results from previous tests on the effect of ionizing radiation on Csl stability. The work should, ~

include:

a. Complete analyses on remaining samples from previous tests to obtain material balances #cr the tests.
b. Conduct reference experiments in the absence of radiation with the present apparatus so that a direct comparison between results from experiments with and without radiation can be made,
c. Determine the role of structural surfaces in the dissociation of Cs! in a radiation field.
8. Conduct analyses to determine the mechanism of Cs! dissociation in a radiation field. Establish a model to predict the chemical forms and distribution of iodine in the RCS under severe accident conditions.

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REVISED FIN A1227 January 16, 1986 DELIVERABLES AND MAJOR MILESTONES:

Topical . report on SnTe chemistry February 1986 Topical report on the thermodynamic data base for the Cs, 1,.0, P (including ions) system- ' February 1986 Complete confirmatory experiments on the effect of ionizing radiation on Cs! stability March 1986 Complete' calculations to predict RCS iodine forms and distribution May 1986 t

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