ML20237F594
| ML20237F594 | |
| Person / Time | |
|---|---|
| Issue date: | 05/11/1987 |
| From: | Sheron B NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Wade T ENERGY, DEPT. OF |
| Shared Package | |
| ML20237F598 | List:
|
| References | |
| CON-FIN-A-6328-7, FOIA-87-388 NUDOCS 8709010354 | |
| Download: ML20237F594 (6) | |
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MAY I 11987 i
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l Mr. Troy E. Wade 11. Manager 1
Idaho Operctions Office U. S. Department of Energy 7E5 DOE Place Idaho Falls, Idaho 83402
Dear Mr. Wade:
FY 1987 NUCLEAR REGULATORY RESEARCH ORDER NO. 60-87-156 FOR~ IDAHO NATIOf!AL 4
ENGINEERING LABORATORY Please authorize Idaho National Engineering Laboratory to execute the program described in the enclosed NRC Order.
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j If this meets with your approval, it is requested that acceptance be indicated
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on the enclosed fonn and the original be sent to the NRC Office of Adminis -
tration and Resource Management and one copy returned to this office.
Sincerely, Ori;in' !!id tr.
Elis \\!. E.=3 Brian W. Sheron, Director Division of Reactor and Plant Systems Office of Nuclear Regulatory Research
Enclosures:
Distr 1.
NRC Order sub;;
i Circ 2.
Program Brief Chron cc w/ enclosures:
D. Dandois, ARN R. W. Barber, DOE /EH-33 M. Farr, DRPS T. Charlton, INEL D. Soleb:re, DP.PS Uylbur RECOP.D NOTE:
1102 i.st b.2n sen'c.
SCRC approval for FY:ri.
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u a NUCtEAR REOULATOav CouwisSoN oRoER NUMaER NRC. FOau 173 l
P) 87-156:
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STANDARD ORDER FOR DOE WORK.
gy 11 1987 4
ACOOUNTING CITATION i.
ISSUED TO: (DOE Off.ce)
ISSUE.D BY: (NRC Office)
APPROPRIATION SYMBOt.
Idaho Operations.0ffice Division of Reactor a Plc.nt 31X0200.607 i
Systems saa NuueER 7EnFoRMING ORGANIZ.ATION AND LOCATION 601901' FIN NUMBER I'daho National' Engineering Laboratory A6328 -7 WORK PERIOD - THIS ORDER i
FIXED O ESTIMATED @
FIN TITLE Thermal-Hydraulic Technical. Integration Center
'"Yhru 9/30/87 i
1 OsuGATION AVAILABILITY PROVIDED SY:
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4 70,000' q
s A.
THS OaoER j
8.
TOTAL OF ORDERS PLACED PR80R TO THIS DATE WITH THE PERFORMitC ORGANIZATION UNDER THE g
sAME " APPROPRIATION SYMBOL" AND THE FIRST FOUR DGITS OF THE "S&R NUMBER" CITED A40VE. '
16,28},000-C. Tovat oRoERS To oATE (Tot At 4 a si s'
16,351,000:
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D. AMOUNT INCLUDED W "C" AWULASW TO TM "FM NUM8ER" CffED W THIS ORDER.
1~;407 nnn FMANCSAL FEXIBluTY:
O FUNO$ WILL NOT BE REPROGRAMMED SETWEEN FINS. UNE D CONSTITUTES A LIMITATION CA OeuGATIONS AUTHORIZED]
E) FUNDS MAY BE REPROGRAMMED NOT TO EXCEED 110% OF FW EVEL UP TO $50K. UNE C COsETITUTES A UMITATION ON 08LIGAT80NS AUTHORLZED,
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rea STANDARD TERMS AND CONDfTIONS (ese NRC Manuel Chapter 1102. Appendia Part 4) ARE PART ( en ;FMt UNdSS OTHERWISE NOTED ATTACHMENTS THE FOLLOwiN6 ATT ACHMENTS ARE HEr.E8Y MADE A PART OF THtS SECURITY; O WORK ON THt$ ORDER INVOLVES CLASStF4E0 ORDER INFORMATION NRC FORM 107 IS ATTACHEO.
3 STATEMENT OF WORK O WORK ON THIS ORDER INVOLVES UNCLAS$1FIED O ADOtT#0NAL TERMS AND CONDITCNS SAFEOUAROS, PROMWETARY rR OTHER SENSITfvE
- i D OTMER INFORMATION FE E BLE WOR g) WOR 8( ON THis ORDER IS UNCLASSIFIED AND NOT SENSfffvE.
REGAARKS (Reaproace Wie proposef er number and elete, and andbc.efe # she sneenr1N, ;ement of set sviaddas Wie DOE proposel) l 1
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ACCEPTueG ORGANtZATKH4 V N"-
ScNAruRE ScNATum Br an W.'
Sheron. Diretnr TrTLE Division Of Reacter a Plant Systecas ma Office of Nuc'. ear Regulatory Research D^rE NRC POau m ow
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1 FY 1987 PROGRAM BRIEF PROGRAM:
DRSS.
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TITLE:
Thermal-Hydraulic Technical FIN:
A6328 Integration Center CONTRACTOR:
INEL SITE:
Idaho Falls STATE:
Idaho NFC TECHNICAL MONITOR:
Ds Solberg PRINCIPAL INVESTIGATOR:
T. Charlton OBJECTIVES:
(1)
Provide management and planning for the Thermal-Hydraulic Technical Integration Center (TIC).
(2)
Provide integrated safety analysis methodology for priority problem studies.
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(3)
Provide code applicability evriuation of TRAC-PWR, TRAC-BWR and RELAP5 for analys3s of T/H transients in B&W, 1
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i (4)
Provide for on-going program support, BUDGET ACTIVITY: 601901 PREVIOUS FY 1987 OBLIGATION: $1437 THIS ORDER:
S 70 TOTAL FY 1987 OBLIGATION:
lII307 FY 1987 SCOPE:
1.
Management and Planning a.
Review all ongoing T/H research; consult with research p':ncipal investigators as needed, provide integration and coordination as needed regarding application and assessment of codes and regarding experiments and advise NRC concerning ability of ongoing research to satisfy goals and needs for additional research.
b.
Prepare program plan for Thermal Hydraulic TIC for FY-88.
c.
Prepare draft thennal-hydraulic experimental program f%n for Westinghouse and Combustion Engineering reactors, d.
Prepare draft thermal-hydraulic experimental program plan for GE reactors.
e.
Consult and advise RES on research program and RRRG meetings and other planning and program development meeting as directed by NRC.
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l Thermal-Hydraulic Technical-Integration Center FIN: A6328 2.
E&W Methods Integration Study Prepare an interim report on the principal results and lessons learned from the study and perform the follow-on application as agreed upon and directed by NRC and defined by. accepted proposals submitted by the ccntractor.
When completed provide the NRC staff with a detailed briefing.
o' the methods, methods applications and insights resulting from the study.
Publish the results as a NUREG/CR report.
As requested by NRC, use these methods to. evaluate the effects on plant safety of design and operational changes to'B&W plants.
3.
BE and FSAR Analysis Support for NRR.(Task initiated in FV86)
Review the FSARs for three PWR vendors to compare the predicted response for comparable transients.
For each transient' establish and compare key system response parameters for each plant that characterize the important-response characteristics of that transient and establish, to the degree possible, the causes of the major differences among the three PWR types, e.g., establish the critical plant components, control system characteristics, safety system response, operator actions assumed, etc.
that have the most significant effect'on improving or degrading the key response parameters.
Expand the scope of the previous' best estimate analysis study similarly. Prepare an informal letter report which documents the key responses for comparable transients in each plant, discusses the reasons for the observed differences and provides reconinendations for additional best estimate analyses required for NRC.
(1) to evaluate relative safety of B&W plants compared with other vendor plants and (2) enable evaluation of the design and operational.
differences which have major effects on those safety differences.
4.
Code Applicabil:ty 4.1 Develop RELAPS quality assurance document which includes the following information for all constitutive relations and models:
a.
The specific correlation, coefficient, or method used.
b.
The technical basis for its use, including the range of applicability.
c.
A description of how the method is coded in the source programs.
d.
A description of any modifications to the method required to overcome computational difficulties.
e.
An assessmer.t of the impact of the changes in item d. upon code accuracy.
q Thertnal-Hydraulic Technical Integration Center'. FIN:~ A6328 3.
4.2 Complete documentation of. RELAP5 assessment calculations for three
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OTIS. tests and the GERDA nodalization anclysis..
4.3. Complete the code applicability document for RELAPS calculations of B&W loss-of-feedwater transients' including:
1 a.
Code scalability to. detemine the accuracy and scalability of selected constitutive relations.
b.
' Code assessment of constitutive relations needed to predict controlling phenomena in the transient.
c.
Effect of variations in controlling phenomena' to the probability of reaching postulated plant conditions (e.g. core melt).
d.
Document the RELAPS B&W' loss-of-feedwater transient appl 4 ability in a }lUREG/CR recort.
4.4 Exercise the code applicability methodology on a second B&W plant transient, such as the small-break loss-nf-coolant accident, if directed by NRC.
5.
On-going Program Support a.
Maintain TRAC-PF1 for INEL applications.
b.
Coordinate with LANL on code applicability document for TRAC-PWR. The first effort should be on LBLOCA in PWR's.
4 6.
10 CFR 50 Support a.
Provide needed support to NRC for ECCS rule revision.
b.
Perform a scoping study to evaluate potential risk reduction initiatives based on the proposed ECCS rule revision.
4 c.
Assist NRC in (1) resolution of public coments on the ECCS rule,
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regulatory guide and compendium and '(2) revision of the regulatory guide and compendium as appropriate based on the agreed upon resolution of those coments.
7.
Other tasks subject to available funding:
Review previous conservative vendor analyses'of "prIps'on_vs; pumps a.
.off" for SBLOCA, as well as-previous best-estimate calculations and experimental results, and provide NRC with a letter report on the effect of~the proposed ECCS rule change on this issue.
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Thermal-Hydraulic Technical Integration Center FIN: A6328 b.
Provide a surmary report on previous NRC - sponsored work on shut-down decay heat removal systems.
Include previous SASA and NRR analyses, as well as applicable experimental test results.
Provide a risk and thermal-hydraulic analysis for a possible separate, bunkered, dedicated decay-heat removal system. Evaluate the potential that a water hamer event could jeopardize the removal of decay heat.,
j c.
Assist NRC in organizing regional / industry workshops to explore potential repercussions of the proposeo ECCS rule change on plant operation and risk reduction.
i d.
Evaluate risk reduction initiating based on proposed ECCS rule l
revision as defined by scoping study in 6b.
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e.
Synthesis reports if requested by NRC.
f.
Provide additional ECCS rule support as defined by NRC.
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