ML20238B343
| ML20238B343 | |
| Person / Time | |
|---|---|
| Issue date: | 11/25/1986 |
| From: | Morris B NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Wade T ENERGY, DEPT. OF |
| Shared Package | |
| ML20237F598 | List:
|
| References | |
| CON-FIN-A-6039-7, CON-FIN-A-6052-7, CON-FIN-A-6100-7, CON-FIN-A-6102-7, CON-FIN-A-6305-7, CON-FIN-A-6321-7, CON-FIN-A-6328-7, CON-FIN-A-6340-7, CON-FIN-A-6360-7, CON-FIN-A-6400-7, CON-FIN-A-6827-7, FOIA-87-388 NUDOCS 8709010176 | |
| Download: ML20238B343 (7) | |
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U S NucttAR REGULATOAY COMMISSON ORDER NuuBER NRC FORu 173 (14A) 60-87-011
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STANDARD ORDER FOR DOE WORK NOV 2 51986 ACCOUNTING CATATION t$5UED BY: (NRC Office)
ISSUED TO: (DOE Ofhce)
APPROPRtATON SvuBOL Division of Reactor W Lem 31X0?00.607 Idaho Operations Office Safety sanNuwBER See Attached
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PERFORMING ORGANIZATION AND LOCATION FIN NUMBER
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See Attached Idaho National Engineering Laboratory woRx PERIOD - TH S ORDER q
FtXED D ESTIMATED G 1
FIN TITLE FRY 1/86 9/30/87 1O See Attached j
OBLIGATION AVu A88LITY PROVIDEO BY:
s 4.124,000
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T"'S ORDER 1
O. TOTAL OF ORDERS PLACED PROR TO THr5 DATE WITH THE P g
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- o. AuCUwT INCLUDED IN "C" APPUCABLE TO TW " FIN NUWBER" CITED IN THIS ORDER.
g FINANCIAL FLEXIBILffy O FUNOS WILL NOT SE REPROGRAMMED SETWEEN FINS. UNE D CONSTITUTES IXFUNDS WAY BE REPROGRAMMED NOT TO EXCEED t10% OF fin LEVEL UP TO
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OBLIGATONS AUTHORIZED ST ANDARD TERMS AND CONDITONS (see NRC Wormat Chapter 1102. Apperds Part 4) ARE PART OF THIS O SECURITY:
OTT ACHME NTS THE FOLLOWING ATT ACHMENTS ARE HEREBV MADE A PART OF THr$
C WORK ON THIS ORDER INVOLVES CLASSIFIED ORDER LNFORMATON NRC FORM tef f5 ATTACHED E STATEMENT OF WOAK O WORK ON THis ORDER INVOLVES UNCLASSIFIED C ADDITONAL TERMS AND CONDITONS SAFEGUARDS. PROPRIETARY. OR OTHER SENSITIVE C OTHER INFORMATON.
11 WORK ON THt$ ORDER LS UNCLAS$1FIED AND NOT SENSITIVE O FEE RECOVERABLE WORK O NON FEE RECOVERA8LE WORK RtMARKS (Roterence the proposef by nebar eM cote eM o+cere H the eneched statement of nort moehes the DOE proposet)
ACCEPTING ORGAN!LATION ISSUING AUTHORITY SONATURE SsGNATURE p,.,
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l FY 1987 PROGRAM BRlJ PROGRAM:.DPSS.
~
-l TITLE:
Thermal-Hydraulic Technical
'i FINi 56328 Integration' Center CONTRACTOR:
INEL SITE:
Idaho Fallt
)
STATE:
Idabo-
]
)
HRC TECHNICAL MONITOR:
D. Solberg
'E i
PPINCIPAL INVESTIGATOR:
T. Charlton OBJECTIVES:
(1)
' Provide management and planning for the Thermal-Hycraulic Technicel-Integratico-Centar { TIC).
(2)
Provide integrated 56fety analysis' methodology for priority
'l problem studies.
(3)
Provide code applicability evalua' tion of TRAC-PWR, o
TRAC-BWR and RELAP5 for analyses of T/H transients in 6&W, W, CE and GE reactors.
.j (4)
Provide for on-going program support, f
I BUDGET ACTIVITY: 60190101 FY.1987 OBLIGATION:
$350K FY 1987 PLAN:
$1392K l
FY 1987 SCOPE:
1.
Management ar.d Planning a.
Review all ongoing T/H research; consult with research principle investigators as needed, provide integration and coordination as i
needed regarding application and assessment of codes and regardino 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 thermal-hydraulic experimental program plan for I
Westir.ghouse and Combustion Engineering reactors.
d.
Prepare draft thermal-hydraulic experimental program plan for GE i
reactors.
e.
Provide synthesis reports (definad by NRC).
2 1
j 1
Thermal-Hvc'raulic Technical I
Integraticr Center
' FIN: A632F, l
l l
P.
B&W Pethods Integration Stud) 1 Prepare an interit.1 report on the principal results ano lessons learned.
from the study and perform the follow-on application as agreed upori and directed by NRC and defined by accepted proposals submitted by the contractor.
When completed prcvide the NRC staff with a detailed briefing of the methods, methods applications and insights resulting frorr the
- s tudy'.
Publish the results as a NUREG/CR report.
i
-l As requested by NRC, use'these methods to evaluate the effects on plant j
safety of design and operational charges to B&W plants.
j 3.
BE and FSAR Analysis Support for NRR (Task initiated in FY86)
Review the FSARs for three PWR vendors to compare 'the predicted respcnse 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 at;d 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, operecor actions assumed, etc.
that have the most significant effect on improving or degrading the key-response parameters.
Expand the sccpe 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 recommendations for additier.al best estimate analyses required for NRC.
l (1) to evaluate relative sa%ty of B&W plants compared with other vendor l
plants and (2) enable evaluation of the design and operational differences which have major effects on those safety differences.
4.
Code Applicability 4.1 Develop RELAP5 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 methnd is coded in the source programs.
d.
A description of any modifications to the method reauired to i
overcome computational difficulties.
e.
An assessment of the impact of the charps in itom d. upon code accu acy.
-l
Thermal-Pydraulic Technical Integration Center FIN:
A632E 4.2 Complete documentation of RELAF5 assessment calculations for. three OTIS tests and the GERDA nodalization analysis.
4.3 Cornplete the ccde applicability' document for PELAPS calculations of B&W loss-of-feedwater transients including:
a.
Code scalabili_ty to determine 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. cote melt)..
d.
Document the RELAPS B&W loss-of-feedrater transient applicability in a NUREG/CR report.
4.4 Exercise the' code applicability methodology or a second B&K plant transient, such as the small-break loss-of-coolant accident, if directed by NRC.
5.
On-going Program Support a.
Maintain TRAC-FF1 for INEL applications.
b.
Coordinate with LANL on code applicability document for TRAC-FhR. The first effort should be on LBLOCA in PWR's.
6.
10 CFR 50 Support e.
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.
7.
Other tasks subject to available funding:
a.
Review previous conservative vendor analyses of " pumps on vs. pun:ps.
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.
b.
Provide a sumary report on previous NRC - sponsored work on shut-down decey heat remeval systerrs.
Include previous SASA and NRR analyses, as well as applicable experimental test results.
~
Thermal-hydraulic Technical i
Integration Center FIN:
A63P8 Provide a risk and thermal-hydraulic analysis for a possible separate, bunkered, dedicated decay-heat removal systen..
Evaluate the potential that e rater hamer event could jeopardize the removal of decay heat.
c.
Assist NPC in organizing regional / industry workshops to explore potcr.tial repercussions.of the proposed ECCS rule change on plant operation and risk reduction.
d.
Evaluate risk reduction initiating based on proposed ECCS rule revision as defined by scoping study in 6b.
1 i
4 i