ML20238B608
| ML20238B608 | |
| Person / Time | |
|---|---|
| Issue date: | 02/10/1987 |
| From: | Morris B NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Wade T ENERGY, DEPT. OF |
| Shared Package | |
| ML20237F598 | List:
|
| References | |
| CON-FIN-A-6328-7, CON-FIN-A-6843-7, FOIA-87-388 NUDOCS 8709010308 | |
| Download: ML20238B608 (8) | |
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FEB 1 d 1987 hr. Troy E. Wade-II,I;ar.ager.
lldaho Operations Office U. S. Depcrtner.1 of. Energy 85 00E Plcce
.Id;ho fells... Idaho 8340:.-
.De0r fir. W<de:
fY 1987 MJCLEAR REGULATtsRY RESEARCH GRDER 110. 60-07-105 FOR IDA!!O I'/. TIC"AL s
EliGII:EEF.lliG LABORATORY Picasc auth<..rize I'dthe lutierial Engineering Libert, tory to axecutc the program
- I describcd ii. the enciesed hRC Order.
If this nects with your approval, it is requested that acceptance be irdicatad or, the enclosed forn end the original be sent to: thc (!RC Office 'of Resocr:e-i:6negenent and one copy returr.ed to this office.
i Sincerely, 1
Dill t'. Morris, Acting Director Division c.f Rtacter Systera Safety Office of f,uclear Regulate.rp Reseerch Er.clic.ure::-
DISTR' 1.
t!RC Order Progren Orief hh.
Chron cc w/ enclosures:
R. U. Ecrber, 00E/EH-33 cCuW,n j Mg D. Dandois, RM T. l!. Charlton, II:EL
- 0. R. Unif, IllEL
<O'.
bOIeberg, DRSS N Price, DRSS
.Wylbur ECORD NOTE:
SCRB approved for FY87 (1/29/87).
See previous 50EWs'for 1102.
8709010308 870827
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SHOLLYB7-388 PDR
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RPPE/RES RPPB/RES RPPB/
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NRC FOau 173 60-87-105 044)
^ FEB 10 1097 ST ANDARD ORDER FOR DOE WORK ACcovo<Tp+0 CrT AT60N ISSUED BY:. (NRC Offa)
ISSUED TO. (DOE Cma)
APtioPR4ATION ST'WSOL Division of Reactor Systen 31X0200.607 Idaho'0perations Office mR NOWum Safety
'601901-PERF ORWING ORGAN 12.ATiON ANo LOCAT60N Fm NuuuR See Below Idaho National Engineering Laboratory WORK rouOo - TNiS oRoER FIXED D -
ESTIMATEo Q FIN TITLE FROM TO Thru 9/30/87 See Below j
i OsuGATtON AVAILABILITY PROVIDED SY:
e i,667,000 l
A.
THis ORDER ZATcN UNDER THE s
13.467,000 TOT AL OF ORDERS PLACED Prom 10 THIS DATE WrTH THE PE t.
n OTAL A a e) 15,154.000
- c. tot AL ORDERS TO DATE See Below mOUwT wCtvDED m -C APeucAsLE TO THE -rm NuusER cerEo w TNr5 ORDER.
O.
F4NANCtAL FLEXI8ILffY.
O ruNDS WILL NOT BE REPROGRAWWED BETWEEN F1NS UNE D CCNSirT Q FUNDS WAY BE REPROGRAWWED NOT TO EXCEED s10% Or F 06LCATONS AVIHOR. ZED ST ANDARD TERWS AND CONDfTONS (nes N8tC WeNel Chapeo< 1102. AppeWa Pvt d} ARE PA SECURITY.
ATT ACHWE NT S
'~
THE FOLLOwiNC AT7 ACHWENTA ARE HERE8Y W ADE A PART Or THis D WORK ON THIS ORDER WVOLVES CLASSFnED e#0R6AATON NRC FORM isT f5 ATTACHED ORDER D WORK ON THis ORDER IWCKVES UNCLASSsrsED
& ST ATE ME NT Or wor <
SAFEGOARDS. PROPRIET ARY, OR OTHER SEN$fflVE D ADDITcNAL TERMS AND CONDITONS
~
e< 0RuAToN D OTHER C WORK ON TH15 ORDER 13 UNCLASSF1ED AND NOT SENS RA f WO" g
1 w w w.. - ro w.<r..n w me n :. % w.,,W oOE RsW ARas (R.<m, e. - er PREV-($ in K)
TOTAL FY 87 THIS FY 87 OBLIG ORDER OBLIG~
TITLE
$350
$1087 51437 F.,
NO.
Thermal Hydraulic Technical Iritegration Ctr 0
600
'600 X6.28-7 A6843-7 CEC-Scaled B&W Integral Facility
~33Td-
$1687 S2037 TOTAL ACCEPTlHG CHGANIZAT)ON issulHG AVTHORITY SGMATURE
//[fytvu g )is, Actina Director SCNATURE Morr B.
4 TrTLE Division of Reacter System Safety TrT tE Of fice of Nuclear Regulatory Research DATE MAC FORM 1T3 (tM)
_-_________m___-m.
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FY 1987 PROGRAM BRIEF I
l PROGRAM:
DRSS FIN:
A6328 TITLE:
Thermal-Hydraulic Technical CONTRACTOR:
INEL I
Integration Center
' SITE:
Idaho Falls j
STATE:
Idaho l
l l
NRC TECHNICAL MONITOR:
D. Solberg PRINCIPAL 1 INVESTIGATOR:
T. Charlton Provide management and plant.ing for the Th'ermal-Hydraulic OEJECTIVES:
(1).
Technical Integration Center (TIC).
(2)
Provide ' integrated safety analysis methodology for priority.
problem studies.
Previde code applicability evaluation of TRAC-PWR, (3)
TRAC-BWR and RELAP5 for analyses of T/H transients.in B&W, j{, CE and GE reactors.
(4)
Provide for on-going program support.
BUDGET ACTIVITY:
601901 PREV. FY87 OBLIG: $ 350 THIS ORDER: $1037 TOTAL FY87 OBLIG: $1437 FY 1987 SCOPE:
1.
Management and Planning Review all ongoing T/H research; consult with research principal a.
investigators as needed, provide integration and coordination as needed regarding application and assessnent of codes and regarding experiments and advise NRC concerning ability of ongofng research to satisfy goals and needs for additional research, b.
Prepare program plan for Thermal-Hydraulic TIC for FY-88.
Prepare draf t thermal-hydraulic experimental program plan for c.
Westinghouse and Combustion Engineering reactors.
Prepare draft thermal-hydraulic experimental program plan for GE d.
reactors.
Consult and advise RES on research program and RRRG meeti$gs and e.
other planning and program development reeting;as directed by NRC.
L
1 Thermal-Hydraulic Technical FIN: A6328 Integration Center 2.
B&W Methods Integration-Study
)
Prepare an intecim report on the principal results and lessons. learned!
.from. the study and perform the follow-cn application as. agreed upon.and directed by NRC and defined by accepted proposals'subtritted by the When completed provide.the NRC staff with a detailed briefing
'J contractor.
of the methods,' methods applications and insights resulting from the-H study. Publish the results as a NUREG/CR report.
J
~
i these methods to evaluate the effects on plant
'As requested by NRC, u e
safety of design and operational changes to B&W plants.
l i
BE and-FSAR Analysis Support for NRR (Task initiated in FY86) 3.
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 sipificant effect on improving or degreding the key' response parameters.
Expand the scope of the previous best ' estimate analysis study similarly.
Prepare an informal letter report which documents the key responsts for comparable transients in each plant, discusses the reasons for the observed differences and provides recommendations for additicial best estimate analyses required for NF.C.
(1) to evaluate relative safety of B8W 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 Applicability J
~
4.1 Jevelop RELAP5 quality assurance document which includes the following information for all constitutive relations and models:
The specific correlation, coefficient, or method used.
a.
b.
The technical basis for its use, including the range of applicability.
i A description of how the method is coded in the source programs, c.
d.
A description of any modifications'to the method required to overcome computational difficulties.
An assessment of the impact of the changes in item d.'~upon code e.
accuracy.
)
l Thermal-Hydraulic Technical Integration Center FIN: A6328 4.2 Complete documentation of RELAPS assessment calculations for.three OTIS tests and the GERDA nodalizaticn analysis.
4.3 Complete the code applicability document for RELAP5 calculations of B&W loss-of-feedwater transients including:
Code scalability to determine the accuracy and scalability of a.
selected constitutive' relations, b.
Code assessment of constitutive relations needed to predict controlling phenomena in the transient.
Effect of variations in controlling phenomena to the probability.
c.
ofreachingpostulatedplantconditions(e.g.coremelt).
d.
Dccument the RELAPS B&W loss-of-feedwater transient applicability in a NUREG/CR report.
4.4 Exercise the code applicability methodology on a second B&W clar.t-transient, such as the small-break loss-of-coolant accident, if directed by NRC.
5.
On-going Program Support a.
Maintain TRAC-PF1 for INEL applications.
Coordinate with LANL on code applicability document for. TRAC-PWR. The b.
first effort should be on LBLOCA in PWR's.
6.
10 CFR 50 Support a.
Provide needed support to NP.C fcr 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. pumps 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 summary rt. port on previous NRC - sponsored work on shut-down decay heat remo<a1 systems.
Include previous SASA and NRR analyses, as well as app 1mable. experirnental test results..
1
_ _ = _ _ _ _ _ _ _ _ - _.
A
Tremal-Hydraulic Technical 4-FIN: A6328 ir.tegration Cer.ter 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..
Assist NRC in organizing regional / industry workshops to explore c.
pcter.tial repercussions of the proposed.ECCS rule change on plant operation and risk reduction.
Evaluaterisk'reductioninitiatWang based on proposed ECCS rule d.
revision as defined by scoping study in.6b.
Synthesis reports if requested by NRC.
e.
f.
Provide additional ECCS rule support as defined by NRC.
l e
e 9
e's L-
l FY 87 PROGRAM BRIEF PROGRAM: :0RSS l
l TITLE:
CEC--Scaled B&W Integral Facility.
FIN: A6843 CONTRACTOR:
INEL SITE:
Idaho Falls STATE:
IDAHO NRC TECHNICAL MONITOR:
D. E. Solberg PRINCIPAL INVESTIGATOR:
J. R. Wolf l
OBJECTIVE:
Provide Conceptual Design for a Scaled B&W Integral Experimental Facility.
BUDGET ACTIVITY:
601901.
1 i
FY87 OBLIG:
$600K FY 1987 SCOPE:
Complete conceptual engineering and design for an integral test facility. based-on the preferred scaling concept for a B&W 177-FA lowered loop plant design.
Recommendations for the preferred scaling will be provided by the contractor and a panel of experts; NRC will make the final decision on the future design ba si s.
Specific tasks to be performed are:
Construct a TRAC-PF1 model of the proposed facility based on the scaling 1.
concept chosen.
2.
Obtain a. steady state balance for.the modelfat rated conditions.
3.
Perform three transient calculations 3.
Steam line break c.
Loss of feedwater.
4.
Compare results tc available calculations for a connercial B&W plant to assess preservation of local phenomena in the: scaled facility and report results in a NUREG/CR report.
5.
Perform tradeoff studies on the proposed scaled facility' design necessary.
to improve preservation of local phenomena and to optimize system response; report results in a NUREG/CR report.
f
_j
i j
4 s 6.
Develop system design' requirements and provide analysis support during the conceptual design.
l 7.
Initiate system conceptual design.
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