ML19347B479
| ML19347B479 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, North Anna  |
| Issue date: | 09/29/1980 |
| From: | Dunenfeld M Office of Nuclear Reactor Regulation |
| To: | Johnston W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8010150143 | |
| Download: ML19347B479 (8) | |
Text
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MEETING
SUMMARY
DISTRIBUTION CORE PERFORMANCE BRANCH S EP 2 S ;ggg Central File Principal Staff Particicants eJHtt POR Local PDR M. Dunenfeld NRR R/F CPB R/F H. Denton E. Case NRR-PPAS D. Ross L. Rubenstein W. Johnston W. Butler e
J. Stolz P. Check W. Kreger D. Eisenhut F. Schroeder R. Vollmer S. Hanauer IE (3)
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G90 MEMORANDUM FOR:
W. V. Johnston, Chief Core Perfomance Branch, DSI FROM:
M. Dunenfeld, Reactor Physics Section Core Perfomance Branch, DSI THRU:
D. Fieno, Section Leader Reactor Physics Section Core Perfomance Branch, DSI l
SUBJECT:
MEETING WITH BNL ON AUGUST 28 & 29, 1980 ON PHYSICS TECHNICAL ASSISTANCE M. Dunenfeld visited BNL on August 28 and 29 to discuss progress on the Physics Technical Assistance program. Discussions were held with D. Diamond, J. Carew and M. Levine, with M. Todosow, L. Eisenhart, A. Aronson, D. Cokinos, S. Cheng, M. Zentner, D. Safier and P. Neogy in attendance as appropriate.
A detailed outline of the topics discussed, progress and future activities is enclosed.
Of particular interest is the work done by D. Safier from Israel. He has been working at BNL for the summer only. He has performed calculations trying to describe the characteristics of the North Anna Cycle 1 and 2 tilts.
Impressive is the number of calculations he has done in so short a time.
Although he has looked at everything we can think of, there is no real explanation of what is going on. Data from the end of Cycle 2 and study of the report being prepared perhaps will provide insight for further analyses.
s NYdf t
c M. Dunenfel Reactor Physics Section Core Perfomance Branch Division of Systems Integration
Enclosure:
As stated
.t CALCULATION OF RADIATION EMBRITTLEMENT Current Activities (July-August,1980)
I.
Review of Maine Yankee /Battelle dosimetry analysis underway II.
Review of Westinghouse Point Beach dosimetry analysis undenvay III. Analysis of PCA pressure vessel dosimetry benchmark experiment a) Using ANISN, collapsed 100 group EPR library to 16 groups for each zone and fuel type. Compared results of 100 group ANISN and 16 group ANISN runs to determine adequacy of group struc-ture.
b) Constructed one-dimensional DDT tnodel similar to ANISN mcdel.
Compared results of ANISN and DDT runs to insure ANISN cross section worked well in 00T.
c) Using 100 group ANISN flux, collapsed ENDF/B-V dosimetry cross section to 16 groups for each detector location.
d) Preliminary calculation of reaction rates using ANISN fluxes and comparison with other results.
e) Constructed two-dimensional (x,y) and (x,z) 00T models - source normalization and power distribution 'of PCA core.
Future Activities (September-October,1980)
I.
Analysis of PCA Experiment a) Perform DDT calculations b) Calculate measured activation rates c) Compare SNL results with measurement and PCA blind test results.
REACTOR CORE ANALYSIS / RELOAD REVIEW SUPPORT Current Activities (July-August,1980)
I.
Ft. Calhoun Rod Shodowing Analysis a) Using ANISN, collapsed 100 group EPR library to 16 groups. Com-pared results of 100 group ANISN and 16 group ANISN runs to de-termine adequacy of group structure.
b) Constructed 1-and 2-dimensional DDT models similar to ANISN model. Compared ANISN and 00T results to insure ANISN cross sections worked well in DDT.
c) Used several different calculational options available in DOT to determine optimum mode.
d) Constructed 2-dimensional R-G model of octant of Ft. Calhoun core / shield configuration.
e) Obtained weights and fuel assembly powers from Exxon for use as input and comparison.
f) DDT 3.5 was expanded to enable use of large R-G model.
g) Wrote program to calculate point wise power distribution for input to 00T.
II.
Reload Review - Review of Brunswick-1 (Cycle 3) Reload Submittal Planned Activities (September-October, 1980).
I.
Ft. Calhoun Rod Shadowing Analysis a) Determine fuel assembly ex-core weights b) Using fuel assembly powers provided by Exxon, determine ex-core instrumentation response c) Develop R-Z model of Ft. Calhoun d) Determine axial weights II. Reload Review - On Call Assistance 1
REACTOR PHYSICS SUPPORT (RELOADS)
Current Activities (July-August,1980)
I.
NES Fuel Storage Rack Design for IP-2 a) Review of experimental benchmarks completed i
b) PNL experiments selected for analysis c) Preliminary model of geometry set up with SAM-F II. A review of Duke Power's Oconnee reload methodology was done and comments transmitted to the staff.
III. A meeting was attended at which Exxon presented its BWR calculational methodology to the staff.
IV. Pressure Pulse in BWR Rod Drop Accident a)
Initial calculations using BNL-TWIGL and RELAP-38 completed b)
Iterated calculatic.,s using P(t) determined from initial cal-culations (Item a) underway V.
Detector core monitoring system program implemented Planned Activities (September-October,1980)
I.
NES Fuel Storage Rack Design for IP-2 a) Benchmark SAM-F Monte Carlo calculations of the PNL facility b) Perfor= SAM-F calculation for the reference NES configuration II. RDA Pressure Pulse memo to be issued I I.
Detector test problems will be executed CORE TRANSIENT ANALYSIS Current Activities (July-August,1980)
I.
" Scram with stuck rod" transient has been followed with itEKIN to nearly ccaplete control rod intertion. Graphs are being generated to follow various parameters as a function of time.
Planned Activities (September-October,1980)
I.
Results of the PWR 3-D space-time kinetics study will be documented.
A part of the transient will be redone in the point kinetics approx-imation to allow a comparison of 30 and OD results.
REACTOR PHYSICS CODE ACCEPTANCE CRITERIA Current Activities (July-August,1980)
I.
A critical lattice at the KRITZ facility has been modeled using EPRI-CELL /P0Q07-II. The results have been documented in a memo dated August 21, 1980.
Planned Activities (September-October,1980)
None
~
PREPARATION OF DATA SETS FOR STATIC AND TRANSIENT ANALYSIS Current Activities (July-August,1980)
I.
CASMO validation for QC-1 fuel.
Equivalence with CPM established.
Work documented.
II. QC-1 Cycle 2 fuel data generation. M0, 7x7 and 8x8 reload assem-blies.
2 III.
SIMULATE testing IV. QC-1 Cycle 1 simulation report. Typing and proofreading completed.
Planned Activities (September-October,1980)
I.
Data Sets a) SIMULATE (i) Complete testing of major options b) SIMJLATE for QC-1 Cycle 2 (i)
Input data generation (ii) BOC-2 code normalization (iii) Simulation of Cycle 2 operation c) M02 pin cell with CASM0/ CPM vs. HAMMER LICENSING SUPPORT CALCULATIONS (Study on Power Tilting Effects in North Anna Unit #1 Cycle 1 & 2 (NICI and NIC2))
Current Activities (July-August,1980)
The following effects were considered as possible causes for asymetric power distributions:
- 1) Control rod misalignment (Bank D)
- 2) Temperature maldistribution due to nonunifommixing in the lower plenum and one of the primary icops having lower entrance temperatures 3)
Increased (reduced) reflection - increased albedo
- 4) Difference in fuel assembly enrichment
- 5) Misplaced fuel assembly
- 6) Partial flow blockage
- 7) Partial flow increase in some channels
- 8) Higher k, of one subassembly due to a variety of reasons
- 9) Lower k, of one subassembly due to a variety of reasons EPRI-NODE-P has been changed to permit (a) a different inlet temperature at the entrance to each subassembly, and (b) quadrant tilt to be ca'culated di-rectly for any of the core state variables.
All the above cases were simulated for NAC1 at different power levels and for EU cf up to 16 GWD/MTU with N00E-P. The following was observed:
- 1) Tilt decreases with increasing power
- 2) Tilt is wiped out as core BU increases The first observation is consistent with the measurements made at North Anna; the seccnd, however, is not.
1 Planned Activities (September-October,1980)
Cycle 2 calculations will be repeated with a better core representation in order to see if the model can duplicate the data. A report will be written.
OFF-CENTER ROD OROP ACCIDENT Current Activities (July-August,1980)
A work plan was drawn up outlining the calculations to be done with the RAMONA-III code.
Planned Activities The cross sections set (BOL BWR/4) used in the BNL-TWIGL study of CRDA is to be input into RAMONA-III.
The code will be initialized at HIP.
Center and off-center rod drops will be calculated.
REACTOR PHYSICS Current Activities (July-August, 1980)
I.
SAM-CE Implementation SAM which were recently converted to the 7600 by NN 4
RESEND, LINEAR and SIGMAl programs is being perf Independent II. RCP01 Implementation 1)
Preproduction version of the Advanced File Manager has been i
implemented on our 7600.
i E) format to a random access file usi~ng the A.F.M. Pr 3)
Cata base retrieval routines written and tested for use in i
RCPLl.
4)
The gecmetry plotting package was converted for use at BNL but is not thoroughly debugged.
Planned Activities (September-October, 1980)
I.
t N-CE Implementation The data generated by SIGMAl for U-235 and further processed by the SAM-related programs /or U-238 at 300 K will be for use in SAM-F.
inorde5t 98"*"*te dot
- cessed through the appropriate codes for use in SAM-F.In additi will then be ccmpared to the data currently on the SAM libraries to The resultant data vide assurance that (1) the converted processing codes are operat data for use with SAM-F, and/ce be able to check 3
II. RCP01 Implementation a)
Execute RCPL1 with the data base retrieval routines b)
Form a cross section library for the TRX isotopes t
c) Execute TRX Monte Carlo on RCP01 d)
Finish installing geometry plotting in RCP01.