ML19211C548
| ML19211C548 | |
| Person / Time | |
|---|---|
| Issue date: | 08/23/1979 |
| From: | Triplett M NRC COMMISSION (OCM) |
| To: | |
| Shared Package | |
| ML19211C549 | List: |
| References | |
| CON-FIN-A-3318-9, REF-GTECI-A-03, REF-GTECI-SG NUDOCS 8001110664 | |
| Download: ML19211C548 (9) | |
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0/ 173 U S. NUCL L A R REGULATOM Y COMM'SSION O R O L R P. L '/ H L R t
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20-79-152 STANDARD ORDER FOR DOE WORK August 23, 1979 j_
..~ v L D 10 IDOL Of f.cel ISSUED BY: (NRC Of fice)
ACCDUNTING CIT ATION s n 3
20$.509 Chicago Operations Office N
le R ac or B&R NUMBER Demel a t 4 nn
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PERFORMING ORGANIZATION AND LOCATION 20-19-03-01-2 FIN NUMBER Brookhaven National Laboratory, Upton, N.Y.
11973 A3318 -9 WORK PERIOD THis ORDER FIXFD 0 ESTIM ATED O FIN TITLE ATWS Audit Calculations hl[79
$31/80 OBLIGATION AVAILABILITY PROVIDED BY:
A. THIS ORDER S 100.000
~B.
TOTAL OF ORDERS PLACED PRIOR TO THIS DATE WITH THE PERFORMING ORGANIZATION
' ^ '
' " ^ "
YTA"NU 3,148,000 B
Cl E
C. TOTAL ORDERS TO DATE (TOTAL A & B) 5 3,248,000 D AMOUNT INCLUDED IN "C" APPLICABLE TO THE " FIN NUMBER" CITED IN THIS ORDER.
S 100,000 FINANCI AL FLEXIBILITY:
@ FUNDS WILL NOT BE REPROGRAMMED BETWEEN FINS. LINE D CONSTITUTES A LIMITATION ON OBLIGATIONS
' AUTHOR IZ E D.
O FUNDS MAY BE REPROGR AMMED NOT TO EXCEED 110% OF FIN LEVEL UP TO $50K. LINE C CONSTITUTES A LIMITATION ON OBLIGATIONS AUTHORIZED.
STANDARD TERMS AND CONDITIONS PROVIDED DOE ARE CONSIDERED PART OF THIS ORDER UNLESS OTHERWISE NOTED.
ATTACHMENTS:
THE FOLLOWING ATTACHMENTS ARE HEREBY SECURITY:
MADE A PART OF THIS ORDER:
h WORK ON THIS ORDER IS NOT CLASSIFIED.
@ STATEMENT OF WCRK O WORK ON THis ORDER INVOLVES CLASSIFIED
@ ADDITIONAL TERMS AND CONDITIONS INFORMATION. NRC FORM 187 IS ATTACHED.
AFTER SIGNATURE, PLEASE SEND A COPY OF THIS ORDER TO M. PAULETTE TRIPLETT, NRR, P-428 ISSUING AyTHORITY ACCEPTING ORGANIZATION J
SIGNATURE SIG N ATt* RE M.P.Triplett/f) g&_,
TITLE TITLE I/13/77 -
Fiscal Assistant DATE NRCFORM 173(2 78) 1740 065
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STATEMENT OF WORK
Title:
ATWS Audit Calculations FIN No.: A-3318 B&R No.: 20-19-03-01-2 Technical Monitors:
A. Thadani, 492-7341, F. Odar, 492-7911 Cognizant Branch Chief:
T. P. Speis, 492-7359 Purpose of Program This program is designed to obtain expert technical assistance in developing the technical bases for a staff position for the ATWS rulemaking hearing and for ATWS impact assessment for THI-2.
General Information Audit calculations for selected ATWS events will be performed utilizing exist-ing computer codes and PWR and BWR initial decks available at Brookhaven National Laboratory.
TASK 1 - PWR AUDIT CALCULATIONS
Background
Occurrence of the TMI-2 accident indicated that systems transients may lead to a small LOCA and a core uncovering coupled with shutdown problems. While previous ATWS audit calculations were performed to evaluate the overpressurization effects which occur for a short time in the beginning of the transient, the aspects of core uncovering and boiling in the primary system were overlooked.
The TMI-2 accident also proved that ATWS audit calculations must cover some failures which impact consquences, such as: stuck open valve; delay in auxiliary feedwater; and, reduction in feedwater. Also, the inadvertent opening of a safety or relief valve is an anticipated transient which may have significant consequences and must be analyzed.
Objectives The objectives of this task are: (1) to establish the validity of the vendors codes used in ATWS anlayses in de went of boiling (2) to perform audit calculations in the primary system, and if there is boiling, the effects of core uncovering; to' establish the sensitivities of ATWS event failures.
1740 0.66
. Work Requirements Using the IRT and RELAP3B codes, perform the following) analyses for the Trojan (Westinghouse), Calvert Cliffs (Combustion Engineering and Oconee (Babcock and Wilcox) nuclear power plants.
(a) Loss of feedwater with stuck open valve (b) Loss of offsite power with stuck open valve For each of these two transients, calculate the following five cases:
(1) Base case - 95% moderate temperature coefficient and homogeneous equilibrium discharge model (without factot-of 0.9) for the stuck open valve.
(2) 99% moderator temperature coefficient.
(3) Time delay (to be specified by the staff) in auxiliary feedwater and reduce auxiliary feedwater by 50%.
(4) Use factor of 0.9 on homogeneous equilibrium discharge model from the stuck open valve.
(5) Use different HPSI head curve (to be specified by the staff).
Scheduled Milestone This task should be completed by March 1,1980.
TASK 2 - BWR AUDIT CALCULATIONS Sub-task 2.1 - Short-term Calculations
Background
peach Bottom tests showed that steam line dynamics and space-time Linetics were important factors in predicting overpressurization events. The previous calcu-lations performed by GE utilizing the REDY code did not model these two aspects.
Previous ATWS audit calculations performed by the staff also did not model these two aspects.
Objective The objective of this sub-task is to obtain the results of overpressurization events using steam line dynamic and space kinetics.
1740 OA7
. !!o_ r_k_F; equi remen ts Using the BNL/TWIGL and RELAP3B computer codes or the RAMONA III computer code, if available, perform audit calculations for ATWS events: turbine trip without bypac; and MSIV closure for BWR (Peach Bottom) E0C2 conditions.
(a) Perform these cal ulations on a short-term basis, i.e., one minute of transient time and evaluate the effects of steam line dynamic and point kinetics (b) Calculate other quantities such as neutron flux, heat flux and pressure and evaluate the results.
Scheduled Milestone uramber This sub-task should be completed bypi!Tr 1,1979.
_Sub-task 2_.2_ - Long-Term Calculations B_ackground Previous audit calculations did not extend long enough to verify GE calculations for long term behavior.
The effectiveness of the fix, " Boron reactivity feed-back" was never evaluated. Also, the long-term energy releases are important to evaluate torus behavior.
Since the frequency and duration of the opening of the valves are governed by the effectiveness of the fix and the dynamics of the steam line, long-term calculations must be performed.
Objective The objective of this sub-task is to evaluate the long-term behavior of the core and evaluate the effectiveness of the boron fix.
Work Requirements Perform the same calculations as in sub-task 2.1 on a long-term basis, i.e.,10 minutes of transient time and evaluate the effects of boron injection and frequent actuation and closure of relief valves.
Scheduled Milestone This sub-task should be completed by March 1,1980.
Level of Effort and Period of Performance The estimated level of effort is 1.5 man-years over a 6 month period (September 1, 1979 to March 1, 1980).
1740 068
4 Reporting Eequirements (1) The contractor shall provide a plan of work and methodology to the Cognizant Branch Chief.vithin 4 weeks after acceptance of this work order. The plan shall establish and identify a set of project mile-stones accompanied by a brief narrative description.
(2) A brief monthly busines's letter report is to be submitted by the 15th of the month to the Cognizant Branch Chief with a copy to the Director, Division of Systens Safety, ATTN:
B. L. Grenier.
These reports will contain:
- A listing of any efforts completed during the period; milestones reached, or if missed, an explanation provided.
- The amount of funds expended during the period and cumulative to date.
Note: The first month letter report should contain the planned monthly rate of expenditure.
- Any problems or delays encountered or anticipated.
Note:
Submit a proposed resolution of the problems including the schedule for resolution.
- A summary of the progress to date.
- Plans for the next reporting period.
(3) At the completion of each sub-task, a letter report shall be provided to the Cognizant Branch Chief that describes the results and the bases upon which they were obtained.
'. 4 ) At the completion of the program, a final report shall be prepared and submitted to the Cognizant Branch Chief in accordance with NRC Manual Chapter 3202. This report shall contain a summary of the results and conclusions obtained under each task and the detailed technical boses.
f e.et_i ngs_ a_nd_Tr_a ve1 j
Two meetings to Bethesda, fiaryland should be planned.
NRC Furnish.ed_fjaterials
}740 00 None.
Billing Requir_ements Vouchers submitted for payment should list expenditures for manpower and any other major items of expenditures associated with review of each individual plan.
ENCLOSURE 4 STEAM GENERATOR MODEL, MAJOR STEPS FOR IMPLEMENTATION OF CANDU BOILER CODE AND IMPROVEMENT AT BNL U-Tube Steam Generator 1.
Implementation at BNL, 2.
Detailed Review of Models l
Numerics (AECL Presentation)
Code Structure 1
3.
Decision to adopt B0lLER-2.
If yes, then 4.
Tasks as needed:
4.1 Revision of Steam Dome Model, 4.2 Level Tracking below Stean Dome and Separators, tube side shell side downcomer, 4.3 Flow Reversal (upwind differencing for V or Vh < 0).
a Investigation and correction of instability problem (may need a new numerical scheme),
4.4 Separator Model, 4.5 Condensation for primary side, 4.6 Auxiliary Feed Water Injection, 4.7 Correction of Preheater location (" rewiring of code"),
4.8 Cross-mixing in S.G. without Preheater Divider, 5.
Parallel U-Tube Flow Instability (Cross-sectional area in primary side varies with time to account for stalled U-tubes during low-flow natural circulation),
6.
U.S. UTSG Geometries and Conditions 6.1 Add necessary control systems for three vendors, 1740 070
7.
OTSG Geometries 7.1
" Rewire" code for OTSG with and without aspirator, 7.2 Auxiliary Feedwater Injection into super-heated steam, 7.3 Add necessary B&W control systems.
1740 071
ENCLOSURE 5 Comparison of Power Variation in Peach Bottom Turbine Trip Test III using two BNL models, test data and RAMONA-III code 1740 072
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