ML20147E455
| ML20147E455 | |
| Person / Time | |
|---|---|
| Issue date: | 09/21/1978 |
| From: | Odar F Office of Nuclear Reactor Regulation |
| To: | Fabic S NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML20147E439 | List: |
| References | |
| NUDOCS 7812210084 | |
| Download: ML20147E455 (4) | |
Text
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c 4p UNITED STATES y 4 NUCLEAR REGULATORY COMMISSION
% o WASHINGTON, D. C. 20555 E
((* SEP 21 1978 NOTE T0: S. Fabic, Chairman, Code Selection Committee FROM: F. Odar, Analysis Branch, DSS
SUBJECT:
CODE SELECTION Enclosed is my evaluation of the three codes for the LOCA analysis only. The scores will be different if non-!.0CA transients are considered since the requirements for the analysis of these transients are different from those for the LOCA.
For the LOCA analysis the sumary of thc scores is TRAC RELAP5 THOR 11.0 112 105 Hence, my recommendation will be that the TRAC code should be selected for the LOCA analysis.
The scoring was based on the list of items enclosed in your letter of September 3, 1978. Each item in the list was scored between 0 and 10.
The details of the scoring for each item are presented in the enclosure.
For the analysis of system transients two separate improved codes (PWR and BWR) are needed by 1984-1985. Another BWR system transient I code is needed to satisfy the requirements for audit calculations in l the short term (1979 or 1980). I recommend that these transient codes j should be developed, h4W hk Fuat Odar Systems Anaiysis Section Analysis Branch Division of Systems Safety cc: Z. Rosztoczy, OSS W. Paulson, NRR 9 I N. Lauben, DSS % t.
N. Zuber, RSR g7Chvfg 4 L. Shotkin, RSR A SEP #
- 11. Lyon, RSR C 2# 0 78 I:#
F. Odar, DSS e z
Contact:
F. Odar, NRR, X27911 p rg812210d d
l l Enclosure Item Scores TRAC RELAPS TH0R ,
Ct.rrent Capabilities
- 1. Modeling of thermal & hydraulics 8 8 8
- 2. Geometric description; adaptability 8 8 8
- 3. Neutronics 5 5 5 ,
- 4. Computation Efficiency 5 5 5 ,
. 5. Verification 8 5 1 -
Total for current capabilities 31 28 24 I
l N
4 0
o ,
TRAC RELAP5 TH0R Adaptability _
8 8 8 i-
- 1. S.G. Tube Break 8 8 8 2.
SLBA Alternate ECCS (e.g. UHI) 8 8 8 3.
8 8 3
- 4. PWR LOCA-EM 8 8 8
- 7. RIA 8
6
- 8. Operational Transients 7 57 56 56 Total v
s 4
4 l
r J ... . .
L_._.______ .
Assessment of Code Development Team and Facility TRAC RELAPS THOR
- 1. Record of past performance 10 8 1
- 2. Knowledge of information obtained in reactor safety research 8 8 8
- 3. Personnel Port Access 6 6 8
- 4. Computer Access 8 6 8 Total: 32 28 25 Overall Scores: 120 112 105
- - - - . - . - - _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ __________ ______