ML19210B190
| ML19210B190 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/20/1974 |
| From: | Stratton W Advisory Committee on Reactor Safeguards |
| To: | Ray D US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19210B184 | List: |
| References | |
| NUDOCS 7911040118 | |
| Download: ML19210B190 (4) | |
Text
APPENDIX.B
~
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS UNITED STATES ATOMIC ENERGY COMMISSION WAsHINCTON. D.C. 20'A3 lionorable Dixy Lee Ray Chairman U. S. Atomic EncrCy Co::r.ission Washington, D. C. 20545 u
Subject:
REPORT ON EVAi,UATIO'd MODELS FOR COMMISSION CRITERIA FOR EMERCENCY CORE COOLING SYSTi'MS FOR LICliT-WATER-COOLED NUCLEAR POWER REACTORS
Dear Dr. Ray:
At its 175th meeting, November 14-16, 1974, the /sdvisory Con nittee on Reactor Safeguards completed a review of Evaluation'Models which have been submitted in accordance with the Coc=tission criteria set forth in 10 CFR 50.46.
The following subcor.r.ittee ecctings with reactor vendors'wcre held in Washington, D. C. : March 23, 1974, Babcock and Wilcox; April 25, 1974, General Electric Company; April 26, 1974, Westin&housa Electric Corporation; and l'ay 13, 1974, Cambustica Engineering, Inc.
Subec.r.ittec.ccctings wcra held with the Regulatory Staf f and their consultadts in Washington, D. C.,
on August 6, 1974, September 28, 1974 and October 26, 1974. The Co-aittee also had the benefit of the docu=cnts listed below.
Previous reports to the Commission on interim acceptance critcria were made on January 7, 1972, and on the proposed changes on September 10, 1973. The.Co.--.ittee has also addressed the safety research programs and the latest report is on November 20, 1974.
The ACRS believes that the four light-water reactor vendors have developed Evaluation ::odels which, with the additional modifications required by the Regulatory Staff, will conform to^ Appendix K to Part 50.
Approved Evaluation Models will aid in conducting the licensing reviews,.
but a variety of specifics must be evaluated on a case-by-case basis. ' Items such as the particular features of a containment, sequencing of operations, single failure analysis and special features of the reactor design, are noted in the Staff's review of the vendor codels. Additional items involving peaking factors and treatment of the uncertainties in the power distributions and monitoring of the power levels remain to be, incorporated, case-by-case, in the Technical Specifications with appropriate conservatism.
En3Gr IU' 20.,0so OE : h lid 02 A04 FL 1 c; c.7 1 c 6 o
a G.,...., A. l o,
=,.: :u.
Ilono'rable Dixy Lee Rr'
~2-Move:nber 20, 1974 s.
T$c generic review of the ven' dor models proposed for Appendix K, like the reviews of the Interita Acceptance Criteria codels, has contributed to irproved understanding cif the modeling techniques, including the applicability and limitations on current knowledge of thermal and hydraulic phenonena, and the need for more definitive safety research programs and code developacnts. The icplcncatation of safety research programs, noted, in the Comittcc's (November 20, 1974) report, and their results should have impact on the future evaluation methods and ECC systems.
The ACRS remains mindful that the Evaluation Models, in themselves are not the desired end products, but that effective, reliable emergency core cooling systems are the objective.
The Comittee acknowledges the contri-bution to reduced peak clad temperatures resulting fro:a tecent core design changes but reaffir.s its. position stated in the September 10, 1973 report that i:nproved ECCS reliability and capability sho.uld continue to be sought and, to the extent practical, cmployed.
Sincerely your's,
~b 4
f,
/v NA U..R.
Stratton Chairman References Attached.
D D
- D
~3~
M' l }l/L i
oo o
15.u7 157
3 m
Honor,able Dixy Lc_c Ray
~3 Novemocr 20, 1974 ma m
9 ',
D 3.
References
_ Wc W
- 1) UCAP-S170 (P) dated June 1974, " Calculational Model for Core Reflooding Af ter a Loss-of-Coolant Accident"
- 2) UCAP-S200 (Rev. 2 (P)) dated June 1974, "WFLASH - A Fortran - IV Computer Program for Simulation of Transients in a Multi-Loop P'n'R"
- 3) UC/J-8301'(P) dated June 1974, "LCCTA - IV Program Loss-of-Coolant Transient Analysis"
- 4) UCAP-S302 (P) dated June 1974, " SATA!! IV Program: Comprehensive Space-Time Dependent Analysis of Loss-of-Coolant"
'5) WCAP-5327 (P) dated July 1974, " Containment Pressure Analysis"
- 6) UCAP-6339 (NP) dated June 1974, " Westinghouse Emergency Core Cooling System Evaluation Model, Summary"
- 7) UCAP-S340 dated July 1974, " Westinghouse ECCS - Plant Sensitivity Studics"
- 8) WC/2-5341 (P) dated July 1974, " Westinghouse Emergency Core Cooling System Evaluation Model Sensitivity Studies"
- 9) UCAP-8354 (P) dated July 1974, "Long Tem Ice Condcascr Containment Code -
1/3 TIC Code" 10)
DAU-10091, "B&U's ECCS Evaluation Model Report with Specific Application to 177 FA Cless Plancs with Lowcred Loop Arrangement," Augu:t 1974
- 11) DAV-10092, CRAFT 2 - Fortran Program for Digital Simulation of a Multinode Reactor Plant During Loss-of-Coolant," July 1974
- 12) BAU-10093, "REFLOOD - Description of Model for Multinode Core Reflood Analysis," July 1974
- 13) BAW-10094, " Revisions to THETA 1-B, A Computer Code for Nuclear Reactor Core Thermal Analysis," IN-1445, July 1974 14)
BAU-10095, " CONTEMPT - Computer Program for Predicting Containment Pressure-Temperaturc Response to a Loss-of-Coolant Accident," July 1974-
- 16) CENPD-134 (P) April 1974, "COMPERC-II, A Program for Emergency Refill--
Reflood of the Corc"
- 17) CENPD-135 (P) April 1974, "STRIKIN-II, A Cylindrical Geometry Fuct Rod Heat Transfer Program"
- 18) CENPD-136 (P) July 1974, "High Temperature Properties of Zircaloy and UO2 for Use in LOCA Evaluation Models"
- 19) CEN?D-137 (P) August 1974, " Calculative Methods for the CE Small Break.
LOCA Evaluation Model"
- 20) CENPD-138 (P) April 1974, " PARCH - A Fortran,IV Digital Computer Progra:n to Evaluate Pool-Boiling Axial Rod and Coolant Heatup"
- 21) CENPD-139, "CE Fuel Evaluation Model (FATES Thermal Performance and Densification Model)"
- 22) NEDO-20566 (BRAFT) (P)
"Ccacral Electric Analytical Madcl for Loss-of-Coolant Analysis in Accordance with 10 CFR 50 Appendix K"
'23) S.atus Report By The Directorate of Licensing In The Matter Of Sabcock and Wilcox ECCS Evaluation Model Conformance To 10 CFR 50, Appendix K (ondated) 19a7 153
- Honorable Dixy Lee Ray
'l goyet,]r 20, 1974 24)\\- Supple =ent 1 To The Status Report By The Directorate of Licensing' In The Matter of Babcock And Vilcox ECCS Evaluation Model Confornance To 10 CFR 50, Appendix K, November 13, 1974 25)
Status Report By The Directorate Of Licensing In The Matter of Combustion Engineering, Inc. ECCS Evaluation Model Confor=ance To 10 CFR 50, Appendix (undated) 26)
Suppic= cat To The Status Report By The Directorate Of Licensing In The Matter Of Combustion Engineering, Inc. ECCS Evaluation Model Confor=ance To 10 CFR 50, appendix K, November 13, 1974 27)
Status Report By The Directorate Of Licensing In The Matter of General Electric ECCS Evaluation Model Conformance To 10 CFR 50, Appendix K (undated) 28)
Supple = cat 1 To The Status Rcport By The Directorate Of Licensing In The Matter of Cencral Electric ECCS Evaluation Model Confor=ance To 10 CTR 50, Appendi:< K, Nove=ber 13, 1974 29)
Status Report' By The Dircatorate Of Liccasing.;In The Matter Of Westinghouse Electric Conpany ECCS Evaluation Model Conformance To 10 CFR 50, Appendix K (undated) 30)
Supplcr.ent To The Status Report By The Directorate of Licensing In The Hatter of Westinchouse Electric Conpany.ECCS Evaluation Model Confor:.ance To 10 CFR 50, Appendix K, November 13, 1974
- 31) WREP.: Water Reactor Evaluation Model, October 1974, Regulatory Staff-Technical Review
- 32) Water Reactor Evaluation Model (k2EM): Pk"A Nodalization And Sensitivity Studics, October 1974, Regulatory Staff-Technical Review 33)
Vater Reactor Evaluation ::odel (k7.IM): SVR Nodalization And Sensitivity -
Studics, October 1974, Regulatory Staff-Technical Review 34)
Evaluation Of LOCA Hydrodynamics, Nov'c=ber 1974, Regulatory Staff-Technical Review e
9 e
T esm=
) j -l
\\J 7
9 e
.