ML20137D117
| ML20137D117 | |
| Person / Time | |
|---|---|
| Issue date: | 03/20/1997 |
| From: | Craig C NRC (Affiliation Not Assigned) |
| To: | Matthews D NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9703260019 | |
| Download: ML20137D117 (32) | |
Text
March 20, 1997 0
MEMORANDUM T0: David B. Matthews, Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Claudia M. Craig, Senior Project Manager Original Signed By:
Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF MEETING WITH WESTINGHOUSE TO DISCUSS MECHANICAL MODEL ASSOCIATED WITH THE INCOMPLETE R0D CLUSTER CONTROL ASSEMBLIES (RCCA) INSERTION ISSUE The subject meeting was held at the Nuclear Regulatory Commission (NRC) offices in Rockville, Maryland on February 19-20, 1997, between representatives of Westinghouse and the NRC staff.
The purpose of the meeting was for Westinghouse to discuss in detail the mechanical model associated with the incomplete RCCA issue. Attachment 1 is a list of meeting participants.
Prior to the meeting the staff sent Westinghouse a list of areas of interest to be discussed at the meeting. The list is included as Attachment 2.
The meeting was closed to the public due to the proprietary nature of the information being discussed with regard to the mechanical model.
However, by letter dated February 26, 1997, Westinghouse submitted both proprietary and non-proprietary versions of the presentation material. Attachment 3 is a copy of the non-proprietary version of the presentation material.
Westinghouse provided the staff with an overview of the different fuel assembly designs, and discussed the model and its development, including the history of the issue beginning with the events at South Texas and Wolf Creek.
Westinghouse discussed examples and provided the staff with the results for particular behaviors using the model. Westinghouse also discussed the validation of the model and future actions they will be taking. Westinghouse would like to use the model with plant-specific data as a predictive tool to determine susceptibility of fuel assembly bowing under specific conditions.
The items in Attachment 2 were also discussed.
By letter dated February,
1997, Westinghouse submitted both proprietary and non-proprietary versions of the presentation material. is a copy of the non-proprietary version of the presentation material.
Attachments: As stated cc w/atts:
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March 20. 1997 V
MEMORANDUM T0:. David B. Matthews, Chief Generic Issues and Environmental 4
Projects Branch t
1
. Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Claudia M. Craig, Senior Project Manager 1]Ld g j Generic Issues and Environmental Projects Branch
(
l Division'of Reactor Program Management l
' Office of Nuclear Reactor Regulation
SUBJECT:
SUfMARY OF MEETING WITH WESTINGHOUSE TO DISCUSS MECHANICAL I
MODEL ASSOCIATED WITH THE INCOMPLETE R00 CLUSTER CONTROL-ASSEMBLIES (RCCA) INSERTION ISSUE 4
[
The subject meeting was held at the Nuclear Regulatory Commission (NRC)
J offices in Rockville, Maryland on February 19-20, 1997, between
. representatives of Westinghouse and the NRC staff. The purpose-of the meeting was for Westinghouse to discuss-in detail the mechanical model associated with the incomplete RCCA issue. Attachment 1 is a list of meeting participants.
j Prior to the meeting the staff sent-Westinghouse a list of areas of interest to be discussed at the meeting. The list is included as Attachment 2. : The meeting was closed to the public due to the proprietary nature of the information being discussed with regard to the mechanical model. However, by-
.[
1etter dated February 26, 1997, Wcstinghouse submitted both proprietary and-F
.non-proprietary versions'of the presentation material. Attachment 3 is a copy of the non-proprietary version of.the presentation material.
i Westinghouse provided the staff with an overview of the different fuel 1-
< assembly designs, and discussed the model and its development, including the history of the issue beginning with the events at. South Texas and Wolf Creek.
Westinghouse discussed examples and provided the staff with the results for particular behaviors using the model. Westinghouse also' discussed the validation of the-model and future actions they will be taking. Westinghouse
.would.like to use the model with plant-specific. data as a predictive tool to l
determine susceptibility of fuel assembly bowing under specific conditions.
i The items in' Attachment 2 were also discussed.
7 v
i l
Attachments: As stated l
cc w/atts:
See next page i-(
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l WESTINGHOUSE / NRC MEETING MECHANICAL MODEL FOR INCOMPLETE RCCA INSERTION ISSUE FEBRUARY 19-20, 1997 i
MEETING PARTICIPANTS NAME ORGANIZATION Claudia Craig NRC/NRR/PGEB Rick Kohrt Wisconsin Electric V. J. Esposito Westinghouse Dennis D. Davis Westinghouse Howard Menke Westinghouse Jim Sparrow Westinghouse Jim Reavis Westinghouse J. Rajan NRC/NRR/EMEB Frank Grubelich NRC/NRR/DE/EMEB H.F. Conrad NRC/NRR/DE/EMCB Muffet Chatterton NRC/NRR/SRXB H.L. Ornstein NRC/AE0D Harold H. Scott NRC/RES m
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~ Areas of Interest for the February 19-20, 1997 Meeting Validation of the Model a
Load tests of the skeleton (guide tubes and grids)
What restricts ' total growth of the fuel assembly between core plates and between grid attachments l'
Detail explanation of why there is sufficient clearance at E0C How the discontinuities in the guide tube are addressed Details of previous structural analysis of fuel assemblies and how this 1
model differs from previous analysis How the model is tested against actual results Design detail information including drawings and figures Sensitivity studies - particularly on temperature, holddown forces, creep t
and fuel assembly growth Details of the oxide growth model as it relates to the input to the mechanical model with respect to the relationship between temperature and power history.
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Westinghouse Non Proprirtary Class 3 b
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Pmsentation to the NRC:
" Fuel Assembly Mechanical Model Associated with Incomplete Rod Cluster Contml Assembly (RCCA) Insertion" February 19-20, 1997 01997 Westinghouse Electric Corporation All Rights Reserved
Westinghouse Propsg f
NRC AGENDA (2/19-2/20)
?
r Fuel Assembly Familiarization Sparrow e
Discussion of Fuel Assembly Configuration, Pans Nomenclature Connections, etc. General Discussion on Manufacturing Process & Methods (Some Parts. Sketches, Drawings will be Helpful.
Fuel AssemblyTypes Sparrow Key Features Differences / Nomenclature r
General Metheds Development Plan Menke e
"GRBOW" Rev. 0 "GRBOW" Rev. I FEM "GRBOW" Physical Phenomena Represented Reavis l
e Fuel Rod Growth 7
Corrosion Irradiation Growth Reavis Input Dimensions Material Characteristics Reavis Model Assumptions Code Methodology Output Menke/Reavis Comparisons with Field Data e
Address only Plant Data Questions Davis / Sparrow e
Address only Hot Cell / Field Data Davis / Sparrow e
MW.KRC AGENDA.HFM.Page 1 of i
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