ML20141D999
| ML20141D999 | |
| Person / Time | |
|---|---|
| Issue date: | 06/27/1997 |
| From: | Wang E NRC (Affiliation Not Assigned) |
| To: | Matthews D NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9706300185 | |
| Download: ML20141D999 (17) | |
Text
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June 27, 1997
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' MEMORANDUM 10:
David B. Matthtws, Chief Generic Issues and Environmental Projects Branch i
Division of Reactor Program Management j
Office of Nuclear Reactor Regulation FROM:
Egan Y. Wang, Reactor System Engineer Original Signed By:
Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
MEETING SUMARY OF JUNE 11, 1997, REGARDING LOCA NEUTRONICS INPUT METH00S On June 11, 1997, representatives of Siemens Power Corporation (SPC) met with representatives of the Nuclear Regulatory Commission (NRC) in Rockville, MD.
The purpose of this meeting was for SPC to discuss LOCA neutronics input methods.
SPC briefly discussed background for topical report XN-75-43 (A) core physics methods and data used as input to LOCA analysis.
SPC also provided an outline of topical report XN-75-43(A) with a list of sections which describe current models and data.
In the following sections, SPC stated that CASMO, a NRC approved code is used in place of XPOSE: (1) Section 3.2, Moderator Density Feedback Reactivity, (2) Section 3.3, Doppler (fuel l
temperature) Reactivity Feedback, (3) Section 3.4, Scram and Scram Reactivity, and (4) Section 4.2, Actinide Decay Model.
NRC staff stated that if both codes are approved by NRC, there should not be a problem with using either code for the approved analysis / calculation. The staff and SPC discussed two ways of officially informing the staff of the changes in using different codes. These include: (1) revising topical report to incorporate all the changes, then submit it to NRC for approval, and (2) for each code, list all the changes, then submit it to NRC. The staff stated that since both codes have been approved, there is no need revise and submit the topical report for approval again. The staff also stated that it is prebably less time consuming for the staff to review one list of all changes for a code than several different lists of changes.
List of Attendees :
. Presentation Slides D F DS
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DISTRIBUTION: Mtg. Summary of June 11 Meeting with Siemens Power Corporation Dated June 27. 1997 l LARD COPY CentraleFile Public PGEB r/f E. Wang A. Attard 0GC ACRS E-MAIL F. Miraglia A. Thadani R. Zimmerman G. Holahan T. Martin D. Matthews F. Akstulewicz E. Kendrick A. Attard J. Lyons I
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June 27, 1997 MEMORANDUM T0:
David B. Matthews, Chief Generic Issues and Environmental l
Projects Branch Division of Reactor Program Managementi Office of Nuclear Reactor Regulation l
FROM:
Egan Y. Wang, Reactor System Engineer Generic Issues and Environmental Projects Branch Division of Reactor Program Management l
Office of Nuclear Reactor Regulation
SUBJECT:
MEETING
SUMMARY
OF JUNE 11, 1997, REGARDING LOCA NEUTRONICS INPUT METH00S I
On June 11, 1997, representatives of Siemens Power Corporation (SPC) met with representatives of the Nuclear Regulatory Commission (NRC) in Rockville, MD.
The purpose of this meeting was for SPC to discuss.LOCA neutronics input methods. SPC briefly discussed background for topical report XN-75-43 (A) core physics methods and data used as input to LOCA analysis. SPC also i
provided an outline of topical report XN-75-43(A) with a. list of sections which describe current models and data.
In the following sections, SPC stated that CASMO, a.NRC approved code is used in place'of XPOSE: (1) Section 3.2, Moderator Density Feedback Reactivity, (2) Section 3.3, Doppler (fuel temperature) Reactivity Feedback, (3) Section 3.4, Scram and Scram Reactivity, and (4) Section 4.2, Actinide Decay Model.
NRC staff stated that if both codes are approved by NRC, there should not be a problem with using either code for the approved analysis / calculation. The staff and SPC discussed two ways of officially inferming the staff of the changes in using different codes. These include: (1) revising topical report to incorporate all the changes, then submit it to NRC for approval, and (2) for each code, list all the changes, then submit it to NRC. The staff stated that since both codes have been approved, there is no need revise and submit the topical report for approval again. The staff also stated that it is probably less time consuming for the staff to review one list of all changes for a code than several different lists of changes.
List of Attendees :
Presentation Slides Attachments: As stated I
L cc w/atts: Mr. H. D. Curet, Manager l
Product Licensing Siemens Power Corporation i
2101 Horn Rapids Road I
P. O. Box 130 Richland, WA 99352-0130 i
l
NRC/SIENENS POWER CORPORATION NEETING ON LOCA NEUTRONICS INPUT NETH00S LIST OF ATTENDEES JUN 11, 1997
- NE_f, ORGANIZATION Holm, Jerry Siemens Curet, D. H.
Siemens Lyons, Jim NRC/SRXB l
Attard, Anthony NRC/SRXB Kendrick, Edward NRC/SRXB Wang, Egan NRC/PGEB Staudenmaier, Joseph NRC/DSSA Ulses, Tony NRC/SRXB ATTACHMENT 1
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l Neutronics Input to LOCA - XN-75-43(A) l
. XN-75-43 (A) Core Physics Methods and Data Used as Input to LOCA Analysis l
"This report provides a description of the Exxon Nuclear j
Company core physics methods and data used as input to
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the WREM analysis of PWRs."
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. Submitted to NRC August 1975
. Approved by NRC October 1975 l
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JSH:37:023 I
SIEMENS XN-75-43(A) Outline - Sections Which Describe Current M'odel/ Data 3.0 Fission Heat Calculation 3.1 Reactor Kinetics Model 4
3.2 Moderator Density Feedback Reactivity
- 3.3 Doppler (Fuel Temperature) Reactivity Feedback 3.4 Scram and Scram Reactivity 3.5 Power (Fission) Decay History 4
4.0 Fission Product Decay and Decay of Actinides 4.1 Fission Product Decay Model 4
4.2 Actinide Decay Model 4.3 Gamma Smearing 3
JS't97:023
SIEMENS XN-75-43(A) Outline - Sections Which Describe Current Model/ Data 5.0 Power Distribution Treatment 5.1 Limiting Axial Power Profiles 5.2 Previous Results 5.3 ENC Treatment 5.4 Power Spike Considerations 4
i l
JSH:97:023
SIEMENS l
XN-75-43(A) Section 3.2 Moderator Density Feedback Reactivity l
. CASMO used in place of XPOSE
. MTC set by Technical Specification
. Conservative value for B versus a constant =.007 JSH:97:023
SIEMENS XN-75-43(A) Section 3.3 Doppler (Fuel Temperature? Reactivity Feedback
. CASMO used in place of XPOSE f
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i SIEMENS XN-75-43(A) Section 3.4 Scram and Scram Reactivity CASMO used in place of XPOSE A 3D Nodal Code instead of PDQ
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.SIEMENS XN-75-43(A) Section 4.2 Actinide Decay Model
. CASMO used instead of XPOSE k
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SIEMENS XN-75-43(A? Section 4.3 Gamma Smearing
. CASMO 3G used instead of the codes ANISN and QAD Gamma smearing has three components
. Fraction absorbed in fuel and clad r
. Redistribution between rods within an assembly
. Redistribution between assemblies I
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SIEMENS
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. XN-75-43(A) Section 5.1 Limiting Axial Power Shapes
. XN-75-43(A)
. Approach relied on " Westinghouse Emergency Core Cooling System - Plant Sensitivity Studies," WCAP-8356, l
July 1974.
. Current Analysis
. Plant specific shapes based on analyses i
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10 JSH:97:023
SIEMENS Summary
. Neutronics guidelines to be updated to specify-procedures for developing BWR and PWR LOCA input P
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SIEMENS Additional Issues
. Gamma Smearing Factor Values
. Radiation Heat Transfer for Gadolinia Bearing Fuel Rods I
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o DISTRIBUTION: Mtg. Suasary of June 11 Meeting with Siemens Power Corporation Dated June 27. 1997 H&BD COPY Central File
- Public.
PGEB r/f E. Wang A. Attard OGC ACRS E-MAIL F. Miraglia A. Thadani R. Zimmerman G. Holahan T. Martin D. Matthews F. Akstulewicz E. Kendrick A. Attard J. Lyons
.-~ -... -.. -
June 27, 1997 MEMDRANDUM T0:
David B. Matthews, Chief A
GenGric Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation i
FROM:
Egan Y. Wang, Reactor System Engineer Original Signed Ey:
Generic Issues and Environmental Projects Branch-Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
MEETING SUNIARY OF JUNE 11, 1997, REGARDING LOCA NEUTRONICS INPUT METHODS On June 11, 1997, representatives of Siemens Power Corporation (SPC) met with representatives of the Nuclear Regulatory Commission.(NRC) in Rockville, MD.
The purpose df this meeting was for SPC to discuss LOCA neutronics input methods.
SPC briefly discussed background for topical report XN-75-43 (A) core physics methods and data used as input to LOCA analysis.
SPC also j
provided an outline of topical report XN-75-43(A) with a list of sections which describe current models and data.
In the following sections, SPC stated that CASMO, a NRC approved code is used in place of XPOSE: (1) Section 3.2, Moderator Density Feedback Reactivity, (2) Section 3.3, Doppler (fuel i
temperature) Reactivity Feedback, (3) Section 3.4, Scram and Scram Reactivity, and (4) Section 4.2, Actinide Decay Model.
j NRC staff stated that if both codes are approved by NRC, there should not be a problem with using either code for the approved analysis / calculation.
The staff and SPC discussed two ways of officially informing the staff of the changes in using different codes. These include: (1) revising topical report 1
to incorporate all the changes, then submit it to NRC for approval, and (2) for each code, list all the changu, then submit it to NRC. The staff stated that since both codes have been approved, there is no need revise and submit
)
the topical report for approval again. The staff also stated that it is probably less time consuming for the staff to review one list of all changes for a code than several different lists of changes. :
List of Attendees :
Presentation Slides j
Attachments: As stated i
cc w/atts: Mr. H. D. Curet, Manager Product Licensing Siemens Power Corporation 2101 Horn Rapids Road P. O. Box 130 Richland, WA 99352-0130 DISTRIBUTION:
See attached page Document name: 970611-1. SUM Nf kh oFC PGEB C_{
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June 27, 1997 MEMORANDUM TO:
David B. Matthews, Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Egan Y. Wang, Reactor Systom Engineer Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
MEETING SUMARY OF JUNE 11, 1997, REGARDING LOCA NEUTRONICS INPUT METHODS On June 11, 1997, representatives of Siemens Power Corporation (SPC) met with representatives of the Nuclear Regulatory Commission (NRC) in Rockville, MD.
The purpose of this meeting was for SPC to discuss LOCA neutronics input methods. SPC briefly discussed background for topical report XN-75-43 (A) core physics methods and data used as input to LOCA analysis.
SPC also provided an outline of topical report XN-75-43(A) with a list of sections which describe current models and data.
In the following sections, SPC stated that CASMO, a NRC approved code is used in place of XPOSE: (1) Section 3.2, Moderator Density Feedback Reactivity, (2) Section 3.3, Doppler (fuel temperature) Reactivity Feedback, (3) Section 3.4, Scram and Scram Reactivity, and (4) Section 4.2, Actinide Decay Model.
NRC staff stated that if both codes are approved by NRC, there should not be a problem with using either code for the approved analysis / calculation.
The staff and SPC discussed two ways of officially informing the staff of the changes in using different codes.
These include: (1) revising topical report to incorporate all the changes, then submit it to NRC for approval, and (2) for each code, list all the changes, then submit it to NRC.
The staff stated that since both codes have been approved, there is no need revise and submit the topical report for approval again.
The staff also stated that it is probably less time consuming for the staff to review one list of all changes for a code than several different lists of changes. :
List of Attendees :
Presentation Slides Attachments: As stated cc w/atts: Mr. H. D. Curet, Manager Product Licensing Siemens Power Corporation 2101 Horn Rapids Road P. O. Box 130 Richland, WA 99352-0130
4 1
NRC/SIENENS POWER CORPCRATION MEETING ON LOCA NEUTRONICS INPUT METH00S LIST OF ATTENDEES JUN 11, 1997 NMiE ORGANIZATION i.
Holm, Jerry Siemens Curet, D. H.
Siemens Lyons, Jim NRC/SRXB i
Attard, Anthony NRC/SRXB Kendrick, Edward NRC/SRXB Wang, Egan NRC/PGEB Staudenmaier, Joseph NRC/DSSA Ulses, Tony NRC/SRXB i
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ATTACHMENT 1 i
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XN-75-43(A? Neutronics input to LOCA h
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Presented by: Jerry S. 'Holm, Manager Neutronic Analysis Methods l
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SIEMENS Neutronics input to LOCA - XN-75-43(A?
XN-75-43 (A) Core Physics Methods and Data Used as input to LOCA Analysis "This report provides a description of the Exxon Nuclear Company core physics methods and data used as input to the WREM analysis of PWRs."
Submitted to NRC August 1975 Approved by NRC October 1975 l
4 5
i JSH:97:023
SIEMENS XN-75-43(A? Outline - Sections Which Describe Current Model/ Data
~
l 3.0 Fission Heat Calculation 3.1 Reactor Kinetics Model 4
l 3.2 Moderator Density Feedback Reactivity 3.3 Doppler (Fuel Temperature) Reactivity Feedback i
3.4 Scram and Scram Reactivity 3.5 Power (Fission) Decay History 4
4.0 Fission Product Decay and Decay of Actinides 4.1 Fission Product Decay Model 4
e 4.2 Actinide Decay Model 4.3 Gamma Smearing
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JSH:97:023 m
SIEMENS i
XN-75-43(A? Outline - Sections Which Describe Current Model/ Data 1
5.0 Power Distribution Treatment 5.1 Limiting Axial Power Profiles l
r 5.2 Previous Results 5.3 ENC Treatment j
5.4 Power Spike Considerations 4
v r
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f i
JSH:57:023
~
SIEMENS XN-75-43(A? Section 3.2 Moderator Density Feedback Reactivity L
. CASMO used in place of XPOSE
. MTC set by Technical Specification
. Conservative value for B versus a constant =.007 i
i I
t 1
I 5
JSH:97:023
SIEMENS XN-75-43(A) Section 3.3 Doppler (Fuel Temperature? Reactivity Feedback
. CASMO used in place of XPOSE
[
6 JSH:97:023
SIEMENS XN-75-43(A? Section 3.4 Scram and Scram Reactivity 4
. CASMO used in place of XPOSE i
. A 3D Nodal Code instead of PDQ
. Conservative value of B versus a constant =.007 i
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SIEMENS 1
XN-75-43(A) Section 4.2 Actinide Decay Model CASMO used instead of XPOSE f
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SIEMENS XN-75-43(A) Section 4.3 Gamma Smearing
. CASMO 3G used instead of the codes ANISN and QAD
. Gamma smearing has three components
. Fraction absorbed in fuel and clad
. Redistribution between rods within an assembly
. Redistribution between assemblies JSH:97:023
SIEMENS-XN-75-43(A) Section 5.1 Limiting Axial Power Shapes
. XN-75-43(AD i
. Approach relied on " Westinghouse Emergency Core Cooling System - Plant Sensitivity Studies," WCAP-8356, July 1974.
j r
. Current Analysis i
. Plant specific shapes based on analyses i
to JSH:97:023
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SIEMENS r
Summary
. Neutronics guidelines to be updated to specify procedures for developing BWR and PWR LOCA input Y
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i JSH:97:023
SIEMENS Additional Issues
. Gamma Smearing Factor Values Radiation Heat Transfer for Gadolinia Bearing Fuel Rods
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i b
i 12 JSH:97:023
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