ML20129J455
| ML20129J455 | |
| Person / Time | |
|---|---|
| Issue date: | 11/01/1996 |
| From: | Wang E NRC (Affiliation Not Assigned) |
| To: | Matthews D NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9611060276 | |
| Download: ML20129J455 (22) | |
Text
_ _ _ _ _
d November 1, 1996 e
MEMORANDUM T0:
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 System Engineer Egan Y. Wang /for Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation i
SUBJECT:
MEETING SUMARY OF OCTOBER 23, 1996, REGARDING THE REQUIREMENTS NEEDED TO LICENSE A RELOAD CONTAINING MIXED OXIDE FUEL.
'On October 23, 1996, representatives of Siemens Power Corporation (SPC) met with representatives of the Nuclear Regulatory Commission (NRC). The purpose j
.of this meeting was to provide an opportunity for SPC representatives to l
review the requirements needed to license a reactor core reload containing mixed oxide (M0X) fuel. SPC representatives provided an introduction and a brief description on utility activities regarding M0X.
SPC representatives also presented SPC's. response to Department of Energy M0X plans.
In addition, SPC resresentatives indicated that SPC had evaluated U.S. codes & methods that i
would >e used to perform reload calculations and determined that a relatively i
small number of reload modifications are required. A portion of the meeting involved presentation of proprietary information.
Attachment I provides a list of meeting attendees. Attachment 2 is the non-proprietary version of the presentation material.
l Attachments: As stated cc w/att:
See next page I.
DISTRIBUTION:
l See attached page i
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November 1, 1996 l
l MEMORANDUM TO:
David B. Matthews, Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation l
FROM:
Egan Y. Wang, Reactor System Engineer Generic Issues and Environmental Projects Branch g
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Division of Reactor Program Management tg C
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Office of Nuclear Reactor Regulation i
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SUBJECT:
MEETING SUMARY OF OCTOBER 23, 1996, REGARDING THE REQUIREMENTS NEEDED TO LICENSE A RELOAD CONTAINING MIXED OXIDE FUEL i
On October 23, 1996, representatives of Siemens Power, Corporation (SPC) met i
with representatives of the Nuclear Regulatory Commission (NRC).
The purpose 1
l of this meeting was to provide an opportunity for SPC~ representatives to review the requirements needed to license a reactor core reload containing mixed ~ oxide (MOX) fuel.
SPC representatives provided an introduction and a brief description on utility activities regarding MOX. SPC representatives L
'also presented SPC's response to Department of Energy M0X plans.
In~ addition, l
SPC representatives indicated that SPC had evaluated U.S. codes ~& methods that would be used to perform reload calculations and determined that a relatively l
~
small number of reload modifications are required. A portion of.the meeting involved presentation of proprietary information._ provides a list of meeting attendees. Attachment 2 is the non-proprietary version of the presentation material.
Attachments: As stated cc w/att: see next page
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cc:
Mr. H. D. Curet, Manager l
Product Licensing Siemens Power Corporation 2101 Horn Rapids Road P. O. Box 130 t
Richland, WA 99352-0130 t
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Mtg.SummaryofOctober23MeetingwithSiemensPower Corporation Dated November 1.; 19 p
HARD COPY 4
+ Central: File Public PGEB r/f R. Cooper, RI E. Merschoff, RII W. Alexion, RIII J. Dyer, RIV E. Wang l
F. Miraglia A. Thadani R. Zimmerman T. Martin E. Jordan D. Matthews F. Akstulewicz T. Collins j
K. Kavanagh H. Richines i
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0 NRC/SIEMENS POWER CORPORATION MEETING ON MIXED OXIDE FUEL LIST OF ATTENDEES Oct 23, 1996 HAME ORGANIZATION l
l i
Burns, J. P.
WPPSS l
Heiks, R. L.
Siemens l
Garner, N. L.
Siemens l
Garber, D. E.
Siemens l
Copeland, R.
Siemens Collins, T. E.
NRC/NRR Kavanagh, K.
NRC/NRR Richines, H.
NRC/NRR l
Wang, Egan NRC/NRR I
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l ATTACHMENT 1 r
SIEMENS i
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i NRC Meeting on Licensing MOX Reloads Siemens Power Corporation October 23,1996
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Siemens Power Corporation o c;,,,,,ny,,
t SIEMENS i
Agenda Introduction / Utility Activity--J. Burn WPPSS 1
. Siemens Experience with MOX Fuel l
. Review of US Codes and Methods i
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. Reactor Licensing issues i
Summary / Conclusions Siemens Power Corporation uc.se.oenoiss
i SIEMENS Goal:
Review License Needs for Reload Fuel and Reactors and Identify Issues Not Addressed
]
SPC has reviewed US codes and methods needed to j
support MOX l
t Relatively small number of reload modifications are required 1
Limited number of reactor issues to be resolved I
Siemens Power Corporation nac.ss.oorwse
SIEMENS DOE May Issue Contract to Dispose of Weapons Grade Pu by Burning it in Commercial Reactors l
1
. Have estimated 50 MT of weapons grade plutonium to l
dispose
. One alternative is to fabricate into mixed oxide fuel for use in commercial reactors P
i
. Contract would require the fabrication and use of MOX fuel Siemens Power Corporation l
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SIEMENS Siemens Has Experience in Fabricating MOX
. Previously provided MOX in US to Big Rock Point and R. E. Ginna reactors
. Developed Hanau facility in Germany for MOX fabrication Initial facility provided 35 MThm/yr
. Upgraded facility to provide 120 MThm/yr (not operated due to change in licensing policy of state)
Siemens Power Corporation me.w oonan
SIEMENS a
European Experience is Technical Basis for Fabrication and Use of MOX Siemens inserting reloads of ATRIUM-10 MOX fuel in Gundremmirigen starting in 1997
. Working with consortium of US BWR licensees to supply similar ATRIUM-10 designs in US
. Note:
Gadolinia to be used in only UO rods 2
i Siemens Power Corporation
SIEMENS t
Reload Licensing Requires Approved Design Codes, Methods, and Criteria f
. SPC is reviewing currently approved methodology and criteria for applicability i.
. Review focused on Chapters 4 and 15 of SRP
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Siemens Power Corporation uc.s eiese
SIEMENS i
Design Methods Review Mechanical design RODEX2--Fuel performance code, gives FGR, pellet densification/ swelling, cladding strain, cladding oxidation, etc. as function of exposure RAMPEX--Cladding stress during transients Generic BWR design criteria l
l i
. Thermal hydraulic design l
XCOBRA--Steady state thermal hydraulic analysis j
ANFB--Critical power correlation Safety limit methodology Siemens Power Corporation nac e cer-io,n i
SIEMENS Design Methods Review (Continued;l i
. Non-LOCA transient r
COTRANSA2--System response code
. XCOBRA-T--Transient fuel thermal hydraulic code STAIF--Frequency domain code to determine susceptibility to power instabilities f
LOCA--EXEM BWR evaluation model
. RELAX--System response code, hot channel code i
. FLEX--Time to reflood l
. HUXY--Fuel rod heatup l
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Siemens Power Corporation
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a SIEMENS Design Methods Review (Continued)
Neutronic design
. CASMO-3G--Cross section code
. MICROBURN-B--Core simulator I
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i Siemens Power Corporation
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SIEMENS MOX Fuel Changes in the Neutronic Kinetics Have to be Incorporated in the Transient Analyses
. Control rod worths decreased t
. Lower delayed neutron fraction and shorter prompt neutron lifetime 1
. Void fraction reactivity is more negative A
L Siemens Power Corporation ucm.osnom
SIEMENS BWR Transients and Accidents Have Only Small Impact from MOX Fuel
. CRDA is limiting reactivity transient Reduced control rod worth, increased temperature and void reactivity feedback tend to compensate for the l
smaller delayed neutron fraction
. Net impact is not significantly changed j
. Pressurization transients affected by void reactivity and increases ACPR which will require slightly higher operating limit i
. DNB controlled by heat flux LHGR [imits set to provide similar peak heat fluxes i
Geometry unchanged from standard fuel I
Siemens Power Corporation nacm oerase
t SIEMENS Stability and Shutdown Margin Concerns are Helped by ATRIUM-10 Design 3
t L
. Because of smaller rod worth, MOX fuel has less shutdown margin than UO
. Central water canister 2
provides additional hot to cold reactivity change which improves shutdown margin.
. The more negative void reactivity feedback is mitigated by part length rods in ATRIUM-10. Thus the design compensate for any stability changes from the MOX fuel.
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l Siemens Power Corporation ac:sem some i
SIEMENS LOCA Response Not Significantly I
Changed by MOX 1
. SPC will use EXEM BWR LOCA model Impact of MOX on neutronics not significant in LOCA event i
Geometry and system response unchanged r
I I
Si:. mens Power Corporation ac;ss.oenom I
SIEMENS Reduction in Boron Worth Will Require SLCS f
Analysis I
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. Current SLCS boron levels must be assessed to assure l
sufficient shutdown If not, either the boron level can be increased or enriched boron used l
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Siemens Power Corporation nacuostuwse
e SIEMENS MOX Impact on Reactor Licensing is Limited Three major issues based on DOE sponsored evaluations
. New fuel storage
. Spent fuel storage
. Security I
Reactor systems not changed by the use of MOX i
Siemens Power Corporation
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e CC:
Mr. H. D. Curet, Manager i
Product Licensing Siemens Power Corporation 2101 Horn Rapids Road P. O. Box 130 i
l Richland, WA-99352-0130 t
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