ML20248B226
| ML20248B226 | |
| Person / Time | |
|---|---|
| Issue date: | 05/26/1998 |
| From: | Wang E NRC (Affiliation Not Assigned) |
| To: | Essig T NRC (Affiliation Not Assigned) |
| References | |
| PROJECT-702 NUDOCS 9806010228 | |
| Download: ML20248B226 (50) | |
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UNITED STATES p
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20066-0001
- ,d May 26, 1998 l
l MEMORANDUM TO:
Thomas H. Essig, Acting Chief Generic issues and Environmental Projects Branch l
Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Egan Wang, Reactor Engineer Generic issues and Regulatory improvements Section Generic issues and Environmental Projects Branch 4
Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF MEETING HELD ON MARCH 11,1998 WITH I
SIEMENS TO DISCUSS ISSUES RELATED TO LBLOCA METHODOLOGY MODIFICATIONS On May 21,1998, the staff held a public meeting with Siemens Power Corporation (SPC) at NRC headquarters in Rockville, Maryland. Utility representatives and members of the public were also present for this meeting. The purpose of this meeting was to present to the staff large break loss of coolant accident (LBLOCA) methodology changes. Most material presented during this meeting was proprietary. Attachment i lists meeting participants. Attachment 2 provides a set of non-proprietary slides presented by SPC during the meeting.
i During this meeting, SPC discussed the proposed changes to SPC's EXEM/PWR LBLOCA evaluation model. These changes include variability, model, and correlation changes. To address variability issues, SPC proposed revising numerical solution scheme. The new method uses the latest iterate values in solution matrix and iteration is continued until specified convergence is obtained. The new method is more efficient and assures convergence. SPC also proposed a change in definition of volume flow. The current volume average flow is volumetric flow weighted average of inlet and outlet junction mass flows. In the proposed model, volumetric mass flux is redefined as simple average of inlet and outlet junction mass flows (vector). Small changes in heat transfer and critical heat flux is expected from this change. Other proposed changes include combining system blowdown and hot channel calculations, increasing nodalization and eliminating enthalpy transport model, improve consistency between RODEX2 and RELAP4 fuel rod models, revising film boiling correlation, revising end of bypass model, revising pump degradation model, revising clad creep model in RODEX2, and revising reflood heat transfer correlation (documented in XN-NF-82-20(P),
l Revision 1, Supplement 6). On the changes in clad creep model in RODEX2, the staff queried l
whether 16 samples used to derive primary creep parameters were statistically significant.
In addition to the changes mentioned above, SPC stated that code improvements and code 0) maintenance are planned.
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T. Essi9 May 26, 1998 SPC representatives also discussed pressure water reactor (PWR) LBLOCA evaluation model -
update 1998 topical report outline. SPC plans to provide the report in three sections:
- 1) methodology overview (summary roadmap), 2) model changes, and 3) model applications.
SPC plans to submit this updated topical report in August 1998. This topical report will reference fuel cooling test facility (FCTF) methodology submitted to the staff in 1996.
The staff noted that there is a plan for the agency to convert to electronic documentation and that SPC should be prepared for submitting documents and reports in electronic form.
SPC presented a corrected EXEM/PWR evaluation model which is revised from the current model. The corrected modelincorporated changes addressing issues of variability, Dougall-Rosenow correlation, film boiling correlation, end of bypass model, pump degradation model, cladding creep model, and reflood heat transfer correlation. SPC stated that this corrected model provides more accurate simulation of core axial power profiles and steam generator conditions. It also improves consistency between RODEX2 and RELAP4 fuel rod models.
The staff raised a question on how SPC treats 10 CFR 50.46 requirement of reporting 50 degree Fahrenheit (F) temperature change in calculated peak cladding temperature (PCT).
SPC indicated that SPC evaluates and reports errors individually to licensees. It is SPC's understanding that 10 CFR 50.46 requires errors to be reported to the NRC when accumulated changes and errors in PCT reaches 50 degrees F. However, SPC does not believe it is the I
intention of 10 CFR 50.46 to require each subsequent change or error in the same model to be reported within 30 days.
Attachments: As stated Project No. 702 cc:
Mr. Jerry Holm Product Licensing Siemens Power Corporation 2101 Hom Rapid Road P.O. Box 130 Richland, Washington 99352-0130 l
l
T. Essig
-2 May 26, 1998 SPC representatives also discussed pressure water reactor (PWR) LBLOCA evaluation model -
update 1998 topical report outline. SPC plans to provide the report in three sections:
- 1) methodology overview (summary roadmap), 2) model changes, and 3) model applications.
SPC plans to submit this updated topical report in August 1998. This topical report will reference fuel cooling test facility (FCTF) methodology submitted to the staff in 1996.
The staff noted that there is a plan for the agency to convert to electronic documentation and that SPC should be prepared for submitting documents and reports in electronic form.
I SPC presented a corrected EXEM/PWR evaluation model which is revised from the current
)
model. Tv corrected modelincorporated changes addressing issues of variability, Dougall-l Rosenow correlation, film boiling correlation, end of bypass model, pump degradation model, cladding creep model, and reflood heat transfer correlation. SPC stated that this corrected model provides more accurate simulation of core axial power profiles and steam generator conditions. It also improves consistency between RODEX2 and RELAP4 fuel rod models.
The staff raised a question on how SPC treats 10 CFR 50.46 requirement of reporting 50 degree Fahrenheit (F) temperature change in calculated peak cladding temperature (PCT).
j SPC indicated that SPC evaluates and reports errors individually to licensees, it is SPC's l
understanding that 10 CFR 50.46 requires errors to be reported to the NRC when accumulated changes and errors in PCT reaches 50 degrees F. However. SPC does not believe it is the intention of 10 CFR 50.46 to require each subsequent change or error in the same model to be reported within 30 days.
Attachments: As stated Project No. 702 cc:
Mr. Jerry Holm Product Licensing Siemens Power Corporation 2101 Horn Rapid Road P.O. Box 130 Richland, Washington 99352-0130 DISTRIBUTION: See attach page Document name: G:\\980521MT. SUM
- See previous concurrence
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05k98 05/hf98 05/h/98 DATE OFFICIAL RECORD COPY
List of Attendees Name Organization Phone Number Egan Wang USNRC 301-415-1076 Ralph Landry USNRC 301-415-1140 Joseph Staudenmeier USNRC 301-415-2869 Jack Donohew USNRC 301-415-1307 S. E. Jensen SPC 509-375-8477 Alan Levin USNRC 301-415-2890 Daniel Denver SPC 509-375-8395 J. S. Holm SPC 509-375-8142 Daniel Mcdonald USNRC 301-415-1408 Ralph Caruso USNRC 301-415-1813 Paul Gunter NIRS 202-328-0002 Martin Van Haltem Northeast Utilities 860-832-4776 Gregory Baustian Consumer Energy s
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i l
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A DISTRIBUTION: Mtg. Summary w/Siemens Dated May 26, 1998 Hard Cooy Project File l
PUBLIC PGEB r/f OGC ACRS EWang' Email SCollins FMiraglia BSheron JRoe DMatthews GHolahan Alevin JDonohew RCaruso DMcDonald JStaudenmeier RLandry
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