ML20217H316
| ML20217H316 | |
| Person / Time | |
|---|---|
| Issue date: | 03/24/1997 |
| From: | Wang E NRC (Affiliation Not Assigned) |
| To: | Curet H SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| References | |
| NUDOCS 9710150127 | |
| Download: ML20217H316 (3) | |
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- I j UNITEG) STATES NUCLEAR REGULATORY COMMISSION
%, [g WASHINGTON, D.C. 30866-0001 March 24. 1997 Mr. H. D. Curet, Manager Product Licensing Siemens Power Corporation 2101 Horn Rapids Road P. O. Box 130 Richland, WA 99352 0130
SUBJECT:
REQUEST FOR ADDITION L IN RAI REPORT, "EXEM/PWR Al) RELATED TO THE TOPICAL XN-NF 82 20(P), REVIS@IO'N Y,$WilEMENT 6GK BREAKLOCA ECCS MOD
Dear Mr. Curet:
The U.S. Nuclear Regulatory Commission (NRC) Ruactor Sptems Stanch (SRXB) staff has determined that it needs additional information in order to complete its rav;ew of the Siemens Topical Report *EXEM/PWR Large Break LOCA ECCS Model Updates,"
XN NF 82 20(P), Revision 1, Supplement 6.
RAI 1 Paragraph 2 of Page 1-1 refers to 10 CFR 50.56 criteria. Should this be a reference to 10 CFR 50.46 criteria?
RAI 2 Figure 1.1 in the sub}ect report indicates that with e flooding rate greater than 1.74 inches /second, the 1996 changes to the fuel cooling usdag facilit/ (FCTF)
Correlation yield a heat transfer coefficient that is higher than the 1986 FCTF Correlation. This is also stated at the top of Page 2 7. .lustify the non-conservative greater nature than 1.74 inchesof this increase in the heat transfer coefficient at flooding rates
/second.
RAI 3 Explain how the FCTF based quench time calculation, wl.ich h.,s Men modified in XN NF-82 20(P), Rev 1, Supp 6,is different from the patch ti.nc calculation of Supp. 5, which was rejected by the staff in its safety evaluation report.
RAI 4 10 CFR 50, Appendix K.ll.4 states, "To the extent practical!e, predictions of the evaluation model, or portions thereof, shall be compared with spi,licable experimental information."
A large body of large scale reflood heat transfer test data now exists. Provide an assessment of your methodology against cylindrical core test facility and slab core test facility data that are independent of the dato used to derive your correlations. This assessment should compare predictions with I axperimental data for key quantities such as clad temperature, heat transfer coefficient, collapsed leval and quench front position. The assessment should -%hg include a discussion of why the particular experiments were chosen for the assessment.
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Mr. H. D. Curet .
You have requested that portions of the information, "EXEM/PWR Large Break LOCA ECCS Model Updates," XN NF 82 20(P), Revision 1. Supplement 6,submitteo in December 1996 be' exempt from mandatory public disclosure. While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staff's final determination. The staff concludes that these questions and comments do not contain
- those portions of the information for which exemption is sought. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Siemens the opportunity to verify the staff's conclusions, if, after that time, you do not request that all or portions of the information b: withheld from public disclosure in accordance with 10 CFR 2.790, this letter will be placeo in the NRC Public Document Room.
These questions affect nine or fewer respondents, and therefore are not subject to review by the Office of Management and Budget under P.L.96-511.
It will be very helpfulif you could respond this RAI within 30 days, if you have any questions regarding this metter, you may contact me at (301) 415-1076.-
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Sincerely,
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Egan Y Wang, Reactor Engineer Generic issue and Envnonmental Projects Branch Division of Reactor Program Managenient Office of Nuclear Rsactor Regulation
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SC:PGEB C:PyE/II NAME EWang* FAkstulewicz* DNathews DATE 03/11/97 03/20/97 03/#/97 0FFICIAL RECORD COPY
Mr. H. D. Curet 0 2-March 24, 1997 You have requested that portions of the information, 'EXEM/PWR Large B Model Updates,' XN NF 82 20(P), Revision 1, Supplement ,
eak LOCA EOCS 8 submitted in be exempt from mandatory public disclosure. Whileecember the staff 1996has not co of your request in accordance with the requirements mpleted itsof review 10 CFR 2 790 t portion of the submitted information is being withheld from public disclosure pen determination. The staff concludes that these questions o s naland comment those portions of the information for which exemption s do not is sought contain
. However, the staff will to a) low Siemens the opportunity toa everify of this letterthe staff's c du not request that all or portions of the information be withheld fs. If, efter t accordance Room.- with 10 CFR 2.790, this letter will rombe public disclosure placed in inthe NRC Publi c Document by the Office of Management and Budget under P.L. 9 re not subject to review l,
It will be very helpfulif you could respond this RAI within 30 d questions regarding this matter, you may contact me at (301) 4151076ay -
l Sincerely,
- : .. . wA Egon Y. Wang, Reacto Engineer censric Projects issuw Stanch and Environmental Division of Reactor Program Management
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Office of Nuclear N6 actor Regulation l
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