ML20203G131
| ML20203G131 | |
| Person / Time | |
|---|---|
| Issue date: | 12/10/1997 |
| From: | Birmingham J NRC (Affiliation Not Assigned) |
| To: | Joseph Kelly BABCOCK & WILCOX OPERATING PLANTS OWNERS GROUP |
| References | |
| NUDOCS 9712180058 | |
| Download: ML20203G131 (3) | |
Text
. _ .
Decembar 10, 1997 3 -Mr. J._J. Kelly.. Manager B&W Owners Group Services P.O. Box 10935 -
Lynchburg, VA 24506-0935.
SUBJECT:
- RE0 VEST FOR ADDITIONAL INFORMATION FOR TOPICAL BAW 10199P.
-ADDENDUM 1, "THE BWV CRITICAL HEAT FLUX. CORRELATIONS."
f Dear Mr. Kelly;L '
By letter dated September 30, 1996. Framatome Cogema Fuels (FCF) submitted the subject report for NRC review. The Reactor Systems Branch has reviewed the report and determined a need for additional information. The information requested Lis identified in the enclosure to this letter. NRC requests that
- the FCF' provide a response to these questions by December 31 1997. You should
' address your response to the'NRC Document Control Desk.
If you have any questions on this' matter, please ' contact me by phone, at
-301/415 2829. or by email. jlb4(anrc. gov.
Sincerely.
Original Signed By:
Joseph L. Birmingham. Project Manager Generic issues and Environmental Projects Branch-Office of Wuclear Reactor Regulation cc;. Mr. F. _McPhatter. Manager Framatome Cogema fuels }
3315 Old Forest Road s P,0. Box 10935 - )
Lynchburg, VA 24506-0935 g%
Enclosure:
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%, /g December 10, 1997 Mr. J. J. Kelly, Manager B&W Owners Group Services P.O. Box 10935 Lynchburg. VA 24506-0935 ;
SUBJECT:
RE0 VEST FOR ADDITIONAL INFORMATION FOR TOPICAL BAW 10199P.
ADDENDUM 1 "THE BWV CRITICAL HEAT FLUX CORRELATIONS."
Dear Mr. Kelly:
By letter dated September 30, 1996, framatome Cogema Fuels (FCF) submitted the !
subject report for NRC review. The Reactor Systems Branch has teviewed the report and determined a need for additional information. The information requested is identified in the enclosure to this letter. NRC requests that the B&WOG provide a response to these questions by January 31, 1998. You should address your response to the NRC 00cument Control Desk.
If you have any questions on this matter, please contact me by phone, at 301/415 2829. or by email, jlb4Canrc. gov.
Sincerely, i
/>M r k
)?.L Joseph L. Birmingham, Project Manager Generic Issues and Environmental ProjectsBranch Office of Nuclear Reactor Regulation cc: Mr. F. McPhatter. Manager Framatome Cogema Fuels-3315 Old Forest Road P.O. Box 10935 .
Lynchburg, VA 24506-0935
Enclosure:
As stated-4 , r - _ -- ,% .
REQUEST FOR ADDITIONAL INFORMATION FOR ADDENDUM 1 TO BAW-10199P-A j
- 1. Describe schematically the spacer grid designs-for Mark B11. Mark BW17 MSM (mid span mixer), and Mark BW17 and identify their differences in the '
bundle geometrical configurations and the thermal-hydraulic performance with respect to that of the Mark BW17 design.
- 2. Describe the data bases obtained from 5 tests in 3 different geometrical configurations on a 5 by 5 matrix of electrically heated fuel rods, and explain why the tests are applicable to a 15 by-15 and a 17 by-17 Mark BW17 design and the obtained data are sufficiently to support new critical heat flux correlation for the Mark B11,
- 3. The data bases for the BWU-Z correlation do not include test data for the Mark Bil and Mark BW17 MSM fuel design. Explain why the BWu Z correlation is still valid for the Mark B11 and Mark BW17 MSM. Provide the bases which conclude that a simple multiplier is valid for the proposed applications. Describe how accurate and conservative a proposed simple multiplier to the BWU-Z correlation is derived based on limited Mark B11 and Mark BW17 MSM data bases. Provide the prc.?dures to obtain the simple multiplier and justify that the numbers for Fm and Fu shown in Tables E-7 and E-8, and Tables F-2 and F-3, respectively, are the best results.
- 4. Table E-1 states that Test 27.0 and 27.1 are considered as separate tests and notes that Test 27.0 is not analyzed in this appendix E. Explain the purpose of the test for unit cell guide tube and cold unit and why Test 27.0 is not analyzed but still listed in the Table E-1.
- 5. It appears that only one axial power distribution (Table E-4) was used in
- Mark B11 CHF test program. Provide the justification that the data
(
obtained from this single axial power shape will support the proposed methodology for the Mark Bil fuel design by adopting the old BWU-Z correlation without even changing its coefficients.
- 6. Based on the data shown in Table E-5 there are six thermocouple locations, however. there are 21 heater rod axial powers in Table E-4.
Describe the procedures to generate these data. Also, explain the setup on the spacer gi locations with respect to the application to the tests and data-obtair, for comparison with the data bases for the BWU-Z correlation and why BIS is at -4.47 in Table E-5,
- 7. Provide the experimental data to support the form loss coefficients shown in Table E-2 under cell geometry, and describe the procedures to obtain these data including the approved methodologies used.
ENCLOSURE
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