ML20034D487
| ML20034D487 | |
| Person / Time | |
|---|---|
| Issue date: | 10/28/1992 |
| From: | Rosalyn Jones Office of Nuclear Reactor Regulation |
| To: | Copeland R SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| References | |
| TAC-M81070, NUDOCS 9211040039 | |
| Download: ML20034D487 (3) | |
Text
October 28, 1992 R. A. Copeland, Manager Reload Licensing Siemen.; Power Corporation 2101 Horn Rapids Road, P. O. Box 130 Richland, WA 99352-0130
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON TOPICAL REPORT ANF-89-98(P), REVISION 1, " GENERIC MECHANICAL DESIGN CRITERIA FOR BWR FUEL DESIGNS" (TAC NO. M81070)
Dear Mr. Copeland:
The review of topical report ANF-89-98(P), Revision 1 is currently in progress. During the course of our review, the staff has identified the need for some additional information as indicated in the enclosure.
Please contact S. L. Wu of my staff on (301) 504-3284, if there are any questions concerning this request.
Sincerely,
/s/
Robert C. Jones, Chief Reactor Systems Branch Office of Nuclear Reactor Regulation
Enclosure:
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OUESTIONS ON SIEMENS NUCLEAR POWER COMPANY'S REPORT ANF-89-98 The stability requirement for new fuel designs cited (based on a decay 1.
ratio of <1.0) in Section 4.1.6 and in Tables 4.1 and 5.1 is not There are several adequate for maintaining thermal hydraulic stability.
design parameters that need to be considered in order to maintainThe decay ratio should stability consistent with previous fuel designs.
be limited to be equal to or less than for current NRC approved Siemens Nuclear Power Company (SNPC) designs utilizing the same analysis Please provide a detailed proposal of how this assumptiens/ methods.
In comparison to existing approved designs will be implemented.
addition, what analysis methods are used for determining the decay ratio Criteria should and how are uncertainties factored into these analyses?
also be proposed for making sure that the new design will be compatible in mixed cores of existing fuel designs in terms of core pressure drop, l
bypass ficw fraction, and core loading patterns.
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No specific criteria or procedures were found in ANF-89-98 on how a critical power correlation will be developed for new fuel designs other than the basic SNPC correlation will remain the same except for the additive constants which are empirical. The critical issues in this
- 1) the applicability of the basic SNPC correlation to a approach are:
new fuel design; 2) the design and range of the critical power test data; and 3) the ability of the correlation to predict critical power to provide assurance that the fuel will remain within thermal margins.
For example, on Criteria should be developed that address these issues.
1at "For new fuel designs Page 19 of tne subject document it is stated ;.
and changes in features, usage of the correlacions is reviewed and What criteria are used in this review to justify usage justified."
In addition, what is the procedure applicability of the correlation?
for determining the L" constants for the correlation for a new design?
When a new critical power data set is generated for a new design how is it determined that this data is from the same data set population as used to develop the SNPC correlation and if it is not from the same population how will the uncertainties be combined with the uncertainties of the previous data sets?
No specific fuel surveillance program is defined for new fuel designs.
Please provide a definitive fuel surveillance program for new fuel 3.
designs.
The use of the specific temperature limit (Section 3.3.4) to protect-against excessive oxidation and hydrogen absorption may not protectAre there cladding 4
i against excessive corrosion at high Durnup levels.
l data at this temperature and extended burnup levels that demonstrate this limit protects the cladding at extended burnup levels and normal variations in water chemistry?
1
How are the steady-state and transient power histories (discussed in 5.
Section 5.1) determined. Are they based on Technical Specification If so, how?
If not, what are they based on?
limits for rod power?
If Also, are these power histories used for all mechanical-analyses?
not, which analyses use these histories?
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