ML20202G255
| ML20202G255 | |
| Person / Time | |
|---|---|
| Issue date: | 02/09/1998 |
| From: | Essig T NRC (Affiliation Not Assigned) |
| To: | Curet H SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| Shared Package | |
| ML20202G259 | List: |
| References | |
| TAC-M96729, NUDOCS 9802200096 | |
| Download: ML20202G255 (4) | |
Text
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February 9, 1998 Mr. H. Don 11d Curet, M: nager Product Licensing Slemens Power Corporation 2101 Horn Rapids Road P. O. Box 130 Richland, WA 99352 0130
SUBJECT:
ACCEPTANCE FOR REFERENCING OF SPC TOPICAL REPORT EMF 45 74(F),
REVISION 0, SUPPLEMENTS 1 AND 2: "RODEX2A (BWR) FUEL ROD THERMAL. MECHANICAL EVALUATION MODEL" (TAC NO. M96729)
Dear Mr. Curet:
The staff has reviewed the subject report submitted by SPC by letters of Janut.ry 15 and August 13,1997, and your response dated December 3,1997, to our requests for additionalInforenation. On the basis of our review, the staff has found the subject report to be acceptable for referencing in license applications to the extent specified and under
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the limitations stated in the enclosed report and U.S. Nuclear Regulatory Commission (NRC) technical evaluation. The ovaluation definos the basis for acceptance of the report.
l l
The staff will not repeat its review of the matters described in SPC Topical Report i.
EMF 85 74(f", Revision 0, Supplements 1 and 2, and found acceptable when the report appears as a reference in license applications, except to ensure that the material presented applies to the specific plant involved.- NRC acceptance applies only to the matters described in SPC Topical Report EMF 45 74(P), Revision 0, Supplements 1 and
- 2. In accordance with procedures established in NUREG 0390, the NRC requests that SPC publish accepted versions of the report, proprietary and non-proprietary, within 3 months of receipt of this letter. The accepted versions shallincorporate this letter and the enclosed evaluation between the title page and the abstract and an A (designating accepted) following the report identification symbol.
Should our acceptance criterla or regulations change so that our conclusions as to the acceptability of the report are no longer valid, applicants referencing this topical report will be expected to rey!se and resubmit their respective documentation, or submit justification for the continued applicability of the topical report without revision of their respective documentation.
Sincerely, Frank Akstulewicz for/
[j, Thomas H. Essig, Acting Chief Generic issues and Environmental Projects Branch Division of Reactor Program Management R d.g'-
Office of Nuclear Reactor Regulation m
Enclosure:
As stated
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February 9, 1998 Mr. H. Donald curet, Manager Product Lloonsing Siemens Power Corporation 2101 Horn Rapids Road P. O. Box 130 Richland, WA 993524130 l
SUBJECT:
ACCEPTANCE FOR REFERENC8NO OF SPC topical. REPORT EMF 45 74(P).
l l
REVISION 0 SUPPLEMENTS 1 AND 2:"RODEX2A (SWR) FUEL ROD l
THERMAL MECHANICAL EVALUATION MODEL" (TAO NO. M98729)
Dear Mr. Curet:
l The staff has reviewed the subject report submitted by SPC by lettore of Januaiy is and l
August 13,1997, and your response dated December 3,1997, to ou' requests for additional information. On the basis of our review, the s'aff has found the subloot report to be l
acceptable for referencing in license applications to the extent spec. fled and under the limitations stated in the enclosed report and U.S. Nuclear Regulatory Commission (NRC) technical evaluation. The evaluation defines the basis for acceptanco of the report.
The staff will not repeat its review of the matters described in SPC Toolcal Repo't EMF-85 74(P), Revisien 0, Supplements 1 and 2, and found acceptable when the report appears as a reference in license applications, except to ensure that it a materia presented applies to the specific plant involved. NRC acceptance applies only to the mattere described in SPC Topical Report ElWF45 74(P), Revision 0, supplements 1 and 2. In accordance w!th procedures established in NUREG 0390, the NRC requosts that SPC publish accepted versions of the report, proprietary arid non proprietar), within 3 months of receipt of this letter. The accepted versions shall incorporate this letttr and the enclosed evaluation between the title page and the abstract and an A (de signating accepted) following the report identification eymbol.
Should our acceptance criteria or regulations change so that our conclusians as to the acceptability of the report are no longer valid, applicanto referencing this tapical report will te expected to revise and resubmit their respectivt documentation, or sub itit just;ficaWon for the co itinued applicability of the topical report without revision of their cospective documentatien.
Sincerely,.
)4 (d$n Lo sbbW Ttiomas H. E sig, Acting Chiel' 4 Generic issues and Environm9ntaWro ects Brancti Division of Reactor Program Management office of Nuclear Reactor Regulation
Enclosure:
As stated
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i ENCLOSURE i
l SAFETY EVALUATION OF SIEMENS POWER CORPORATION l
TOPICAL REPORT EMF 45 74(P), REVislON 0, SUPPLEMENTS 1 AND 2, "RODEX2A (SWR) FUEL ROD THERMAL MECHANICAL EVALUATION MODEL" 1
l
_ 1 INTRODUC'NON i
in letters dated Janut:ry is and August 13, igt7, from H. D. Curet Siemens Power l
Corpo etion (SPC), to the U.S. Nuclear Regulatory commission (f?C), SPC submitted a l
TopicW ttoport EMF 45 74(P), Revision 0, Supplemes.ts 1 and 2. "RODEX2A (SWR) Fuel Rod i
l Thermal Mechanical Evaluation Model," for NRC review.
i EMF 45 74(P), Revision 0, Supplements 1 and 2, describes an improved fuel rod i
performance code, RODEX2A, and the associated methodology that SPC Intends to epply for fuel reload licensing applications in boiling water reactors (SWRs). The purpose of j
these improved code and rr.ethodology is to extend the analytical capability to a slightly higher burnup range tW the previously approved burnup range. The new code and methodology improve tho analytical predictions of fission gas release, fuel rod growth, fuel assembly growth, fuel chinnel growth, etc.
l The NRC staff v;3s supposted in this review by its consultant, Pacific Northwest National Laboratory (PNNL). Our consultant's technical evaluation report (TER), which is attached, provides technical findings relative to its review.
2 EVALUATION l
The staff has reviewed the eaclosed TER, and concludes that the TER provides an j
adequate technical basis to a pprove EMF 45 74(P), Revision 0, Supplements 1 and 2.
j
- Therefore, the staff agrees with PNNL's conclusion that the irgroved RODEX2A code and i-the associated methodology described in EMF 45-74(P), Revision 0, Supplements 1 and 2, are acceptable. Based on our review, the staff adopts the findings in the attached TER.
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- 3. CONCLUSIONS -
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. Tho staff has reviewed the SPC's I.nproved RODEX2A code and the associated methodology described in EMF 45-74(P), Revision 0, Supplements 1 and 2, and finds that f -~
.the code and methodology are adequate. Therefore, we conclude that (1) the RODEX2A
- co te is acceptiible for licenLing opplications to 62,000 mwd /MTU rod average burnup, and (2) the fuel rod growth, fuel asseeably growth, and fuel channel growth models and analytical methods are acceptabb for ATRIUM 9 and 10 fuel designs up to 64,000 mwd /MTU assembly average burnup.
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