ML080710139
| ML080710139 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 03/19/2008 |
| From: | Alexander Adams NRC/NRR/ADRA/DPR/PRTA |
| To: | Reese S Oregon State University |
| MONTGOMERY C, NRR/DPR/PRTA 415-3398 | |
| References | |
| TAC MC5155 | |
| Download: ML080710139 (5) | |
Text
March 19, 2008 Dr. Steven R. Reese, Director Radiation Center Oregon State University 100 Radiation Center Corvallis, Oregon 97331-5903
SUBJECT:
OREGON STATE UNIVERSITY-REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE RENEWAL REQUEST (TAC No. MC 5155)
Dear Dr. Reese:
We are continuing our review of your request for license renewal for the Oregon State University TRIGA Research Reactor which you submitted on October 5, 2004, as supplemented. During our review of your January 23, 2008 response to Question 14 of the May 21, 2007 RAI request, questions have arisen for which we require additional information and clarification. Please provide responses to the enclosed request for additional information within 45 days of the date of this letter. In accordance with 10 CFR 50.30(b), your response must be executed in a signed original under oath or affirmation. Following receipt of the additional information, we will continue our evaluation of your license renewal request.
If you have any questions regarding this review, please contact me at 301-415-1127.
Sincerely,
/RA/
Alexander Adams, Jr., Senior Project Manager Research and Test Reactors Branch A Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-243 License No. R-106
Enclosure:
As stated cc w/enclosure: See next page
Oregon State University cc:
Docket No. 50-243 Mayor of the City of Corvallis Corvallis, OR 97331 David Stewart-Smith Oregon Office of Energy 625 Marion Street, N.E.
Salem, OR 97310 Dr. John Cassady, Vice Provost for Research Oregon State University Administrative Services Bldg., Room A-312 Corvallis, OR 97331-5904 Dr. Michael Hartman, Reactor Administrator Oregon State University Radiation Center, A-100 Corvallis, OR 97331-5903 Dr. Todd Palmer, Chairman Reactor Operations Committee Oregon State University Radiation Center, A-100 Corvallis, OR 97331-5904 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611
March 19, 2008 Dr. Steven R. Reese, Director Radiation Center Oregon State University 100 Radiation Center Corvallis, Oregon 97331-5903
SUBJECT:
OREGON STATE UNIVERSITY-REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE RENEWAL REQUEST (TAC No. MC 5155)
Dear Dr. Reese:
We are continuing our review of your request for license renewal for the Oregon State University TRIGA Research Reactor which you submitted on October 5, 2004, as supplemented. During our review of your January 23, 2008 response to Question 14 of the May 21, 2007 RAI request, questions have arisen for which we require additional information and clarification. Please provide responses to the enclosed request for additional information within 45 days of the date of this letter. In accordance with 10 CFR 50.30(b), your response must be executed in a signed original under oath or affirmation. Following receipt of the additional information, we will continue our evaluation of your license renewal request.
If you have any questions regarding this review, please contact me at 301-415-1127.
Sincerely,
/RA/
Alexander Adams, Jr., Senior Project Manager Research and Test Reactors Branch A Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-243 License No. R-106
Enclosure:
As stated cc w/enclosure: See next page DISTRIBUTION:
PUBLIC PRTA r/f RidsNrrDprPrta Accession Number: ML080710139 OFFICE PRTA:PM PRTA:LA PRTA:BC PRTA: PM NAME CMontgomery cm EHylton (egh) for EBarnhill DCollins dsc AAdams aa DATE 3/19/08 3/19/08 3/19/08 3/19/08 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION REGARDING APPLICATION FOR LICENSE RENEWAL OREGON STATE UNIVERSITY DOCKET NO. 50-243
- 1.
Were any data (like excess reactivity or control rod worth) available at other than BOL to use to benchmark the neutronic model for the HEU core? If so, why werent they used?
- 2.
Table 1 - Why does the calculated transient rod worth deviate from the measurement for the HEU core at BOL while the other three control rods showed much closer agreement between calculated and measured worth?
- 3.
Table 1 - Total measured rod worth data is inconsistent with data shown in the SAR, Table 13-12. Do the data reflect different sets of measurements?
- 4.
Table 2 - Please elaborate on the aspects of the evaluation techniques that contribute to the discrepancy between the measured and calculated shutdown margin for the HEU BOL core when the regulating rod is fully withdrawn. How does the calculated shutdown margin compare with the measured value for the other control rods?
- 5.
In Table 3 the hot channel peak factor for BOL is listed at 1.442 with corresponding thermal power of 18.02 kW. For MOL the thermal power is increased to 18.37 kW while the peak factor decreased to 1.420 indicating a potential inconsistency, if the number of fuel elements remained the same. Please clarify.
- 6.
What is the effect on power peaking of replacing a burnt fuel rod (e.g., an IFE) with a fresh fuel rod? What controls are in place with respect to loading new fuel? Provide a calculation to indicate the change in the peaking factor when fresh fuel is placed in an EOL core at the worst location.
- 7.
Please provide analytical justification for ignoring cross flow between neighboring flow channels.
- 8.
Was the transient rod also removed for the calculation of the rod power distribution in the core?
- 9.
Does the peak power density (maximum local heat flux) at steady-state occur in the fuel element (rod) with the maximum rod power?
- 10.
Why did the thermal analysis not use the Groeneveld Look-up table built into RELAP5-3D?
- 11.
What is the number of HEU fuel elements assumed in calculating the hot rod peak factors for the HEU core in Table 3?
- 12.
Are changes in gap properties (e.g., gap size, oxidation at the fuel boundary, gas composition) over time taken into account when calculating fuel temperatures?
- 13.
Have the consequences of pulsing the reactor from full power operation been considered? If yes, what are the results; if no, why not?