ML17118A322: Difference between revisions
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{{#Wiki_filter:May 4, 2017 | {{#Wiki_filter:May 4, 2017 | ||
Mr. Andrew Kauffman Associate Director Nuclear Reactor Laboratory The Ohio State University 1298 Kinnear Road Columbus, OH 43212 | Mr. Andrew Kauffman Associate Director Nuclear Reactor Laboratory The Ohio State University | ||
1298 Kinnear Road Columbus, OH 43212 | |||
==SUBJECT:== | ==SUBJECT:== | ||
OHIO STATE UNIVERSITY - NON-POWER REACTOR CLOSEOUT OF GENERIC LETTER 2016-01, "MONITORING OF NEUTRON-ABSORBING MATERIALS IN SPENT FUEL POOLS," FOR THE OHIO STATE UNIVERSITY RESEARCH REACTOR DOCKET NO. 50-150 (CAC NO. A11010) | OHIO STATE UNIVERSITY - NON-POWER REACTOR CLOSEOUT OF GENERIC LETTER 2016-01, "MONITORING OF NEUTRON-ABSORBING MATERIALS IN SPENT FUEL POOLS," FOR THE OHIO STATE UNIVERSITY RESEARCH REACTOR DOCKET NO. 50-150 (CAC NO. A11010) | ||
For the non-power reactors, GL 2016-01 requested that licensees provide facility-specific information related to the use of NAM. This information was needed by the NRC staff to verify continued compliance through licensee implementation of effective methods for monitoring of reactor fuel in wet storage so as to detect and mitigate any degradation or deformation of NAM when credited in the facility licensing or design basis for criticality control of fuel in wet storage. On March 23, 2017, you submitted a revised response to GL 2016-01 (ADAMS Accession No. ML17088A127) superseding your March 20, 2017, response (ADAMS Accession No. ML17081A442) for the Ohio State University Research Reactor (OSURR). Your most recent response to the GL added an additional Monte Carlo N-Particle (MCNP) code criticality analyses for a total of two cases. Both cases assume that the fuel storage well is fully loaded with fuel. The first case results in the need to credit one percent of the BORAL installed in the facility's wet fuel storage well to meet the OSURR technical specification limit of a maximum keff of 0.9. The second case analyzed a hypothetical and unrealistic loss of the 100 percent of BORAL in the OSURR wet fuel storage well. The MCNP code analysis for this case shows, with high statistical confidence, a maximum | On April 7, 2016, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2016-01, "Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16097A169), to address the degradation of neutron-absorbing materials (NAM) in wet storage systems for reactor fuel at power and non-power reactors. | ||
A. Kauffman | |||
For the non-power reactors, GL 2016-01 requested that licensees provide facility-specific information related to the use of NAM. This information was needed by the NRC staff to verify continued compliance through licensee implementation of effective methods for monitoring of reactor fuel in wet storage so as to detect and mitigate any degradation or deformation of NAM when credited in the facility licensing or design basis for criticality control of fuel in wet storage. | |||
On March 23, 2017, you submitted a revised response to GL 2016-01 (ADAMS Accession No. ML17088A127) superseding your March 20, 2017, response (ADAMS Accession No. ML17081A442) for the Ohio State University Research Reactor (OSURR). Your most recent response to the GL added an additional Monte Carlo N-Particle (MCNP) code criticality analyses for a total of two cases. Both cases assume that the fuel storage well is fully loaded with fuel. The first case results in the need to credit one percent of the BORAL installed in the facility's wet fuel storage well to meet the OSURR technical specification limit of a maximum keff of 0.9. The second case analyzed a hypothetical and unrealistic loss of the 100 percent of BORAL in the OSURR wet fuel storage well. The MCNP code analysis for this case shows, with high statistical confidence, a maximum k eff of 0.968 indicating that the wet fuel storage well would remain subcritical with no BORAL. | |||
A. Kauffman Based upon the information you submitted in responses to GL 2016-01 and the results of the NRC staff review, the NRC staff has determined that the submission addresses the information requested in GL 2016-01. No further information or action is requested regarding this matter. | |||
Sincerely, | Sincerely, | ||
/RA/ | /RA/ | ||
Alexander Adams Jr., Chief Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation | Alexander Adams Jr., Chief Research and Test Reactors Licensing Branch | ||
Chief Ohio Department of Health Bureau of Environmental Health and Radiation Protection | |||
Division of Policy and Rulemaking Office of Nuclear Reactor Regulation cc: See next page Ohio State University Docket No. 50-150 | |||
cc: | |||
Chief Ohio Department of Health Bureau of Environmental Health and Radiation Protection 246 North High Street Columbus, OH 43215 | |||
Radiological Branch Chief Ohio Emergency Management Agency 2855 West Dublin-Granville Road | Radiological Branch Chief Ohio Emergency Management Agency 2855 West Dublin-Granville Road Columbus, OH 43235-2206 | ||
David B. Williams, Dean College of Engineering The Ohio State University 142A Hitchcock Hall 2070 Neil Ave. | |||
Columbus, OH 43210-1278 | Columbus, OH 43210-1278 | ||
Test, Research and Training | Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida | ||
Gainesville, FL 32611 | |||
Dr. Lei Cao, Director Nuclear Reactor Laboratory | |||
The Ohio State University 201 West 19th Avenue E402 Scott Lab | |||
Columbus, OH 43210 | |||
ML17118A322; *concurrence via e-mail OFFICE NRR/DPR/PRLB/PM NRR/DPR/PRLB/LA*NRR/DPR/PGCB/BC NRR/DPR/PRLB/BCNAME XYin NParker SStuchell AAdams DATE 5/1/17 5/1/17 5/4/17 5/4/17}} | ML17118A322; *concurrence via e-mail OFFICE NRR/DPR/PRLB/PM NRR/DPR/PRLB/LA*NRR/DPR/PGCB/BC NRR/DPR/PRLB/BCNAME XYin NParker SStuchell AAdams DATE 5/1/17 5/1/17 5/4/17 5/4/17}} | ||
Revision as of 20:06, 29 June 2018
| ML17118A322 | |
| Person / Time | |
|---|---|
| Site: | Ohio State University |
| Issue date: | 05/04/2017 |
| From: | Alexander Adams NRC/NRR/DPR/PRLB |
| To: | Kauffman A Ohio State University |
| Yin X S | |
| References | |
| CAC A11010, GL-16-001 | |
| Download: ML17118A322 (4) | |
Text
May 4, 2017
Mr. Andrew Kauffman Associate Director Nuclear Reactor Laboratory The Ohio State University
1298 Kinnear Road Columbus, OH 43212
SUBJECT:
OHIO STATE UNIVERSITY - NON-POWER REACTOR CLOSEOUT OF GENERIC LETTER 2016-01, "MONITORING OF NEUTRON-ABSORBING MATERIALS IN SPENT FUEL POOLS," FOR THE OHIO STATE UNIVERSITY RESEARCH REACTOR DOCKET NO. 50-150 (CAC NO. A11010)
On April 7, 2016, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2016-01, "Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16097A169), to address the degradation of neutron-absorbing materials (NAM) in wet storage systems for reactor fuel at power and non-power reactors.
For the non-power reactors, GL 2016-01 requested that licensees provide facility-specific information related to the use of NAM. This information was needed by the NRC staff to verify continued compliance through licensee implementation of effective methods for monitoring of reactor fuel in wet storage so as to detect and mitigate any degradation or deformation of NAM when credited in the facility licensing or design basis for criticality control of fuel in wet storage.
On March 23, 2017, you submitted a revised response to GL 2016-01 (ADAMS Accession No. ML17088A127) superseding your March 20, 2017, response (ADAMS Accession No. ML17081A442) for the Ohio State University Research Reactor (OSURR). Your most recent response to the GL added an additional Monte Carlo N-Particle (MCNP) code criticality analyses for a total of two cases. Both cases assume that the fuel storage well is fully loaded with fuel. The first case results in the need to credit one percent of the BORAL installed in the facility's wet fuel storage well to meet the OSURR technical specification limit of a maximum keff of 0.9. The second case analyzed a hypothetical and unrealistic loss of the 100 percent of BORAL in the OSURR wet fuel storage well. The MCNP code analysis for this case shows, with high statistical confidence, a maximum k eff of 0.968 indicating that the wet fuel storage well would remain subcritical with no BORAL.
A. Kauffman Based upon the information you submitted in responses to GL 2016-01 and the results of the NRC staff review, the NRC staff has determined that the submission addresses the information requested in GL 2016-01. No further information or action is requested regarding this matter.
Sincerely,
/RA/
Alexander Adams Jr., Chief Research and Test Reactors Licensing Branch
Division of Policy and Rulemaking Office of Nuclear Reactor Regulation cc: See next page Ohio State University Docket No. 50-150
cc:
Chief Ohio Department of Health Bureau of Environmental Health and Radiation Protection 246 North High Street Columbus, OH 43215
Radiological Branch Chief Ohio Emergency Management Agency 2855 West Dublin-Granville Road Columbus, OH 43235-2206
David B. Williams, Dean College of Engineering The Ohio State University 142A Hitchcock Hall 2070 Neil Ave.
Columbus, OH 43210-1278
Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida
Gainesville, FL 32611
Dr. Lei Cao, Director Nuclear Reactor Laboratory
The Ohio State University 201 West 19th Avenue E402 Scott Lab
Columbus, OH 43210
ML17118A322; *concurrence via e-mail OFFICE NRR/DPR/PRLB/PM NRR/DPR/PRLB/LA*NRR/DPR/PGCB/BC NRR/DPR/PRLB/BCNAME XYin NParker SStuchell AAdams DATE 5/1/17 5/1/17 5/4/17 5/4/17