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Category:Letter
MONTHYEARML24012A0282024-01-0808 January 2024 Administrative Change at the Ohio State University Research Reactor (OSURR) ML24002A7372024-01-0303 January 2024 Ohio State University - Change of Facility Project Manager ML23258A0892023-09-11011 September 2023 Ohio State University, Annual Report for Fy 2022/2023 IR 05000150/20232012023-03-16016 March 2023 Ohio State University - U.S. Nuclear Regulatory Commission Safety Inspection Report No. 05000150/2023201 IR 05000150/20232022023-03-13013 March 2023 Ohio State University - U.S. Nuclear Regulatory Commission Security Inspection Report No. 05000150/2023202 (Public) ML22257A1052022-09-0909 September 2022 Annual Report for the Ohio State University Research Reactor ML22070B0942022-04-12012 April 2022 Ohio State University U.S. Nuclear Regulatory Commission Safety Inspection Report ML22060A1042022-02-24024 February 2022 Report Regarding Loss of Building Exhaust Fan on February 14, 2022, While Operating the Ohio State University Research Reactor ML21267A3982021-09-13013 September 2021 Annual Report for the Ohio State University Research Reactor ML21215A0802021-08-11011 August 2021 Examination Confirmation Letter No. 50-150/OL-21-01, Ohio State University IR 05000150/20202012021-03-30030 March 2021 Ohio State University Routine Inspection Report 05000150/2020201 ML20295A4242020-11-16016 November 2020 Notification of Mailing Address Change Regarding Submittal of Fingerprint Cards ML20262H0622020-09-0909 September 2020 Annual Report for the Ohio State University Research Reactor, License R-75, Docket 50-150 ML19317D7992019-11-0606 November 2019 Replacement Pages for Modified Technical Specification 3.5 of Renewed Facility Operating License No. R-75 of the Ohio State University Research Reactor ML19298A1102019-10-22022 October 2019 Ohio State University - Revision to the Request for Modification of Technical Specifications 3.5 and 5.1.2 of Renewed Facility Operating License No. 75 ML19266A0282019-09-16016 September 2019 Annual Report for the Ohio State University Research Reactor ML19253A0512019-09-0606 September 2019 Additional Information to Support the Request for Modification of Technical Specifications 3.5 and 5.1.2 of Renewed Facility Operating License No. R-75 of the Ohio State University Research Reactor ML19105A1372019-04-10010 April 2019 Response to NRC Request for Additional Information (RAI) Letter to the Ohio State University Research Reactor (OSURR, License R-75) Dated January 16, 2019 ML19063A4992019-02-27027 February 2019 Response to NRC RAI Letter Dated 16-January-2019 Regarding License Amendment Request to Modify Technical Specifications 3.5 and 5.1.2 for License R-75 of the Ohio State University Research Reactor ML18360A3592019-01-16016 January 2019 the Ohio State University - Request for Additional Information License Amendment Request to Modify Technical Specifications 3.5 and 5.1.2 of Renewed Facility Operating License No. R-75 of the Ohio State University Research IR 05000150/20182012019-01-0909 January 2019 Ohio State University - U.S. Nuclear Regulatory Commission Safety Inspection Report 05000150/2018201 ML18324A5852018-11-14014 November 2018 Relevant Sections of the Ohio State University Research Reactor (OSURR, License R-75, Docket 50-150) Safety Analysis Report (SAR) to Support a Technical Specifications Amendment Request ML18303A1892018-10-31031 October 2018 the Ohio State University - Acceptance of Requested Licensing Action License Amendment Request to Modify Technical Specifications 3.5 and 5.1.2 of Renewed Facility Operating License No. R75 ML18291A9132018-10-16016 October 2018 Additional Information to Support a Technical Specifications Amendment Request for the Ohio State University Research Reactor (OSURR, License R-75, Docket 50-150) ML18270A1662018-10-0303 October 2018 the Ohio State University Nuclear Reactor Laboratory, Non-Acceptance of Amendment Request with Opportunity to Supplement, for the Renewed Facility License No. R-75 (CAC No. A11010/05000150) ML18267A0602018-09-18018 September 2018 the Ohio State University, Submittal of Annual Report for Fy 2017/2018 ML18242A0752018-08-27027 August 2018 Request for an Amendment to the Ohio State University Research Reactor IR 05000150/20172012018-02-13013 February 2018 Ohio State University - Nuclear Regulatory Commission Safety Inspection Report No. 50-150/2017-201 ML17285A4802017-10-18018 October 2017 the Ohio State University Nuclear Reactor Laboratory, Non-Acceptance of Amendment Request with Opportunity to Supplement, for the Renewed Facility License No. R-75 ML17244A2322017-08-22022 August 2017 Request for an Amendment to the Ohio State University Research Reactor Technical Specifications ML17118A3222017-05-0404 May 2017 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 ML17088A1272017-03-23023 March 2017 the Ohio State University - Response to Generic Letter 2016-01 ML17086A0282017-03-22022 March 2017 Ohio State University Research Reactor - Updated Emergency Plan ML17081A4422017-03-20020 March 2017 Ohio State University, Response to Generic Letter 2016-01 IR 05000150/20162022016-10-20020 October 2016 Ohio State University - Nuclear Regulatory Commission Security Inspection Report No. 50-150/2016-202 (Letter Only) ML16273A0082016-09-30030 September 2016 Ohio State University - NRC Safety Inspection Report 05000150/2016201 ML16210A4042016-07-21021 July 2016 Ohio State University, Administrative Change Update ML16200A3542016-07-13013 July 2016 the Ohio State University - Submittal of Updated Emergency Plan for the Ohio State University Research Reactor (Osurr), License R-75, Docket 50-150 ML16084A0012016-04-0101 April 2016 CAL closure letter for Ohio State ML16060A1032016-02-23023 February 2016 Request to Closeout the Compensatory Measures for the Ohio State University Research Reactor IR 05000150/20152012015-12-0404 December 2015 IR 05000150/2015201, November 2-5, 2015, Ohio State University ML15265A5212015-09-18018 September 2015 Ohio State University - Annual Report for Fy 2014/2015 ML14290A4862015-06-0303 June 2015 Y020140127 - Withdrawal of Order EA-05-007, Order Imposing Additional Security Measures IR 05000000/20001502014-11-0606 November 2014 IR 05000000-150-2014-201 on October 6-9, 2014, Ohio State University, NRC Routine Inspection Report ML14272A0942014-09-24024 September 2014 Ohio State University Research Reactor,Submittal of Annual Report for Fy 2013/2014 ML14133A7222014-05-27027 May 2014 Ohio State University - Change of Facility Project Managers ML13269A0762013-09-23023 September 2013 Ohio State University Research Reactor, Annual Report ML13226A0702013-08-12012 August 2013 Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit ML12286A0442012-10-16016 October 2012 Examination Report No. 50-150/OL-12-01, the Ohio State University ML12286A0422012-10-16016 October 2012 Examination Results Letter, No. 50-150/OL-12-01, the Ohio State University 2024-01-08
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML19105A1372019-04-10010 April 2019 Response to NRC Request for Additional Information (RAI) Letter to the Ohio State University Research Reactor (OSURR, License R-75) Dated January 16, 2019 ML19063A4992019-02-27027 February 2019 Response to NRC RAI Letter Dated 16-January-2019 Regarding License Amendment Request to Modify Technical Specifications 3.5 and 5.1.2 for License R-75 of the Ohio State University Research Reactor ML17081A4422017-03-20020 March 2017 Ohio State University, Response to Generic Letter 2016-01 2019-04-10
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01 THE OHIO STATE UNIVERSITY College of Engineering Nuclear Reactor Laboratory 1298 Kinnear Road . Columbus, OH 43212 March 20, 2017 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Xiaosong Yin One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 RE: Response to Generic Letter 2016-01 from The Ohio State University Research Reactor (OSURR), License R-75, Docket 50-150 Phone: 014-688-8220 Fax: 614-292-2209 reactor.osu.edu This resubmission of our response to GL 2016-01 originally dated October 31, 2016, removes extraneous header information.
The body of the Jetter is unchanged.
NRC Generic Letter 2016-01 requested of non-power reactor licensees answers to three questions regarding their use of neutron absorbing materials for reactor fuel storage. This letter provides answers to these questions for The Ohio State University Research Reactor (OSURR). The questions and answers follow, with the questions in italics. 1. Are neutron-absorbing materials used in a reactor pool, fuel storage pool, or other wet locations designed for the storage of reactor or spent fuel? Yes, a boron carbide and aluminum metal matrix material (Baral) is used in the OSURR fuel storage well in the form of X" Baral plates that span the width of the fuel rack in the well. 2. If neutron-absorbing materials are used, is their use credited in the licensing or design basis (i.e., criticality safety analysis) for the storage of reactor fuel or spent fuel in a reactor pool, fuel storage pool, or other wet locations, as applicable?
Yes, OSURR Technical Specification (TS) 5.4 states that kett shall not exceed 0.90 for the fuel storage well. Monte Carlo analysis indicates that the storage-well rack fully loaded with fuel elements and with the Baral plates would have kett < 0.9. Without the Baral plates, a fully-loaded rack would be subcritical but would have kett > 0.9. 3. If neutron-absorbing materials are credited in the facility licensing or design basis for the storage of reactor or spent fuel in a reactor pool, fuel storage pool, or other wet locations, as applicable, then provide a description of, and technical basis for, any surveillance or monitoring programs used to confirm continued acceptable performance of the neutron-absorbing materials over time. The Electric Power Research Institute (EPRI) published a report in July 2012 entitled "Strategy for Managing the Long Term Use of BORAL in Spent Fuel Storage Pools" (Report No. 1025204), and this report looked at long-term performance of Baral used in power-reactor spent fuel pools. The report states:* It is important to note that the corrosion observed to date has not led to any significant loss or redistribution of B-10, nor have any mechanisms been identified that would lead to either of these conditions.
1 In conjunction with fabrication and delivery of LEU fuel to the OSURR in 1988, a Monte Carlo criticality analysis was performed using KENO at Idaho National Engineering Laboratory (INEL, now Idaho National Laboratory or INL). This analysis indicated that the keff of the LEU fuel would be well belovif the TS limit for the OSURR fuel storage well fully loaded with fuel and with the Bora! plates. To expand upon this analysis from 1988, the OSURR staff has performed criticality analysis for the fuel storage well using MCNP. This effort involved creation of a detailed model of the fuel and storage well, benchmarking the model against the INEL results, and analyzing numerous configurations.
In addition to confirming that the storage well rack fully loaded with fuel elements would be under the TS limit for keff with the Bora! plates in place, the modeling shows that even if 99% of the B-10 was removed from the Bora! plates, the TS limit would still be met. Therefore, even if there were a significant loss of B-10 from the Bora! (which is very unlikely according to the EPRI report), there is no danger of exceeding the TS limit. Furthermore, the modeling shows that removal of the highest-worth Bora! plate would not result in the TS keff limit being exceeded.
When the fuel storage well covers are removed for semi-annual inventory of fuel, the plates are obviously in place as viewed from the pool top, where the OSURR staff is performing the inventory.
Therefore, the staff regularly observes that the Boral plates are in place, and even if a plate was not in place in the storage well, the TS keff limit would not be exceeded.
Finally regarding the TS keff limit, credit for the Boral plates is only needed when the reactor core is unloaded for a full fuel inspection, which typically occurs every 5 yrs or when maintenance is performed in the pool. Under normal circumstances, the majority of fuel elements are located in the reactor core, leaving only about X of the fuel elements in the fuel storage well. MCNP modeling indicates that even without Bora! plates in the fuel storage well, the fuel that is stored there under normal operating conditions does not result in keff > 0.9. Regarding blistering of Boral, the EPRI report cited above has the following to say: Similarly, in-pool blistering of BORAL has, to date, proven to primarily affect the operational aspects of the storage racks by impacting fuel assembly dimensional clearances.
In addition, it also states: For most metals, including aluminum, an increased environmental temperature produces an increased potential for corrosion.
Due to a significantly lower inventory of fission fragments in its fuel, the OSURR fuel storage well has much lower temperatures than that seen in power reactor spent-fuel pools, so the potential for the Boral plates to blister should correspondingly be lower. This assertion is supported by operational experience with the fuel storage well. When inserting or removing fuel elements from either the reactor core or the fuel storage well, the OSURR staff is mindful to notice if there is any sticking or binding, and there has been none to date. This has most recently been observed in the summer of 2016, when all of the fuel elements in the core were unloaded to the storage well and all of the fuel elements were inspected.
There was no sticking or binding of fuel elements, and there were no marks on fuel elements that would indicate scraping on the Bora! plates. 2 Therefore, given that there are no criticality concerns and there are no operational concerns, the Baral used in the OSURR fuel storage well continues to exhibit acceptable performance.
I declare under penalty of perjury that the foregoing is true and correct. Executed on 20-Mar-2017. Sincerely, Andrew C. Kauffman, Associate Director The Ohio State University Research Reactor 3