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| | issue date = 12/19/2011 | | | issue date = 12/19/2011 |
| | title = Written Communication Regarding University of Missouri - Columbia - Request for Additional Information, License Amendment, Center Test Hole | | | title = Written Communication Regarding University of Missouri - Columbia - Request for Additional Information, License Amendment, Center Test Hole |
| | author name = Fruits J L, Butler R A | | | author name = Fruits J, Butler R |
| | author affiliation = Univ of Missouri | | | author affiliation = Univ of Missouri |
| | addressee name = | | | addressee name = |
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| | page count = 6 | | | page count = 6 |
| | project = TAC:ME1876 | | | project = TAC:ME1876 |
| | stage = RAI | | | stage = Request |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNIVERSITY of MISSOURIRESEARCH REACTOR CENTERDecember 19, 2011U.S. Nuclear Regulatory CommissionAttention: Document Control DeskMail Station PI-37Washington, DC 20555-0001 1REFERENCE: Docket 50-186University of Missouri-Columbia Research ReactorAmended Facility License R-103 | | {{#Wiki_filter:UNIVERSITY of MISSOURI RESEARCH REACTOR CENTER December 19, 2011 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station PI-37 Washington, DC 20555-00011 |
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| | ==REFERENCE:== |
| | Docket 50-186 University of Missouri-Columbia Research Reactor Amended Facility License R-103 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Written communication regarding "University of Missouri -Columbia -Request forAdditional Information, Re: License Amendment, Center Test Hole (TAC No.ME1876)"By letter dated August 6, 2009, the University of Missouri-Columbia Research Reactor (MURR)submitted a request to the U.S. Nuclear Regulatory Commission (NRC) to amend the TechnicalSpecifications, which are appended to Facility License R-103, that would authorize the implementation ofan engineered safety device that would prevent operation of the reactor unless the center test hole canisteror strainer is inserted and latched onto the inner reactor pressure vessel. Approval of this Amendmentwould allow greater flexibility and capacity in the center test hole for the irradiation of high specificactivity radioisotopes that are used for radiopharmaceutical research and cancer treatments.By letter dated June 1, 2010, as part of the facility license renewal process, the NRC requested additionalinformation and clarification regarding the proposed Amendment in the form of seven (7) questions. Byletter dated August 31, 2010, the MURR responded to those questions.By letter dated December 27, 2010, the NRC requested additional information and clarification regardingthe proposed Amendment in the form of five (5) questions. By letter dated January 31, 2011, the MURRresponded to those questions.On July 1, 2011, the NRC requested additional information and clarification regarding the proposedAmendment in the formn of four (4) questions. By letter dated July 11, 2011, the MURR responded tothose questions.On December 15 and 16, 2011, by telephone and electronic mail (e-mail), the NRC (Alexander Adams,Jr., Senior Project Manager) requested clarification on the usage of the "center test hole Strainer" and itsrelationship to the Technical Specifications (TS). Enclosed is a more detailed description of the Strainerand revised TS pages based on this discussion.'W1513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: www.murr.missouri.eduFighting Cancer with Tomorrow's Technology If there are any questions regarding this response, please contact me at (573) 882-5319. I declare underpenalty of perjury that the foregoing is true and correct.Sincerely,John L. FruitsReactor ManagerENDORSEMENT:Reviewed and Approved,Ralph A. Butler, P.E.DirectorAttachments: 1. Revised Technical Specification 3.3, Pages 3 of 5 and 5 of 5xc: Reactor Advisory CommitteeReactor Safety SubcommitteeDr. Robert Duncan, Vice Chancellor for ResearchMr. Craig Basset, U.S. NRCMr. Alexander Adams, U.S. NRCMMRGE P. STWUMy0=*um~s~nE~INMudi24,2012-1'2 of 4 The center test hole Strainer is briefly described on Page 2 of the original application, dated August 6,2009, to Amend the Technical Specification appended to Facility License R-103. The Strainer is installedto preclude the possibility of any foreign objects from entering the flux trap region if the reactor isoperated without the Center Test Hole Canister inserted. The Strainer latching mechanism is of the exactsame design as that of the Center Test Hole Canister. When installed, the Strainer is positivelydetermined by a latching mechanism located at the top of the assembly. The latching mechanism consistsof two Inconel or Stainless Steel fingers which secure the Strainer to the upper portion of the inner reactorpressure vessel. The fingers, which are attached to the upper section (head piece) of the Strainer by four(two per finger) countersunk, stainless steel screws, are positioned 180 degrees apart and are totallyindependent of one another. The Strainer latching mechanism has not been modified or altered from itsoriginal design and no failures have occurred in the nearly 45 years of operation.Center Test Hole StrainerOne of Two Latching FingersInner ReactorPressure Vessel"Reactor PressureVessel HeadAs described on Page 5 of the responses, by letter dated July 11, 2011, to the Request for AdditionalInformation (RAI), a special removal tool, with an overall length of approximately 20 feet, is required tounlatch and remove the center test hole canister from the inner pressure vessel. The head of the removaltool must be inserted into the center test hole canister wear ring in order to spread the latching fingers3 of 4 sufficiently to disengage the canister from the inner pressure vessel. This same tool is also used toremove the Strainer from the inner pressure vessel.The overall length of the center test hole Strainer is only 7 inches; therefore it does not enter into the fluxtrap region of the core and hence there is no reactivity contribution to the reactor when it is installed.Essentially, the only time that it is used is to perform reactivity measurements of the center test holecanister (empty and with experiments loaded) at very low powers (at or below 50 kW, or less than 0.5%of the MURR full core power level of 10 MW). Reactivity measurement methodology was previouslydescribed in detail in the response to Question 10.5.e, by letter dated August 31, 2010, from therelicensing RAIs, by letter dated June 1, 2010.Below are two photographs of the center test hole Strainer.4 of 4 TECHNICAL SPECIFICATIONUNIVERSITY OF MISSOURIRESEARCH REACTOR FACILITYNumber 3.3Page 3 of 5DateAmendment No. | | Written communication regarding "University of Missouri - Columbia - Request for Additional Information, Re: License Amendment, Center Test Hole (TAC No. |
| | ME1876)" |
| | By letter dated August 6, 2009, the University of Missouri-Columbia Research Reactor (MURR) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) to amend the Technical Specifications, which are appended to Facility License R-103, that would authorize the implementation of an engineered safety device that would prevent operation of the reactor unless the center test hole canister or strainer is inserted and latched onto the inner reactor pressure vessel. Approval of this Amendment would allow greater flexibility and capacity in the center test hole for the irradiation of high specific activity radioisotopes that are used for radiopharmaceutical research and cancer treatments. |
| | By letter dated June 1, 2010, as part of the facility license renewal process, the NRC requested additional information and clarification regarding the proposed Amendment in the form of seven (7) questions. By letter dated August 31, 2010, the MURR responded to those questions. |
| | By letter dated December 27, 2010, the NRC requested additional information and clarification regarding the proposed Amendment in the form of five (5) questions. By letter dated January 31, 2011, the MURR responded to those questions. |
| | On July 1, 2011, the NRC requested additional information and clarification regarding the proposed Amendment in the formn of four (4) questions. By letter dated July 11, 2011, the MURR responded to those questions. |
| | On December 15 and 16, 2011, by telephone and electronic mail (e-mail), the NRC (Alexander Adams, Jr., Senior Project Manager) requested clarification on the usage of the "center test hole Strainer" and its relationship to the Technical Specifications (TS). Enclosed is a more detailed description of the Strainer and revised TS pages based on this discussion. |
| | 'W 1513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: www.murr.missouri.edu Fighting Cancerwith Tomorrow's Technology |
| | |
| | If there are any questions regarding this response, please contact me at (573) 882-5319. I declare under penalty of perjury that the foregoing is true and correct. |
| | ENDORSEMENT: |
| | Sincerely, Reviewed and Approved, John L. Fruits Ralph A. Butler, P.E. |
| | Reactor Manager Director Attachments: 1. Revised Technical Specification 3.3, Pages 3 of 5 and 5 of 5 MMRGE P.STWU xc: Reactor Advisory Committee My0=*um~s~nE~IN Reactor Safety Subcommittee Mudi24,2012 Dr. Robert Duncan, Vice Chancellor for Research Mr. Craig Basset, U.S. NRC Mr. Alexander Adams, U.S. NRC -1' 2 of 4 |
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| | The center test hole Strainer is briefly described on Page 2 of the original application, dated August 6, 2009, to Amend the Technical Specification appended to Facility License R-103. The Strainer is installed to preclude the possibility of any foreign objects from entering the flux trap region if the reactor is operated without the Center Test Hole Canister inserted. The Strainer latching mechanism is of the exact same design as that of the Center Test Hole Canister. When installed, the Strainer is positively determined by a latching mechanism located at the top of the assembly. The latching mechanism consists of two Inconel or Stainless Steel fingers which secure the Strainer to the upper portion of the inner reactor pressure vessel. The fingers, which are attached to the upper section (head piece) of the Strainer by four (two per finger) countersunk, stainless steel screws, are positioned 180 degrees apart and are totally independent of one another. The Strainer latching mechanism has not been modified or altered from its original design and no failures have occurred in the nearly 45 years of operation. |
| | Center Test Hole Strainer One of Two Latching Fingers Inner Reactor Reactor Pressure Pressure Vessel" Vessel Head As described on Page 5 of the responses, by letter dated July 11, 2011, to the Request for Additional Information (RAI), a special removal tool, with an overall length of approximately 20 feet, is required to unlatch and remove the center test hole canister from the inner pressure vessel. The head of the removal tool must be inserted into the center test hole canister wear ring in order to spread the latching fingers 3 of 4 |
| | |
| | sufficiently to disengage the canister from the inner pressure vessel. This same tool is also used to remove the Strainer from the inner pressure vessel. |
| | The overall length of the center test hole Strainer is only 7 inches; therefore it does not enter into the flux trap region of the core and hence there is no reactivity contribution to the reactor when it is installed. |
| | Essentially, the only time that it is used is to perform reactivity measurements of the center test hole canister (empty and with experiments loaded) at very low powers (at or below 50 kW, or less than 0.5% |
| | of the MURR full core power level of 10 MW). Reactivity measurement methodology was previously described in detail in the response to Question 10.5.e, by letter dated August 31, 2010, from the relicensing RAIs, by letter dated June 1, 2010. |
| | Below are two photographs of the center test hole Strainer. |
| | 4 of 4 |
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| | TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY Number 3.3 Page 3 of 5 Date Amendment No. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Reactor Safety System (continued)Manual Scram 1 1 1 Push Button at Control ConsoleCenter Test Hole 2(6) 2(6) 2(6) Scram as a result of removing the center testhole removable experiment test tubes or strainer(I) Flow orifice or heat exchanger AP (psi) in each operating heat exchanger legcorresponding to the flow value in the table.(2) Not required below 50 KW operation if natural convection flange and pressurevessel cover are removed or in operation with the reactor subcritical by amargin of at least 0.0 15 AK.(3) Trip pressure is that which corresponds to the pressurizer pressure indicatedin the table with normal primary coolant flow.(4) Flow orifice AP (psi) corresponding to the flow value in the table.(5) Core AP (psi) corresponding to the core flow value in the table.(6) Not required if reactivity worth of the center test hole removable experiment test tubes and itscontents or the strainer is less than the reactivity limit of specification 3.1 .h. This safety functionshall only be bypassed with specific authorization from the Reactor Manager.Basesa. The specifications on high power, primary coolant flow, primary coolant pressure,and reactor inlet temperature provide for the safety system settings outlined inspecifications 2.2.a, 2.2.b, and 2.2.c. In Mode I and II operation the coredifferential temperature is approximately 17 F. | | Reactor Safety System (continued) |
| TECHNICAL SPECIFICATIONUNIVERSITY OF MISSOURIRESEARCH REACTOR FACILITYNumber 3.3Page 5 of 5DateAmendment No. | | Manual Scram 1 1 1 Push Button at Control Console Center Test Hole 2(6) 2(6) 2(6) Scram as a result of removing the center test hole removable experiment test tubes or strainer (I) Flow orifice or heat exchanger AP (psi) in each operating heat exchanger leg corresponding to the flow value in the table. |
| | (2) Not required below 50 KW operation if natural convection flange and pressure vessel cover are removed or in operation with the reactor subcritical by a margin of at least 0.0 15 AK. |
| | (3) Trip pressure is that which corresponds to the pressurizer pressure indicated in the table with normal primary coolant flow. |
| | (4) Flow orifice AP (psi) corresponding to the flow value in the table. |
| | (5) Core AP (psi) corresponding to the core flow value in the table. |
| | (6) Not required if reactivity worth of the center test hole removable experiment test tubes and its contents or the strainer is less than the reactivity limit of specification 3.1 .h. This safety function shall only be bypassed with specific authorization from the Reactor Manager. |
| | Bases |
| | : a. The specifications on high power, primary coolant flow, primary coolant pressure, and reactor inlet temperature provide for the safety system settings outlined in specifications 2.2.a, 2.2.b, and 2.2.c. In Mode I and II operation the core differential temperature is approximately 17 F. |
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| | TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY Number 3.3 Page 5 of 5 Date Amendment No. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Reactor Safety System (continued)The scrams from the primary and pool coolant isolation valves (507A/B and509) leaving their full open position provide a first line of protectionfor a loss of flow accident in that system initiated by an inadvertentclosure of the isolation valve/s.The power level interlock (PLI) scram provides assurance that the reactorcannot be operated with a power level greater than that authorized for themode of operation selected on the Mode Selector Switch. The PLI scram alsoprovides the interlock to assure that the reactor cannot be operated inMode I with a pool or primary coolant flow scram by-passed.The facility evacuation and reactor isolation scrams provide assurance thatthe reactor is shutdown for any condition which initiates or leads to theinitiation of an evacuation or isolation.The manual scram provides assurance that the reactor can be shutdown by theoperator if an automatic function fails to initiate a scram or if the opera-tor detects an impending unsafe condition prior to the automatic scraminitiation.The center test hole scram provides assurance that the reactor can not beoperated unless the removable experiment test tubes or the strainer is insertedand latched in the center test hole. This is required any time the reactivityworth of the center test hole removable experiment test tubesand the contained experiments or the strainer exceeds the limit of specification 3.1 .h.(Ref. Section 3.5 of Add. 3 to HSR). The center test hole scram may bebypassed if the total reactivity worth of the removable experiment test tubesand the contained experiments or the strainer does not exceed the limit of specification 3.1 .hand is authorized by the Reactor Manger. | | Reactor Safety System (continued) |
| }} | | The scrams from the primary and pool coolant isolation valves (507A/B and 509) leaving their full open position provide a first line of protection for a loss of flow accident in that system initiated by an inadvertent closure of the isolation valve/s. |
| | The power level interlock (PLI) scram provides assurance that the reactor cannot be operated with a power level greater than that authorized for the mode of operation selected on the Mode Selector Switch. The PLI scram also provides the interlock to assure that the reactor cannot be operated in Mode I with a pool or primary coolant flow scram by-passed. |
| | The facility evacuation and reactor isolation scrams provide assurance that the reactor is shutdown for any condition which initiates or leads to the initiation of an evacuation or isolation. |
| | The manual scram provides assurance that the reactor can be shutdown by the operator if an automatic function fails to initiate a scram or if the opera-tor detects an impending unsafe condition prior to the automatic scram initiation. |
| | The center test hole scram provides assurance that the reactor can not be operated unless the removable experiment test tubes or the strainer is inserted and latched in the center test hole. This is required any time the reactivity worth of the center test hole removable experiment test tubes and the contained experiments or the strainer exceeds the limit of specification 3.1 .h. |
| | (Ref. Section 3.5 of Add. 3 to HSR). The center test hole scram may be bypassed if the total reactivity worth of the removable experiment test tubes and the contained experiments or the strainer does not exceed the limit of specification 3.1 .h and is authorized by the Reactor Manger.}} |
Letter Sequence Request |
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MONTHYEARML1035606622010-12-27027 December 2010 University of Missouri - Columbia - Request for Additional Information License Amendment Center Test Hole Project stage: RAI ML1117515642011-07-0101 July 2011 University of Missouri - Columbia - Request for Additional Information License Amendment, Center Test Hole (TAC N0. ME1876) Project stage: RAI ML11193A2652011-07-11011 July 2011 University of Missouri-Columbia Research Reactor Response to NRC Most Recent Request for Additional Information Regarding Proposed Amendment to Technical Specifications Appended to Facility License R-103 Project stage: Request ML11356A0842011-12-19019 December 2011 Transmittal Letter Response to a Recent Discussion with Alexander Adams, Jr., Senior Project Manager, Regarding Application Project stage: Request ML11356A0852011-12-19019 December 2011 Written Communication Regarding University of Missouri - Columbia - Request for Additional Information, License Amendment, Center Test Hole Project stage: Request ML1200502562012-02-0909 February 2012 University of Missouri-Columbia, Issuance of Amendment No. 35 to Amended Facility License No. R-103 Flux-Trap Irradiations Reactivity Safety Trip Device Project stage: Approval ML13144A7672013-05-28028 May 2013 RAI for Review Regarding Relief Request I3R-11 Reactor Vessel Closure Head Nozzles Inservice Inspection Program - Third Interval Project stage: RAI ML13150A0712013-05-31031 May 2013 Verbal Authorization of Relief Request I3R-11 for Reactor Vessel Closure Head Penetration Nozzel Repair Inservice Inspection Program - Third 10-Year Interval Project stage: Other 2011-07-11
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Category:Letter
MONTHYEARIR 05000186/20232022023-12-12012 December 2023 the Curators of the University of Missouri - U.S. Nuclear Regulatory Commission Safety Inspection Report No. 05000186/2023202 ML23198A0232023-08-29029 August 2023 Examination Result Letter No. 50-186/OL-23-02, University of Missouri-Columbia ML23198A0222023-08-29029 August 2023 Examination Report Letter No. 50-186/OL-23-02, University of Missouri - Columbia ML23221A1172023-08-0303 August 2023 Written Communication as Specified by 10 CFR 50.4(b)(4) Regarding the Submittal of the Physical Security Plan for the University of Missouri Research Reactor as a Part of the Process to Renew Amended Facility Operating License R-103 ML23213A0592023-08-0101 August 2023 Written Communication as Specified by University of Missouri Research Reactor Technical Specification 6.6.2(d) Regarding a Permanent Change in the Facility Organization Involving the Executive Director IR 05000186/20232012023-07-31031 July 2023 the Curators of the University of Missouri U.S. Nuclear Regulatory Commission Safety Inspection Report No. 05000186/2023201 ML23186A2132023-07-31031 July 2023 Examination Confirmation Letter No. 50-186/OL-23-03, University of Missouri - Columbia ML23124A0422023-05-0808 May 2023 Examination Confirmation Letter 50-186/OL-23-02, University of Missouri - Columbia ML23103A0742023-04-10010 April 2023 University of Missouri, Columbia Research Reactor, Shipment of Radioactive Material Shipment Identifier MURR 23-01 Highway Route Controlled Quantity ML23024A2772023-04-0707 April 2023 Cover Letter for the Security Inspection Report for the University of Missouri (Public) - October 2022 ML23087A1142023-03-29029 March 2023 Examination Results Letter No. 50-186/OL-23-01, University of Missouri - Columbia ML23089A3162023-03-29029 March 2023 Letter Notifying Univ. of Missouri That Us Dept. of Energy Funding Will Not Be Available in Fiscal Year 2023 to Complete the Conversion of MURR to LEU Fuel ML23087A1132023-03-29029 March 2023 Examination Report No. 50-186/OL-23-01, University of Missouri-Columbia ML23055B1372023-02-24024 February 2023 Submittal of Annual Operating Report for the University of Missouri-Columbia Research Reactor as Required by MURR Technical Specification 6.6.e IR 05000186/20222022023-02-23023 February 2023 the Curators of the University of Missouri - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000186/2022202 - Cover Letter and Enclosure ML23031A0132023-02-14014 February 2023 Examination Confirmation Letter No. 50-186/OL-23-01, University of Missouri-Columbia ML23017A2072023-01-13013 January 2023 Written Communication as Required by University of Missouri Research Reactor Technical Specification 6.6.c(3) Regarding a Deviation from Technical Specification 6.1.f ML22349A0422022-12-0808 December 2022 Written Communication as Specified in 10 CFR 50.54(b)(5) Regarding Changes to the University of Missouri-Columbia Research Reactor Facility Emergency Plan Without Prior Commission Approval Pursuant to 10 CFR 50.54(q)(3) ML22314A2102022-11-0909 November 2022 Written Communication as Required by Technical Specification 6.6.d(2), Other Reports, Regarding a Change in University of Missouri-Columbia Research Reactor Organization Involving the Reactor Facility Director ML22304A0042022-10-27027 October 2022 University of Missouri - Columbia, Shipment of Radioactive Material, Highway Route Controlled Quantity ML22291A0322022-10-14014 October 2022 University of Missouri Written Communication as Required by 10 CFR 73, Appendix G Regarding a Deviation from the MURR Physical Security Plan ML22290A0042022-10-12012 October 2022 University of Missouri-Columbia Research Reactor, Reportable Event Report Pursuant to 20.2201(a)(ii) Regarding Loss of Licensed Material During Shipment IR 05000186/20222012022-06-14014 June 2022 the Curators of the University of Missouri - U.S. NRC Routine Inspection Report No. 05000186/2022201 ML22158A0792022-06-0606 June 2022 Submittal of Revised Annual Operating Report for the University of Missouri-Columbia Research Reactor as Required by MURR Technical Specification 6.6.e ML22097A0592022-04-0707 April 2022 Approval for Spent Nuclear Fuel Highway Route Application - NRC Route No. 182D - Docket Number 050-0186 ML22088A0782022-03-25025 March 2022 Univ. of Missouri, Federal Funding for the Conversion of the Columbia Research Reactor from Highly-Enriched Uranium Fuel to Low-Enriched Uranium Fuel IR 05000186/20212032022-03-0202 March 2022 the Curators of the University of Missouri U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000186/2021203 ML22056A5162022-02-25025 February 2022 Submittal of Annual Operating Report for the University of Missouri-Columbia Research Reactor as Required by MURR Technical Specification 6.6.e ML22038A6012022-02-0808 February 2022 Acceptance for Spent Nuclear Fuel Highway Route Application NRC No. 182D-Docket No. 050-0186 ML22013B1412022-01-21021 January 2022 Examination Confirmation Letter No. 50-186-OL-22-02, University of Missouri-Columbia ML21327A3042021-11-23023 November 2021 Written Communication as Required by University of Missouri Research Reactor Technical Specification 6.6.c(3) Regarding a Deviation from Technical Specification 3.2.f.6 ML21298A1972021-10-25025 October 2021 University of Missouri-Columbia Research Reactor - Written Communication as Required by University of Missouri Research Reactor Technical Specification 6.6.c(3) Regarding a Deviation from Technical Specification 3.2.g.6 ML21253A2482021-09-23023 September 2021 Examination Confirmation Letter No. 50-186/OL-22-01, University of Missouri Columbia ML21221A3252021-08-0909 August 2021 University of Missouri-Columbia Research Reactor, Written Communication as Required by Technical Specification 6.6.c(3) Regarding a Deviation from Technical Specifications 3.2.a ML21217A2982021-08-0505 August 2021 University of Missouri-Columbia Research Reactor - Reportable Event Report Pursuant to 20.2203(a)(2)(iv) ML21215A4982021-07-0707 July 2021 Univ of Missouri, Submittal of Revised Road Transportation Security Plan for the Shipment of Irradiated Reactor Fuel ML21098A1992021-06-10010 June 2021 the Curators of the University of Missouri Issuance of Amendment No. 40 to Renewed Facility Operating License No. R 103 to Amend Technical Specifications 6.2 and 6.4 for the University of Missouri Columbia Research Reactor IR 05000186/20212022021-05-28028 May 2021 the Curators of the University of Missouri - U.S. Nuclear Commission Routine Inspection Report No. 05000186/2021202 IR 05000186/20212012021-05-27027 May 2021 University of Missouri-Columbia U. S. Nuclear Regulatory Commission Security Inspection Report No. 05000186/2021201 - Non-OUO-Sri Cover Letter ML21118A9682021-04-28028 April 2021 Examination Confirmation Letter No. 50-186/OL-21-01, University of Missouri-Columbia ML21092A1712021-04-0202 April 2021 University of Missouri-Columbia Research Reactor - Federal Funding for the Conversion of the University of Missouri-Columbia Research Reactor from Highly-Enriched Uranium Fuel to Low-Enriched Uranium Fuel ML21078A5002021-03-19019 March 2021 University of Missouri-Columbia Research Reactor Written Communication as Specified by 10 CFR 20.1007 Regarding a Reportable Event Pursuant to 20.2203(a)(2)(iv) ML21075A2922021-03-16016 March 2021 Written Communication as Specified by 10 CFR 50.4(b)(l) Requesting U.S. Nuclear Regulatory Commission Approval to Revise the Technical Specifications Appended to Renewed Facility Operating License No. R-103 Pursuant to 10 CFR 50.90 IR 05000186/20202022021-03-12012 March 2021 University of Missouri - Columbia - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000186/2020202 - Cover Letter and Enclosure ML21050A2512021-02-19019 February 2021 Submittal of Annual Operating Report for the University of Missouri-Columbia Research Reactor as Required by MURR Technical Specification 6.6.e ML21041A5402021-02-10010 February 2021 Univ. of Missouri-Columbia Research Reactor - Written Communication as Specified by Univ. of Missouri Research Reactor Tech Spec 6.6.d(2) Regarding a Permanent Change in the Facility Organization Involving the Office of the Chancellor ML20295A4242020-11-16016 November 2020 Notification of Mailing Address Change Regarding Submittal of Fingerprint Cards ML20287A5432020-10-0909 October 2020 University of Missouri, Columbia Research Reactor - Written Report, in Accordance with IO CFR 71.1, as Required by IO CFR 71. 9 5(b) for NRC Docket 71-9338), Regarding Conditions in the Certificate of Compliance for the Safkeg-HS 3977A, Us ML20238C0812020-09-28028 September 2020 Examination Report Letter No. 50-186/OL-20-01, University of Missouri-Columbia IR 05000186/20202012020-07-10010 July 2020 University of Missouri-Columbia - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000186/2020-201 - Cover Letter and Enclosure 2023-08-03
[Table view] Category:Technical Specification
MONTHYEARML21075A2922021-03-16016 March 2021 Written Communication as Specified by 10 CFR 50.4(b)(l) Requesting U.S. Nuclear Regulatory Commission Approval to Revise the Technical Specifications Appended to Renewed Facility Operating License No. R-103 Pursuant to 10 CFR 50.90 ML20153A4602020-06-0101 June 2020 Univ. of Missouri - Written Communication as Specified by 10 CFR 50.4(b)(l) Regarding Revisions to the Bases for Technical Specifications 3.4.a, 3.4.b, and 4.4.a ML19263A6632019-09-18018 September 2019 Univ. of Missouri - Written Communication as Specified by 10 CFR 50.4(b)(l) Requesting U.S. Nuclear Regulatory Commission Approval to Revise the Technical Specifications Appended to Renewed Facility Operating License No. R-103 Pursuant to 1 ML18319A0962018-11-13013 November 2018 University of Missouri-Columbia Research Reactor, Supplemental Information to Support a Revision to the Technical Specifications Appended to Renewed Facility Operating License No. R-103 Pursuant to 10 CPR 50.90 ML18109A0392018-04-17017 April 2018 Written Communication as Specified by 10 CFR 50.4(b)(l) Requesting U.S. Nuclear Regulatory Commission Approval to Revise the Technical Specifications Appended to Renewed Facility Operating License No. R-103 Pursuant to 10 CFR 50.90 ML15203A8672015-07-20020 July 2015 Written Communication as Specified by 10 CFR 50.4(b)(1) Requesting U.S. Nuclear Regulatory Commission Approval to Amend the Technical Specifications Appended to Amended Facility License No. R-103 Pursuant to 10 CFR 50.59(c) and 10 CFR 50.90 ML15203A8512015-07-20020 July 2015 Written Communication as Specified by 10 CFR 50.4(b)(1) Requesting U.S. Nuclear Regulatory Commission Approval to Amend the Technical Specifications Appended to Amended Facility License No. R-103 Pursuant to 10 CFR 50.59(c) and 10 CFR 50.90 ML15203A8552015-07-20020 July 2015 Written Communication as Specified by 10 CFR 50.4(b)(1) Requesting U.S. Nuclear Regulatory Commission Approval to Amend the Technical Specifications Appended to Amended Facility License No. R-103 Pursuant to 10 CFR 50.59(c) and 10 CFR 50.90 ML14030A1322014-01-27027 January 2014 Letter from the University of Missouri-Columbia Research Reactor Regarding Amended Facility License R-103 ML11356A0852011-12-19019 December 2011 Written Communication Regarding University of Missouri - Columbia - Request for Additional Information, License Amendment, Center Test Hole ML0716301312007-06-0808 June 2007 University of Missouri - Columbia Research Reactor, Request to Amend the Technical Specifications Appended to License R-103 ML0716301252007-06-0808 June 2007 University of Missouri - Columbia Research Reactor, Request to Amend the Technical Specifications Appended to License R-103 2021-03-16
[Table view] Category:Amendment
MONTHYEARML21075A2922021-03-16016 March 2021 Written Communication as Specified by 10 CFR 50.4(b)(l) Requesting U.S. Nuclear Regulatory Commission Approval to Revise the Technical Specifications Appended to Renewed Facility Operating License No. R-103 Pursuant to 10 CFR 50.90 ML19263A6632019-09-18018 September 2019 Univ. of Missouri - Written Communication as Specified by 10 CFR 50.4(b)(l) Requesting U.S. Nuclear Regulatory Commission Approval to Revise the Technical Specifications Appended to Renewed Facility Operating License No. R-103 Pursuant to 1 ML18319A0962018-11-13013 November 2018 University of Missouri-Columbia Research Reactor, Supplemental Information to Support a Revision to the Technical Specifications Appended to Renewed Facility Operating License No. R-103 Pursuant to 10 CPR 50.90 ML18109A0392018-04-17017 April 2018 Written Communication as Specified by 10 CFR 50.4(b)(l) Requesting U.S. Nuclear Regulatory Commission Approval to Revise the Technical Specifications Appended to Renewed Facility Operating License No. R-103 Pursuant to 10 CFR 50.90 ML15203A8672015-07-20020 July 2015 Written Communication as Specified by 10 CFR 50.4(b)(1) Requesting U.S. Nuclear Regulatory Commission Approval to Amend the Technical Specifications Appended to Amended Facility License No. R-103 Pursuant to 10 CFR 50.59(c) and 10 CFR 50.90 ML15203A8512015-07-20020 July 2015 Written Communication as Specified by 10 CFR 50.4(b)(1) Requesting U.S. Nuclear Regulatory Commission Approval to Amend the Technical Specifications Appended to Amended Facility License No. R-103 Pursuant to 10 CFR 50.59(c) and 10 CFR 50.90 ML15203A8552015-07-20020 July 2015 Written Communication as Specified by 10 CFR 50.4(b)(1) Requesting U.S. Nuclear Regulatory Commission Approval to Amend the Technical Specifications Appended to Amended Facility License No. R-103 Pursuant to 10 CFR 50.59(c) and 10 CFR 50.90 ML14030A1322014-01-27027 January 2014 Letter from the University of Missouri-Columbia Research Reactor Regarding Amended Facility License R-103 ML11356A0852011-12-19019 December 2011 Written Communication Regarding University of Missouri - Columbia - Request for Additional Information, License Amendment, Center Test Hole ML0716301312007-06-0808 June 2007 University of Missouri - Columbia Research Reactor, Request to Amend the Technical Specifications Appended to License R-103 ML0716301252007-06-0808 June 2007 University of Missouri - Columbia Research Reactor, Request to Amend the Technical Specifications Appended to License R-103 2021-03-16
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UNIVERSITY of MISSOURI RESEARCH REACTOR CENTER December 19, 2011 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station PI-37 Washington, DC 20555-00011
REFERENCE:
Docket 50-186 University of Missouri-Columbia Research Reactor Amended Facility License R-103
SUBJECT:
Written communication regarding "University of Missouri - Columbia - Request for Additional Information, Re: License Amendment, Center Test Hole (TAC No.
ME1876)"
By letter dated August 6, 2009, the University of Missouri-Columbia Research Reactor (MURR) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) to amend the Technical Specifications, which are appended to Facility License R-103, that would authorize the implementation of an engineered safety device that would prevent operation of the reactor unless the center test hole canister or strainer is inserted and latched onto the inner reactor pressure vessel. Approval of this Amendment would allow greater flexibility and capacity in the center test hole for the irradiation of high specific activity radioisotopes that are used for radiopharmaceutical research and cancer treatments.
By letter dated June 1, 2010, as part of the facility license renewal process, the NRC requested additional information and clarification regarding the proposed Amendment in the form of seven (7) questions. By letter dated August 31, 2010, the MURR responded to those questions.
By letter dated December 27, 2010, the NRC requested additional information and clarification regarding the proposed Amendment in the form of five (5) questions. By letter dated January 31, 2011, the MURR responded to those questions.
On July 1, 2011, the NRC requested additional information and clarification regarding the proposed Amendment in the formn of four (4) questions. By letter dated July 11, 2011, the MURR responded to those questions.
On December 15 and 16, 2011, by telephone and electronic mail (e-mail), the NRC (Alexander Adams, Jr., Senior Project Manager) requested clarification on the usage of the "center test hole Strainer" and its relationship to the Technical Specifications (TS). Enclosed is a more detailed description of the Strainer and revised TS pages based on this discussion.
'W 1513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: www.murr.missouri.edu Fighting Cancerwith Tomorrow's Technology
If there are any questions regarding this response, please contact me at (573) 882-5319. I declare under penalty of perjury that the foregoing is true and correct.
ENDORSEMENT:
Sincerely, Reviewed and Approved, John L. Fruits Ralph A. Butler, P.E.
Reactor Manager Director Attachments: 1. Revised Technical Specification 3.3, Pages 3 of 5 and 5 of 5 MMRGE P.STWU xc: Reactor Advisory Committee My0=*um~s~nE~IN Reactor Safety Subcommittee Mudi24,2012 Dr. Robert Duncan, Vice Chancellor for Research Mr. Craig Basset, U.S. NRC Mr. Alexander Adams, U.S. NRC -1' 2 of 4
The center test hole Strainer is briefly described on Page 2 of the original application, dated August 6, 2009, to Amend the Technical Specification appended to Facility License R-103. The Strainer is installed to preclude the possibility of any foreign objects from entering the flux trap region if the reactor is operated without the Center Test Hole Canister inserted. The Strainer latching mechanism is of the exact same design as that of the Center Test Hole Canister. When installed, the Strainer is positively determined by a latching mechanism located at the top of the assembly. The latching mechanism consists of two Inconel or Stainless Steel fingers which secure the Strainer to the upper portion of the inner reactor pressure vessel. The fingers, which are attached to the upper section (head piece) of the Strainer by four (two per finger) countersunk, stainless steel screws, are positioned 180 degrees apart and are totally independent of one another. The Strainer latching mechanism has not been modified or altered from its original design and no failures have occurred in the nearly 45 years of operation.
Center Test Hole Strainer One of Two Latching Fingers Inner Reactor Reactor Pressure Pressure Vessel" Vessel Head As described on Page 5 of the responses, by letter dated July 11, 2011, to the Request for Additional Information (RAI), a special removal tool, with an overall length of approximately 20 feet, is required to unlatch and remove the center test hole canister from the inner pressure vessel. The head of the removal tool must be inserted into the center test hole canister wear ring in order to spread the latching fingers 3 of 4
sufficiently to disengage the canister from the inner pressure vessel. This same tool is also used to remove the Strainer from the inner pressure vessel.
The overall length of the center test hole Strainer is only 7 inches; therefore it does not enter into the flux trap region of the core and hence there is no reactivity contribution to the reactor when it is installed.
Essentially, the only time that it is used is to perform reactivity measurements of the center test hole canister (empty and with experiments loaded) at very low powers (at or below 50 kW, or less than 0.5%
of the MURR full core power level of 10 MW). Reactivity measurement methodology was previously described in detail in the response to Question 10.5.e, by letter dated August 31, 2010, from the relicensing RAIs, by letter dated June 1, 2010.
Below are two photographs of the center test hole Strainer.
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TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY Number 3.3 Page 3 of 5 Date Amendment No.
SUBJECT:
Reactor Safety System (continued)
Manual Scram 1 1 1 Push Button at Control Console Center Test Hole 2(6) 2(6) 2(6) Scram as a result of removing the center test hole removable experiment test tubes or strainer (I) Flow orifice or heat exchanger AP (psi) in each operating heat exchanger leg corresponding to the flow value in the table.
(2) Not required below 50 KW operation if natural convection flange and pressure vessel cover are removed or in operation with the reactor subcritical by a margin of at least 0.0 15 AK.
(3) Trip pressure is that which corresponds to the pressurizer pressure indicated in the table with normal primary coolant flow.
(4) Flow orifice AP (psi) corresponding to the flow value in the table.
(5) Core AP (psi) corresponding to the core flow value in the table.
(6) Not required if reactivity worth of the center test hole removable experiment test tubes and its contents or the strainer is less than the reactivity limit of specification 3.1 .h. This safety function shall only be bypassed with specific authorization from the Reactor Manager.
Bases
- a. The specifications on high power, primary coolant flow, primary coolant pressure, and reactor inlet temperature provide for the safety system settings outlined in specifications 2.2.a, 2.2.b, and 2.2.c. In Mode I and II operation the core differential temperature is approximately 17 F.
TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY Number 3.3 Page 5 of 5 Date Amendment No.
SUBJECT:
Reactor Safety System (continued)
The scrams from the primary and pool coolant isolation valves (507A/B and 509) leaving their full open position provide a first line of protection for a loss of flow accident in that system initiated by an inadvertent closure of the isolation valve/s.
The power level interlock (PLI) scram provides assurance that the reactor cannot be operated with a power level greater than that authorized for the mode of operation selected on the Mode Selector Switch. The PLI scram also provides the interlock to assure that the reactor cannot be operated in Mode I with a pool or primary coolant flow scram by-passed.
The facility evacuation and reactor isolation scrams provide assurance that the reactor is shutdown for any condition which initiates or leads to the initiation of an evacuation or isolation.
The manual scram provides assurance that the reactor can be shutdown by the operator if an automatic function fails to initiate a scram or if the opera-tor detects an impending unsafe condition prior to the automatic scram initiation.
The center test hole scram provides assurance that the reactor can not be operated unless the removable experiment test tubes or the strainer is inserted and latched in the center test hole. This is required any time the reactivity worth of the center test hole removable experiment test tubes and the contained experiments or the strainer exceeds the limit of specification 3.1 .h.
(Ref. Section 3.5 of Add. 3 to HSR). The center test hole scram may be bypassed if the total reactivity worth of the removable experiment test tubes and the contained experiments or the strainer does not exceed the limit of specification 3.1 .h and is authorized by the Reactor Manger.