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MONTHYEARML0620600262006-10-0303 October 2006 Request for Additional Information Regarding License Renewal, Oregon State University Triga Reactor Project stage: RAI ML0632101822006-11-10010 November 2006 Oregon State University Triga Reactor (Ostr), Request for Extension 60 Days to Respond to the Request for Additional Information Regarding License Renewal Project stage: Request ML0633205002006-11-21021 November 2006 Oregon State University Response to Request for Additional Information Regarding License Renewal, Osu Triga Reactor, Dated October 3, 2006 Project stage: Response to RAI ML0713000102007-05-21021 May 2007 Oregon State University - Request for Additional Information Regarding License Renewal Request Project stage: RAI ML0714503072007-06-0707 June 2007 Determination of Acceptability and Sufficiency for Docketing and Opportunity for a Hearing Regarding the Application from the Oregon State University for Renewal of the Facility License for the Oregon State University Triga Reactor (Ostr) Project stage: Other ML0723305292007-06-25025 June 2007 Oregon State University Triga Reactor, Request for Extension of 45 Days to Respond to the RAI Re License Renewal, Dated May 21, 2007 Project stage: Request ML0721503622007-07-10010 July 2007 Oregon State University Response to RAI Regarding License Renewal, Oregon State University Triga Reactor Dated May 21, 2007 Project stage: Response to RAI ML0721503632007-07-27027 July 2007 Additional Oregon State University Response to RAI Regarding License Renewal, Oregon State University Triga Reactor Dated May 21, 2007 Project stage: Response to RAI ML0721900432007-07-31031 July 2007 Oregon State University Triga Reactor (Ostr), Decommissioning Funding Statement of Intent Project stage: Other ML0723405802007-08-0606 August 2007 Response to Request for Additional Information (RAI) Regarding License Renewal, Oregon State University Triga Reactor Dated May 21, 2007 Project stage: Response to RAI ML0807101392008-03-19019 March 2008 Oregon State University - Request for Additional Information Regarding License Renewal Request Project stage: RAI ML0822703832008-08-11011 August 2008 Oregon State University Submission of Relicensing Technical Specifications Revision J Project stage: Request ML0616501972008-09-0202 September 2008 Oregon State University Triga Reactor Environmental Assessment Regarding Amendment for Renewal of Facility Operating License No. R-106 Project stage: Other ML0825305092008-09-10010 September 2008 Technical Specifications for the Renewed Facility License No. R-106 for the Oregon State University Triga Reactor Project stage: Other ML0825200472008-09-10010 September 2008 Issuance of Renewed Facility License No. R-106 for the Oregon State University Triga Reactor Project stage: Approval ML0830203032008-10-30030 October 2008 Massachusetts Institute of Technology-Request for Additional Information Regarding Amendment Request Project stage: RAI ML0832204262008-11-0707 November 2008 Massachusetts Institute of Technology - Response to Request for Additonal Information Regarding Amendment Request Project stage: Request ML0831801352008-11-0707 November 2008 Massachusetts Institute of Technology - Response to Request for Additional Information Regarding Amendment Request Project stage: Response to RAI ML0907506442009-04-24024 April 2009 Massachusetts Institute of Technology - Issuance of Amendment No. 38 Number of Heat Exchangers Required by Technical Specifications Project stage: Approval 2007-07-31
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Category:Letter
MONTHYEARML24022A0972024-01-22022 January 2024 Massachusetts Institute of Technology Change of Facility Backup Project Manager ML23354A1442024-01-0505 January 2024 Examination Confirmation Letter No. 50-020/OL-24-01, Massachusetts Institute of Technology IR 05000020/20232032023-11-21021 November 2023 Massachusetts Institute of Technology - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000020/2023203 ML23242A3382023-11-0606 November 2023 Examination Report Letter No. 50-020/OL-23-01, Massachusetts Institute of Technology ML23242A3392023-11-0606 November 2023 Examination Result Letter No. 50-020/OL-23-01, Massachusetts Institute of Technology IR 05000020/20232012023-10-12012 October 2023 Massachusetts Institute of Technology - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000020/2023201 IR 05000020/20232022023-09-27027 September 2023 Massachusetts Institute of Technology - U.S. Nuclear Regulatory Commission Security Inspection Report No. 05000020/2023202 ML23194A0412023-07-11011 July 2023 Mit Research Reactor - Duties of Reactor Superintendent ML23103A2632023-05-10010 May 2023 Examination Confirmation Letter No. 50-020/OL-23-01 Massachusetts Institute of Technology ML23094A1102023-03-30030 March 2023 Massachusetts Institute of Technology (Mit), Submittal of Annual Report for 2022, Technical Specification 7.7.1 ML23072A0242023-03-0707 March 2023 Mit, Nuclear Reactor Lab., Proposal for Conversion to Low Enriched Uranium (Leu), Mit Research Reactor IR 05000020/20222012023-02-0707 February 2023 Massachusetts Institute of Technology - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000020/2022201 ML22189A0492022-07-25025 July 2022 Examination Confirmation Letter No.50-020/OL-22-02, Massachusetts Institute of Technology ML22095A2412022-03-31031 March 2022 Annual Report for the Mit Research Reactor for the Period from January 1, 2021, to December 31, 2021 ML22062B0422022-02-10010 February 2022 Proposal for Conversion to Low Enriched Uranium (Leu), Mit Research Reactor, Docket No. 50-20, 10 CFR 50.64 (c)(2)(ii) of That Paragraph ML21328A2342021-11-29029 November 2021 Examination Confirmation Letter No. 50-020/OL-22-01, Massachusetts Institute of Technology IR 05000020/20212032021-11-0909 November 2021 Massachusetts Institutes of Technology - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000020/2021203 IR 05000020/20212012021-09-30030 September 2021 Massachusetts Institute of Technology - U.S. Nuclear Regulatory Commission Routine Inspection Report 05000020/2021201 ML21186A0032021-07-16016 July 2021 Examination Confirmation Letter No. 50-020/OL-21-02, Massachusetts Institute of Technology ML21165A1542021-05-28028 May 2021 Mit - Emergency Plan and Procedures, 10 CFR 50.54(q)(5) ML21140A3622021-05-17017 May 2021 Massachusetts Institute of Technology (Mit) - Supplement to Response to the Request for Additional Information for Battery Upgrade License Amendment Request (EPID: L-2021 -NFA-0000) ML21132A2512021-05-0606 May 2021 Massachusetts Institute of Technology, License No. R-37, Docket No. 50-20, Reportable Occurrence 50-20/2021-: Operation with Less than the Required Staffing on Site; NRC OPS Center Log EN 55212 ML21112A1672021-04-12012 April 2021 Massachusetts Institute of Technology - Physical Security Plan Revision Regarding Biometric Readers ML21105A3602021-04-0707 April 2021 Duties of Reactor Superintendent ML21099A1132021-03-31031 March 2021 Massachusetts Institute of Technology - Annual Report, Docket No. 50-20, License R-37, Technical Specification 7.7.1 ML21091A2082021-03-24024 March 2021 Mit Nuclear Reactor Lab - Response to Request for Additional Information for Battery Upgrade License Amendment Request ML21076A0232021-03-18018 March 2021 Requests for Additional Information - Related to License Amendment Request to Replace Emergency Power System Batteries ML21070A1852021-03-0202 March 2021 Mit Nuclear Reactor Laboratory, License Amendment Request Regarding Emergency Battery Surveillances in Technical Specification 4.6, Docket No. 50-20, License R-37 ML21063A2552021-02-25025 February 2021 Proposal for Conversion to Low Enriched Uranium (Leu), :Mit Research Reactor, Docket No. 50-20, 10 CFR 50.64 (c)(2)(ii) of That Paragraph ML21053A4372021-02-23023 February 2021 Examination Confirmation Letter No. 50-020/OL-21-01, Massachusetts Institute of Technology ML21036A0852021-02-19019 February 2021 Massachusetts Institute of Technology - Acceptance of License Amendment Request to Revise Surveillance Frequency During Extended Reactor Shutdown ML21035A2582021-01-29029 January 2021 Massachusetts Institute of Technology (Mit), Supplement to Technical Specifications Surveillance Frequency Definition Update for Improved Compliance Under 10 CPR 50.36(c)(3) ML20295A4242020-11-16016 November 2020 Notification of Mailing Address Change Regarding Submittal of Fingerprint Cards ML20307A4202020-11-0505 November 2020 Granting of Extension Request to Supplement License Amendment to Revise Surveillance Requirement Frequency ML20304A1172020-10-19019 October 2020 Time Extension Request for LAR on Technical Specifications Surveillance Frequency Update for Improved Compliance Under 10 CFR 50.36(c)(3) for the Mit Research Reactor ML20248H5682020-09-22022 September 2020 Mit Research Reactor Routine Inspection Report with Enforcement Discretion (EA-20-109) - August 2020 ML20161A3342020-07-24024 July 2020 Massachusetts Institute of Technology - Issuance of Amendment NO.44 to Renewed Facility Operation License No. R-37 to Amend Technical Specifications Related to Level 1 Position Title Change ML20182A7092020-07-0909 July 2020 Acceptance Review Amendment Request to Revise Surveillance Frequency - Opportunity to Supplement ML20192A0762020-06-30030 June 2020 Mit - Supplemental Information for License Amendment Request for Position Title Change in Technical Specifications for Level 1 Staff ML20070H2672020-06-0404 June 2020 Examination Report No. 50-020/OL-20-01, Massachusetts Institute of Technology ML20119A8272020-05-29029 May 2020 Massachusetts Institute of Technology - Issuance of Amendment No. 43 Extending Time to Implement License Amendment No. 42 to Facility Operating License No. R-37 ML20149K4142020-05-27027 May 2020 NRC LAR Extension Supplemental Letter 2020-05-27 ML20135H1882020-05-15015 May 2020 Massachusetts Institute of Technology - Exemption from Select Requirements of 10 CFR Part 55, Operators' Licenses ML20122A0622020-04-21021 April 2020 Massachusetts Institute of Technology, Regarding the, Amendment No. 42 to Renewed Facility Operating License No. R-37 for the Nuclear Safety System Digital Upgrade (Epdi No. L-2016-LLA-0003) ML20090E2272020-04-16016 April 2020 Massachusetts Institute of Technology - Acceptance of the Application for a License Amendment Level 1 Position Title Change ML20097B6932020-03-31031 March 2020 Amendment No. 42 to Renewed Facility Operating License No. R-37 Regarding the Nuclear Safety System Digital Upgrade (Epdi No. L-2016-LLA-0003) ML20097D2992020-03-27027 March 2020 Massachusetts Institute of Technology (Mit) - Annual Report for the Year 2019 ML20078J4852020-03-12012 March 2020 Massachusetts Institute of Technology (Mit), License Amendment Request for Position Title Change in Technical Specifications for Level 1 Staff ML20055D3322020-02-18018 February 2020 Proposal for Conversion to Low Enriched Uranium (Leu), Mit Research Reactor, Docket No. 50-20, 10 CFR 50.64 (c)(2)(ii) of That Paragraph IR 05000020/20192032020-01-15015 January 2020 Massachusetts Institute of Technology U.S. Nuclear Regulatory Commission Security-Related Inspection Report 05000020/2019203 2024-01-05
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MIT NUCLEAR REACTOR LABORATORY AN MIT INTERDEPARTMENTAL CENTER John A. Bernard Director of Reactor Operations Principal Research Engineer Mail Stop: NW12-208a 138 Albany Street Cambridge, MA 02139 Phone: 617 253-4202 Fax: 617 253-7300 Email: Bemardj@mit.edu November 7, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Room Washington, DC 20555 Re: Massachusetts Institute of Technology
-Request for Additional Information Regarding Amendment Request (TAC No. MC5155); License No. R-37; Docket No. 50-20
Dear Sir or Madam:
The Massachusetts Institute of Technology hereby provides the response for the above request.Please contact the undersigned with any questions.
Sincerely, f A. Bernard, Ph , PE, CHP Director of Reactor Operations I declare under the penalty of perjury that the foregoing is true and correct.17 Executed on Date 7- &'ý-; 0 Sign e cc: w/enclosures w/enclosures w/enclosure w/o enclosure Cindy Montgomery i Research and Test Reactors Branch A Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Senior Project Manager Research and Test Reactors Branch A Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Senior Reactor Inspector Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Document control Desk 14 6(ZI0
.Heat Exchanger RAI Response 1. The radiation detection systems in both the primary and secondary coolant systems (as specified in TS 3.8.3) will remain unchanged with the installation of the new heat exchanger.
Thus, the radiological impact is unchanged.
Detection of a primary to secondary leak is as follows: Operating:
Primary pressure exceeds secondary pressure.
As in the current system, any leak of primary water into the secondary system would be immediately detected by the secondary water monitors.
Appropriate action would then be taken, including shutting down the reactor until repairs could be made.Shutdown:
Primary pressure exceeds secondary pressure.
Immediately after shutdown,* the coolant system remains in operational alignment.
Although the radiation levels in the coolant are significantly reduced, the secondary water monitors remain sensitive enough to detect the presence of radionuclides in the water, and thus a leak would still be detected immediately.
Once the reactor is in shutdown alignment, there is. no secondary water flow to the main heat exchanger.
The attached Appendix describes the secondary water monitors.2. The thermal-hydraulic safety limits for the MITR-II are based on reactor power, core tank level, primary flow, and primary temperature.
The heat exchangers in the primary system can only significantly affect the latter two parameters.
Whether there are one, two, or three heat exchangers in use, as long as the heat from the reactor can be adequately removed under the nominal flow, and temperature conditions, the reactor safety limits will be met. The new heat exchanger has a significantly larger heat transfer surface area than one of the current heat exchangers, it has a higher overall heat transfer coefficient, and it is designed to remove at least 6 MW of heat under nominal conditions.
A comparison of the two heat exchangers under the normal operating configurations and operating conditions is shown in the table below. This clearly shows the superiority of the new heat exchanger in removing heat. In particular, the primary to secondary temperature difference is greatly reduced.It should be noted that all of the reactor safety instrumentation, including primary flow and temperature scrams, will be unchanged by this installation.
Heat removed Primary AT (°C) Primary to secondary mean AT (°C)Old (two shell-and-4.0 MW 7.2 17.8 tube)*New (single plate 6.6 MW 12.6 8.5 type)Comparison of old and new heat exchangers at a primary flow rate of 2000 gpm, reactor outlet temperature 52 'C, and secondary inlet temperature
-30 °C.*measured data Appendix Two redundant water monitors are mounted in a shielded location in the equipment room. Each system separately samples water from the eight-inch pipe leading to the cooling towers. Sample water is returned to the inlet pipe. Flow through the monitors depends on the pressure differential between the two pipes produced by the main pumps in the secondary system.Activity could be introduced to the secondary water if a leak developed within any of the heat exchangers serviced by the secondary water system.Each of the redundant monitors uses a gamma-sensitive scintillation detector that views a volume of water contained in a lead shield. It is sensitive to N- 16 and F- 18 which are present in the light water coolant whenever the reactor is operating and to Na-24 which is present both during operating and shutdown conditions because of its half-life.
The N- 16 isotope has a half-life of a few seconds, that of F- 18 is approximately fifteen minutes, and that of Na-24 is about 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. A flow of about two gpm is maintained through each lead shield as indicated by local flow meters, HF-5 and HF-5A. Flow switches will produce a "Trouble Radiation Monitor Alarm" if the flow falls below one gpm.