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MONTHYEARML0224103752002-09-0505 September 2002 Massachusetts Institute of Technology Research Reactor, Request for Additional Information, Amendment Request for Amended Facility Operating License No. R-37 Project stage: RAI ML0229603322002-10-15015 October 2002 Response to TAC No. MB3761, License No. R-37 Dated 10/15/2002 Project stage: Other ML0235201902002-12-10010 December 2002 Response to TAC No. MB3761, License No. R-37, Docket No. 50-20 Project stage: Other ML0230103982003-03-25025 March 2003 Massachusetts Institute of Technology, License Amendment, Fission Converter Surveillance Requirements Project stage: Other 2002-12-10
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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
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARML14094A2462014-03-27027 March 2014 Response to Apparent Violation in NRC Investigation No. 1-2013-004; EA-13-170 ML0802307202008-01-15015 January 2008 NRC Special Inspection Report No. 50-020-07-203 and Notice of Violation EA-06-113 ML0333606942003-11-25025 November 2003 Massachusetts Institute of Technology (Mit) - Response to a Notice of Violation, EA-03-155 ML0229603322002-10-15015 October 2002 Response to TAC No. MB3761, License No. R-37 Dated 10/15/2002 2014-03-27
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NUCLEAR REACTOR LABORATORY AN INTERDEPARTMENTAL CENTER OF MASSACHUSETTS INSTITUTE OF TECHNOLOGY JOHN A. BERNARD 138 Albany Street, Cambndge, MA 02139-4296 Activation Analysis Director Telefax No (617) 253-7300 Coolant Chemistry Director of Reactor Operations Tel. No. (617) 253-4211 Nuclear Medicine Principal Research Engineer Reactor Engineenng October 15, 2002 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Subject:
Response to TAC No. MB3761, License No. R-37, Docket No. 50-20.
Gentlemen:
On 11/21/01, the Massachusetts Institute of Technology submitted a request to amend its operating license (R-37) to modify Fission Converter surveillance requirements and eliminate unnecessary procedures, in accordance with ALARA considerations. On 09/05/02, the U.S. Nuclear Regulatory Commission sent a request for additional information. Enclosed is our response to that request.
Please contact either of the undersigned should further information be required. This request has been reviewed and approved by the MIT Committee on Reactor Safeguards.
Thomas New on, P.E. Aohn A. Bemard, Ph.D.
Reactor Engineer Director MIT Nuclear Reactor Laboratory MIT Nuclear Reactor Laboratory I declare under penalty of perjury that the foregoing is true and correct.
Executed on Date JAB/gw cc: USNRC - Senior Project Manager, NRR/ONDD USNRC - Region I - Project Scientist, Effluents Radiation Protection Section (ERPS)+
FRSSB/DRSS A- b2-D
Response to NRC reauest for additional information 9/5/02
- 1. Installation or repair of a level probe will result in the probe being placed in a non-adjustable position that will result in actuation at or above 2.1 m above the top of the fuel. Because of the probe's fixed position, a calibration requirement is not needed. All that is necessary to ensure proper operation is a functional check.
The proposed TS has been modified (new provision 5) to make this explicit.
- 2. The float switch is bolted to the FC tank at 2.2 m above the top of the FC fuel.
This determines the actuation position. Testing to date has shown no change in probe function. The functional test consists of insertion of pressurized helium into the annular space surrounding the float. This forces the coolant around the float to drop, thus activating the switch. When the helium supply is stopped, the helium is vented to the helium cover gas space of the tank, allowing the coolant around the float to rise to its normal level.
- 3. A loss of coolant in the FC tank during FC operation would result in loss of coolant to the intake of the coolant pumps, resulting in a low flow indication, as well as a reactor scram and CCS closure from loss of flow. A loss of coolant would also be indicated on a digital coolant level indicator. Also, it would result in increased radiation levels above the FC.
- 4. Removal of the tank ,trp is very difficult and is done only when maintenance is required inside the tank. This has not happened in the two years that the tank has been in place. Functional testing of the probe with the tank lid removed is possible, but has no added advantage beyond the monthly functional check that is currently preformed.
- 5. Units in TS 6.6.2.6 have been changed to jIS/cm.
- 6. Attached is a graph of H2 0 and D2 0 conductivity vs. pH from D. Barber and J.P.
Van Berlo, "An Introduction to CANDU Chemistry," AECL CANDU, March 1994. It shows both H20 and D20 have similar shapes, with the D 20 conductivity slightly lower. Measurements of pH are made monthly. The data are close (i.e.,
within measurement error) to the calculated pH-conductivity curve for D20.
- 7. Conductivity of pure D2 0 at pH 7 is about 0.013 [tS/cm (0.0013 mS/cm). A measurement of 0.04 #iS/cm would be a normal indication. Indications of conductivity below 0.013 pS/cm constitute the lower limit of sensitivity of the conductivity probe.
10 I
0001*!
,.0 5.0 6.0 7.0 B.0 P.0 10.0 MEASURED pH OR pHA Figure 9-2 Thcorefical Relationships for pH and PHiA to Spccific Conductivity
I pH - CONDUCTIVITY WITH MIT MEASUREMENTS 19 0.01 4.0 4.001 5.0 6.0 7.0 JIG 9.0 MEASURED PH OR PHA FigRp 9-2 Theoretical Relationships for pH and PHA tO Specific Condletiit'hy
- a. Neutron flux level channel,
- b. Primary coolant flow channel, and
- c. Primary coolant outlet temperature channel.
- 3. The neutron flux level channel and a fission converter primary system heat balance shall be checked against each other at least annually and when design changes in the reactor and/or the fission converter are made that may affect the existing calibration result.
- 4. The gross P-7 activity of the fission converter primary coolant shall be determined at least monthly. The conductivity of the fission converter primary coolant shall be determined either by a continuous on-line instrument or a monthly sample.
The pH of the fission converter primary coolant shall be measured monthly if the average conductivity exceeds 0.10 #S/cm. The tritium content of the coolant shall be determined quarterly if D20 is used as the fission converter primary coolant.
- 5. The following instruments used in the fission converter shall be subject to a functional test when initially installed, any time that the instrument has been repaired, and at least annually:
Fission Converter tank coolant level channel Basis The specification for functional tests, calibrations, and primary coolant sampling adhere to current MITR practice.
The annual frequency for performance of the calorimetric was chosen because the fission converter's power is a function of the MITR's power and the burnup of the fission converter fuel. The latter will occur very slowly. Hence, the annual performance of a calorimetric is sufficient to detect any change in fission converter power production.
Experience with the MITR primary and D2 0 systems has shown that an out-of specification chemistry condition is extremely rare. Heat fluxes present in the fission converter are too low to contribute to fuel cladding degradation in the event of out-of specification chemistry. Continued operation of the fission converter is thus permitted.
6-59
6.6.2.6 Fission Converter Primary Coolant Quality Requirements Applicability This specification applies to the pH, conductivity, and activity of the fission converter primary coolant.
Obiective To control corrosion of the fission converter fuel and primary coolant loop structure, and activation of impurities and leakage of fission products in the fission converter primary coolant.
Specification
- 1. The pH of the fission converter primary coolant shall be kept between 5.5 and 7.5, except as noted in provision (4) below.
- 2. The conductivity of the fission converter primary coolant shall be kept less than 5 pS/cm at 20'C, except as noted in provision (4) below.
- 3. Any gross B-y sample activity that exceeds the average of the previous monthly values (normalized by power) by a factor of three or more shall be investigated to determine the cause.
- 4. Operation of the fission converter with the pH or conductivity outside the limits given in (1) and (2) above is permitted provided:
- a. The pH is between 5.0 and 8.0,
- b. Any increase in conductivity is not the result of a chloride ion concentration in excess of 5 ppm,
- c. Sampling of the fission converter coolant is done at least once every eight hours, and
- d. The pH band specified in provision (1) is re-established with 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, Otherwise, the fission converter shall not be operated.
6-56 Amendment No. 31 December 21, 1999