|
---|
Category:Letter
MONTHYEARIR 05000166/20232032024-01-16016 January 2024 University of Maryland - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000166/2023203 IR 05000166/20232022023-10-0505 October 2023 University of Maryland - U.S. Nuclear Regulatory Commission Security Inspection Report No. 05000166/2023202 (Public) IR 05000166/20232012023-07-31031 July 2023 University of Maryland - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000166/2023201 - Cover Letter and Enclosure ML23102A1682023-07-27027 July 2023 Examination Report No. 50-166/OL-23-01, University of Maryland ML23102A1692023-07-27027 July 2023 Examination Result Letter No. 50-166/OL-23-01 ML23080A1042023-03-0606 March 2023 Univ. of Maryland - College Park, Submittal of Annual Report for 2022 ML22077A6732022-03-30030 March 2022 Examination Confirmation Letter No. 50-166/OL-22-01, University of Maryland ML22101A0492022-03-28028 March 2022 Logbook Entry 61904, Maryland University Training Reactor, License No. R-70 IR 05000166/20212022021-11-0808 November 2021 University of Maryland Nuclear Regulatory Commission Routine Inspection Report 05000166/2021202 ML21328A1942021-10-0101 October 2021 Notification of Change in Level 1 Management for the Maryland University Training Reactor IR 05000166/20212012021-06-10010 June 2021 University of Maryland Nuclear Regulatory Commission Routine Inspection Report No.05000166/2021201 ML21139A1262021-05-12012 May 2021 University of Maryland - Applicant Withdrawal from Exam Dated May 24, 2021 ML21097A1512021-04-0707 April 2021 Examination Confirmation Letter No. 50-166/OL-21-01, University of Maryland ML20295A4242020-11-16016 November 2020 Notification of Mailing Address Change Regarding Submittal of Fingerprint Cards ML20241A1792020-09-15015 September 2020 University of Maryland - Approval of Exemption from Select Requirements of 10 CFR Part 55, Operators' Licenses ML20241A1762020-08-24024 August 2020 Ltr from Ajohnson, Maryland University Training Reactor (R-070): Request for Exemption from the Medical Examination Requirements of 10 CFR 55.21 and 10 CFR 55.53(i) for a Reactor Operator - Redacted ML20069J3912020-05-29029 May 2020 Letter, University of Maryland-Issuance of Amendment No. 10 to Renewed Facility Operating License No. R-70 for the Maryland University Training Reactor for the Use of 16 Additional Triga Fuel Elements ML20142A2882020-05-22022 May 2020 University of Maryland - Exemption from Select Requirement of 10 CFR Part 55, Operator' Licenses ML20133K1212020-05-12012 May 2020 University of Maryland License Amendment Request for the Maryland University Training Reactor, License No. R-070 for the Use of Additional Fuel ML20111A1162020-04-0101 April 2020 Notification of Change in Level 1 Management for the Maryland University Training Reactor, License No. R-070 ML20076C3472020-03-10010 March 2020 Univ. of Maryland - College Park - Supplemental Information Regarding RAI 1.3 Response Submitted on January 13, 2020 (ML20016A314) ML20070H6372020-03-0505 March 2020 Univ. of Maryland - College Park - Transmittal of Annual Report for the Period Beginning January 1, 2019 and Ending December 31, 2019 ML20062A1692020-02-24024 February 2020 Univ of Maryland - College Park - Proposed Change to Remove the a from License Condition 2.B.3 ML20016A3142020-01-13013 January 2020 University of Maryland Response to Requests for Additional Information Issued on November 22, 2019 ML19312C3762019-11-22022 November 2019 University of Maryland - Second Request for Additional Information License Amendment Request for the Use of 16 Additional Fuel Elements in the Maryland University Training Reactor IR 05000166/20192012019-09-18018 September 2019 University of Maryland - Nuclear Regulatory Commission Routine Inspection Report 05000166/2019201 ML19254A7602019-09-11011 September 2019 Examination Confirmation Letter No. 50-166/OL-20-01, University of Maryland ML19214A2322019-08-0606 August 2019 University of Maryland - Regulatory Audit for License Amendment Request for the Use of 16 Additional Fuel Elements in the Maryland University Training Reactor ML19205A0852019-07-15015 July 2019 Notification of Change in Level 1 Management for the Maryland University Training Reactor, License No. R-070 ML19165A0212019-06-0606 June 2019 Univ. of Maryland - College Park - Transmittal of Responses to Request for Additional Information Dated April 16, 2019 ML19024A2912019-04-16016 April 2019 University of Maryland - Request for Additional Information of Requested Licensing Action Amendment Request for the Use of 16 Additional Fuel Elements in the Maryland University Training Reactor ML19094A2582019-03-25025 March 2019 Annual Report: January 1, 2018 - December 31, 2018 for the Maryland University Training Reactor, License No. R-70, University of Maryland ML19071A1042019-03-0808 March 2019 Univ. of Maryland - College Park, Change in Level 2 Personnel Update ML18276A2122018-10-0404 October 2018 Examination Confirmation Letter No. 50-166/OL-19-01, University of Maryland ML18177A0562018-06-25025 June 2018 Letter to T. Koeth, University of Maryland, from L. Lund, NRC, NRC Office of Investigations Report No. 1-2017-018 - Release of OI Synopsis. ML18156A1962018-06-12012 June 2018 National Level Exercise 2018 Eagle Horizon ML18101A1122018-04-26026 April 2018 University of Maryland-Acceptance of Requested Licensing Action Amendment Request the Use of 16 Additional Training Reactor and Isotopes Production, General Atomics Fuel Elements in the Maryland University Training Reactor ML18094A1162018-03-27027 March 2018 MD University, Submittal of Annual Report for January 1, 2017 and Ending December 31, 2017 ML18092A0862018-03-26026 March 2018 Submittal of Request for License Amendment Authorizing Changes to Technical Specifications for the Use of 16 Additional Triga Fuel Elements in the Maryland University Training Reactor ML18060A0482018-03-0909 March 2018 University of Maryland - Supplemental Information Needed for Acceptance of Requested Licensing Action Request for License Amendment Authorizing Changes to Technical Specifications for the Use of 16 Additional Training Reactor and Isotopes . ML18033B3292018-02-0606 February 2018 University of Maryland - Change of Facility Project Manager ML18032A0962018-01-29029 January 2018 University of Maryland, Submittal of Request for License Amendment Authorizing Changes to Technical Specifications for the Use of 16 Additional Triga Fuel Elements in the Maryland University Training Reactor ML17354A6562017-12-26026 December 2017 Examination Report No. 50-166/OL-18-01, University of Maryland ML17257A0072017-09-14014 September 2017 Examination Confirmation Letter No. 50-166/OL-18-01, University of Maryland ML17081A2862017-04-21021 April 2017 University of Maryland - U.S. Nuclear Regulatory Commission Inspection Report No. 50-166/2017-202 - Cover Letter ML17089A7832017-04-19019 April 2017 University of Maryland Closure of Confirmatory Action Letter No. NRR-04-004 on the Site-Specific Compensatory Measures Implementation Plan for the Maryland University Training Reactor IR 05000166/20172012017-03-29029 March 2017 University of Maryland - NRC Routine Inspection Report No. 50-166/2017-201 ML17087A0062017-03-17017 March 2017 Annual Report: January 1, 2016 - December 31, 2016 for the Maryland University Training Reactor, License No. R-70, University of Maryland ML17061A1432017-03-0101 March 2017 Letter from T. W. Koeth Request for Approval of a Part 71 Quality Assurance Program for the Maryland University Training Reactor, License R-70 ML16075A2112016-12-22022 December 2016 Letter Notice of Issuance of Renewed MUTR Facility Operating License 2024-01-16
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML20016A3142020-01-13013 January 2020 University of Maryland Response to Requests for Additional Information Issued on November 22, 2019 ML19165A0212019-06-0606 June 2019 Univ. of Maryland - College Park - Transmittal of Responses to Request for Additional Information Dated April 16, 2019 ML16323A4462016-11-17017 November 2016 University of Maryland - Request for Additional Information Regarding the Review of License Renewal for the Maryland University Training Reactor ML16323A4472016-11-17017 November 2016 University of Maryland - Request for Additional Information ML16320A0072016-11-10010 November 2016 University of Maryland - Response to Request for Additional Information for the Renewal of Facility Operating License No. R-70 the Maryland University Training Reactor ML16319A3692016-11-0202 November 2016 Mutr Triga Response to Us NRC Generic Letter 2016-01 ML16309A1842016-11-0202 November 2016 University of Maryland - Response to Request for Additional Information for Renewal of Facility Operating License No. R-070 ML16061A0032016-02-29029 February 2016 University of Maryland - Request for Additional Information for the Renewal of Facility Operating License No. R-70 the Maryland University Training Reactor Docket No. 50-166 ML16008A0722016-01-0505 January 2016 Univ. of Maryland - Response to Request for Additional Information for License Renewal ML15349A8942015-12-0202 December 2015 University of Maryland - Request for Additional Information for License Renewal Pertaining to Thermal Hydraulics ML15190A3432015-07-0101 July 2015 University of Maryland - Request for Additional Information Review of the Physical Security Plan for the License Renewal for University for Maryland Training Reactor 2020-01-13
[Table view] |
Text
<.l~RSJ'.l'J-- Dr. Timothy W. Keeth
~,;;..-'-~ INSTITUTE FOR RESEARCH IN . Associate Research Professor Director, Nuclear Reactor & Radiation Facilities 18 . . 56 ELECTRONICS Energy Research Facility, Building 223,
~<1 ~I::) & APPLIED PHYSICS Paint Branch Drive, College Park, MD 20742-3511
.l{yL~ TEL: 301.405.4952 - FAX 301.314.9437 - koeth@umd.edu Nov.2,2016 Document Control Desk United States Nuclear Regulatory Commission Washington, D.C. 20555-0001
SUBJECT:
UNIVERSITY OF MARYLAND - REQUEST FOR ADDITIONAL INFORMATION RE: FOR THE RENEWAL OF FACILITY OPERATING LICENSE NO. R-70 THE MARYLAND UNIVERSITY TRAINING REACTOR DOCKET NO. 50-166 Enclosed please find the responses to RAls #3, 5-12 dated July 28, 2016 for the University of Maryland Training Reactor (MUTR).
In addition to the RAls that we have answered, additional definitions were added or enhanced as noted in the enclosure. We have removed the numbering and capitalized definitions throughout the technical specifications to enhance readability.
I declare under penalty of perjury that the foregoing response is true and correct.
Since~ J/'.. ~/
-1...... ~::;t u /f~
Timotliy W. Koeth
3.
- a. How many separate modes can the MUTR be operated in, and what if, any protective functions, and interlocks exist for each mode?
2
- b. What is the significance of defining the STEADY STATE MODE in the TSs and not the others?
We have included the definition for Automatic Mode. The definition reads:
Automatic mode operation shall mean operation of the reactor with the mode selector switch in the automatic position.
- 5. MUTR proposed TS 1.15, "Isolation," may contain a grammatical error. Provide a definition removing the "leads to," or justify why no change is necessary.
The definition was updated to now read:
/SOLA TION / Isolation is the establishment of confinement by closing of doors leading from the reactor bay area into the balcony area on the top door, the door to the reception area on the ground door, and the building exterior doors.
Sa. Provide a definition by removing the redundant requirement, or justify why no change is necessary. For example, "No experiments in or near the reactor are being moved or serviced that have, on movement, the smaller of: a reactivity worth exceeding the maximum value allowed for a single experiment, or a reactivity of one dollar." to "no experiments are moved or serviced that have, on movement, a reactivity worth exceeding $1.00.;'
There was no numbering between 5 & 6 so we have changed this number to Sa. We have updated the wording to agree with TS 3. 6 Limits on Experiments specification 1.
The new definition will now read:
(d) No experiments in or near the reactor are being moved or serviced that have, on movement, a reactivity worth of $1.00.
6.MUTR proposed TS 1.30, "Reactor Shutdown," describes two conditions which when met ensure the reactor is shutdown. Two separate reactivity values are described in proposed TS 1.30, item b, "maximum allowed value for a single experiment, or one dollar."
Revise the definition for proposed TS 1.30 by removing the redundant requirement, or justify why no change is necessary. For example, "No experiments are being moved or serviced that have, on movement, a reactivity worth exceeding the maximum value allowed for a single experiment, or one dollar, whichever is smaller." to "no experiments are moved or serviced that have, on movement, a reactivity worth exceeding $1.00."
We have adopted the ANSl/ANS-15.1-2007 standard definition of Reactor Shutdown.
The definition now reads:
The reactor is shut down if it is subcritical by at least one dollar in the reference core condition with the reactivity worth of all installed experiments included.
- 7. MUTR proposed TS 1.31, "Reference Core Condition," provides a definition for the reference core. ANSl/ANS-15.1-2007 definition reference core condition states, "The condition of the core when it is at ambient temperature (cold) and the reactivity worth of xenon is negligible (<0.30 dollar)." While proposed TS 1.31 does define the temperature and xenon values, it is not clear how the core could be critical if xenon were zero.
Revise the definition for proposed TS 1.31 to clarify what conditions are used for the reference core or justify why no change is necessary. For example, "The reference core condition is the reactivity condition of the core when it is at 20 °C and the reactivity worth of xenon is zero (i.e., cold, clean, and critical)." to "The reference core condition is the reactivity condition of the core when it is at 20 °C and the reactivity worth of xenon is neglibile."
We have adopted the ANSl/ANS-15.1-2007 standard definition of Reference Core Condition with our definition of negligible. The definition now reads:
The reference core condition is the reactivity condition of the core when it is at 20 degrees C and the reactivity worth of xenon is negligible, $0.01 or less.
8.Revise the definition for proposed TS 1.32," that is either consistent with the guidance provided in ANSl/ANS-15.1-2007, Section 6.7.2, item (c)(iii) for the reporting of malfunctions in the reactor safety system, or explain why "discovered during maintenance tests" and "caused by maintenance" are equivalent and should share the same reporting exemption.
We have adopted the wording in ANSI/ANS-15.1-2007, Section 6. 7.2 for our definition of Reportable Occurrence. The definition now reads:
Operation with a required reactor safety system component in an inoperative or failed condition which renders or could render the system incapable of performing its intended safety function. If the malfunction or condition is caused during maintenance, then no report is required; We have updated item 4 to agree with ANSl/ANS-15.1-2007, Section 6.7.2 An unanticipated or uncontrolled change in reactivity greater than one dollar. Reactor trips resulting from a known cause are excluded; To enhance our Technical Specifications, we have updated our definition of Secured Shutdown to read:
Secured shutdown is achieved when the reactor meets the requirements of the definition of "reactor secured" and the facility administrative requirements for leaving the facility with no licensed reactor operators present.
.. '\
\
9.Revise the definition for proposed TS 1.39 to be consistent with that provided in the regulatory requirement 10 CFR 55.4 or justify why the no change is necessary.
We have adopted the ANSllANS-15.1-2007 standard definition of Senior Reactor Operator with the addition of licensed by the NRG. The definition now reads:
A senior reactor operator is an individual who is licensed by the NRC to direct the activities of reactor operators. Such an individual is also a reactor operator.
- 10. Revise proposed TS 1.41 or 1.42, as applicable, to correct the differences in these definitions for consistency, or justify why no change is necessary.
We have adopted the ANSl/ANS-15.1-2007 standard definition of Shutdown Margin. The definition now reads:
Shutdown margin is the minimum reactivity necessary to provide confidence that the reactor can be made subcritical by means of the control and safety systems starting from any permissible operating condition and with the most reactive rod in its most reactive position, and that the reactor will remain subcritica/ without further operator action.
- 11. Revise proposed TS 1.42 to provide a defined value for "ambient conditions," as found in the definition for reference core condition, or justify why no change is necessary.
We have updated our definitions to include the reference core in our definition of Shutdown Reactivity. The definition now reads:
Shutdown reactivity is the value of the reactivity of the reactor with all control rods in their least reactive position (e.g., inserted). The shutdown reactivity includes the
- reactivity value of all installed experiments plus the reactivity of the Reference Core Condition.
- 12. Revise proposed TS 2.2 to only describe the LSSS by removing the reference to the IFE location or justify why no change is necessary.
We have removed the reference to the JFE location in TS 2.2 and updated the definition of Standard Core to include the location. The definition now reads:
STANDARD CORE -A standard core is an arrangement of standard TR/GA fuel in the reactor grid plate and the JFE in grid position DB.