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Category:E-Mail
MONTHYEARML23058A0602023-02-24024 February 2023
Email - Regarding Request for State Comment on Pending NIST License Amendment and Restart Determination
ML22342A5062022-12-0707 December 2022
NRR E-mail Capture - Request for Additional Information Regarding Nist'S Request to Operate with Debris in Primary Coolant
ML22322A0872022-11-18018 November 2022
NRR E-mail Capture - Request for Additional Information Regarding Nist'S Proposed Revision to the Reactor Operator Requalification Plan
ML22312A4272022-11-0808 November 2022
NIST Acceptance Review of License Amendment Request Related to Operating with Debris in Primary Coolant System
ML22280A1262022-10-0707 October 2022
NRC Staff Review of NIST all-staff Safety Culture Improvement Message Per Co EA-21-148
ML22287A0942022-09-28028 September 2022
NIST Confirmatory Order Engineering Review of Latching Alternatives
ML22277A7222022-09-20020 September 2022
Draft all-staff Message from the NIST Director
ML22238A1372022-08-25025 August 2022
Email NRC Staff Review of the Proposed NIST Trtr Presentation Per Co EA-21-148
ML20132A3162020-05-11011 May 2020
Chief Examiner Change in Upcoming License Examination No. 50-184/OL-20-01, National Institute of Standards and Technology.Email
ML20136A4422020-05-11011 May 2020
External Sender) E-mail COVID-19 Part 55 Exemption Request NIST - Redacted
ML15072A1732015-03-13013 March 2015
Examination Notification Letter No. 50-184/OL-15-02, National Institute of Science and Technology
ML0911904512009-04-22022 April 2009
NIST Response to ACRS Question
ML0718300212007-06-29029 June 2007
Request for Additional Information, Nist'S May 30, 2007 Response
ML0704403282007-02-0909 February 2007
NIST Environmental Response to Request for Clarification on Figure 2-5
ML0703600122007-01-31031 January 2007
E-Mail from W. Kennedy to Dr. Richards of NIST Transmitting the Draft Rais for Re-Licensing of the Nbsr, Docket No. 50-184 (TAC No. MD 3410)
ML0703605792007-01-0404 January 2007
NIST Environmental Title V Permit Information
ML0633202412006-11-27027 November 2006
NIST Response to Question on Fission Product Release for Re-Licensing Application
ML0629800772006-10-23023 October 2006
E-mail to Research and Test Reactor from M. Mendonca Draft Directors Decision on Uncontrolled/Unmonitored Releases
ML0630301872006-10-23023 October 2006
NIST Environmental Review Questions, Follow Up Clarification for NIST
ML0522303982005-08-10010 August 2005
Detailed Description of an Occurrence from July 27, 2005
ML0411804062004-04-26026 April 2004
National Institute of Standards & Technology Reactor (Nbsr Reactor) Safety Analysis Report Sensitive Info Review E-mail
2023-02-24
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML22342A5062022-12-0707 December 2022
NRR E-mail Capture - Request for Additional Information Regarding Nist'S Request to Operate with Debris in Primary Coolant
ML22322A0872022-11-18018 November 2022
NRR E-mail Capture - Request for Additional Information Regarding Nist'S Proposed Revision to the Reactor Operator Requalification Plan
ML21294A2772021-11-18018 November 2021
National Institute of Standards and Technology - Supplemental Information Needed for the Request to Restart the National Bureau of Standards Reactor
ML17318A6952017-11-16016 November 2017
National Institute of Standards and Technology, Request for Additional Information of License Amendment Request for the Renewed Facility License No. TR-5 for the National Bureau of Standards Test Reactor (CAC No. 000955)
ML17187B0122017-08-10010 August 2017
National Institute of Standards and Technology Request for Additional Information Preliminary Safety Analysis Report for the National Bureau of Standards Reactor
ML16103A1402016-04-25025 April 2016
National Institute Of Standards And Technology - Preliminary Safety Analysis Report For The National Bureau Of Standards Reactor
ML15022A1012015-01-30030 January 2015
National Institute of Standards and Technology - Request for Additional Information for the Review of Technical Specification Amendment Request
ML0906100612009-03-0303 March 2009
National Institute of Standards and Technology Test Reactor - Request for Additional Information Advisory Committee on Reactor Safeguards Subcommittee Meeting Follow-up Items (Tac MD3410)
ML0903707372009-02-18018 February 2009
National Institute of Standards and Technology Test Reactors - Request for Additional Information Operator Requalification Program
ML0832307102008-11-19019 November 2008
Request for Additional Information Regarding Emergency Planning for the National Institute of Standards and Technology Test Reactor License Renewal
ML0822802192008-08-25025 August 2008
Request for Additional Information Regarding Financial Qualifications and Decommissioning Funding for the National Institute of Standards and Technology Test Reactor Application for License Renewal
ML0818302942008-07-0101 July 2008
Request for Additional Information Regarding the National Institute of Standards and Technology Test Reactor Application for License Renewal
ML0718300212007-06-29029 June 2007
Request for Additional Information, Nist'S May 30, 2007 Response
ML0704400432007-02-13013 February 2007
Request for Additional Information Regarding the National Institute of Standards and Technology Test Reactor Application for Re-Licensing
ML0703200102007-02-0202 February 2007
National Institute of Standards and Technology Test Reactor (Nbsr) - Draft Request for Additional Information (Rai), Regarding Amendment Request for Re-Licensing
ML0527104802005-10-0707 October 2005
RAI Letter - Security Measures - Richards
2022-12-07
[Table view] |
Text
-Maiin-Mendon - Requestion for AdditionalInformation ___Page_1 From: Marvin Mendonca To: Wade Richards Date: 06/29/2007 1:02:06 PM
Subject:
Requestion for Additional Information Wade, Attached is the request for additional information we discussed. Your timely response is needed to support completion of the review. Please provide me a date, when you feel you can provide a response.
In accordance with 10 CFR 50.30(b), your response must be executed in a signed original under oath or affirmation.
Regards, Mary
P~g~JJj I cAternp\GW}OO001 .TMP Fi61ýI Mail Envelope Properties (46853BOE. 16F : 1: 35040)
Subject:
Requestion for Additional Information Creation Date 06/29/2007 1:02:06 PM From: Marvin Mendonca Created By: MNMM@nrc.gov Recipients Action Date & Time nist.gov Transferred 06/29/2007 1:02:31 PM wade.richards (Wade Richards)
Post Office Delivered Route nist.gov Files Size Date & Time MESSAGE 817 06/29/2007 1:02:06 NIST RAI Response Review 06-27-2007_2.doc 24576 06/27/2007 10:45:43 AM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification: None Concealed
Subject:
No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened
NIST RAI Response Review The following questions are numbered to correspond to NIST's May 30, 2007, response to request for additional information.
2.1 Provide a reference to the mentioned previous response or a copy of the response.
2.2 Provide a reference to the mentioned previous response or a copy of the response.
4.2 Provide revised Figures 4.2.3 and 4.2.4, which were not attached to the response.
4.9 Provide justification for the conclusion that there are no lifetime issues regarding the strength of the Al or the bumup of the Cd used in the poison tubes. The neutron flux and duration of exposure should be compared to design limits for the tubes to ensure the tubes will continue to function as designed under the most limiting conditions for the license renewal period.
4.25 Provide an update to Table 4.2.3. Alternatively, remove or commit to remove Table 4.2.3 from the SAR, if the SAR contains all necessary information elsewhere.
4.28 Provide or reference analysis to support the conclusion that there would be no fuel damage from the decreased flow through the fuel elements cooled by the inner plenum. Also, the response should discuss how poison tube buckling would be detected and what actions would be required as these considerations may affect the consequences of such an accident 4.35 Provide the alloy or alloys, which compose the core frames and cladding.
4.36 Provide an update to Table 4.2.3. Alternatively, remove or commit to remove Table 4.2.3 from the SAR, if the SAR contains all necessary information elsewhere.
4.39 Provide the pressure of the helium left in the voids in the shim arms.
5.7 Provide verification that the nominal air supply pressure in the response is capable of operating the valves, and that the larger pressure is not required to operate the valves.
5.12 Provide clarification on the temperature range for TR-1 in degrees C. Verify that TR-1 is a temperature difference instrument. Verify that the SAR gives the correct temperature range for TR-1. Note TR-1 was not included in the RAI.
13.9 For each accident analysis, provide the limiting assumptions, conditions and safety system settings and where these limiting assumptions, conditions and safety system settings are required by Technical Specifications as required by 10CFR50.36. Compare the assumptions, conditions and safety system settings to those in ANSI 15.1 and NUREG 1537, which are applicable to test reactors.
1
The response should provide a distinct set of information regarding accident scenarios so that a determination can be made that each accident scenario assumed the most conservative conditions allowed by the Technical Specifications. The information should show that the TS limits are supported by the appropriate accident analyses.
2