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| Full operability is not available, nor is it needed, when operating as permitted by the specifications of Sections 2.2(4) and 33.1(1). However, the 3000 gallon D 2 0 emergency cooling tank and a source of makeup water would be available. | | Full operability is not available, nor is it needed, when operating as permitted by the specifications of Sections 2.2(4) and 33.1(1). However, the 3000 gallon D 2 0 emergency cooling tank and a source of makeup water would be available. |
| (2) The emergency core cooling system employs one sump pump to return spilled coolant to the overhead storage tank. Because only one sump p11mp is used, it must be operational whenever the reactor is operational. | | (2) The emergency core cooling system employs one sump pump to return spilled coolant to the overhead storage tank. Because only one sump p11mp is used, it must be operational whenever the reactor is operational. |
| There is sufficient D20 available to provide approximately 2.5 hours of cooling on a once-through basis. In the event that the sump pump fails and the D20 supply in the overhead storage tank is exhausted, domestic water or a suitable alternative would be used to furnish water for once-through cooling. The water makeup capacity must be in excess of.25 gpm, which_ was found adequate in cooling calculations to prevent fuel damage. 18}} | | There is sufficient D20 available to provide approximately |
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| | ===2.5 hours=== |
| | of cooling on a once-through basis. In the event that the sump pump fails and the D20 supply in the overhead storage tank is exhausted, domestic water or a suitable alternative would be used to furnish water for once-through cooling. The water makeup capacity must be in excess of.25 gpm, which_ was found adequate in cooling calculations to prevent fuel damage. 18}} |
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Category:Letter
MONTHYEARIR 05000184/20232012024-01-25025 January 2024 National Institute of Standards and Technology - U.S. Nuclear Regulatory Commission 1st and 2nd Quarter Supplemental Inspection Report 05000184/2023201 ML24023A6182024-01-23023 January 2024 Us Dept. of Commerce, National Institute of Standards & Technology - Nuclear Program Assessments Response and Leadership Accountability ML23257A1972023-12-26026 December 2023 Examination Results Letter No. 50-184/OL-23-02, National Institute of Standards and Technology ML23257A1982023-12-26026 December 2023 Examination Report No. 50-184/OL-23-02, National Institute of Standards and Technology ML23306A1642023-11-0202 November 2023 Examination Report Letter No. 50-182/OL-24-01, University of Missouri - Columbia ML23306A1652023-11-0202 November 2023 Examination Result Letter No. 50-184/OL-24-01, University of Missouri - Columbia ML23207A0402023-07-26026 July 2023 Us Dept. of Commerce, National Institute of Standards & Technology, Nuclear Safety Culture Assessment and Response ML23195A1042023-07-12012 July 2023 NIST Center for Neutron Research (Ncnr), Withdrawal of License Amendment Request of December 11, 2020 ML23104A3002023-04-10010 April 2023 U.S. Dept. of Commerce, National Institute of Standards & Technology (Nist), Transmitted Herewith Is Operations Report No. 74 for the Nbsr for the Cy 2022 ML23089A1132023-03-30030 March 2023 Us Dept. of Commerce - National Institute of Standards & Technology - Non-Availability of Fuel and Funding to Convert Nbsr from HEU to LEU in 2021 ML23086B3832023-03-27027 March 2023 Us Dept. of Commerce, National Institute of Standards & Technology (NIST) - Change of Ncnr Director ML23040A3372023-03-0909 March 2023 NIST Restart Authorization Letter ML23059A0502023-03-0707 March 2023 Examination Confirmation Letter No. 50-184/OL-23-02, National Institute of Standards and Technology IR 05000184/20222022023-03-0707 March 2023 National Institute of Standards and Technology U.S. Nuclear Regulatory Commission 4th 2022 Quarter Supplemental Inspection Report 05000184/2022202 ML23055A3002023-03-0303 March 2023 NIST License Amendment 15 - Core Alternative Reload Methodology Scheme ML23020A9112023-02-0101 February 2023 National Institute of Standards and Technology Issuance of Amendment No. 14 to Renewed Facility Operating License No. TR 5 ML23033A1152023-02-0101 February 2023 Us Dept. of Commerce, National Institute of Standards & Technology, License Amendment Request IR 05000184/20222032023-01-27027 January 2023 National Institute of Standards and Technology - U.S. Nuclear Regulatory Commission Security Inspection Report 05000184/2022203 ML22350A0652022-12-13013 December 2022 Us Dept. of Commerce, National Institute of Standards & Technology (Nist), License Amendment Request ML22322A2182022-11-28028 November 2022 National Institute of Standards and Technology - Report on the Regulatory Audit Re Restart Request Following Exceedance of Cladding Temperature Safety Limit ML22322A2112022-11-17017 November 2022 NIST Center for Neutron Research, License Amendment Request. Response to NRC Questions Regarding the Primary and Effluent Monitoring Systems ML22293B8082022-10-19019 October 2022 National Institute of Standards & Technology (NIST) - License Amendment Request ML22235A1172022-08-23023 August 2022 Us Dept of Commerce, National Institute of Standards & Technology, Transmittal of Draft of a Proposed Presentation of 02/03/2021, Nbsr Event for NRC Review ML22227A1502022-08-15015 August 2022 Us Dept of Commerce, National Institute of Standards & Technology (Nist), Request NRC Permission to Restart the Reactor Upon Completion of Listed Corrective Actions and Recovery Efforts ML22223A1462022-08-11011 August 2022 Docket Number 50-184 and the Nbsr Requalification Plan ML22206A2132022-08-0101 August 2022 Letter to National Institute of Standards and Technology, Center for Neutron Research - Confirmatory Order (EA-21-148) ML22206A0102022-08-0101 August 2022 U.S. Nuclear Regulatory Commission Supplemental Inspection Plan for National Institute of Standards and Technology ML22181A1282022-07-21021 July 2022 National Institute of Standards and Technology - Issuance of Amendment No. 13 to Renewed Facility Operating License No. TR-5 ML22187A1272022-06-29029 June 2022 Nbsr Restart Request ML22160A2852022-06-0808 June 2022 Nbsr License Amendment Request Supplement ML22122A0882022-04-27027 April 2022 Letter for T. H. Newton, NIST Center for Neutron Research, from J. S. Bowen, Nrc/Nrr/Danu, NRC Office of Investigations Report No. 1-2022-005 - Release of OI Synopsis ML22094A1082022-04-0404 April 2022 Transmittal of Operations Report No. 74 for the Nbsr for January 1, 2021 to December 31, 2021 ML22084A4082022-03-30030 March 2022 NIST - Non-availability of Fuel and Funding to Convert Nbsr from HEU to LEU in 2021 IR 05000184/20222012022-03-16016 March 2022 National Institute of Standards and Technology - Us Nuclear Regulatory Commission Special Inspection Report No 05000184-2022201 ML22012A0902022-01-11011 January 2022 Nbsr License Amendment Request, Revised No Significant Hazard Consideration Determination ML21349A3772022-01-0404 January 2022 December 7, 2021, Summary of Mtg with Nist to Discuss Proposed Technical Specification Changes at the National Bureau of Standards Reactor EPID L-2021-LLN-0000 ML21361A2472021-12-23023 December 2021 Nbsr License Amendment Request ML21355A2752021-12-21021 December 2021 Us Dept. of Commerce, National Institute of Standards & Technology, Nbsr Response to Request for Supplemental Information on Request to Restart the Nbsr ML21355A2742021-12-20020 December 2021 Us Dept. of Commerce, National Institute of Standards & Technology, Supplement to October 1, 2021 Report and Restart Request ML21340A0092021-12-0303 December 2021 Nbsr Response to Request for Supplemental Information on Request to Restart the Nbsr 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 ML21294A3732021-10-21021 October 2021 National Institute of Standards and Technology - Submittal of Supplement to October 1, 2021 Report and Restart Request ML21288A5552021-10-15015 October 2021 Us Dept. of Commerce, National Institute of Standards and Technology (NIST) - Supplement to October 1, 2021 Report and Restart Request ML21274A0272021-10-0101 October 2021 Nbsr Report on February 3, 2021 Fuel Failure Event, Root Causes, Corrective Actions, and Restart Readiness ML21265A4352021-09-24024 September 2021 National Institute of Standards and Technology - Change of Facility Project Manager ML21153A4162021-06-15015 June 2021 National Institute of Standards and Technology - Acceptance of the Application for a License Amendment Request for License Amendment and Addjustment of Tritium Effluent Values for D2 Cold Source Under Title 10 of the Code of Federal Regulat ML21153A3962021-06-0202 June 2021 Us Dept of Commerce, National Institute of Standards & Technology (NIST) - Docket Number 50-184 and the Nbsr Requalification Plan ML21133A2662021-05-13013 May 2021 Us Dept. of Commerce, National Institute of Standards & Technology, Follow-Up to Event Report ML21130A6042021-04-30030 April 2021 Us Dept of Commerce, National Institute of Standard & Technology - Non-Availability of Fuel and Funding to Convert Nbsr from HEU to LEU in 2021 IR 05000184/20212012021-04-14014 April 2021 National Institute of Standards and Technology U.S. Nuclear Regulatory Commission Interim Special Inspection Report No. 05000184/2021201 2024-01-25
[Table view] Category:Technical Specifications
MONTHYEARML23020A9112023-02-0101 February 2023 National Institute of Standards and Technology Issuance of Amendment No. 14 to Renewed Facility Operating License No. TR 5 ML22181A1282022-07-21021 July 2022 National Institute of Standards and Technology - Issuance of Amendment No. 13 to Renewed Facility Operating License No. TR-5 ML20230A2932020-09-22022 September 2020 National Institute of Standards and Technology License Amendment No. 12 Approval of the Physical Security Plan for the Center for Neutron Research ML17292A0622017-12-15015 December 2017 National Institute of Standards and Technology, Amendment No. 11 to the Renewed Facility License No. TR-5 for the National Bureau of Standards Reactor (CAC No. 000955) ML17335A3692017-12-0101 December 2017 Supplemental Information National Institute of Standards and Technology Request for Additional Information of License Amendment Request for the Renewed Facility License No. R-5 for the National Bureau of Standards Test Reactor ML17328A5042017-11-20020 November 2017 Supplement for Request for Changes to Nbsr Technical Specifications to Allow Low Power Testing ML17333A1242017-11-17017 November 2017 Supplement for Request for Changes to Nbsr Technical Specifications to Allow Low Power Testing ML13247A0332013-08-23023 August 2013 Report of Ncnr Violation of Limiting Conditions for Operations ML0908903272009-03-19019 March 2009 Submittal of Response to Request for Additional Information Regarding Advisory Committee on Reactor Safeguards Subcommittee Meeting Follow-Up Items and the Revised Nbsr Technical Specifications 2023-02-01
[Table view] |
Text
December 1, 2017 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 UNiTECI STATES IJEFIARTMENT OF COMMERCE National Institute of Standards and Technology Gaitheroburg, Maryland 20888-
Subject:
Supplement for request for changes to NBSR Technical Specifications to allow low power testing. Ref: Docket 50-184. TR-5 Facility License Sirs/Madams:
On November 20, 2017. NCNR sent a request for subsequent changes regarding our license amendment request of March 2, 2017. Afl:cr discussions with NRC staff. we are requesting additional changes to technical specifications 3.3.1 and 3.3.2. Attached is a copy of the Technical Specification pages to be changed, with change bars. Please contact Dr. Thomas Newton at (301) 975-6260 if you have any questions.
Respectfully, WM.~ Robert M. Dimeo, Director NIST Center for Neutron Research 100 Bureau Drive, MS 6100 Bldg. 235, Room K 107 Gaithersburg, MD 20899 I declare under penalty of perjury that the foregoing is true and correct. Rxecuted on December 1, 2017 By:~M.0;-.. cc: Xiaosong Yin, BRR/DPR/PRLB NlSI The nuclear and process channels of Table 3.2.2 initiate protective action to Ensure that the safety limit is not exceeded.
With these channels operable, the safety system has redundancy.
3 .3 Coolant System 3 .3 .1 Primary and Secondary Applicability:
Primary fluid systems Objective:
To prevent degradation of primary systems' materials.
Specifications The reactor shall not be operated unless: ( 1) The reactor vessel coolant level is no more than 25 inches below the overflow standpipe.
Exception:
To perform periodic surveillance of the effectiveness of the moderator dump or approach to critical testing for a previously unmeasured core loading, it is necessary to operate the reactor as permitted in the specifications of Section 2.2(4) and without restriction on reactor vessel level above the top of the 6" overflow pipe (refueling level) (2) The D2 concentration in the Helium Sweep System shall not exceed 4% by volume. (3) All materials, including those of the reactor vessel, in contact with the primary coolant shall be compatible with the D 2 0 environment . . ! (1) The limiting value for reactor vessel coolant level is somewhat arbitrary because the core is in no danger so long as it is covered with water. However, a drop of vessel level indicates a malfunction of the reactor cooling system and possible approach to uncoyering the qore. Thus, a measurable value well above the mfoimum level is chosen i~ order to provide a generous margin of approximately 7 feet (2.13 m) above the fuel elements.
To permit periodic t~sting, such as surveillance of the effectiveness of the moderator dump or approach to criticaf for a previously unmeasured core loading, h is necessary to operate the reactor without restriction on reactor vessel level. This is permissible urider conditions when forced reactor cooling flow is not required, such as is permitted in.the specifications of Section 2.2( 4). i7 (2) Deuterium gas will collect in the helium cover gas system because of radiolytic disassociation of D 2 0. Damage to the primai;y system could occur if this gas were to reach an explosive concentration (about 7.8% by volume at 77°F (25°C) in helium if mixed with air). To ensure a substantial margin below the lowest potentially explo.sive value, a . . 4% limit is imposed. . . . . (3) Materials of construction, being pri~~rily low aqtivation alloys and stainless steel, are chemically compatible with the primary coolant. The stainless steel pumps are heavy walled members and are in areas of low stress, so they should not be susceptible to chemical attack or stress corrosion failures.
A failure of the gaskets or valve bellows would not result in catastrophic failure of the primary system. Othei* materials should be compatible so as not to cause a los~ of material and system integrity.
3 .3 .2 Emergency Core Cooling Applicability:
Emergency Core Cooling System Objective:
To ensure an emergency supply of coolant. Specifications The reactor shall not be operated unless: (1) The D 2 0 emergency core cooling system is operable, except when operating under specification 2.2( 4) (2) A source of makeup water to the D 2 0 emergency cooling tank is available.
(1) In the event of a loss of core coolant, the emergency core cooling system provides adequate protection against melting of the reactor core and associated release of fission products.
Full operability is not available, nor is it needed, when operating as permitted by the specifications of Sections 2.2(4) and 33.1(1). However, the 3000 gallon D 2 0 emergency cooling tank and a source of makeup water would be available.
(2) The emergency core cooling system employs one sump pump to return spilled coolant to the overhead storage tank. Because only one sump p11mp is used, it must be operational whenever the reactor is operational.
There is sufficient D20 available to provide approximately
2.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />s
of cooling on a once-through basis. In the event that the sump pump fails and the D20 supply in the overhead storage tank is exhausted, domestic water or a suitable alternative would be used to furnish water for once-through cooling. The water makeup capacity must be in excess of.25 gpm, which_ was found adequate in cooling calculations to prevent fuel damage. 18