Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
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Results
Other: ML17292A062, ML22028A002, ML22039A226, ML22040A338, ML22089A166, ML22143B016, ML22286A167, ML23093A027, ML23290A030, ML23353A069, ML24284A171
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MONTHYEARML17068A1632017-03-0202 March 2017 NIST Center for Neutron Research Test Reactor - Request for Changes to Technical Specifications to Allow Low Power Testing Project stage: Request ML17068A1642017-03-0202 March 2017 NIST Center for Neutron Research - Statement of No Significant Hazard Resulting from License Amendment Request Dated 03/02/2017 Project stage: Request ML17097A2432017-03-29029 March 2017 Marked-up Version of the License Amendment Request of the Nbsr Technical Specifications Project stage: Request ML17153A1722017-05-25025 May 2017 NIST - Supplement for Request for Changes to Nbsr Technical Specifications to Allow Low Power Testing Project stage: Request 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) Project stage: RAI ML17324A4412017-11-17017 November 2017 Supplement for Request for Changes to Nbsr Technical Specifications to Allow Low Power Testing Project stage: Request ML17328A5042017-11-20020 November 2017 Supplement for Request for Changes to Nbsr Technical Specifications to Allow Low Power Testing Project stage: Request 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 Project stage: Supplement 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) Project stage: Other ML18010A5622018-02-0202 February 2018 Aerotest Radiography and Research Reactor - Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML18054A2022018-02-21021 February 2018 Response to Request for Holding Information from Public Disclosure Project stage: Request ML18066A0802018-02-28028 February 2018 Submittal of Response to Request for Holding Information from Public Disclosure Project stage: Request ML18074A1112018-04-0202 April 2018 Request for Withholding Information from Public Disclosure Response to Request to Aerotest Operations, Inc. to Supplement the License Renewal Application Project stage: Withholding Request Acceptance ML21272A3762021-09-29029 September 2021 Kairos Power, LLC - Submittal of the Preliminary Safety Analysis Report for the Kairos Power Fluoride Salt-Cooled, High Temperature Non-Power Reactor (Hermes) Project stage: Request ML21306A1322021-10-31031 October 2021 Kairos Power LLC Submittal of the Environmental Report for the Kairos Power Fluoride Salt-Cooled, High Temperature Non-Power Reactor (Hermes) Project stage: Request ML22024A4922022-01-10010 January 2022 Hermes CP RAI - Preliminary Questions on the Hermes PSAR, Email 1 Project stage: Request ML22028A0022022-02-0202 February 2022 Kairos Hermes Environmental Audit Plan Project stage: Other ML22041A3372022-02-0303 February 2022 Kairos Power LLC, Transmittal of Responses-to NRC Questions 2.3-1 and 2.3-2 on the Hermes Preliminary Safety Analysis Report Project stage: Request ML22040A3362022-02-0909 February 2022 Kairos Power LLC, Submittal of Response to NRC Questions 2.5-1, 2.5-2, 2.5-3, and 2.5-4 for PSAR Section 2.5 on Hermes Construction Permit Application Project stage: Request ML22040A3382022-02-0909 February 2022 Kairos Power LLC, Response to NRC Questions 2.5-1, 2.5-2, 2.5-3, and 2.5-4 for PSAR Section 2.5 on Hermes Construction Permit Application Project stage: Other ML22039A2262022-02-17017 February 2022 Audit Plan for the Kairos Hermes Preliminary Safety Analysis Report (PSAR) Section 6.3 Decay Heat Removal System - February 2022 Project stage: Other ML22089A1662022-04-0808 April 2022 Kairos Power LLC - Hermes Construction Permit Preliminary Safety Analysis Report I&C Repor (Chapter 7) Audit Plan (Cac/Epid No. 000955/05007513/L-2021-NEW-0011) Project stage: Other ML22143B0162022-05-27027 May 2022 Audit Plan for Hermes Site Characteristics PSAR Chapter 2 Project stage: Other ML22286A1672022-10-17017 October 2022 Atomic Alchemy Inc Preliminary Safety Analysis Report Pre-Submittal Audit Plan Project stage: Other ML23093A0272023-04-0404 April 2023 Atomic Alchemy, Inc., PSAR Secondary Pre-Submittal Audit Plan Project stage: Other ML24284A1712023-07-14014 July 2023 NRC-002B - Kairos Power LLC, Construction Permit Application - General Information (July 14, 2023) Project stage: Other ML23195A1252023-07-14014 July 2023 Enclosure 3: Environmental Report H2-ER-0000001, Rev. 0 Project stage: Request ML23237B4652023-09-11011 September 2023 FRN: General Notice. Acceptance for Docketing of the Kairos Power LLC Hermes 2 Test Reactor Construction Permit Project stage: Request ML23290A0302023-10-17017 October 2023 Atomic Alchemy Inc PSAR Tertiary Pre-Submittal Audit Plan Project stage: Other ML23353A0692024-01-0505 January 2024 Kairos Power, LLC-Hermes 2-Environmental Report Audit Plan Project stage: Other 2021-09-29
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Text
UNITED STATES DEPARTMENT DF COMMERCE National Institute of Standards and Technology Gaithersburg, Maryland 20899-March 2, 2017 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Request changes to NBSR Technical Specifications to allow low power testing.
Ref:
Docket 50-184, TR-5 FacilityLicense Sirs/Madams:
The NIST Center for Neutron Research (NCNR) Test Reactor (NBSR) requests several changes to the TR-5 facility license technical specifications (TS).
The first group of these modifications are to the TS that specify the exemptions that are necessary to remove the apparent limitations in the present version of the TS. These limitations prohibit the use of a test procedure that is basic to the safe operation of NB SR. The approach-to-critical testing and TS 2.2(4) reactor operation is necessary to verify characteristics of an unknown core loading. The procedure is a variation of Start-up Test# 201 which was used during first start-up testing performed during the commissioning of the NBSR. The shims are replaced every 4 years because of burn-up of the cadmium poison. After installing the new shims, the core is conservatively defined as an unknown loading. Using an approach to critical during the fuel reload provides assurance that the characteristics of the core loading are within the specified parameters of safe reactor operation. The following Technical Specifications are to be modified:
TS 2.2, Limiting Safety System Settings will be clarified to show that conformance with 2.2 (4) conforms with specification (1) and renders the systems that provide the flow and temperature parameters (2) and (3) inoperable.
TS 3.1.3, Core Configuration will be changed to allow for low power operation without a full core loading for approach-to-critical testing and TS 2.2(4) reactor operation. This change also removes the objective of TS 3.1.3 to prevent broken shim arms from leaving the core.
Reassessment of design, quality assurance in the manufacture of the shim arms, and the extensive operating experience with them, finds it is extremely unlikely shims will break during operation permitted by TS 2.2(4).
TS 3.2.2 (3), (4), (5), (8), Reactor Safety System Channels will be annotated with exceptions to allow low power operations with reactor level and flow SCRAMs, and reactor outlet temperature rundowns bypassed.
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TS 3.3.1, Coolant System, Primary and Secondary will be changed to include an exception for approach-to-critical testing and TS 2.2(4) reactor operation with reactor vessel level as low as the top of the dump tube.
TS 3.3.2, Emergency Core Cooling will be changed to provide an exception and clarify that there is adequate D20 emergency core cooling available for approach-to-critical testing and TS 2.2(4) reactor operation even if the inner reserve tank is drained.
TS 3.7.1(2), (3), Monitoring Systems and Effluent Limits will be changed to provide an exception and clarify that even though the fission product monitor and the secondary coolant activity monitors are not operable during approach-to-critical testing and TS 2.2(4) reactor operation, the two of three gaseous effluent monitors, normal air, irradiated air, and stack air, are adequate to assure detection of abnormal effluent radioactivity.
TS 3.9.2.1, Fuel Handling, Within the Reactor Vessel will be changed to provide an exception and clarify that if operation of the reactor with natural circulation cooling flow is necessary during aprroach-to-critical testing using TS 2.2(4) reactor operation, fuel element latching may be exempted since the force developed from pump flow is not present.
In addition to the changes listed above, Technical Specification Figure 6.1 will be modified to correct a previous error to show NBSR Health Physics has an administrative reporting channel to the NCNR Director.
Also a license change.is requested in order to transfer the sources, necessary for reactor associated instrumentation calibration and testing, from the NIST SNM-362 license to the TR-5 license.
. This will assure-that the availability of sources needed to perform the surveillance required for the safe operation of the reactor is not dependent on a licensee external to the TR-5 license.
Respectfully, flJ,.:1 ~*
Robert M. Dimeo, Director NIST Center for Neutron Research 100 Bureau Drive, MS 6100 Bldg. 235, Room K107 Gaithersburg, MD 20899 I declare under penalty of perjury that the foregoing is true and correct.
- Executed on March 2, 2017 cc
- Xiaosong Yin, NRRIDPR/PRLB 2
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