Letter Sequence Response to RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement, Supplement
Results
Other: ML110270002, ML11318A281, ML113460038, ML120180131, ML120730278, ML120800032, ML120800036, ML12137A151, ML12137A171, ML13022A010, ML13094A006, ML13113A001
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MONTHYEARML1016106562010-06-17017 June 2010 Dow Chemical Company, Request for Additional Information Regarding Financial Qualifications for Triga Research Reactor (Tac ME1595) Project stage: RAI ML1018101622010-07-12012 July 2010 Dow Chemical Company - Request for Additional Information Regarding the Environmental Assessment for the License Renewal Review (TAC Me1595) Project stage: RAI ML1022900132010-08-12012 August 2010 Dow Chemical Company Extension Request for Financial RAI Project stage: Request ML1023802992010-09-0101 September 2010 Dow Chemical Company - Approval of Request for an Extension, Financial Request for Additional Information Dated June 17, 2010 (Tac ME1595) Project stage: RAI ML1025202812010-09-16016 September 2010 Dow Chemical Company - Request for Additional Information Regarding the Emergency Plan for the License Renewal and Power Uprate Application Review Project stage: RAI ML1027900032010-10-27027 October 2010 Dow Chemical Company - Request for Additional Information Regarding the Operator Requalification Program for the License Renewal and Power Uprate Application Review Project stage: RAI ML1027003072010-11-0202 November 2010 Dow Chemical Company - Request for Additional Information Required for the License Renewal and Power Uprate Application Review Project stage: RAI ML1101305012011-01-12012 January 2011 Dow Chemical Company, Withdrawing of to Increase Licensed Power Level to 750 Kw Request Project stage: Request ML1102700022011-01-31031 January 2011 Dow Chemical Company, Retraction of the Power Uprate Request for License Renewal Application Project stage: Other ML1104903912011-02-11011 February 2011 Dow Chemical Triga - Revised Safety Analysis Report, Technical Specifications and RAI Responses (2/11/2011), Redacted Version Project stage: Request ML1107300742011-03-21021 March 2011 Dow Chemical Company - Response to Dow Chemical Request for Additional Information Dated February 11, 2011 for Extension to Answer 18 Project stage: RAI ML1134601202011-04-20020 April 2011 Dow Chemical Company - *Redacted* Response to NRC Request for Additional Information License Renewal Clarifications to March 9, 2011 Telephone Conference Project stage: Response to RAI ML11136A2292011-05-12012 May 2011 Dow Chemical Company - Response to Request for Additional Information for the Renewal of License Triga Research Reactor No. 108 Project stage: Response to RAI ML11144A2872011-05-23023 May 2011 Dow Chemical Company - Management Changes. License No. R-108 Project stage: Request ML1121503272011-05-27027 May 2011 Dow Chemical Company - Redacted Version of ML11151A266, Dow Responses Dated May 27, 2011 Project stage: Request ML1117305822011-07-11011 July 2011 Dow Chemical Company - Request for Additional Information Regarding Financial Qualifications for the Dow Chemical Company Triga Research Reactor License Renewal Project stage: RAI ML1117400552011-07-11011 July 2011 Dow Chemical Company - NON-PROPRIETARY Version - Request for Additional Information Regarding Financial Qualifications for the Dow Chemical Company Triga Research Reactor License Renewal (Tac No. ME1595). License No. R-108; Docket No. 50-26 Project stage: RAI ML1115204782011-07-14014 July 2011 Dow Chemical Company - Response to Request for Additional Information Dated May 12, 2011 (Tac No. ME1595) Project stage: RAI ML11228A1172011-08-10010 August 2011 Dow Chemical Company, Response to Request for Additional Information Regarding Financial Qualifications in Support of License Renewal Project stage: Response to RAI ML11228A1162011-08-12012 August 2011 Letter Dow Chemical Company - Response to the Request for Additional Information for the Renewed License of the Triga Research Reactor Project stage: Request ML11249A0432011-08-31031 August 2011 The Dow Chemical Company, Revised Responses to RAI Questions 6, 11, 15-1, 17-1, 17-3, 34, 35, 36-2, 41,52, 54, 56, 57, 61-3, 62-2, 64-1, 65-1, 65-2 in Support of the License Renewal Project stage: Response to RAI ML1123719452011-09-0606 September 2011 Dow Chemical Company - Response to Request for Additional Information Dated August 10, 2011 and August 12, 2011 Project stage: RAI ML1125902622011-09-26026 September 2011 Dow Chemical Company - Review of the Revised Emergency Plan Submitted July 7, 2011, Project stage: Approval ML11287A0352011-10-12012 October 2011 The Dow Chemical Company - Request for Additional Information Regarding Financial Qualifications for the Dow Chemical Company Triga Research Reactor License Renewal Project stage: Request ML1129300352011-10-12012 October 2011 Dow Chemical Company, Redacted Revised Responses to NRC Request for Additional Information Questions 11, 14, 15-1, 16, 17-1, 17-3, 18, 19, 41, 52, 53, 54, and 56 in Support of the License Renewal Project stage: Response to RAI ML1130400042011-11-0202 November 2011 Dow Chemical Company, Approval of Extension Request to Respond to NRC Request for Additional Information Project stage: RAI ML1134101682011-11-10010 November 2011 Dow Chemical Company - *Redacted* Responses to NRC Request for Additional Information Technical Project stage: Response to RAI ML11318A2812011-11-10010 November 2011 The Dow Chemical Company, Revised Submittal for the Technical Specification in Support of the License Renewal Project stage: Other ML1134600382011-12-0606 December 2011 Dow Chemical Company - Redacted Updated Neutronic and Thermal Hydraulic Reports in Support of the License Renewal Dated December 3, 2011 (Tac No. ME1595) Project stage: Other ML11343A6462011-12-0707 December 2011 Dow, Submittal of Revised Response for the July 11, 2011 NRC Letter Request for Additional Information Regarding Financial Qualifications for Triga Research Reactor License Renewal TAC ME1595 Project stage: Request ML12019A0072012-01-13013 January 2012 The Dow Chemical Company Revised Response for July 11, 2011 NRC Letter Request for Additional Information Regarding Financial Qualifications for the Dow Chemical Company Triga Research Reactor License Renewal Project stage: Request ML12026A1522012-01-20020 January 2012 Dow Chemical Company - *Redacted* Revised Responses to NRC Request for Additional Information Questions 52, 54, and 56 in Support of the License Renewal (Tac ME1595) Project stage: Response to RAI ML12025A0892012-01-20020 January 2012 Dow Chemical Company, Transmittal of Dtrr Revised Responses to RAI Questions 52, 54, and 56 in Support of the License Renewal Project stage: Response to RAI ML1201801312012-01-26026 January 2012 Dow Chemical Company - Letter to Licensee Determination of Acceptability Project stage: Other ML12040A1282012-02-0707 February 2012 The Dow Chemical Company - Dtrr Revised Technical Specifications and Supplemental Information to the Dtrr Revised Response to RAI 54, Dated January 20, 2012 in Support of the License Renewal Project stage: Supplement ML1201801522012-02-0707 February 2012 FRN: Dow Chemical Company - Notice of Acceptance for Docketing of Application and Opportunity to Request a Hearing and Order Imposing Procedures for Access to SUNSI Project stage: Acceptance Review ML1207302782012-03-0505 March 2012 Dow Chemical Company - E-mail from K. Yale, Michigan Dept. of Environmental Quality to G. Wertz, NRC Project Manager, Notification of No Comments Environmental Assessment Project stage: Other ML12164A7842012-06-11011 June 2012 The Dow Chemical Company, Dtrr Revised Technical Specifications and Supplemental Information to the Dtrr Revised Response to RAI 41, Dated November 10, 2011, in Support of the License Renewal Project stage: Supplement ML1208000322012-07-10010 July 2012 Dow Chemical Company - Letter to Licensee Availability of Environmental Assessment Federal Register Notice (Tac ME1595) Project stage: Other ML1208000362012-07-10010 July 2012 General Notice - FRN: Notice of Availability of Environmental Assessment and Finding of No Significant Impact Renewal of Facility Operating License No. R-108 for the Dow Chemical Triga Research Reactor (Tac No. ME1595) Project stage: Other ML13022A0102013-01-18018 January 2013 Dow Chemical Company - E-mail from S. Yusuf, Dow to G. Wertz, NRC Dow Technical Specification Typographical Edits (Tac No. ME1595) Project stage: Other ML13094A0062013-05-0101 May 2013 FRN: General Notice: Dow Chemical Company - Supplement to Environmental Assessment (77 Fr 42771-42774) Waste Confidence Rule Project stage: Other NRC-2012-0026, FRN: General Notice: Dow Chemical Company - Supplement to Environmental Assessment (77 Fr 42771-42774) Waste Confidence Rule2013-05-0101 May 2013 FRN: General Notice: Dow Chemical Company - Supplement to Environmental Assessment (77 Fr 42771-42774) Waste Confidence Rule Project stage: Supplement ML13113A0012013-05-0606 May 2013 Dow Chemical Company - Letter to Licensee Notification of Supplemental Federal Register for Environmental Assessment Waste Confidence Rule Project stage: Other ML13157A4122013-06-26026 June 2013 Dow Chemical Company - Request for Additional Information Regarding the Renewal of Facility Operating License No. R-108 for the Dow Chemical Triga Research Reactor Project stage: RAI ML13196A2992013-07-11011 July 2013 Dow Chemical Company Response to RAI Letter Dated June 26, 2013 and Dtrr Revised Technical Specifications Project stage: Request ML13225A2512013-09-0606 September 2013 Dow Chemical Company - Request for Additional Information Regarding the Renewal of Facility Operating License No. R-108 for the Dow Chemical Triga Research Reactor Project stage: RAI ML14058B1342014-03-0606 March 2014 Dow Chemical Company Request for Additional Information Regarding Renewal of Facility Operating License No. R-108 for Dow Chemical Triga Research Reactor Project stage: RAI ML14070A1792014-03-0707 March 2014 Dow Triga Research Reactor - Annual Report - 2013 Project stage: Request ML14100A3492014-04-0909 April 2014 The Dow Chemical Co., Submittal of Responses to RAI Letter Dated 03/06/2014 and Dtrr Revised Technical Specifications Project stage: Request 2011-07-14
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Category:Letter
MONTHYEARML25056A0582025-02-19019 February 2025 Dow Chemical Co., Response to Order EA-NRR-2025-0013 ML25041A2132025-02-11011 February 2025 Dow Chemical Company-Conforming Amendment No. 9 for the Dow Triga Research Reactor to Conform It with Order EA-NRR-2025-0013 ML24354A2062025-02-0606 February 2025 Transmittal Letter and Order - NPUF Rule Order ML24354A2072025-02-0606 February 2025 Order for NPUF Rule (Single Order to All) ML24341A0422024-12-0404 December 2024 Dow Chemical Co. - a Dow Triga Researcher Reactor Senior Reactor Operators (SRO) on Medical Leave IR 05000264/20242012024-05-22022 May 2024 Dow Chemical Company - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000264/2024201 ML24066A1472024-03-11011 March 2024 Dow Chemical Company - Change of Facility Project Manager ML24057A0092024-02-21021 February 2024 Dow Triga Research Reactor Annual Report - 2023 IR 05000264/20232012023-08-0101 August 2023 Dow Chemical Company - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000264/2023201 - Cover Letter and Enclosure ML23062A1132023-02-28028 February 2023 Dow Chemical Co., Submittal of Annual Report for 2022 ML22284A0472022-10-0606 October 2022 Closure of Level 1 Finding for the Quad Cities Generating Station ML22062B6492022-05-24024 May 2022 Supplemental Information Needed for Acceptance of Proposed Alternative to Use ASME Code Case N-921 IR 05000264/20222012022-04-15015 April 2022 Dow Chemical Company - U.S. Nuclear Regulatory Commission Routine Inspection Report 05000264/2022201 ML22080A0722022-03-11011 March 2022 Dow Chemical Company - Management Change ML22055A5772022-02-0404 February 2022 Dow Chemical Co., Submittal of Annual Report for 2021 ML21271A0952021-10-0404 October 2021 Dow Chemical Company Change of Facility Project Manager IR 05000264/20212022021-08-10010 August 2021 Dow Chemical Company U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000264/2021202 IR 05000264/20212012021-05-27027 May 2021 Dow Chemical Company - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000264/2021201 ML21153A1642021-05-26026 May 2021 Dow Chemical Company - Management Change Update ML21063A2492021-02-16016 February 2021 Dow Triga Research Reactor Annual Report - 2020 ML20295A4242020-11-16016 November 2020 Notification of Mailing Address Change Regarding Submittal of Fingerprint Cards ML20247J3712020-09-0303 September 2020 Examination Confirmation Letter No. 50-264/OL-21-01, Dow Chemical Company Reactor ML20045F1952020-04-17017 April 2020 The Dow Chemical Company - Order Approving Indirect Transfer of Renewed Facility Operating License No. R-108 for the Dow Triga Research Reactor ML20062A1872020-02-24024 February 2020 Dow Chemical Co., Submittal of Annual Report ML19339F8002020-02-0606 February 2020 Dow Chemical Co., Notice of Consideration of Approval of Indirect License Transfer and Conforming Amendment and Opportunity for a Hearing and Petition for Leave to Intervene ML19330E2442019-11-22022 November 2019 Dow Chemical Co., Transmittal of Consent for an Indirect License Transfer IR 05000264/20192022019-10-30030 October 2019 Cover Letter - Dow Chemical Company - U.S. Nuclear Regulatory Commission Security Inspection Report No. 05000264/2019202 IR 05000264/20192012019-10-30030 October 2019 Dow Chemical Company Nuclear Regulatory Commission Routine Inspection Report No. 05000264/2019201 ML19063A4972019-02-22022 February 2019 Annual Report for the Dow Triga Research Nuclear Reactor, Docket No. 50-264 ML18365A3552019-01-0808 January 2019 Dow Chemical Company - Change of Facility Back-Up Project Manager IR 05000264/20182012018-10-19019 October 2018 Dow Chemical Company - U.S. Nuclear Regulatory Commission Routine Safety Inspection Report No. 05000264/2018201 ML18060A0792018-02-22022 February 2018 2017 Annual Report for the Dow Triga Research Reactor IR 05000264/20172012017-11-0808 November 2017 Dow Chemical Co., NRC Routine Inspection Report 05000264/2017201 ML17067A2792017-03-23023 March 2017 Dow Chemical Company - Non-Power Reactor Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools, for the Dow Triga Research Reactor, Docket No. 50-264 (CAC No. A11010) ML17061A5102017-02-24024 February 2017 Annual Report for the Dow Triga Research Nuclear Reactor IR 05000264/20162022016-09-16016 September 2016 Dow Chemical Company, NRC Security Related Inspection Report 05000264/2016202 IR 05000264/20162012016-09-14014 September 2016 Dow Chemical Company - NRC Routine Inspection Report 05000264/2016201, July 19-21, 2016 ML16166A4152016-06-13013 June 2016 The Dow Triga Research Reactor, Response to NRC Generic Letter 2016-01: Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML16068A1772016-02-29029 February 2016 Dow Triga Research Nuclear Reactor - Transmittal of Annual Report for 2015 ML15364A3732016-01-19019 January 2016 Dow Chemical Company Triga Research Reactor - Closure of Confirmatory Action Letter No. NRR-04-009 on Site-Specific Compensatory Measures Implementation Plan ML14290A4862015-06-0303 June 2015 Y020140127 - Withdrawal of Order EA-05-007, Order Imposing Additional Security Measures ML15051A3672015-02-17017 February 2015 Annual Report 2014 for the Dow Triga Research Nuclear Reactor IR 05000264/20142012014-09-15015 September 2014 IR 05000264/2014201 on August 26-28, 2014 at Dow Chemical Company -NRC Routine Inspection Report No. 50-264/2014-201 ML14202A3282014-07-23023 July 2014 Dow Chemical Company Review of the Surety Bond Increase Rider and Updated Standby Trust Agreement (TAC No. M79548) ML12137A1512014-06-18018 June 2014 Dow Chemical Company - Letter to License and Renewed Facility Operating License No. R-108 for the Dow Triga Research Reactor (Tac No. ME1595) ML14129A2742014-05-27027 May 2014 Dow Chemical Company - Change of Facility Backup Project Manager ML14100A3492014-04-0909 April 2014 The Dow Chemical Co., Submittal of Responses to RAI Letter Dated 03/06/2014 and Dtrr Revised Technical Specifications ML14070A1792014-03-0707 March 2014 Dow Triga Research Reactor - Annual Report - 2013 ML14133A0182014-03-0707 March 2014 Dow Chemical Company Surety Bond Increase Rider and Updated Standby Trust Agreement Schedules (TAC M79548) ML14058B1342014-03-0606 March 2014 Dow Chemical Company Request for Additional Information Regarding Renewal of Facility Operating License No. R-108 for Dow Chemical Triga Research Reactor 2025-02-06
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-41ýThe Dow Chemical Company Midland, Michigan 48667 Mr. Geoffrey Wertz Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
Subject:
Dow Chemical Company- Response to the Request for Additional Information for the renewed license of the TRIGA research reactor. License No. R-108; Docket No. 50-264 Enclosed the response to the request for additional information questions 8, 15, 17, and 28.In addition, I am requesting a 90 day extension for the following questions.
RAI 7,14,16,18,19,24,26,29,52,53,54,55,56,57.
Should you have any questions or need additional information, please contact the undersigned at 989-638-6932.
I declare under penalty of perjury that the foregoing is true and correct.Executed on May. 12,2011 Melinda Krahenbuhl, Ph.D.Director Dow TRIGA Research Reactor Subscribed and sworn to before me this a day of May, 2011 rýýy,Public
/ ,j rty, Michigan NOTARY F Expires: .C IBERLY ANN HARTMAN'UBLIC -STATE OF MICHIGAN OUNTY OF GLADWIN sion ExpiresO cemrne .j,20A6 he County o014\ýý &Lg' --ý PIV.My Commis Acting in ti'Ir cc: Wayde Konze, R&D Director -Analytical Sciences A.Wo Response to request for additional information The Dow Chemical Company May 2011
- 8. NUREG-1537, Part 1, Section 3.3, "Water Damage," requests the applicant to provide a description of the design of facility structures for protection against water damage that could impact instrumentation and control systems. Please provide a discussion of the design of the roof structure above the reactor room and provisions to maintain its integrity from water damage for the term of the renewed license.DTRR response: The roof of building 1602 is poured gypsum with a 6-ft by 6ft dome skylight equipped with two one-piece domes centered over the reactor pool. Maintenance on the building infrastructure is completed on an as need basis. Instrumentation is protected by not storing it directly on the floor in case of flooding.
If water damage is incurred by rod drives, the current to the magnet is interrupted the control rods drop by gravity into the core.15. NUREG-1537, Part 1, Section 4.5.1, "Normal Operating Conditions" requests the applicant to provide a description of the limiting core configuration (LCC), the core configuration that would yield the highest power density using the fuel specified for the reactor. All other core configurations utilized by the applicant should be encompassed by the safety analysis of this configuration.
The description should indicate the number, types, and locations of all core components on the grid plate including fuel, control rods, neutron reflectors, and moderators.
15.1 DTRR SAR, Section D.5.5, provides a list of reactivity worths but control rod worths are not included.
Please provide control rod worths specific to the LCC at the requested power level.15.2 DTRR SAR, Section A.3, describes the original fuel configuration as having 75 stainless steel (SS)-clad elements and one Aluminum (AI)-clad element. The DTRR SAR does not provide information relating to the DTRR fuel element and control rod layout for the requested power level. Please provide a complete description of the LCC for the requested power level and provide a core diagram showing all components.
15.3 The limit on excess reactivity is established in DTRR SAR Table 4. However, the actual excess reactivity of the DTRR LCC is not identified in the DTRR SAR. Please provide the calculated excess reactivity for the LCC at the requested power level.DTRR response: 15.1 At 300 kW the excess reactivity is limited to $3.00, and shutdown margin is $1.00 based on a cold xenon negligible condition
(<0.30$).
The control rod worth for the safety and shim is approximately
$3.00 each. The reg rod is worth -$ 1.00.The reactivity worth of the control rods are Shimi $2.68, Shim 2 $2.73, Reg $1.01 as measured 1/11/11.15.2 The core configuration is found in Figure 1. The core is loaded with 79 SS fuel elements, 1 Al fuel 1 element and 5 graphite dummies.15.3. The excess reactivity of the DTRR as currently configured is $2.28 (1/11/11)*F4-Rabbit Terminus*S-AmBe Source*D-Dummy element*AL- Alum1inum Fuel element*Safe- Safety control rod*Shim-Shim Control rod*Reg-Regulating Control Rod Figure 1. Upper grid plate 2
- 17. NUREG-1537, Part 1, Section 4.5.3, "Operating Limits" requests the applicant to provide information regarding the operating limits applicable to the LCC of its reactor. DTRR SAR, Section D does not provide sufficient information.
17.1 Please describe any limits or conditions on the evaluation of excess reactivity contributors, such as those due to temperature variations and poisons (e.g., xenon and samarium).
Please describe algebraically how DTRR determines excess reactivity showing all components.
17.2 Please describe any limits or conditions on the evaluation of shutdown margin, including a discussion of uncertainties.
17.3 The Safety Limit (SL) is based on fuel temperature, and the Limiting Safety System Setting (LSSS) is based on core power (DTRR TS 2.1 and DTRR TS 2.2). Please describe the relationship between these parameters and how the DTRR operation using the LCC at the new requested power level will result in fuel temperatures that are bounded by the SL.DTRR response: 17.1 Excess reactivity is experimentally determined using the data collected during the control rod worth determinations.at reference core condition.
This excess reactivity analysis is completed twice a year. The reference core condition is defined as -the core is at ambient temperature (cold) and the reactivity worth of xenon in the fuel is negligible (less than $.30). Additionally, excess reactivity is determined hourly when the reactor is operational.
Algebraically the core excess =both shim rod worths + reg rod worth at any given power level.17.2 Shut down margin is experimentally determined using the data collected during the control rod worth determinations which are done twice a year. The core is at the reference core condition.
Algebraically the Shutdown margin = total reactivity worth of the reg rod + the total reactivity of the smaller worth shim rod -the excess reactivity at reference core conditions.
Shutdown margin is $1.33 (1/11/11).
Uncertainties in the measurements of control rod worth are dependent on individual time measurements of reactor power change due to stepwise withdrawal of each individual control rod.Multiple measurements are taken at each step withdrawal for each control rod to minimize uncertainty.
Total rod worth is determined by curve fitting data. Uncertainty for the value of the shutdown margin using in this approach is estimated to be 5%.17.3 Using introductory nuclear physics (Lamarsh and Baratta 2001): fission produces energy. Some of this energy is deposited in the fuel and the cladding.
The result of this energy deposition is a change in the fuel temperature.
The change in the temperature is therefore dependent on the fission rate or power and the heat capacity of the fuel and clad. Limiting the power output (i.e. the rate of fission), limits the fuel temperature.
The DTRR is not equipped with instrumented fuel elements.
The maximum and average fuel temperature at 300 kW were calculated as 260 °C and 140°C, respectively assuming that the maximum and power density is twice the average power density. The model is an iterative 3 process using estimated flux, water temperature (60'C) and correlations for natural convection.
These estimates were confirmed based on measurements in similar facilities (Whittemore W.L. 1994).Lamarsh J.R. and Barratta A.J., "Introduction to Nuclear Engineering 3 rd edition", Prentice Hall Upper Saddle River, New Jersey, 1991 Whittemore W.L., "The General Atomics TRIGA MARK 1 Reactor: Past and Present" General Atomics, July 1994.28. NUREG-1537, Part 1, Section 7.1, "Summary Description" requests the applicant to provide a summary of the technical aspects, safety, philosophy, and objectives of the instrumentation and control (I&C) system design. DTRR SAR, Chapter G, does not provide sufficient information.
28.1 Please describe any bypass and interlock functions in the I&C system.28.2 Please describe the types of parameters monitored, both nuclear and non-nuclear; the number of channels designed to monitor each parameter; and the actuating logic that determines the need for actions to safely shutdown the reactor.28.3 Please describe the parameter display systems and equipment by which the operator can observe and control the operation of the reactor and important subsystems.
DTRR response:
Reference:
"Operation and maintenance manual microprocessor based instrumentation and control for the ICI TRACERCO TRIGA reactor", General Atomics 1990.28.1 The I&C system has an interlock on the start-up count rate, reactor drive control and period.When the start-up channel is less than 2 cps, control rod movement is prevented.
The reactor drive control prohibits the withdrawal of two or greater control rods by the control rod drives. The third interlock prohibits rod withdrawal when the reactor period is less than 3 seconds. Bypassing of the channels and interlocks in table 3.3 is permitted for checks, calibrations, maintenance or measurement with written approval from the Reactor Operations Committee.
28.2 Parameters that are monitored and displayed are Linear Power, Percent Power and Log power, pool water temperature, pool water activity, control rod position, and period. The following table indicates the scrammable channels and the channels monitoring the parameter and the actuating set point. In the case of the loss of high voltage there is no display. Pool water activity, control rod position, pool water temperature are not scrammable channels.
Additionally, the readings from the area radiation monitor and the continuous air monitor can be viewed from the console.4 Scram Channel Minimum Operable Scram Setpoint Reactor Power Level NM1000 & NPP1000 2 Not to exceed maximum licensed power Failure of the detector high-voltage power supply NPP1000 1 Detector High-Voltage Power Supply NM1000 1 Failure of the detector high-voltage power supply Detector High-Voltage Power Supply Manual Scram I Not applicable Not applicable Watchdog (DAC to CSC)1 28.3 The power monitoring channels, pool water temperature, and control rod position are displayed at the console at either the graphic display, status monitor or both. The water activity (Geiger tube) is displayed on top of the console. The area radiation monitor reading is displayed on a shelf to the right of the console. Rod drives movement is controlled by buttons located on the console. Figure 2 is a block diagram of the console.S Instrument Power Direct read bar graphs Power demand Key switch Keyboard Magnet up/own , Acknowledge Or t. IVI Figure 2. Block Diagram of the console 6