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{{#Wiki_filter:MIT NUCLEAR REACTOR LABORATORY AN MIT INTERDEPARTMENTAL CENTER John A. Bernard | {{#Wiki_filter:MIT NUCLEAR REACTOR LABORATORY AN MIT INTERDEPARTMENTAL CENTER John A. Bernard Mail Stop: NW12-208a Phone: 617 253-4202 Director of Reactor Operations 138 Albany Street Fax: 617 253-7300 Principal Research Engineer Cambridge, MA 02139 Email: Bemardj@mit.edu November 7, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Room Washington, DC 20555 Re: Massachusetts Institute of Technology - Request for Additional Information Regarding Amendment Request (TAC No. MC5155); License No. R-37; Docket No. 50-20 | ||
-Request for Additional Information Regarding Amendment Request (TAC No. MC5155); License No. R-37; Docket No. 50-20 | |||
==Dear Sir or Madam:== | ==Dear Sir or Madam:== | ||
The Massachusetts Institute of Technology hereby provides the response for the above request.Please contact the undersigned with any questions. | |||
Sincerely, f A. Bernard, Ph , PE, CHP Director of Reactor Operations I declare under the penalty of perjury that the foregoing is true and correct.17 Executed on Date 7- &'ý-; 0 Sign e cc: w/enclosures | The Massachusetts Institute of Technology hereby provides the response for the above request. | ||
.Heat Exchanger RAI Response 1. The radiation detection systems in both the primary and secondary coolant systems (as specified in TS 3.8.3) will remain unchanged with the installation of the new heat exchanger. | Please contact the undersigned with any questions. | ||
Thus, the radiological impact is unchanged. | Sincerely, f A. Bernard, Ph , PE, CHP Director of Reactor Operations I declare under the penalty of perjury that the foregoing is true and correct. | ||
Detection of a primary to secondary leak is as follows: Operating: | 17 Executed on Date 7- &'ý-; 0 Sign e cc: w/enclosures Cindy Montgomery i Research and Test Reactors Branch A Division of Policy and Rulemaking Office of Nuclear Reactor Regulation w/enclosures Senior Project Manager Research and Test Reactors Branch A Division of Policy and Rulemaking Office of Nuclear Reactor Regulation w/enclosure Senior Reactor Inspector Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation w/o enclosure Document control Desk 14 6(ZI0 | ||
Primary pressure exceeds secondary pressure. | |||
As in the current system, any leak of primary water into the secondary system would be immediately detected by the secondary water monitors. | .Heat Exchanger RAI Response | ||
Appropriate action would then be taken, including shutting down the reactor until repairs could be made.Shutdown: | : 1. The radiation detection systems in both the primary and secondary coolant systems (as specified in TS 3.8.3) will remain unchanged with the installation of the new heat exchanger. Thus, the radiological impact is unchanged. Detection of a primary to secondary leak is as follows: | ||
Primary pressure exceeds secondary pressure. | Operating: Primary pressure exceeds secondary pressure. As in the current system, any leak of primary water into the secondary system would be immediately detected by the secondary water monitors. Appropriate action would then be taken, including shutting down the reactor until repairs could be made. | ||
Immediately after shutdown,* the coolant system remains in operational alignment. | Shutdown: Primary pressure exceeds secondary pressure. Immediately after shutdown, | ||
Although the radiation levels in the coolant are significantly reduced, the secondary water monitors remain sensitive enough to detect the presence of radionuclides in the water, and thus a leak would still be detected immediately. | *the coolant system remains in operational alignment. Although the radiation levels in the coolant are significantly reduced, the secondary water monitors remain sensitive enough to detect the presence of radionuclides in the water, and thus a leak would still be detected immediately. Once the reactor is in shutdown alignment, there is. no secondary water flow to the main heat exchanger. | ||
Once the reactor is in shutdown alignment, there is. no secondary water flow to the main heat exchanger. | The attached Appendix describes the secondary water monitors. | ||
The attached Appendix describes the secondary water monitors.2. The thermal-hydraulic safety limits for the MITR-II are based on reactor power, core tank level, primary flow, and primary temperature. | : 2. The thermal-hydraulic safety limits for the MITR-II are based on reactor power, core tank level, primary flow, and primary temperature. The heat exchangers in the primary system can only significantly affect the latter two parameters. Whether there are one, two, or three heat exchangers in use, as long as the heat from the reactor can be adequately removed under the nominal flow, and temperature conditions, the reactor safety limits will be met. The new heat exchanger has a significantly larger heat transfer surface area than one of the current heat exchangers, it has a higher overall heat transfer coefficient, and it is designed to remove at least 6 MW of heat under nominal conditions. A comparison of the two heat exchangers under the normal operating configurations and operating conditions is shown in the table below. This clearly shows the superiority of the new heat exchanger in removing heat. In particular, the primary to secondary temperature difference is greatly reduced. | ||
The heat exchangers in the primary system can only significantly affect the latter two parameters. | It should be noted that all of the reactor safety instrumentation, including primary flow and temperature scrams, will be unchanged by this installation. | ||
Whether there are one, two, or three heat exchangers in use, as long as the heat from the reactor can be adequately removed under the nominal flow, and temperature conditions, the reactor safety limits will be met. The new heat exchanger has a significantly larger heat transfer surface area than one of the current heat exchangers, it has a higher overall heat transfer coefficient, and it is designed to remove at least 6 MW of heat under nominal conditions. | Heat removed Primary AT (°C) Primary to secondary mean AT (°C) | ||
A comparison of the two heat exchangers under the normal operating configurations and operating conditions is shown in the table below. This clearly shows the superiority of the new heat exchanger in removing heat. In particular, the primary to secondary temperature difference is greatly reduced.It should be noted that all of the reactor safety instrumentation, including primary flow and temperature scrams, will be unchanged by this installation. | Old (two shell-and- 4.0 MW 7.2 17.8 tube)* | ||
Heat removed Primary AT (°C) Primary to secondary mean AT (°C)Old (two shell-and-4.0 MW 7.2 17.8 tube)*New (single plate 6.6 MW 12.6 8.5 type)Comparison of old and new heat exchangers at a primary flow rate of 2000 gpm, reactor outlet temperature 52 'C, and secondary inlet temperature | New (single plate 6.6 MW 12.6 8.5 type) | ||
-30 °C.*measured data Appendix Two redundant water monitors are mounted in a shielded location in the equipment room. Each system separately samples water from the eight-inch pipe leading to the cooling towers. Sample water is returned to the inlet pipe. Flow through the monitors depends on the pressure differential between the two pipes produced by the main pumps in the secondary system.Activity could be introduced to the secondary water if a leak developed within any of the heat exchangers serviced by the secondary water system.Each of the redundant monitors uses a gamma-sensitive scintillation detector that views a volume of water contained in a lead shield. It is sensitive to N- 16 and F- 18 which are present in the light water coolant whenever the reactor is operating and to Na-24 which is present both during operating and shutdown conditions because of its half-life. | Comparison of old and new heat exchangers at a primary flow rate of 2000 gpm, reactor outlet temperature 52 'C, and secondary inlet temperature -30 °C. | ||
The N- 16 isotope has a half-life of a few seconds, that of F- 18 is approximately fifteen minutes, and that of Na-24 is about 16 hours. A flow of about two gpm is maintained through each lead shield as indicated by local flow meters, HF-5 and HF-5A. Flow switches will produce a "Trouble Radiation Monitor Alarm" if the flow falls below one gpm.}} | *measured data | ||
Appendix Two redundant water monitors are mounted in a shielded location in the equipment room. Each system separately samples water from the eight-inch pipe leading to the cooling towers. Sample water is returned to the inlet pipe. Flow through the monitors depends on the pressure differential between the two pipes produced by the main pumps in the secondary system. | |||
Activity could be introduced to the secondary water if a leak developed within any of the heat exchangers serviced by the secondary water system. | |||
Each of the redundant monitors uses a gamma-sensitive scintillation detector that views a volume of water contained in a lead shield. It is sensitive to N- 16 and F- 18 which are present in the light water coolant whenever the reactor is operating and to Na-24 which is present both during operating and shutdown conditions because of its half-life. The N- 16 isotope has a half-life of a few seconds, that of F- 18 is approximately fifteen minutes, and that of Na-24 is about 16 hours. A flow of about two gpm is maintained through each lead shield as indicated by local flow meters, HF-5 and HF-5A. Flow switches will produce a "Trouble Radiation Monitor Alarm" if the flow falls below one gpm.}} | |||
Latest revision as of 12:15, 14 November 2019
| ML083180135 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 11/07/2008 |
| From: | Bernard J Massachusetts Institute of Technology (MIT) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC MC5155 | |
| Download: ML083180135 (3) | |
Text
MIT NUCLEAR REACTOR LABORATORY AN MIT INTERDEPARTMENTAL CENTER John A. Bernard Mail Stop: NW12-208a Phone: 617 253-4202 Director of Reactor Operations 138 Albany Street Fax: 617 253-7300 Principal Research Engineer Cambridge, MA 02139 Email: Bemardj@mit.edu November 7, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Room Washington, DC 20555 Re: Massachusetts Institute of Technology - Request for Additional Information Regarding Amendment Request (TAC No. MC5155); License No. R-37; Docket No. 50-20
Dear Sir or Madam:
The Massachusetts Institute of Technology hereby provides the response for the above request.
Please contact the undersigned with any questions.
Sincerely, f A. Bernard, Ph , PE, CHP Director of Reactor Operations I declare under the penalty of perjury that the foregoing is true and correct.
17 Executed on Date 7- &'ý-; 0 Sign e cc: w/enclosures Cindy Montgomery i Research and Test Reactors Branch A Division of Policy and Rulemaking Office of Nuclear Reactor Regulation w/enclosures Senior Project Manager Research and Test Reactors Branch A Division of Policy and Rulemaking Office of Nuclear Reactor Regulation w/enclosure Senior Reactor Inspector Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation w/o enclosure Document control Desk 14 6(ZI0
.Heat Exchanger RAI Response
- 1. The radiation detection systems in both the primary and secondary coolant systems (as specified in TS 3.8.3) will remain unchanged with the installation of the new heat exchanger. Thus, the radiological impact is unchanged. Detection of a primary to secondary leak is as follows:
Operating: Primary pressure exceeds secondary pressure. As in the current system, any leak of primary water into the secondary system would be immediately detected by the secondary water monitors. Appropriate action would then be taken, including shutting down the reactor until repairs could be made.
Shutdown: Primary pressure exceeds secondary pressure. Immediately after shutdown,
- the coolant system remains in operational alignment. Although the radiation levels in the coolant are significantly reduced, the secondary water monitors remain sensitive enough to detect the presence of radionuclides in the water, and thus a leak would still be detected immediately. Once the reactor is in shutdown alignment, there is. no secondary water flow to the main heat exchanger.
The attached Appendix describes the secondary water monitors.
- 2. The thermal-hydraulic safety limits for the MITR-II are based on reactor power, core tank level, primary flow, and primary temperature. The heat exchangers in the primary system can only significantly affect the latter two parameters. Whether there are one, two, or three heat exchangers in use, as long as the heat from the reactor can be adequately removed under the nominal flow, and temperature conditions, the reactor safety limits will be met. The new heat exchanger has a significantly larger heat transfer surface area than one of the current heat exchangers, it has a higher overall heat transfer coefficient, and it is designed to remove at least 6 MW of heat under nominal conditions. A comparison of the two heat exchangers under the normal operating configurations and operating conditions is shown in the table below. This clearly shows the superiority of the new heat exchanger in removing heat. In particular, the primary to secondary temperature difference is greatly reduced.
It should be noted that all of the reactor safety instrumentation, including primary flow and temperature scrams, will be unchanged by this installation.
Heat removed Primary AT (°C) Primary to secondary mean AT (°C)
Old (two shell-and- 4.0 MW 7.2 17.8 tube)*
New (single plate 6.6 MW 12.6 8.5 type)
Comparison of old and new heat exchangers at a primary flow rate of 2000 gpm, reactor outlet temperature 52 'C, and secondary inlet temperature -30 °C.
- measured data
Appendix Two redundant water monitors are mounted in a shielded location in the equipment room. Each system separately samples water from the eight-inch pipe leading to the cooling towers. Sample water is returned to the inlet pipe. Flow through the monitors depends on the pressure differential between the two pipes produced by the main pumps in the secondary system.
Activity could be introduced to the secondary water if a leak developed within any of the heat exchangers serviced by the secondary water system.
Each of the redundant monitors uses a gamma-sensitive scintillation detector that views a volume of water contained in a lead shield. It is sensitive to N- 16 and F- 18 which are present in the light water coolant whenever the reactor is operating and to Na-24 which is present both during operating and shutdown conditions because of its half-life. The N- 16 isotope has a half-life of a few seconds, that of F- 18 is approximately fifteen minutes, and that of Na-24 is about 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. A flow of about two gpm is maintained through each lead shield as indicated by local flow meters, HF-5 and HF-5A. Flow switches will produce a "Trouble Radiation Monitor Alarm" if the flow falls below one gpm.