ML21316A038
| ML21316A038 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 11/08/2021 |
| From: | US Dept of Defense, Armed Forces Radiobiology Research Institute |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21316A032 | List: |
| References | |
| EPID L-2020-NFA-0012, GA/EMS-5059 T3S990001-FRS, Rev A | |
| Download: ML21316A038 (9) | |
Text
Enclosure 5 - Available to the Public Errata for USUHS/AFRRI TRIGA Reactor Control System Functional Requirements Specification (Conceptual) - T3S990001-FRS Rev A
Errata for USUHS/AFRRI TRIGA Reactor Control System Functional Requirements Specification (Conceptual)
T3S990001-FRS Rev A The purpose of the Functional Requirements Specification (FRS) was to define the conceptual requirements for the design, fabrication, and installation of the replacement systems. For the purposes of the specification; definitions, general system descriptions, and notes were provided as additional information and are not considered conceptual requirements. The conceptual requirements are defined in Section 2 and the Appendices of the document.
As with any complex project, requirements may evolve during the timeline of the project. The errata sheet summaries the major differences in the FRS to the as-built condition. For more in-depth descriptions of the as-built conditions refer to:
- License Amendment Request for the Upgrade of the Instrumentation and Control System for the Armed Forces Radiobiology Research Institute TRIGA Reactor Rev 1
- Supplemental Information for the License Amendment Request for the Upgrade of the Instrumentation and Control System for the Armed Forces Radiobiology Research Institute TRIGA Reactor Rev 1
- FSAR Chapter 7 - Instrumentation and Control Systems Rev 1 Errata Section 2.1 Page 12
- 1. Figure 2 - Functional System Block Diagram. The NP-1000 and the NPP-1000 lists UCIC neutron detectors whereas fission chambers are actually used.
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- 2. Section 2.2 Page 13 The conceptual design of the control console is a proposed functionally equivalent replacement of the existing system at AFRRI. All existing reactor instrumentation, control console, and auxiliary console equipment will be replaced, and the necessary interfaces with existing plant equipment will be provided. Operational upgrades to the existing system will include system data logging and historian capabilities within the control room.
NOTE: The Auxiliary Console was not part of the scope.
- 3. Section 2.2 Page 13 The new DAC will be installed in the reactor room in the same location as the existing DAC. Lt will house the NMP-1000, NP-1000, NPP-1000, NLW- 1000, NFT-1000 nuclear channels, and the PA-1000 preamplifier.
NOTE: The PA-1000 is mounted on the wall of the reactor room.
- 4. Section 2.3.2.1.4 Page 20 Reactor Display #2 contains much of the information found on Reactor Display
- 1. The primary difference is that Reactor Display #2 displays a software strip chart recorder in place of the reactor pool graphic and temperature displays. To make up for the loss of the fuel and water temperature displays, Reactor Display
- 2 displays NFT1 and water temperatures on a bar graph. (We could have displayed this same information in bar graph form on Reactor Display #1; however, tab #1 attempts to mimic the original QNX graphic display as closely as reasonable on the new system.) Reactor Display #2 is generally considered "site configurable" to put any information the local site wants to display in graphic form.
NOTE: The bargraphs remains unchanged from Display #1 to #2, only the core graphic/strip chart changes.
As Built FRS As Built FRS NMP SCRAM NMP HV Low External 3 SCRAM (combined with above) NMP % Power CCS Watchdog SCRAM CSS Watchdog NP SCRAM NP HV Low UIT Watchdog SCRAM UIT Watchdog (combined with above) NP % Power Low Pool SCRAM Low Pool Water Level NPP SCRAM NPP HV Low Software SCRAM (combined with above) NPP % Power SCRAM/EStop SCARM Page 2 of 8
NFT Hi Temp SCRAM NFT 1 Keyswitch off SCRAM Keyswitch (combined with above) NFT 2 AC Power Loss SCRAM External 1 SCRAM FIS SCRAM External 2 SCRAM System SCRAM External Scram CSC Manual WARNINGS Pane WARNINGS Pane, cont.
As Built FRS As Built FRS Mag Pwr Gnded NPP %Pwr 4 NLW Per Hi same NPP NV High NLW HV Low same NPP HV Low same NLW % Pwr 1 Hi NLW % Power NPP Comm same NLW % Pwr 2 Hi NFT 1 Hi T1 NFT 1 Hi NLW 1kW same NFT 1 Hi T2 NMP Low Src NLW Low Src NFT 2 Hi T3 NFT 2 Hi NLW Comm same NFT 2 Hi T4 NMP %Pwr 1 NMP %Pwr NFT 3 Hi T5 NMP %Pwr 1 NFT 3 Hi T6 NMP HV Low same NFT Comm NFT Comm 1 NMP Comm same NFT Comm 2 Pool Temp Hi same DAS Comm Pool Low (RWP) same Pb Door Interlock NP %Pwr 1 NP % Power NP %Pwr 2 NP %Pwr 3 NP %Pwr 4 NP HV Low same NP Comm same NPP %Pwr 1 NPP % Power NPP %Pwr 2 Page 3 of 8
NPP %Pwr 3 STATUS Pane STATUS Pane, cont.
As Built FIS As Built FIS NMP Power same ER 1 Door same NP % Power same ER 2 Door same NPP % Power same RS Door Reactor Shield 1 NLW % Power same Reactor Shield 2 NLW Period sec Core Position Reactor Zone NLW Period DPM same Exp Bypass 1 NFT 1 Temp same Exp Bypass 2 NFT 2 Temp same (grayed out) RAMS (1 through 6)
NFT 3 Temp (grayed out) Gas Stack Monitor Pool Temp same (grayed out) Water Box RAM Outlet Temp same (grayed out) (no Prep Area) CAMs (Primary, Secondary, ER 1, ER 2, Prep Area)
Inlet Temp Demineralizer Temp NLW Remote/Local NMP Remote/Local Inlet Cond (grayed out) NP Remote/Local Outlet Cond 1 (grayed out) NPP Remote/Local Outlet Cond 2 (grayed out) NFT Remote/Local Pool Level (inches) (grayed out)
Low Pool Lvl same Page 4 of 8
INTERLOCKS Pane (not listed in the FRS as a Pane but the interlocks are listed on Page 31.
As Built FRS PI: NMP Low Src Listed as NLW on page 39.
PI: NLW Period Listed TR: NLW 1kW Listed RWP: NLW HV FRS specifies both log and linear (NLW, NMP)
RWP: Two Up mentioned on page 39 RWP: Demin Temp Inlet Temperature RWP: Low Pool TR: Fire Invald TR: Two Up mentioned on page 39
- 6. Section 2.3.2.2 Page 21.
The prestart tests are not performed from the Left Side Status Display, but from Right Side Display under the Reactor Prestart Tests Tab.
- 7. Section 2.3.2.2 Page 21. RAM Pane: The radiation area monitors were not integrated into the console and remain completely separate. This Pane is greyed out.
- 8. Section 2.3.2.3 Page 23. The analog bargraphs do not have a NMP-100 Power Scram.
- NLW-1000 log power level
- NLW-1000 period
- NP-1000 linear power level
- NPP-1000 linear power level
- Fuel Temperature channel 1
- Fuel Temperature channel 2
- Fuel Temperature channel 3
- NV peak power for pulsing operations
- NVT integrated power for pulsing operations
- 9. Section 2.3.4 Page 24. The Reactor Mode Control Panel is not described in detail. Refer to LAR Rev 1 Section 6.3.3 Page 6-17 for a complete description.
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- 10. Section 2.3.6 Page 26. The scram/interlock test switches also include NFT 3 and Pool Lo. The as-built labelled names are slightly different but the functions are the same. There are additional selections for FT3 and Pool Lo (level).
- 11. Section 2.3.7 Page 26. That the selection for Safety/Reg is not an option.
- 12. Section 2.3.8 Page 26. Rod Drop times are not available on the recorders. Drop times are displayed on the Right Side Display. As stated in the FRS, the chart recorders have many more available inputs. Refer to the LAR Rev 1 Section 6.3.5.2 Page 6-22 for a complete description.
- 13. Section 2.3.9 Page 26.
The NLW-1000 also has a Low HV Test as part of the pre-start tests.
The NLW-1000 does not have high power test.
The NMP-1000 does not have a low count rate, high count rate as part of the pre-start tests.
The NMP-1000 does not have a high power test.
The NP/NPP does not have a high power on/off tests.
Refresh Test.
To initiate the prestart test the operator selects the Reactor Prestart Test tab on the Right Side Display and selects RUN to perform all of the tests.
The user presses the 'prestarts' software button on the status display to initiate the prestart tests. Pressing the 'prestarts' button changes the graphics display to the Prestarts tab and initiates the prestart tests.
- 14. Section 2.3.10 Page 27. The RAMs Pane is inactive.
- 15. Section 2.3.14 Page 29. The Radiation Monitoring System is not part of the scope.
- 16. Section 2.3.15 Page 30. AFRRI does have a high water level alarm, but it is locally alarming in the control room and does not interface with the control console and is not part of the scope.
- 17. Section 2.3.17 Page 30. There are no readouts for conductivity in the reactor control room.
- 18. Section 2.3.19 Page 31. There are no readouts or alarms for conductivity in the reactor control room.
Readout for the conductivity monitors is located in the control room and at local indicator in equipment room 2158.
An audible alarm, connected to the water monitor box cell readout in the control room, is activated if the bulk water resistivity falls below 0.5 megohm-cm.
- 19. Section 2.3.20 Page 31. Gamma Activity of the Water is not part of the scope.
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- 20. Section 2.3.21.1 Page 31.Airborne Radioactivity is not part of the scope.
- 21. Section 2.3.21.3 Page 31. Source level is measured and display in watts.
RWP prevents any control rod (including Transient rod) withdrawal unless, as a minimum, source level neutrons (10-5 watts) are present.
RWP prevents any control rod withdrawal unless high voltage is being supplied to the fission detector for the multi-range linear and wide-range log channel.
Interlocks not listed are: Low Pool Level, Fire Invalid, and if more than one up button is pushed.
- 23. Section 2.3.21.5 Page 34. There is not a reactor room scram.
- 24. Section 2.3.23 Page 34. Fuel Temp Channel 3 will cause a scram. Software scram, Reactor Permissive Relay (ROX).
- 25. Section 2.3.24 Page 35. The NP-1000 uses a fission chamber.
One uncompensated ion chamber fission chamber is connected to the NP-1000 safety channel.
- 26. Section 2.3.24 Page 36. The NPP-1000 uses a fission chamber for steady-state.
A fission chamber is connected to the NPP-1000 for steady-state while a second uncompensated ion chamber is used by the NPP-1000 percent power and pulsing channel for pulsing operations.
If a loss of high voltage to the fission chamber is sensed, a bistable circuit will be tripped, resulting in a SCRAM rod withdrawal interlock.
- 28. Section 2.3.24.1.5. In SCRAMmed mode, the rod drives are automatically driven down to the bottom and can only be raised if the scrams have be cleared.
Rod Withdrawal Prevent (RWP) interlock is activated by a low count rate on the NLW-1000 NMP-1000 when the log linear power is not greater than 1 7 % 1x10-5 watts power. An indication is provided on the console low high resolution monitor to indicate when a source level rod withdrawal interlock is present.
- 31. Section 2.3.24.3 Page 40. A short period does not cause a scram, it causes an RWP. External scram is not active. Scrams not listed are: steady-state timer, Software, AC Power Loss, Reactor Permissive Relay (ROX) which can be triggered by an interlock of the FIS not being satisfied, magnet pushbuttons for the Safety, Shim and Reg.
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- 32. Appendix 1. Page 42.
Prestart Tests are shown in Figure 6 not Figure 10 and 11.
Scram and Interlock Tests. Notes: The tests are performed by software but can be initiated by software or by the rotary dials located on the Reactor Mode Control Panel.
The rod drop timer is not on the digital recorder but displayed on the Reactor Display #1 screen.
Removable Data Storage also can be CD/DVD.
- 33. Appendix 2 Page 44.
The table refers to the Facility Interlock System input/outputs.
6 low water level scram is not part of the FIS and should not be listed.
Low water level indication is not part of the FIS and should not be listed.
There is no scram pushbutton in the reactor room.
The Core Dolly Override Switch is listed as reactor move bypass.
All I/O are listed in the Figure in Section 2.3.3. This figure is very difficult to read. A new figure has been uploaded to the portal - Open Item 27 - FIS Interlock Table - SECURED.pdf
- 34. Appendix 3 Page 46/47.
NPP-1000 there is also a NVT Trip for pulsing operations.
NMP-1000 scram are bypassed. The Low Source Trip is on the NMP-1000.
FT3 High Temp Scram is active and is the same as FT1 and FT2.
NLW-1000 Low Source Trip is on the NMP-1000.
Bulk Pool Temp - Trips: None Core Outlet Temp - Trips: None Demin Inlet Temp - Trips: RWP interlock at 60°C The radiation monitors are not connected to the console.
There is no High Pool Level scram.
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