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{{#Wiki_filter:Enclosure 5 - Available to the Public Errata for USUHS/AFRRI TRIGA Reactor Control System Functional Requirements Specification (Conceptual) - T3S990001-FRS Rev A
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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.
Page 1 of 8
: 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.
: 5.      Section 2.3.2.2 Page 21 SCRAM Pane                                          SCRAM Pane, cont.
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
* NMP Power Scram
* 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.
Page 5 of 8
: 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.
Page 6 of 8
: 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.
: 22. Section 2.3.21.3 Page 32. The RWP for Low HV is only on the NLW (log channel).
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.
: 27. Section 2.3.24 Page 36. Loss of HV to the NLW is a RWP interlock not a scram.
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.
: 29. Section 2.3.24.2 Page 39. The RWP interlock is on the NMP.
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.
: 30. Section 2.3.24.3 Page 40. The period is an RWP interlock not scram.
: 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.
Page 7 of 8
: 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.
Page 8 of 8}}

Revision as of 15:58, 16 January 2022

Enclosure 5 - Errata for Usuhs/Afrri Triga Reactor Control System Functional Requirements Specification (Conceptual) - T3S990001-FRS Rev a
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)
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