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{{#Wiki_filter:Appendix D Scenario Outline Form ES-D-1 | {{#Wiki_filter:Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Station Scenario No.: 4 Op Test No.: Dec 2015 NRC Examiners: Operators: | ||
Initial Conditions: MODE 2 at ~1% power - RCS Boron is 959 ppm (by sample). | |||
4 Op Test No.: | Turnover: Continue in OP-2A, Plant Startup and OI-RR-1, Reactor Regulating System Operation to raise Reactor power to 7% power. When MODE 1 is entered, place Steam Dump and Bypass Valves in AUTO per OI-MS-1A, Main Steam System Operation. | ||
Dec 2015 NRC Examiners: | |||
Operators: | |||
Initial Conditions: | |||
MODE 2 at ~1% power | |||
- RCS Boron is 959 ppm (by sample). | |||
Turnover: | |||
Continue in OP | |||
-2A, Plant Startup and OI | |||
-RR-1, Reactor Regulating System Operation to raise Reactor power to 7% power. When MODE 1 is entered, place Steam Dump and Bypass Valves in AUTO per OI-MS-1A, Main Steam System Operation. | |||
Critical Tasks: | Critical Tasks: | ||
Upon Loss of Cooling to Reactor Coolant Pumps (RCPs), Trip the Reactor and Trip Associated RCP(s) within 5 minutes of Total Loss of CCW flow or Motor Bearing Temperatures > 203°F but prior to exceeding 210°F or within 5 minutes of CCW temperature > 110°F. (Event 2). | * Upon Loss of Cooling to Reactor Coolant Pumps (RCPs), Trip the Reactor and Trip Associated RCP(s) within 5 minutes of Total Loss of CCW flow or Motor Bearing Temperatures > 203°F but prior to exceeding 210°F or within 5 minutes of CCW temperature | ||
> 110°F. (Event 2). OR | |||
Event Description 1 | * Manually Trip Reactor to meet Core Design Criteria of Lowering Reactor Power and Negative Startup Rate to Verify Reactivity Control Established During ATWS Event Prior to Exiting EOP-00, Standard Post Trip Actions. (Event 5) | ||
Raise Power Using Control Rods to 7% per OP | * Isolate the Affected Steam Generator to Prevent Excess Plant Cooldown and Reactivity Additions Prior to Steam Generator Level = 0% Wide Range Level. (Event 7) | ||
-2A, Plant Startup. Place Steam Dump and Bypass Valves in AUTO per OI | Event No. Malf. No. Event Type* Event Description 1 R (ATCO) Raise Power Using Control Rods to 7% per OP-2A, Plant Startup. | ||
-MS-1A. 2 | +20 min N (BOPO, CRS) Place Steam Dump and Bypass Valves in AUTO per OI-MS-1A. | ||
-2879A in the Auxiliary Building. 3 | 2 C (ATCO, CRS) Raw Water Pump Discharge Line Leak Upstream of HCV-2879A in | ||
-2A. 4 | +30 min TS (CRS) the Auxiliary Building. | ||
-40A. Loss of Letdown and Pressurizer Level Control. | 3 I (BOPO, CRS) Inadvertent Channel B Auxiliary Feedwater Actuation Signal On | ||
(Alternate Path Event 8) 5 | +45 min TS (CRS) Steam Generator RC-2A. | ||
-3A Trip. Automatic Reactor Trip Failure, Manual Reactor Trip Required. | 4 C (ATCO, CRS) Loss of Instrument Bus AI-40A. | ||
6 | +60 min TS (CRS) Loss of Letdown and Pressurizer Level Control. | ||
-1B and CA-1C Trip. Bearing Cooling Water Pump AC | (Alternate Path Event 8) 5 M (ATCO, BOPO, Reactor Coolant Pump RC-3A Trip. | ||
-9B Trip. 7 | +60 min CRS) Automatic Reactor Trip Failure, Manual Reactor Trip Required. | ||
-2A @ 0.65% Severity on 5 Minute Ramp. | 6 C (BOPO) Instrument Air Compressor CA-1B and CA-1C Trip. | ||
+65 min Bearing Cooling Water Pump AC-9B Trip. | |||
-4) 2 Major transients (1 | 7 M (ATCO, BOPO, Steam Line Break inside Containment on RC-2A @ 0.65% Severity | ||
-2) 1 EOPs entered/requiring substantive actions (1 | +70 min CRS) on 5 Minute Ramp. | ||
-2) 0 EOP contingencies requiring substantive actions (0 | * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 1 Malfunctions after EOP entry (1-2) 3 Abnormal events (2-4) 2 Major transients (1-2) 1 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3) | ||
-2) 2 Critical tasks (2 | FCS 2015 NRC Simulator Scenario ES-D-1 Outline Final As Run | ||
-3) | |||
Appendix D Scenario Outline Form ES-D-1 | Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Station Scenario No.: 4 Op Test No.: Dec 2015 NRC Examiners: Operators: | ||
Initial Conditions: MODE 2 at ~1% power - RCS Boron is 959 ppm (by sample). | |||
4 Op Test No.: | Turnover: Continue in OP-2A, Plant Startup and OI-RR-1, Reactor Regulating System Operation to raise Reactor power to 7% power. When MODE 1 is entered, place Steam Dump and Bypass Valves in AUTO per OI-MS-1A, Main Steam System Operation. | ||
Dec 2015 NRC Examiners: | |||
Operators: | |||
Initial Conditions: | |||
MODE 2 at ~1% power | |||
- RCS Boron is 959 ppm (by sample). | |||
Turnover: | |||
Continue in OP | |||
-2A, Plant Startup and OI | |||
-RR-1, Reactor Regulating System Operation to raise Reactor power to 7% power. When MODE 1 is entered, place Steam Dump and Bypass Valves in AUTO per OI-MS-1A, Main Steam System Operation. | |||
Critical Tasks: | Critical Tasks: | ||
Upon Loss of Cooling to Reactor Coolant Pumps (RCPs), Trip the Reactor and Trip Associated RCP(s) within 5 minutes of Total Loss of CCW flow or Motor Bearing Temperatures > 203°F but prior to exceeding 210°F or within 5 minutes of CCW temperature > 110°F. (Event 2). | * Upon Loss of Cooling to Reactor Coolant Pumps (RCPs), Trip the Reactor and Trip Associated RCP(s) within 5 minutes of Total Loss of CCW flow or Motor Bearing Temperatures > 203°F but prior to exceeding 210°F or within 5 minutes of CCW temperature | ||
> 110°F. (Event 2). OR | |||
Event Description 1 | * Manually Trip Reactor to meet Core Design Criteria of Lowering Reactor Power and Negative Startup Rate to Verify Reactivity Control Established During ATWS Event Prior to Exiting EOP-00, Standard Post Trip Actions. (Event 5) | ||
Raise Power Using Control Rods to 7% per OP | * Isolate the Affected Steam Generator to Prevent Excess Plant Cooldown and Reactivity Additions Prior to Steam Generator Level = 0% Wide Range Level. (Event 7) | ||
-2A, Plant Startup. Place Steam Dump and Bypass Valves in AUTO per OI | Event No. Malf. No. Event Type* Event Description 1 R (ATCO) Raise Power Using Control Rods to 7% per OP-2A, Plant Startup. | ||
-MS-1A. 2 | +20 min N (BOPO, CRS) Place Steam Dump and Bypass Valves in AUTO per OI-MS-1A. | ||
-2879A in the Auxiliary Building. 3 | 2 C (ATCO, CRS) Raw Water Pump Discharge Line Leak Upstream of HCV-2879A in | ||
-2A. 4 | +30 min TS (CRS) the Auxiliary Building. | ||
-40A. Loss of Letdown and Pressurizer Level Control. | 3 I (BOPO, CRS) Inadvertent Channel B Auxiliary Feedwater Actuation Signal On | ||
(Alternate Path Event 8) 5 | +45 min TS (CRS) Steam Generator RC-2A. | ||
-3A Trip. Automatic Reactor Trip Failure, Manual Reactor Trip Required. | 4 C (ATCO, CRS) Loss of Instrument Bus AI-40A. | ||
6 | +60 min TS (CRS) Loss of Letdown and Pressurizer Level Control. | ||
-1B and CA-1C Trip. Bearing Cooling Water Pump AC | (Alternate Path Event 8) 5 M (ATCO, BOPO, Reactor Coolant Pump RC-3A Trip. | ||
-9B Trip. 7 | +60 min CRS) Automatic Reactor Trip Failure, Manual Reactor Trip Required. | ||
-2A @ 0.65% Severity on 5 Minute Ramp. | 6 C (BOPO) Instrument Air Compressor CA-1B and CA-1C Trip. | ||
+65 min Bearing Cooling Water Pump AC-9B Trip. | |||
-4) 2 Major transients (1 | 7 M (ATCO, BOPO, Steam Line Break inside Containment on RC-2A @ 0.65% Severity | ||
-2) 1 EOPs entered/requiring substantive actions (1 | +70 min CRS) on 5 Minute Ramp. | ||
-2) 0 EOP contingencies requiring substantive actions (0 | * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 1 Malfunctions after EOP entry (1-2) 3 Abnormal events (2-4) 2 Major transients (1-2) 1 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3) | ||
-2) 2 Critical tasks (2 | FCS 2015 NRC Simulator Scenario ES-D-1 Outline Final As Run}} | ||
-3)}} | |||
Latest revision as of 02:19, 31 October 2019
| ML16012A349 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/14/2015 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | |
| References | |
| Download: ML16012A349 (35) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Station Scenario No.: 4 Op Test No.: Dec 2015 NRC Examiners: Operators:
Initial Conditions: MODE 2 at ~1% power - RCS Boron is 959 ppm (by sample).
Turnover: Continue in OP-2A, Plant Startup and OI-RR-1, Reactor Regulating System Operation to raise Reactor power to 7% power. When MODE 1 is entered, place Steam Dump and Bypass Valves in AUTO per OI-MS-1A, Main Steam System Operation.
Critical Tasks:
- Upon Loss of Cooling to Reactor Coolant Pumps (RCPs), Trip the Reactor and Trip Associated RCP(s) within 5 minutes of Total Loss of CCW flow or Motor Bearing Temperatures > 203°F but prior to exceeding 210°F or within 5 minutes of CCW temperature
> 110°F. (Event 2). OR
- Manually Trip Reactor to meet Core Design Criteria of Lowering Reactor Power and Negative Startup Rate to Verify Reactivity Control Established During ATWS Event Prior to Exiting EOP-00, Standard Post Trip Actions. (Event 5)
- Isolate the Affected Steam Generator to Prevent Excess Plant Cooldown and Reactivity Additions Prior to Steam Generator Level = 0% Wide Range Level. (Event 7)
Event No. Malf. No. Event Type* Event Description 1 R (ATCO) Raise Power Using Control Rods to 7% per OP-2A, Plant Startup.
+20 min N (BOPO, CRS) Place Steam Dump and Bypass Valves in AUTO per OI-MS-1A.
2 C (ATCO, CRS) Raw Water Pump Discharge Line Leak Upstream of HCV-2879A in
+30 min TS (CRS) the Auxiliary Building.
3 I (BOPO, CRS) Inadvertent Channel B Auxiliary Feedwater Actuation Signal On
+45 min TS (CRS) Steam Generator RC-2A.
4 C (ATCO, CRS) Loss of Instrument Bus AI-40A.
+60 min TS (CRS) Loss of Letdown and Pressurizer Level Control.
(Alternate Path Event 8) 5 M (ATCO, BOPO, Reactor Coolant Pump RC-3A Trip.
+60 min CRS) Automatic Reactor Trip Failure, Manual Reactor Trip Required.
6 C (BOPO) Instrument Air Compressor CA-1B and CA-1C Trip.
+65 min Bearing Cooling Water Pump AC-9B Trip.
7 M (ATCO, BOPO, Steam Line Break inside Containment on RC-2A @ 0.65% Severity
+70 min CRS) on 5 Minute Ramp.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 1 Malfunctions after EOP entry (1-2) 3 Abnormal events (2-4) 2 Major transients (1-2) 1 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3)
FCS 2015 NRC Simulator Scenario ES-D-1 Outline Final As Run
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Station Scenario No.: 4 Op Test No.: Dec 2015 NRC Examiners: Operators:
Initial Conditions: MODE 2 at ~1% power - RCS Boron is 959 ppm (by sample).
Turnover: Continue in OP-2A, Plant Startup and OI-RR-1, Reactor Regulating System Operation to raise Reactor power to 7% power. When MODE 1 is entered, place Steam Dump and Bypass Valves in AUTO per OI-MS-1A, Main Steam System Operation.
Critical Tasks:
- Upon Loss of Cooling to Reactor Coolant Pumps (RCPs), Trip the Reactor and Trip Associated RCP(s) within 5 minutes of Total Loss of CCW flow or Motor Bearing Temperatures > 203°F but prior to exceeding 210°F or within 5 minutes of CCW temperature
> 110°F. (Event 2). OR
- Manually Trip Reactor to meet Core Design Criteria of Lowering Reactor Power and Negative Startup Rate to Verify Reactivity Control Established During ATWS Event Prior to Exiting EOP-00, Standard Post Trip Actions. (Event 5)
- Isolate the Affected Steam Generator to Prevent Excess Plant Cooldown and Reactivity Additions Prior to Steam Generator Level = 0% Wide Range Level. (Event 7)
Event No. Malf. No. Event Type* Event Description 1 R (ATCO) Raise Power Using Control Rods to 7% per OP-2A, Plant Startup.
+20 min N (BOPO, CRS) Place Steam Dump and Bypass Valves in AUTO per OI-MS-1A.
2 C (ATCO, CRS) Raw Water Pump Discharge Line Leak Upstream of HCV-2879A in
+30 min TS (CRS) the Auxiliary Building.
3 I (BOPO, CRS) Inadvertent Channel B Auxiliary Feedwater Actuation Signal On
+45 min TS (CRS) Steam Generator RC-2A.
4 C (ATCO, CRS) Loss of Instrument Bus AI-40A.
+60 min TS (CRS) Loss of Letdown and Pressurizer Level Control.
(Alternate Path Event 8) 5 M (ATCO, BOPO, Reactor Coolant Pump RC-3A Trip.
+60 min CRS) Automatic Reactor Trip Failure, Manual Reactor Trip Required.
6 C (BOPO) Instrument Air Compressor CA-1B and CA-1C Trip.
+65 min Bearing Cooling Water Pump AC-9B Trip.
7 M (ATCO, BOPO, Steam Line Break inside Containment on RC-2A @ 0.65% Severity
+70 min CRS) on 5 Minute Ramp.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 1 Malfunctions after EOP entry (1-2) 3 Abnormal events (2-4) 2 Major transients (1-2) 1 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3)