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| number = ML16012A349 | | number = ML16012A349 | ||
| issue date = 12/14/2015 | | issue date = 12/14/2015 | ||
| title = | | title = 2015-12-FINAL Outlines | ||
| author name = Gaddy V | | author name = Gaddy V | ||
| author affiliation = NRC/RGN-IV/DRS/OB | | author affiliation = NRC/RGN-IV/DRS/OB | ||
| Line 13: | Line 13: | ||
| page count = 35 | | page count = 35 | ||
}} | }} | ||
=Text= | |||
{{#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). | |||
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) | |||
FCS 2015 NRC Simulator Scenario ES-D-1 Outline Final As Run}} | |||
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)