ML16012A349

2015-12-FINAL Outlines

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)

FCS 2015 NRC Simulator Scenario ES-D-1 Outline Final As Run