ML16012A349

Fort Calhoun-2015-12-FINAL Outlines

ML16012A349
Person / Time
Site:	Fort Calhoun
Issue date:	12/14/2015
From:	Vincent Gaddy Operations Branch IV
To:
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Download: ML16012A349 (35)

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Appendix D Scenario Outline Form ES-D-1 FCS 2015 NRC Simulator Scenario ES

-D-1 Outline Final As Run 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 +20 min R (ATCO) N (BOPO, CRS)

Raise Power Using Control Rods to 7% per OP

-2A, Plant Startup. Place Steam Dump and Bypass Valves in AUTO per OI

-MS-1A. 2 +30 min C (ATCO, CRS) TS (CRS) Raw Water Pump Discharge Line Leak Upstream of HCV

-2879A in the Auxiliary Building.

3 +45 min I (BOPO, CRS) TS (CRS) Inadvertent Channel B Auxiliary Feedwater Actuation Signal On Steam Generator RC

-2A. 4 +60 min C (ATCO, CRS) TS (CRS) Loss of Instrument Bus AI

-40A. Loss of Letdown and Pressurizer Level Control.

(Alternate Path Event 8) 5 +60 min M (ATCO, BOPO, CRS) Reactor Coolant Pump RC

-3A Trip.

Automatic Reactor Trip Failure, Manual Reactor Trip Required.

6 +65 min C (BOPO) Instrument Air Compressor CA

-1B and CA

-1C Trip. Bearing Cooling Water Pump AC

-9B Trip. 7 +70 min M (ATCO, BOPO, CRS) Steam Line Break inside Containment on RC

-2A @ 0.65% Severity 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)

Appendix D Scenario Outline Form ES-D-1 FCS 2015 NRC Simulator Scenario ES

-D-1 Outline Final As Run 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 +20 min R (ATCO) N (BOPO, CRS)

Raise Power Using Control Rods to 7% per OP

-2A, Plant Startup. Place Steam Dump and Bypass Valves in AUTO per OI

-MS-1A. 2 +30 min C (ATCO, CRS) TS (CRS) Raw Water Pump Discharge Line Leak Upstream of HCV

-2879A in the Auxiliary Building.

3 +45 min I (BOPO, CRS) TS (CRS) Inadvertent Channel B Auxiliary Feedwater Actuation Signal On Steam Generator RC

-2A. 4 +60 min C (ATCO, CRS) TS (CRS) Loss of Instrument Bus AI

-40A. Loss of Letdown and Pressurizer Level Control.

(Alternate Path Event 8) 5 +60 min M (ATCO, BOPO, CRS) Reactor Coolant Pump RC

-3A Trip.

Automatic Reactor Trip Failure, Manual Reactor Trip Required.

6 +65 min C (BOPO) Instrument Air Compressor CA

-1B and CA

-1C Trip. Bearing Cooling Water Pump AC

-9B Trip. 7 +70 min M (ATCO, BOPO, CRS) Steam Line Break inside Containment on RC

-2A @ 0.65% Severity 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)