Text

Final As-Run Scenarios for the Point Beach Initial Examination - November 2005
	ML060370466
Person / Time
Site:	Point Beach
Issue date:	11/07/2005
From:	Walton R; NRC/RGN-III/DRS/OLB
To:	;
References
	50-266/05-301, 50-301/05-301, ES-D-1 50-266/05-301, 50-301/05-301
	Download: ML060370466 (101)
	v • d • e

Appendix D Scenario Outline Form ES-D-1 Facility: Point Beach Scenario No.: 1 OP-Test No.: 2005301 Examiners: ______________________ Operators: ______________________

Initial Conditions: Unit 1 is at 75% power. Power was stabilized approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago after reducing load at

~12%/hour at the request of the Power System Supervisor. Boron Concentration is 815 PPM. Xenon is building in slightly. Unit 2 is at 100% power.

Turnover: G-01 EDG is out of service for annual maintenance. It was taken out of service 3 days ago and is expected to be returned to service in 3 days. G-02 is aligned to 4.16 kV buses 1A-05 and 2A-05 IAW OI-35A.

1TE-404, Loop B Hot Leg Temperature Element has failed high and has been removed from service IAW 1-SOP-IC-001 Yellow.

1RC-515, Block valve for 1RC-431C is closed due to PORV leakage. Tech Spec 3.4.11, Required Action A.1 has been completed.

IRPI is selected to alternate power (1Y02) due to planned breaker replacement on 1Y06 (Bkr 21).

Today is Sunday, present clock time is real time. An RP Tech and Chemistry Tech are on-site. ERO Maintenance personnel are working on G01.

The objective of the shift is to maintain stable plant conditions until the Power System Supervisor requests power be returned to 100%. OP-1C, Startup to Power Operation, has been prepared.

Event Malf. Event Event No. No. Type* Description I - RO 1 N - BOP 1LT-427 Pressurizer Level Channel Fails Low SRO(T)

C - BOP P-32B Service Water Pump Trip with reduced head capacity on two running SW 2

SRO(T) pumps C - BOP 3 SRO P-28B Main Feed Pump Bearing Failure (Overheat)/Power Reduction R - RO 4 M -ALL Main Feedwater Line Break inside Containment 5 C-RO Reactor Trip manual push buttons on 1C04 fail to operate

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Scenario #1 Initial Conditions: Unit 1 is at 75% power. Power was stabilized approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago after reducing load at ~12%/hour at the request of the Power System Supervisor. Boron Concentration is 815 PPM. Xenon is building in slightly. Unit 2 is at 100% power.

Turnover: G-01 EDG is out of service for annual maintenance. It was taken out of service 3 days ago and is expected to be returned to service in 3 days. G-02 is aligned to 4.16 kV buses 1A-05 and 2A-05 IAW OI-35A.

1TE-404, Loop B Hot Leg Temperature Element has failed high and has been removed from service IAW 1-SOP-IC-001 Yellow.

1RC-515, Block valve for 1RC-431C is closed due to PORV leakage. Tech Spec 3.4.11, Required Action A.1 has been completed.

IRPI is selected to alternate power (1Y02) due to planned breaker replacement on 1Y06 (Bkr 21).

Today is Sunday, present clock time is real time. An RP Tech and Chemistry Tech are on-site. ERO Maintenance personnel are working on G01.

The objective of the shift is to maintain stable plant conditions until the Power System Supervisor requests power be returned to 100%. OP-1C, Startup to Power Operation, has been prepared.

NUREG-1021, Revision 9

ANTICIPATED BOOTH COMMUNICATION/GUIDANCE: Scenario 1 Event 1: 1LT-427 Pressurizer Level Channel Fails Low - Per lead examiner (PLE) activate trigger Crew may contact the PAB operator to look at panel C-59 in response to the Waste Disposal annunciator Event 2: P-32B Service Water Pump Trip - PLE activate trigger Crew may contact AO to investigate tripped SW pump and/or breaker. The pump motor is excessively hot to the touch. The breaker has tripped on overcurrent.

Per AOP 9A step 12, the crew will contact the AO to determine if power is available to Zurn strainers at RK31 and RK 32 in the pump house. Power is available at RK31 and RK32.

Event 3: 1P-28B Main Feed Pump failure/ Power Reduction- PLE activate trigger Crew may send AO to investigate condition of 1P-28B main feed pump. There is discoloration on the bearing housing and the bearing is making a chirping noise. If asked, the other main feed pump, 1P-28A, is normal.

Per AOP 17A step 10 the crew may ask the AO to locally start main feed pump seal water pumps 1P-99A&B if not already running. Start pumps as requested. Pumps should be running, based on initial power level.

Event 4: Main Feedwater Line Break inside Containment - PLE activate trigger Per AOP-2A step 1 RNO, the crew may ask AO to locally shut TD AFW pump steam supply, 1MS-237. Shut valve as requested.

Per EOP-0 Att. A step A7, crew will request AO to check shut SW-LW-61 or 62 at C-180, blowdown evap panel. Both valves are shut.

Per EOP-2 step 7, the crew will ask the AO to locally shut 1P-29 AFP/Radwaste steam isolation for S/G B, 1MS-237. Shut valve as requested.

Per EOP-2 step 7, the crew will ask the AO to locally shut main steam trap isolation for S/G B, 1MS-238. Shut valve as requested.

Event 5: Reactor Trip manual push buttons on 1C04 fail to operate

- No anticipate booth communications

Scenario #1 Sim Setup:

IC-75, Unit 1 is at 75% power, power was reduced ~2 hours at PSS request, Xe is building in.

1RC-515 Shut to isolate leaky PORV G01 Out of Service G02 Aligned to both 1 and 2A05.

B, C, E Service Water Pumps in service IRPI selected to alternate power supply due to 1Y06 Breaker 21 Breaker Replacement.

K2B IA compressor in Constant, K2A in standby.

2P-4B in Auto, 2P-4A in standby.

Ensure P99s are ON.

TE-404 Removed from service IAW SOP. (Two Switches and yellow bistables)

Ensure T-404 and T-408 are removed from scan each time you reset Preloads:

1. PMP1SWS05C: SW Pump Head Capacity Val = 85%

2. PMP1SWS03C: SW Pump Head Capacity Val = 85%

3. OVRPPL033: 1C04 Trip Button Fails Digital Value = OFF

4. OVRPPL034: 1C04 Trip Button Fails Digital Value = OFF

5. XMT1RCS029A: 1TE-404 Failed High Sev = 650

Event Triggers:

T-1 XMT1RCS008A: 1LT-427 Pressurizer Level Fails Low Sev = 0, Ramp = 20 Sec.

T-3 BKR1SWS002: P32B SW Pump Breaker Trip Val = 1 T-5 XMT1CFW038A: P28B MFP Inboard Motor Bearing Hi Temp Sev = 205, Ramp = 280 Sec.

T-7 FLX1CFW031: Feed Line Break inside Containment Sev = 2300, Ramp = 240 Sec.

LOA Triggers:

T-16 LOA1WPS008: Acknowledge Waste Disposal Alarm

Op-Test No: 2005301 Scenario No: 1 Event No: 1 Page 1 of 5 Event

Description:

1LT-427 Pressurizer Level Channel Fails Low Time Position Applicants Actions or Behavior Trigger activated per Lead Examiner RO Identify failure of LT-427 Pressurizer Level

- LI-427 meter indication low

- 1C20D 2-1 PPCS PRIORITY

- 1C04 1C 1-3 Pressurizer Level High or Low RO Acknowledge and respond to instrument failure

- Recognize letdown isolated: letdown flow indication and valve position lights

- Establish minimum charging Direct entry into AOP-24, Response to Instrument Malfunctions.

SRO Note: May initially enter AOP-1D Chemical and Volume Control System Malfunction.

RO Identify Failed Instrument - LT-427 (Pressurizer Level White Channel)

RO Check if failed instrument is a controlling channel - LT-427 failing low will cause letdown to isolate and pressurizer heaters to deenergize RO Establish Manual Control - If not previously performed, establish minimum charging RO/SRO Return Affected Parameter(s) to desired value(s).

Note: Crew should identify when pressurizer pressure goes below 2205 psig. This is the COLR value for operating pressure. TRM 2.11.1 and TS 3.4.1

Op-Test No: 2005301 Scenario No: 1 Event No: 1 Page 2 of 5 Event

Description:

1LT-427 Pressurizer Level Channel Fails Low Time Position Applicants Actions or Behavior SRO Direct entry into 0-SOP-IC-001 - White, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service - White Channels.

- Obtain and implement 0-SOP-IC-001- White

- Review precautions and limitations

- Identify applicable Technical Specifications (reference 0-SOP-IC-002):

- LCO 3.3.1 is not met:

- Action Condition A is entered immediately - Required Action is to enter the Condition referenced in Table 3.3.1-1 for the channel.

- Condition K is referenced from Table 3.3.1-1 Function 8. Required Action is to place the channel in trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR reduce THERMAL POWER to < P-7 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

- Conduct pre-job brief for removing LT-427 from service

- Obtain Shift Manager permission to remove channel from service

- Direct 0-SOP-IC-001Attachment A for LT-427 removal from service

Op-Test No: 2005301 Scenario No: 1 Event No: 1 Page 3 of 5 Event

Description:

1LT-427 Pressurizer Level Channel Fails Low Time Position Applicants Actions or Behavior RO/BOP/SRO Note: The SRO may turn over command and control of the unit to allow direct oversight of actions taken behind the control boards Perform actions as directed by SRO from Attachment A for LT-427 removal.

- Place charging pump speed in manual and adjust for minimum flow

- In cabinet C-110 Place Pressurizer Level Defeat Switch L/428A to Defeat 2 (427 CH II)

- Place charging pump speed control in AUTO, unless directed otherwise by Shift Manager (Note: The Crew may wait to restore charging to Auto until after letdown has been restored.)

- Place the following bistables to TRIP inside C-113: (BOP)

- Verify alarms and trip status lights are proper (RO)

1. High Level Trip

- Remove L-427 from scan on PPCS SRO Inform Shift Manager LT-427 is removed from service and bypassed and that DCS and STA notifications need to be made SRO In AOP-24 Return controls to Automatic if desired Note: SRO may direct entry into AOP 1D Chemical and Volume Control System Malfunction at this point in order to recover letdown.

SRO In AOP-24 Check Failure for TS or TRM applicability (if not already identified)

Determine instrument channel operability requirements satisfied Inform Shift Manager of any operability requirements not satisfied SRO Exit AOP-24

Op-Test No: 2005301 Scenario No: 1 Event No: 1 Page 4 of 5 Event

Description:

1LT-427 Pressurizer Level Channel Fails Low Time Position Applicants Actions or Behavior SRO Direct entry into AOP 1D Chemical and Volume Control System Malfunction at this point in order to recover letdown.

SRO/RO Check RCS leak not in progress SRO/RO Address notes:

Foldout page Pressurizer level should be maintained less than the parametric value of 48% in mode 1.

TS require pressurizer level to be maintained less than or equal to 50.8%

in mode 1. Refer to LCO 3.4.9 SRO/RO Check for charging pump malfunction Crew should use RNO column guidance and proceed to step to restore letdown SRO/RO Check letdown inadvertently isolated SRO/RO Reduce charging to minimum (may have already been performed)

SRO/RO Check that letdown restoration can be performed Note: If the crew has entered AOP 1D prior to removing the LT-427 from service, they may wait to continue in this procedure until the failed channel has been removed.

SRO/RO Ensure Letdown orifice outlet valves shut Ensure normal charging is in service Check PZR level - Greater than 20%

Op-Test No: 2005301 Scenario No: 1 Event No: 1 Page 5 of 5 Event

Description:

1LT-427 Pressurizer Level Channel Fails Low Time Position Applicants Actions or Behavior SRO/RO Establish letdown:

Open letdown line containment isolation valves Open RC loop B cold leg let down isolation valve Ensure component cooling flow to NRHX established Ensure charging flow at least 20 gpm Adjust backpressure as necessary and open letdown orifice outlet valves to establish desired letdown flow SRO/RO Check PZR level at program level control charging and letdown to maintain PZR level at program level SRO/RO Notify DCS and return to procedure and step in effect Proceed to next Event at the Lead Examiners Discretion.

Op-Test No: 2005301 Scenario No: 1 Event No: 2 Page 1 of 3 Event

Description:

P-32B Service Water Pump Trip Time Position Applicants Actions or Behavior Trigger activated per Lead Examiner BOP C01 A 3-5 North or South Service Water Header Pressure Low C01 B 3-4 Motor Breaker Trip Unit 1 Acknowledges/responds to receipt of above annunciators.(Additional low EDG cooling flow alarms will be received on C02)

- Identify P-32B has tripped (white light lit above control switch)

- Recognize SW header pressure has dropped.

- Reference Alarm Response Book

- Notify SRO

- Carry out actions of AOP-9A as directed by the SRO.

Note: The BOP Operator may start an additional service water pump upon recognizing that P-32B has tripped and Service Water Header pressure is low. Referencing of the ARB and AOP entry are expected for verification of these actions.

Note: If an AO is sent to investigate the SW pump and/or breaker the report will be that the pump motor is excessively hot to the touch and that the breaker has tripped on overcurrent.

SRO Entry into AOP-9A, Service Water System Malfunction based on ARB C01 A 3-5.

SRO/BOP Check Forebay Level > -11 feet on PPCS (points 1/2LT-3586B) or recorder YR-5832.

SRO/BOP Check Pumpbay Level > -11 feet on PPCS (points 1/2LT-3586A) or recorder YR-5832.

SRO/BOP Check Traveling Screen Differential Level High Alarm clear (C01 A 4-5)

Op-Test No: 2005301 Scenario No: 1 Event No: 2 Page 2 of 3 Event

Description:

P-32B Service Water Pump Trip Time Position Applicants Actions or Behavior SRO/BOP Check Service Water header Pressure Alarm clear (C01A 3-5) - SRO may answer this question as NO even if alarm is now clear (additional pump may have been already started) in order to verify proper operator response actions.

- Start a non-running SW pump to restore SW header pressure between 50 -90 psig (if a service water pump has already been started, then this step is merely verification of the action).

- SRO proceeds to step 9 of AOP-9A SRO Requests SM make notification to DCS, implement the Emergency Plan, and enter applicable TS Action Conditions.(Note: the Instructor SM will ask the SRO to assess TS when time permits).

- Properly assesses LCO 3.7.8 LCO is not met.

- Condition A and Required Action A.1 of LCO 3.7.8 are applicable (with one SW pump inoperable, there is a completion time of 7 days AND 14 days from discovery of failure to meet the LCO).

SRO/BOP Check supply header integrity

- North and south header pressures approximately equal

- C01 A 3-5 Alarm clear

- Area sump alarms clear SRO/BOP Check Zurn Strainer

- Power available (Contact AO)

- Strainer High DP alarms clear

Op-Test No: 2005301 Scenario No: 1 Event No: 2 Page 3 of 3 Event

Description:

P-32B Service Water Pump Trip Time Position Applicants Actions or Behavior SRO/BOP Verify Service Water Header Valves Open

- SW-2890, 2891, 2869, 2870 SRO/BOP Check Component Alarms Clear - high temperature, low flow.

SRO/BOP Return to step 1 of AOP-9A Repeat procedure steps as above, except service water header pressure has been restored and exit AOP-9A at step 8.

SRO/BOP At SRO discretion, the control switch for P-32B may be placed in pullout to clear the Motor Breaker Trip annunciator.

At the discretion of the lead examiner, proceed to the next event.

Op-Test No: 2005301 Scenario No: 1 Event No: 3 Page 1 of 3 Event

Description:

1P-28B Main Feed Pump Bearing Failure (Overheat) / Power Reduction.

Time Position Applicants Actions or Behavior Trigger activated per Lead Examiner CREW 1P-28B SG Feed Pump Bearing Failure

- Inboard motor bearing will overheat resulting in annunciator 1C04 1C 4-8 1TR-2000A or B Temperature Monitor

- BOP should go behind 1C04 to determine which point is alarming (point 10, 1P28B Inbd Motor Brg, setpoint 175F)

- May send an AO to investigate, the AO will report discoloration on 1P28B bearing housing and a chirping noise from bearing SRO Enter AOP-2B Feedwater System Malfunction based on available indications or on direction from ARP SRO Review foldout page criteria with crew.

CREW Maintain reactor power less than or equal to 100% (continuous action step)

SRO/BOP Check feed regulating valve response normal SRO/BOP Check S/G level less than 78%

SRO/BOP Check both main feed pumps running SRO/BOP Check both condensate pumps running SRO Read note addressing feed pump trip on low oil pressure

Op-Test No: 2005301 Scenario No: 1 Event No: 3 Page 2 of 3 Event

Description:

1P-28B Main Feed Pump Bearing Failure (Overheat) / Power Reduction.

Time Position Applicants Actions or Behavior SRO/BOP Check main feed pumps normal Should perform RNO based on annunciator 1TR-2000A or B Temperature Monitor, 1C04-1C 4-8 CREW Per RNO check 1TR-2000B points 7, 8, 21, 22 for 1P28-A and points 9, 10, 23, and 24 for 1P-28B Point 10 indicates rising temperature CREW Per RNO with imminent main feed pump failure and two main feed pumps running:

If turbine load greater than 60%, then reduce turbine load less than 60% per AOP-17A Unit 1 Rapid Power Reduction Stop affected main feed pump SRO Enters AOP-17A, Rapid Power Reduction SRO Determine Desired Power Level - may initially select any value between 50-60%

Note: Next four steps may be performed in any order SRO Notify PSS of Load Reduction SRO/RO Check Rod Control System in Auto SRO/BOP Select Rate Reduction Method and Reduce Load

Op-Test No: 2005301 Scenario No: 1 Event No: 3 Page 3 of 3 Event

Description:

1P-28B Main Feed Pump Bearing Failure (Overheat) / Power Reduction.

Time Position Applicants Actions or Behavior SRO/RO Borate as Necessary to Maintain Rods Above the Low-Low Insertion Limit Alarm (continuous action step).

- Reference Reactivity Operating Data Book ROD 1.3 for amount of boration required

- Based on desired flow rate, may start a second boric acid transfer pump SRO/RO Check PZR pressure stable at or trending to 2235 psig (continuous action step)

SRO/RO Check Pressurizer level stable at or trending to program level. (continuous action step)

SRO/BOP Check Steam Generator level controlling in Auto (continuous action step)

SRO/RO Maintain RCS Tavg (continuous action step)

- Greater than 540°F

- Less than 574°F

- Within 7°F of program Tavg SRO - Check main feed pump seal water pump running SRO - Determine desired endpoint is not less than 50% turbine load Following 5% power reduction or at the Lead Examiners discretion, proceed to the next event.

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 1 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior Trigger activated per Lead Examiner CREW Identify secondary leak. The following are some indications available which will enable the crew to identify that a feedline break exists inside containment.

- Containment Sump A level rising and associated alarm (BOP)

- Containment humidity and pressure rising (BOP)

- Indicated feed flow high for B train SRO AOP-2A Secondary Coolant Leak is entered based on the above indications.

CREW Determine secondary leakage not hazardous to personnel or equipment Plant habitability Containment pressure less than 2 psig Safeguards bus fault Equipment operability Note: The following is a continuous action step. The crew may continue in AOP-2A but should eventually perform the RNO actions of Step 1 based on Containment pressure approaching or exceeding 2 psig.

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 2 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior AOP-2A Step 1 RNO:

RO/SRO Perform the following Trip reactor Stabilize plant using EOPs while continuing with this procedure If necessary to protect equipment or personnel, then perform the following:

Shut both MSIVs,: 1MS-2018 for S/G A, 1 MS-2017 for S/G B If leak continues, then locally shut turbine driven AFW pump steam supply from affected S/G,:1MS-235 for S/G A, 1MS-237 for S/G B Go to EOP-0 Note: The SRO may also direct a manual Safety Injection and Containment isolation based on approaching the automatic SI setpoint of 5 psig Containment pressure Critical Task: The SRO/RO must ensure that the reactor is tripped prior to the automatic Safety Injection setpoint of 5 psig containment pressure.

SRO Direct a Manual Reactor Trip, (Safety Injection, Containment Isolation) and entry into EOP-0, Reactor Trip or Safety Injection RO Trip Reactor (SI and CI may also be performed). Immediate Actions of EOP-0 (Steps 1-4) performed and informs SRO they are ready for verification.

- Verify reactor trip- The Rx Trip pushbuttons on 1C04 will fail to actuate a trip. The RO should then press the Reactor Trip buttons on C01 which will trip the unit.

- Verify turbine trip

- Verify safeguard buses energized

- Check if SI is actuated

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 3 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior SRO/RO Verify Reactor Trip

- Check reactor trip and bypass breakers OPEN

- Check all rod bottom lights LIT

- Check all rod position indicators ON BOTTOM

- Check neutron flux LOWERING SRO/RO Verify Turbine Trip SRO/RO Verify Safeguard buses energized

- Check at least one 4160 Vac safeguards bus energized (1A05 or 1A06)

- Check at least one 480 Vac safeguards bus energized (1B03 or 1B04)

SRO/RO Check if SI is actuated:

- 1C04-1B 4-2, Manual Safety Injection (if directed)

- 1C04 1B 4-3, Containment Pressure High If SI was not manually actuated, it should have already activated on high Containment pressure.

Check SI - Both trains actuated SI Pumps - both running RHR Pumps - both running

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 4 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior CREW SRO reviews foldout page criteria with the crew

- Determines that the Faulted S/G Isolation Criteria are applicable.

- Auxiliary Feedwater flow should be isolated to the B S/G by closing 1AF-4000 and AF-4021.

- Total feed flow must be maintained 200 gpm until level in at least one S/G is greater than 29% [51% if adverse containment]

Crew Should identify Adverse Containment Conditions when Containment pressure greater than 10 psig SRO EOP-0 Attachment A Automatic Action Verification directed to be completed by the BOP operator while continuing on with EOP-0. The steps for Attachment A are included near the end of this event section.

- All items of Attachment A should indicate normal SRO Read caution addressing motor-driven AFW pump flow > 240 gpm RO/SRO Verify Secondary Heat Sink:

- Level in at least one S/G > [51%] 29%.

- Control pumps and align valves as necessary to maintain S/G level between [51%] 29% and 65%.

Adequate Aux Feedwater will be available, > 200 gpm should be maintained until level is within the band on the A S/G.

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 5 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior SRO/RO Verify RCP Seal Cooling Check labyrinth seal P > 20 inches OR Check component cooling to RCP thermal barrier normal SRO/RO Verify RCS temperature control (continuous action step).

- This procedure step provides actions to stop dumping steam and reducing total feed flow (if S/G levels are in the required band) with RCS temperature trending lower.

SRO/RO Check pressurizer PORVs both shut.

SRO/RO Verify pressurizer spray valves shut Both normal loop spray valves shut.

Auxiliary spray valve shut.

SRO/RO Check if RCPs should remain running - RCPs are running and subcooling is > [60 ºF] 30 ºF SRO Start Monitoring Critical Safety Function Status trees.

The instructor SM/STA will acknowledge this report and begin monitoring.

CREW Verify Containment Sump Recirculation Not Required - sump recirc is not required.

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 6 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior CREW Check if secondary system is intact:

- No S/G pressure trending lower in an uncontrolled manner

- No S/G completely depressurized AND SRO transitions to EOP-2 based on B S/G being faulted SRO Read cautions and reviews foldout page criteria of EOP-2 SRO/RO Check RCS wide range Hot Leg Temperatures STABLE:

- Control feed and dump steam as necessary using A S/G to stabilize RCS hot leg temperatures SRO/BOP Isolate both Main Steam Lines - MSIVs and bypass valves will already be shut.

SRO/BOP Check if any S/G in NOT faulted (determines A S/G is not faulted)

SRO/BOP Identify faulted S/G (determines B S/G is faulted)

SRO/BOP Reset Loss of Feedwater Turbine Trip Critical Task: The SRO/BOP must ensure that the faulted S/G is isolated prior to transition out of EOP-2 (Does not include field actions)

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 7 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior SRO/BOP Isolate Feed to faulted S/G

- Ensure Feed Regulating Valve SHUT

- Ensure Feed Regulating Bypass Valve SHUT

- Ensure Motor Driven AFW pump P-38B is stopped and in pull-out

- Ensure AF-4021 AND 1AF-4000 in manual and SHUT SRO/BOP Isolate flow from faulted S/G

- Ensure 1MS-2015 SHUT (atmospheric dump)

- SHUT 1MS-2019 (turbine driven AFW steam supply)

- Ensure 1MS-5959/2045 SHUT (S/G Blowdown)

- Locally shut 1MS-237 (1P-29 AFP/Radwaste steam isolation)

- Locally shut 1MS-238 (main steam trap isolation)

SRO/BOP Check CST Level > 8 Ft CREW Check secondary system radiation normal SRO Transition to EOP-1 Unit 1, Loss of Reactor or Secondary Coolant CREW SRO Reviews foldout page criteria with the crew

- May determine that SI termination criteria is met, if so, transition to EOP-1.1, SI Termination. Otherwise, crew will continue in EOP-1.

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 8 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior SRO/RO Check if RCPs should remain running (determines RCPs should remain running)

SRO/BOP Check if secondary system is intact (determines B SG is faulted and has been isolated)

SRO/BOP Stabilize intact S/G level: (continuous action step)

- Maintain AFW Flow >200 GPM to A SG until level is > [51%] 29%

- Control feedwater flow to maintain A SG level between [51%] 29%

and 65%.

CREW Check secondary system radiation normal SRO/RO Check PORVs and PORV block valves (continuous action step)

SRO Reads caution concerning SI reset and loss of offsite power CREW Reset SI

- BOP resets SI signal

- RO acknowledges alarm SRO/BOP Reset Containment Isolation SRO/BOP Reset 1B-03 and 1B-04 Non-Safeguards equipment lockouts SRO Reads caution concerning EDG loading

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 9 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior SRO/BOP Check 4160 Vac safeguards buses:

- Both energized from offsite power SRO/BOP Reestablish Instrument Air to Containment

- Start second instrument air compressor

- Check instrument air header pressure > 80 PSIG

- Open one and then the other instrument air containment isolation valve o 1IA-3047 o 1IA-3048

- (Valves take about three minutes to open, BOP may set a timer as a reminder.)

SRO/RO Verify charging flow

- Ensure 1CV-1298 is open

- Check at least one charging pump running

- Start additional charging pumps as desired to establish desired charging flow

- Adjust labyrinth seals to > 20

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 10 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior CREW Check if SI flow should be terminated:

- Check RCS subcooling based on core exit thermocouples > [80ºF]

35ºF

- Verify secondary heat sink

- Check RCS pressure > [1825 PSIG] 1600 PSIG

- Check RCS pressure stable or trending higher

- Check Pressurizer level > [34%] 10%

If conditions are not met, RNO column will direct the Crew to proceed in EOP-1.

CREW Transition to EOP-1.1, SI Termination If SI Termination criteria are not met, the scenario may be terminated at the discretion of the Lead Examiner.

Inform the Examinees that they are to remain in the simulator until any evaluator follow-up questions are answered.

Do not discuss any scenario related events.

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 11 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior The steps for EOP-1.1, SI Termination are contained here. This EOP may be entered from EOP-1 foldout page or from step 13 of EOP-1.

SRO Reads caution concerning SI reset and loss of offsite power CREW Reset SI

- BOP resets SI signal

- RO acknowledges alarm SRO/BOP Reset Containment Isolation SRO/BOP Reset 1B-03 and 1B-04 Non-Safeguards equipment lockouts SRO Reads caution concerning EDG loading SRO/BOP Check 4160 Vac safeguards buses:

- Both energized from offsite power

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 12 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior SRO/BOP Reestablish Instrument Air to Containment

- Start second instrument air compressor

- Check instrument air header pressure > 80 PSIG

- Open one and then the other instrument air containment isolation valve o 1IA-3047 o 1IA-3048

- (Valves take about three minutes to open, BOP may set a timer as a reminder.)

SRO/RO Verify charging flow

- Ensure 1CV-1298 is open

- Check at least one charging pump running

- Start additional charging pumps as desired to establish desired charging flow

- Adjust labyrinth seals to > 20 CREW Stop both SI pumps CREW Stop both RHR pumps

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 13 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior CREW Verify SI flow not required

- Check subcooling > [80ºF] 35ºF o If subcooling cannot be maintained, start SI pumps as necessary to restore subcooling and go to EOP-1

- Check PZR level > [34%] 10%

o If PZR level is not > 10%, control charging to maintain level. If level cannot be maintained, start SI pumps as necessary to restore level and go to EOP-1 CREW Check if containment spray should be stopped

- Check spray pumps running

- Check containment pressure < 15 PSIG

- Reset containment spray signal

- Stop both containment spray pumps and place in auto after stop

- Shut containment spray pump discharge valves

- Ensure both spray additive tank discharge valves shut

- Ensure containment spray pump RWST suction MOVs open.

Upon completion of Containment Spray steps, the scenario may be terminated at the discretion of the Lead Examiner.

Inform the Examinees that they are to remain in the simulator until any evaluator follow-up questions are answered.

Do not discuss any scenario related events.

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 14 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior The remainder of steps listed in this event section are those found in EOP-0 Attachment A, Automatic Action Verification. The SRO should ensure that performance of this Attachment is continued by the BOP operator, and performed in parallel with EOP-0.

BOP Verify feedwater isolation:

- Feedwater Regulating and Bypass Valves SHUT.

- Both main feed pumps tripped.

- MFP discharge MOVs - BOTH SHUT.

BOP Verify containment isolation:

- CI Panels A and B ALL LIGHTS LIT

- RS-SA-9 SHUT.

- No other valves open under administrative control (SM may be asked to verify this).

BOP Verify AFW Actuation:

- Checks both motor driven AFW pumps running.

BOP Check both SI pumps running.

BOP Check both RHR pumps running.

BOP Check only one CCW pump running.

BOP Verify Service Water Alignment:

- 6 service water pumps running.

- Service water isolation valves shut.

- Direct AO to locally check SW-LW-61 or SW-LW-62 shut.

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 15 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior BOP Verify Containment Accident Cooling Units Running

- All accident fans running.

- 1SW-2907 & 2908 OPEN.

- Unit 1 Containment Recirc Coolers Water Flow Low Alarm CLEAR.

BOP Check Control Room Ventilation IN ACCIDENT MODE:

- At least one control room recirc fan RUNNING

- Control room damper solenoid valve PURPLE LIGHT LIT BOP Check if Main Steam Lines Can Remain Open, checks both MSIVs SHUT.

BOP Verify proper SI valve alignment:

- Unit 1 SI active status panel ALL LIGHTS LIT

- Unit 1 SI-Spray Ready status panel NO LIGHTS LIT BOP Verify containment spray not required:

- Recognize containment pressure is rising and if > 25 psig perform continuous actions of RNO

- Containment Spray actuated, C01 B 2-6 LIT

- All containment spray discharge valves OPEN

- At least one spray pump running

- Shutdown one train of spray by placing spray pump in PULL-OUT and shutting its associated suction valve.

- After spray has been activated for greater than two minutes, one spray additive valve verified OPEN

Op-Test No: 2005301 Scenario No: 1 Event No: 4,5 Page 16 of 16 Event

Description:

B Main Feedwater Line Break inside Containment requires Reactor Trip, manual push buttons on 1C04 fail to operate Time Position Applicants Actions or Behavior BOP Verify SI Flow:

- RCS wide range pressure <1400 psig

- Check SI pumps flow indicated

- RCS wide range pressure < [425] 200 psig This ends the steps of EOP-0 Attachment A.

Appendix D Scenario Outline Form ES-D-1 Facility: Point Beach Scenario No.: 2 OP-Test No.: 2005301 Examiners: ______________________ Operators: ______________________

Initial Conditions: Unit 1 is at 100% power, MOL, equilibrium xenon conditions. Boron Concentration is 813 PPM.

Unit 2 is at 100% power.

Turnover: G-01 EDG is out of service for annual maintenance. It was taken out of service 3 days ago and is expected to be returned to service in 3 days. G-02 is aligned to 4.16 kV buses 1A-05 and 2A-05 IAW OI-35A.

1TE-404, Loop B Hot Leg Temperature Element has failed high and has been removed from service IAW 1-SOP-IC-001 Yellow.

1RC-515, Block valve for 1RC-431C is closed due to PORV leakage. Tech Spec 3.4.11, Required Action A.1 has been completed.

IRPI is selected to alternate power (1Y02) due to planned breaker replacement on 1Y06 (Bkr 21).

Today is Sunday, present clock time is real time. An RP Tech and Chemistry Tech are on-site. ERO Maintenance personnel are working on G01.

The objective of the shift is to lower power to 90% for Atmospheric Dump Valve (ADV) testing.

Event Malf. Event Event No. No. Type* Description R - RO 1 N - BOP Lower power for ADV testing N - SRO I - RO 2 Power Range NI Channel 41 Summing and Level Amp fails low.

SRO(T)

I - BOP 3 1LT-461, A Steam Generator Level Transmitter fails low.

SRO(T)

C - RO 4 B RCP #2 Seal Fails SRO 5 M - ALL B RCP Seal Package fails C-RO 6 SI pumps fail to auto start on SI signal.

SRO 7 C-BOP Two Containment Isolation auxiliary relays fail to actuate on CI signal.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9

Scenario #2 Initial Conditions: Unit 1 is at 100% power, MOL, equilibrium xenon conditions. Boron Concentration is 813 PPM. Unit 2 is at 100% power.

Turnover: G-01 EDG is out of service for annual maintenance. It was taken out of service 3 days ago and is expected to be returned to service in 3 days. G-02 is aligned to 4.16 kV buses 1A-05 and 2A-05 IAW OI-35A.

1TE-404, Loop B Hot Leg Temperature Element has failed high and has been removed from service IAW 1-SOP-IC-001 Yellow.

1RC-515, Block valve for 1RC-431C is closed due to PORV leakage. Tech Spec 3.4.11, Required Action A.1 has been completed.

IRPI is selected to alternate power (1Y02) due to planned breaker replacement on 1Y06 (Bkr 21).

Today is Sunday, present clock time is real time. An RP Tech and Chemistry Tech are on-site.

ERO Maintenance personnel are working on G01.

ANTICIPATED BOOTH COMMUNICATION/GUIDANCE: Scenario 2 Event 1: Lower power 10% for ADV testing

- AOs will be notified of the load reduction and to monitor S/G blowdown flows.

Event 2: Power Range NI - 41 fails low - Per lead examiner (PLE) activate trigger No anticipated booth communications Event 3: 1LT-461, A S/G Level fails low - PLE activate trigger No anticipated booth communications Event 4: B RCP #2 Seal Fails - PLE activate trigger Per AOP 1B, crew will contact AO to monitor RCDT level. The level is rising 3%

every 2 minutes.

Event 5: B RCP Seal Package fails - PLE increase leak rate to 400 GPM No anticipated booth communications Event 6: SI pumps fail to auto start on SI signal.

Per EOP-0 Att. A step A7, crew will request AO to check shut SW-LW-61 or 62 at C-180, blowdown evap panel. Both valves are shut.

Event 7: Two Containment Isolation Valves fail to shut on CI signal.

- No anticipated booth communications

Scenario #2 Sim Setup:

IC-76, Unit 1 is at 100% power, MOL, equilibrium Xe.

1RC-515 Shut to isolate leaky PORV G01 Out of Service G02 Aligned to both 1 and 2A05.

TE-404 Removed from service IAW SOP. (Two Switches and yellow bistables)

B, C, E Service Water Pumps in service IRPI selected to alternate power supply due to 1Y06 Breaker 21 Breaker Replacement.

K2B IA compressor in Constant, K2A in standby.

2P-4B in Auto, 2P-4A in standby.

Ensure T-404 and T-408 are removed from scan each time you reset into this IC.

Preloads:

1. XMT1RCS029A: 1TE-404 Failed High Sev = 650

2. BKR1SIS001: A SI Pump fails to auto start Mal = 4 (Fail Auto Close)

3. BRK1SIS002: B SI Pump fails to auto start Mal = 4 (Fail Auto Close)

4. RLY1PPL086: Runback Relay Val = 2 (Fail As Is)

5. BST1PCS011: LT-462 High Level Bistable Mal = 1 (As Is)

6. MAL1PPL001A: A Train Auto Rx Trip Fails Mal = 1 (Auto Fail)

7. MAL1PPL001B: B Train Auto Rx Trip Fails Mal = 1 (Auto Fail)

8. RLY1PPL012 (Train A Cont Iso Aux Rly)

Mal = 2 (Fail as is)

9. RLY1PPL015 (Train B Cont Iso Aux Rly)

Mal = 2 (Fail as is)

Event Triggers:

T-1 MAL1NIS011A: PR NI-41 Summing and Level Amp Fails Low Sev = 0, Ramp = 30 Sec.

T-3 XMT1SGN007A: LT-461 A SG Level Transmitter Fails Low Sev = 0, Ramp = 30 Sec.

T-5 MAL1RCP002B: B RCP #2 seal fails to 6 GPM Sev = 6 initially, raise to 400 when all seals fail, Ramp = 0 Sec.

T-7 MAL1RCP001B Sev = 325, Ramp = 120 MAL1RCP003B Sev = 400, Ramp = 120 T-30 BKR1RCP002 Val = 1 (Trip), Delay = 30 Sec.

Set JCRFTR, Reactor Trip to Trigger 30 LOA Triggers:

T-16 LOA1CFW083: Start P99A Seal Water Pump Val = ON, Then Auto, Then Delete T-17 LOA1CFW084: Start P99B Seal Water Pump Val = ON, Then Auto, Then Delete

Op-Test No: 2005301 Scenario No: 2 Event No: 1 Page 1 of 3 Event

Description:

Lower power 10% for ADV testing (Reactivity Manipulation)

Time Position Applicants Actions or Behavior Scenario begins at the discretion of the Lead Examiner The normal down-power brief may be conducted in the classroom, prior to entering the simulator, at the discretion of the lead examiner to minimize the amount of time in the simulator.

SRO Brief crew on commencing down-power.

SRO OP-2A Normal Power operations Attachment A Determine magnitude and rate of load reduction.

SRO Make notifications per NP 2.1.5 and notify Auxiliary Operators of down-power.

SRO/BOP Notify PAB operator to monitor blowdown flows per OI-14.

BOP Record VPL and Governor Valve #3 and #4 positions.

RO/BOP Set PPCS trends as desired.

BOP Reduce PPCS constants for S/G Blowdown flow by 5 klb/hr.

RO If desired, place additional letdown orifice in service. (Note: additional orifice will most likely NOT be placed in service due to the small load reduction.)

RO Estimate the amount of boron/rod motion needed for the desired load change per Rod 1.3.

The blender should be used to inject the desired amount of boron per OP-5B Attachment D.

Op-Test No: 2005301 Scenario No: 2 Event No: 1 Page 2 of 3 Event

Description:

Lower power 10% for ADV testing (Reactivity Manipulation)

Time Position Applicants Actions or Behavior SRO Record time of load change.

BOP Ensure EH control in Operator Auto.

BOP Transfer turbine control from the Valve Position Limiter (VPL) as follows:

a) Depress Reference Control (lower) pushbutton to set terminal load (SETTER) less than the indicated REFERENCE load.

b) Set desired ramp rate using thumbwheel. (Note: Coming off the VPL may be accomplished at a faster than normal rate.)

c) Depress the GO pushbutton and ensure REFERENCE display indicates a controlled reduction towards SETTER value at the selected rate.

d) When the VPL light goes out (green status light), then depress the HOLD pushbutton.

Note: Transfer to IMP-IN mode per the next step may be performed prior to this step.

BOP Transfer turbine control to IMP IN if desired.

(Note: IMP-IN provides the most linear load response and is the recommended mode of operation)

BOP Depress the Reference Control (lower) pushbutton to set terminal load (SETTER) to the target value previously specified.

BOP Using thumbwheel, set the desired ramp rate previously specified.

Op-Test No: 2005301 Scenario No: 2 Event No: 1 Page 3 of 3 Event

Description:

Lower power 10% for ADV testing (Reactivity Manipulation)

Time Position Applicants Actions or Behavior BOP Depress the GO pushbutton and ensure REFERENCE display indicates a controlled load reduction at the selected rate.

Note: Prior to reducing load, the crew may wait to see the effect of the boration (RCS temperature drop).

RO/BOP Maintain controls in AUTO as practicable.

- Rod control (may be placed in Manual at SM discretion)

- Blender controls

- Turbine controls RO Control Delta Flux in accordance within limits of the COLR (LCO 3.2.3)

RO Maintain Tavg within 1.5° F of Tref.

BOP Maintain 345 kV voltage per Section 9.0 of OP-2A Maintain the controller deviation for the Main Feed Regulating Valves nulled.

Maintain the controller setpoint for the LP Feedwater Heater Bypass Valve (CS-2273) at 25 psig below SG Feed Pump suction pressure.

Note: Adjusting Power Range NIS should not be required.

Once power has been lowered 5% and/or at the discretion of the Lead Examiner, proceed to the next event.

Op-Test No: 2005301 Scenario No: 2 Event No: 2 Page 1 Of 4 Event

Description:

Power Range NI Channel 41 Summing and Level Amp fails low Time Position Applicants Actions or Behavior Trigger activated per Lead Examiner RO Acknowledge and respond to receipt of annunciators SRO/RO Determine N-41 failed low:

- Meter indication on 1C04

- Annunciators 1C04 1A 3-3 Power range channel deviation 1C04 1A 1-7 Auto rod motion SRO/RO Realize rod motion is due to instrument failure and place rods in Manual The crew may go to hold on the load ramp and may also stop the boration RO/BOP Refer to appropriate ARB 1C04 1A 3-3 Power range channel deviation 1C04 1A 1-7 Auto rod motion SRO Direct entry into AOP-6C Uncontrolled motion of RCCA(s). (Crew may initially enter AOP-24, Response to Instrument Malfunctions)

Note: The crew may restore rods to their initial position CREW Check rod motion required:

Change in Turbine load Change in steam demand Tavg/Tref mismatch greater than 1.5F Should answer no, and perform the RNO actions

Op-Test No: 2005301 Scenario No: 2 Event No: 2 Page 2 Of 4 Event

Description:

Power Range NI Channel 41 Summing and Level Amp fails low Time Position Applicants Actions or Behavior SRO/RO Place rod control bank selector switch in manual (verify if already accomplished)

SRO/RO Maintain RCS Tavg (continuous action step)

Greater than 540F Less than 574F Within 7F of program Tavg SRO/RO Check RCS Tavg at or trending to Tref Based on RNO crew may restore rods to initial position SRO/RO Check control rods above minimum insertion limits SRO Read Note addressing AFD SRO/RO Verify AFD within limit: (continuous action)

Check PPCS axial flux alarm clear Check control board meters at least three within limit SRO/RO Check rod motion due to instrument failure Direct entry into AOP-24, Response to Instrument Malfunctions.

SRO/RO SRO/RO Identify Failed Instrument: N-41 SRO/RO Check if failed instrument is a controlling channel: N - 41 affects automatic rod control SRO/RO Establish Manual Control: Verify rods in manual

Op-Test No: 2005301 Scenario No: 2 Event No: 2 Page 3 Of 4 Event

Description:

Power Range NI Channel 41 Summing and Level Amp fails low Time Position Applicants Actions or Behavior RO/SRO Return Affected Parameter(s) to desired value(s): Crew may restore rods to initial position if not already done SRO Read caution against placing an additional bistable in a tripped condition SRO Direct entry into 0-SOP-IC-001 - Red, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service - Red Channels.

- Obtain and implement 0-SOP-IC-001- Red

- Review precautions and limitations

- TS 3.2.4 requires QPTR to be verified with incore detectors within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if power remains > 75%

Critical Task: SRO or BOP must prevent a reactor trip due to inadvertently removing related instruments from service in multiple protection channels.

SRO If removing a second sensor causes two trip bistables to be removed from service then:

Refer to TS 3.3.1, 3.3.2, 3.3.3, and Tables 3.3.1-1, 3.3.2-1, 3.3.3-1 Remove sensor bistables that will not cause a reactor trip or safeguards actuation

Op-Test No: 2005301 Scenario No: 2 Event No: 2 Page 4 Of 4 Event

Description:

Power Range NI Channel 41 Summing and Level Amp fails low Time Position Applicants Actions or Behavior SRO Identify applicable Technical Specifications (reference 0-SOP-IC-002):

- LCO 3.3.1 is not met:

- Action Condition A is entered immediately - Required Action is to enter the Condition referenced in Table 3.3.1-1 for the channel.

- Condition D is referenced from Table 3.3.1-1 Functions 2, 5 and 6.

Required Action is to place the channel in trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR be in Mode 3 within 7 hrs Because the channel can not be placed in trip, the unit will need to be in Mode 3 within 7 hrs At the discretion of the lead examiner, continue with the next event.

Op-Test No: 2005301 Scenario No: 2 Event No: 3 Page 1 Of 2 Event

Description:

1LT-461, A Steam Generator Level Transmitter fails low.

Time Position Applicants Actions or Behavior Trigger activated per Lead Examiner BOP Recognize 1LT-461, A Steam Generator Level Transmitter fails low.

- LI-461 meter indication lowering

- 1C03 1E2 1-2 Steam generator A level setpoint deviation

- 1C03 1E2 4-3 Steam generator A low-low level channel alert Critical Task: BOP must take manual action to prevent going off-scale high on the SG narrow range level transmitters.

BOP - Take manual control of A Feed Reg Valve (HC-466)

- Take manual control of A Feed Reg Bypass (HC-480)

- Restore S/G level to normal band (continuous action)

SRO Ensure plant is stabilized

- Ensure S/G Water Level Control is regained and level stabilized CREW May enter AOP-2B Feedwater System Malfunction (Crew may initially enter AOP-24, Response to Instrument Malfunctions)

SRO reads foldout page Maintain Rx Power less than or equal to 100% (continuous)

Op-Test No: 2005301 Scenario No: 2 Event No: 3 Page 2 Of 2 Event

Description:

1LT-461, A Steam Generator Level Transmitter fails low.

Time Position Applicants Actions or Behavior SRO Check feed reg valve response normal - perform actions of RNO Check manual control power available light on Place affected feed reg valve controller to manual Match feed flow to steam flow Stabilize S/G level at programmed level If transient caused by instrument failure then defeat instrument per AOP-24 SRO Direct entry into AOP-24, Response to Instrument Malfunctions.

SRO - Identify applicable Technical Specifications (reference 0-SOP-IC-002):

- LCO 3.3.1 is not met:

- Action Condition A is entered immediately - Required Action is to enter the Condition referenced in Table 3.3.1-1 for the channel.

- Condition D is referenced from Table 3.3.1-1 Function 13. Required Action is to place the channel in trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR be in Mode 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months

- LCO 3.3.2 is not met:

- Action Condition A is entered immediately - Required Action is to enter the Condition referenced in Table 3.3.2-1 for the channel.

- Condition D is referenced from Table 3.3.2-1 Function 5b and 6b.

Required Action is to place the channel in trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR be in Mode 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND be in Mode 4 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months It is not the intent to observe another SOP-IC for this scenario, therefore at the discretion of the lead examiner and when the malfunction has been identified and plant has been stabilized, proceed to the next event.

Op-Test No: 2005301 Scenario No: 2 Event No: 4, 5, 6,7 Page 1 of 13 Event

Description:

B RCP #2 Seal Fails leading to B RCP Seal Package failure, SI pumps fail to auto start on SI signal and two Containment Isolation auxiliary relays fail to actuate on CI.

Time Position Applicants Actions or Behavior Trigger activated per Lead Examiner Crew Acknowledge and respond to annunciators:

1C03 1D 3-3 1P-1B RCP No. 1 Seal Water Flow High or Low 1C03 1D 1-3 1P-1B RCP Standpipe Level High Alarm SRO Enter AOP-1B Reactor Coolant Pump Malfunction, based on indications or ARB guidance CREW SRO reviews foldout page: RCP trip criteria RCP shaft vibration RCP frame vibration RCP No. 1 seal leakage RCP No. 1 and No. 2 seal combined leakage RCP stator temperature RCP No. 1 seal outlet temperature RCP motor bearing temperature Lab seal P not positive with CCW thermal barrier flow less than 21 gpm Fire located in RCP cubicle Notes:

AO will report RCDT level increase equivalent to 5.25gpm.

Trip criteria will not be met on No. 1 seal leakage less than 0.8 gpm due to stable seal water outlet temperature

Op-Test No: 2005301 Scenario No: 2 Event No: 4, 5, 6,7 Page 2 of 13 Event

Description:

B RCP #2 Seal Fails leading to B RCP Seal Package failure, SI pumps fail to auto start on SI signal and two Containment Isolation auxiliary relays fail to actuate on CI.

Time Position Applicants Actions or Behavior SRO/RO Check Annunciators clear:

P-1A&B RCP Vibration alarm 1TR-2001 Temperature monitor alarm (continuous action) 1P1A or B RCP Upper or lower sump oil level high or low SRO Read notes addressing Figures 1 and 2 SRO/RO Check RCP No. 1 seal leakage greater than 0.8 gpm (continuous action)

Note: SRO should address RNO, however, no conditions exist that will require branching SRO/RO Check RCP No. 1 seal leakage less than 6 gpm (continuous action)

SRO Read note regarding running RCP without seal injection SRO/RO Verify RCP seal cooling:

Lab seal P greater than 20 inches CCW to RCP thermal barrier normal RCP CCW return temperature alarm clear SRO/RO Check RCP related fireworks panel alarm clear (continuous action)

SRO/RO Check RCP No. 2 seal indications normal:

Per RNO, if No. 2 seal leakage greater than 1.1 gpm then go to step 10

Op-Test No: 2005301 Scenario No: 2 Event No: 4, 5, 6,7 Page 3 of 13 Event

Description:

B RCP #2 Seal Fails leading to B RCP Seal Package failure, SI pumps fail to auto start on SI signal and two Containment Isolation auxiliary relays fail to actuate on CI.

Time Position Applicants Actions or Behavior SRO/RO Determine RCP seal status RCP No. 1 and No. 2 combined seal leakage between 0.8 gpm and 6 gpm RCP No. 2 seal leakage less than 1.1 gpm - should perform RNO Note: Per RNO of above step, crew should decide to shutdown per OP-3A at which time the next event will be initiated. The lead examiner may choose to initiate the next event prior to reaching this step.

CREW Identify RCS leak. The following are some indications available which will enable the crew to identify that an RCS leak exists inside containment.

- Containment Sump A level rising and associated alarm (BOP)

- Containment humidity and pressure rising (BOP)

- RMS alarms inside containment (RO/BOP)

- Auto Charging Pump speed rising (RO)

- Pressurizer level lowering (RO)

Note: Based on size of the leak and the imminent loss of one RCP the decision should be made to trip the unit. The crew may use the foldout criteria from AOP-1B and proceed to step 18, which directs the RCP to be tripped after the EOP Immediate Actions.

Critical Task: SRO or RO must take action to initiate a manual reactor trip prior to pressurizer level going low off-scale SRO Direct a Manual Reactor Trip and entry into EOP-0, Reactor Trip or Safety Injection The SRO may also direct a manual Safety Injection and Containment Isolation due to RCS leak

Op-Test No: 2005301 Scenario No: 2 Event No: 4, 5, 6,7 Page 4 of 13 Event

Description:

B RCP #2 Seal Fails leading to B RCP Seal Package failure, SI pumps fail to auto start on SI signal and two Containment Isolation auxiliary relays fail to actuate on CI.

Time Position Applicants Actions or Behavior RO Manual Reactor Trip, SI, and CI performed. Immediate Actions of EOP-0 (Steps 1-4) performed and informs SRO they are ready for verification.

Verify reactor trip Verify turbine trip Verify safeguard buses energized Check if SI is actuated- SI pumps will fail to automatically start SRO/RO Verify Reactor Trip Check reactor trip and bypass breakers OPEN Check all rod bottom lights LIT Check all rod position indicators ON BOTTOM Check neutron flux LOWERING SRO/RO Verify Turbine Trip SRO/RO Verify Safeguard buses energized

- Check at least one 4160 Vac safeguards bus energized (1A05 or 1A06)

- Check at least one 480 Vac safeguards bus energized (1B03 or 1B04)

SRO/RO Check if SI is actuated - (if not, will be required at 10% pressurizer level) 1C04-1B 4-2, Manual Safety Injection Check SI both trains actuated SI Pumps both running - the RO will manually actuate both trains of SI and CI with no response RHR Pumps both running

Op-Test No: 2005301 Scenario No: 2 Event No: 4, 5, 6,7 Page 5 of 13 Event

Description:

B RCP #2 Seal Fails leading to B RCP Seal Package failure, SI pumps fail to auto start on SI signal and two Containment Isolation auxiliary relays fail to actuate on CI.

Time Position Applicants Actions or Behavior SRO/RO Declare Immediate Actions completed and verified Critical Task: The RO or the BOP must start at least one SI pump prior to transition out of EOP-0 with Attachment A complete.

CREW Start both SI pumps manually The crew may not start the SI pumps until required in Attachment A of EOP-0 SRO Address step 18 from AOP-1B:

Trip affected RCP (pump will automatically trip 30 secs after Rx trip)

Check at least one RCP running Shut associated PZR normal spray valve: 1RC-431B for RCP B Check RCP has been tripped for 3 minutes Shut affected RCP No. 1 seal MOV: 1CV-270B for RCP B Check RCP seal water bypass control valve shut SRO Review foldout page criteria with the crew SRO EOP-0 Attachment A Automatic Action Verification directed to be completed by the BOP operator while continuing on with EOP-0. The steps for Attachment A are included near the end of this event section.

- All items of Attachment A should indicate normal with the exception of manual starting both SI pumps and 4 containment isolation valves fail to close on CI signal SRO Read caution addressing motor-driven AFW pump flow > 240 gpm

Op-Test No: 2005301 Scenario No: 2 Event No: 4, 5, 6,7 Page 6 of 13 Event

Description:

B RCP #2 Seal Fails leading to B RCP Seal Package failure, SI pumps fail to auto start on SI signal and two Containment Isolation auxiliary relays fail to actuate on CI.

Time Position Applicants Actions or Behavior SRO/RO Verify Secondary Heat Sink:

- Level in at least one S/G > [51%] 29%.

- Control pumps and align valves as necessary to maintain S/G level between [51%] 29% and 65%.

Adequate Aux Feedwater will be available, > 200 gpm should be maintained until level is within the band on the A S/G.

SRO/RO Verify RCP Seal Cooling Check labyrinth seal delta-P > 20 inches OR Check component cooling to RCP thermal barrier normal SRO/RO Verify RCS temperature control (continuous action step).

- This procedure step provides actions to stop dumping steam and reducing total feed flow (if S/G levels are in the required band) with RCS temperature trending lower.

SRO/RO Check pressurizer PORVs both shut.

SRO/RO Verify pressurizer spray valves shut Both normal loop spray valves shut.

Auxiliary spray valve shut.

SRO/RO Check if RCPs should remain running - RCP is running and subcooling is >

[60 ºF] 30 ºF SRO Start Monitoring Critical Safety Function Status trees.

The instructor SM/STA will acknowledge this report and begin monitoring.

CREW Verify Containment Sump Recirculation Not Required - sump recirc is not required.

Op-Test No: 2005301 Scenario No: 2 Event No: 4, 5, 6,7 Page 7 of 13 Event

Description:

B RCP #2 Seal Fails leading to B RCP Seal Package failure, SI pumps fail to auto start on SI signal and two Containment Isolation auxiliary relays fail to actuate on CI.

Time Position Applicants Actions or Behavior CREW Check if secondary system is intact:

- No S/G pressure trending lower in an uncontrolled manner

- No S/G completely depressurized SRO/BOP Check if S/G tubes are intact Secondary radiation levels normal Request local surveys of main steam lines Request chemistry to prepare for periodic activity samples of both S/Gs SRO/RO Check if RCS is intact inside containment Check containment radiation levels normal SRO Transition to EOP-1 Unit 1, Loss of Reactor or Secondary Coolant SRO Address foldout page SRO/RO Check if RCPs should remain running Check RCPs any running Check RCS subcooling greater than or equal to 30F SRO/RO Check if secondary system is intact SRO/BOP Stabilize intact S/G level (continuous action)

Intact S/G level greater than 29%

Control feed flow to maintain intact S/G level between 29% and 65%

Op-Test No: 2005301 Scenario No: 2 Event No: 4, 5, 6,7 Page 8 of 13 Event

Description:

B RCP #2 Seal Fails leading to B RCP Seal Package failure, SI pumps fail to auto start on SI signal and two Containment Isolation auxiliary relays fail to actuate on CI.

Time Position Applicants Actions or Behavior SRO/RO Check secondary system radiation normal SRO/RO Check PORVs and PORV block valves (continuous action)

Check power available to PORV block valves Check PZR PORVs both shut Check PORV block valves at least one open SRO Read caution regarding loss of offsite power after SI reset SRO/BOP Reset SI Reset containment isolation Reset 1B-03 and 1B-04 non-safeguards equipment lockouts SRO/BOP Check 4160 VAC safeguards buses both energized by offsite power SRO/BOP Reestablish instrument air to containment Start second air compressor Check IA header pressure greater than 80 psig Open one then the other IA containment isolation valves SRO/RO Verify charging flow Ensure loop A cold leg normal charging isolation valve open Check charging pumps at least one running Start additional charging pumps and adjust speed as necessary to establish desired charging flow Adjust charging line flow to maintain lab seal P greater than 20 inches

Op-Test No: 2005301 Scenario No: 2 Event No: 4, 5, 6,7 Page 9 of 13 Event

Description:

B RCP #2 Seal Fails leading to B RCP Seal Package failure, SI pumps fail to auto start on SI signal and two Containment Isolation auxiliary relays fail to actuate on CI.

Time Position Applicants Actions or Behavior SRO/RO Check if SI flow should be terminated Subcooling greater than 35F Verify secondary heat sink Check RCS pressure greater than 1600 psig - if not, go to step 14 SRO/BOP Check if containment spray should be stopped (continuous action) - spray not activated SRO/RO Check if RHR pumps should be stopped Check RHR pumps running Check RHR pumps aligned for injection Check RCS pressure greater than 200 psig Check RCS pressure stable or trending higher Stop both RHR pumps Maintain RCS pressure greater than 200 psig (continuous action)

SRO/BOP Check RCS and S/G pressures Check S/G pressures stable or trending higher Check RCS pressure stable or trending lower SRO/BOP Check if diesels should be stopped Check 4160 VAC safeguards buses energized by offsite power Stop all unloaded diesels- SM will have Unit 2 operators address this step

Op-Test No: 2005301 Scenario No: 2 Event No: 4, 5, 6,7 Page 10 of 13 Event

Description:

B RCP #2 Seal Fails leading to B RCP Seal Package failure, SI pumps fail to auto start on SI signal and two Containment Isolation auxiliary relays fail to actuate on CI.

Time Position Applicants Actions or Behavior CREW Initiate evaluation of plant status Ensure one train of containment sump recirculation available Check control room RMS high alarms clear Obtain samples SRO/RO Check if RCS is intact outside containment SRO Read caution regarding RHR pump cubicles SRO/BOP Check RHR pump room high level alarm clear SRO/RO Check if RCS cooldown and depressurization is required Check RCS pressure greater than 200 psig Go to EOP 1.2 Unit 1, Small Break LOCA Cooldown and Depressurization Upon transition to EOP-1.2, the scenario may be terminated at the discretion of the Lead Examiner.

Inform the Examinees that they are to remain in the simulator until any evaluator follow-up questions are answered.

Do not discuss any scenario related events.

Op-Test No: 2005301 Scenario No: 2 Event No: 4, 5, 6,7 Page 11 of 13 Event

Description:

B RCP #2 Seal Fails leading to B RCP Seal Package failure, SI pumps fail to auto start on SI signal and two Containment Isolation auxiliary relays fail to actuate on CI.

Time Position Applicants Actions or Behavior The remainder of steps listed in this event section are those found in EOP-0 Attachment A, Automatic Action Verification. The SRO should ensure that performance of this Attachment is continued by the BOP operator, and performed in parallel with EOP-0.

BOP Verify feedwater isolation:

- Feedwater Regulating and Bypass Valves SHUT.

- Both main feed pumps tripped.

- MFP discharge MOVs - BOTH SHUT.

BOP Verify containment isolation:

- CI Panels A and B ALL LIGHTS LIT - the following valves fail to close on signal and must be manually shut

- 1CV-313A RCP seal return

- 1CV-371A Letdown line

- 1RM-3200B RE-211/212 supply

- 1RM-3200C RE-211/212 supply

- RS-SA-9 SHUT.

- No other valves open under administrative control (SM may be asked to verify this).

BOP Verify AFW Actuation:

- Checks both motor driven AFW pumps running.

BOP Check both SI pumps running- If not previously started, both SI pumps should be manually started and proper operation verified BOP Check both RHR pumps running.

BOP Check only one CCW pump running.

Op-Test No: 2005301 Scenario No: 2 Event No: 4, 5, 6,7 Page 12 of 13 Event

Description:

B RCP #2 Seal Fails leading to B RCP Seal Package failure, SI pumps fail to auto start on SI signal and two Containment Isolation auxiliary relays fail to actuate on CI.

Time Position Applicants Actions or Behavior BOP Verify Service Water Alignment:

- 6 service water pumps running.

- Service water isolation valves shut.

- Direct AO to locally check SW-LW-61 or SW-LW-62 shut.

BOP Verify Containment Accident Cooling Units Running

- All accident fans running.

- 1SW-2907 & 2908 OPEN.

- Unit 1 Containment Recirc Coolers Water Flow Low Alarm CLEAR.

BOP Check Control Room Ventilation IN ACCIDENT MODE:

- At least one control room recirc fan RUNNING

- Control room damper solenoid valve PURPLE LIGHT LIT BOP Check if Main Steam Lines Can Remain Open, checks both MSIVs SHUT.

BOP Verify proper SI valve alignment:

- Unit 1 SI active status panel ALL LIGHTS LIT

- Unit 1 SI-Spray Ready status panel NO LIGHTS LIT

Op-Test No: 2005301 Scenario No: 2 Event No: 4, 5, 6,7 Page 13 of 13 Event

Description:

B RCP #2 Seal Fails leading to B RCP Seal Package failure, SI pumps fail to auto start on SI signal and two Containment Isolation auxiliary relays fail to actuate on CI.

Time Position Applicants Actions or Behavior BOP Verify containment spray not required:

- Recognize containment pressure is rising and if > 25 psig perform continuous actions of RNO

- Containment Spray actuated, C01 B 2-6 LIT

- All containment spray discharge valves OPEN

- At least one spray pump running

- Shutdown one train of spray by placing spray pump in PULL-OUT and shutting its associated suction valve.

- After spray has been activated for greater than two minutes, one spray additive valve verified OPEN BOP Verify SI Flow:

- RCS wide range pressure <1400 psig

- Check SI pumps flow indicated

- RCS wide range pressure < [425] 200 psig This ends the steps of EOP-0 Attachment A.

Appendix D Scenario Outline Form ES-D-1 Facility: Point Beach Scenario No.: 3 OP-Test No.: 2005301 Examiners: ______________________ Operators: ______________________

Initial Conditions: Unit 1 is at ~6.5% power following a Reactor Trip recovery startup. Turbine is off line. Unit 1 is at MOL (8001 MWD/MTU), Xenon is building in slowly. Boron Concentration is 673 PPM. Currently in OP-1C, Startup to Power Operation, at step 5.26. Step 5.22 is being held open, pending shift to Main Feed Regulating Valves.

Unit 2 is at 100% power.

Turnover: G-01 EDG is out of service for annual maintenance. It was taken out of service 3 days ago and is expected to be returned to service in 3 days. G-02 is aligned to 4.16 kV buses 1A-05 and 2A-05 IAW OI-35A.

1TE-404, Loop B Hot Leg Temperature Element failed high after entry into MODE 1 and removal from service IAW 0-SOP-IC-001 Yellow has just been accomplished. I&C plans to repair the channel during 28% chemistry hold.

1RC-515, Block valve for 1RC-431C is closed due to PORV leakage. Tech Spec 3.4.11, Required Action A.1 has been completed.

IRPI is selected to alternate power (1Y02) due to planned breaker replacement on 1Y06 (Bkr 21).

Today is Sunday, present clock time is real time. An RP Tech and Chemistry Tech are on-site. ERO Maintenance personnel are working on G01.

The objective of the shift is to raise power and roll the Main Turbine. Approved Reactivity Plan designates that power should be raised using Control Rods.

Event Malf. Event Event No. No. Type* Description R-RO 1 N-BOP Raise Power and Prepare to roll the turbine.

N-SRO I-BOP 2 1FT-413, Loop Flow Transmitter fails high.

SRO(T)

C-BOP 3 B Containment Accident Fan Trips 3 T-SRO B Containment Accident Fan Trips 4 C-ALL 1A05 Lockout 5 M-ALL 1X04 Lockout, Reactor Trip due to Loss of RCS Flow, G03 fails to start C-RO 6 Two rods fail to insert on trip SRO

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9

Scenario #3 Initial Conditions: Unit 1 is at ~6.5% power following a Reactor Trip recovery startup. Turbine is off line. Unit 1 is at MOL (8001 MWD/MTU), Xenon is building in slowly. Boron Concentration is 673 PPM. Currently in OP-1C, Startup to Power Operation, at step 5.21. Step 5.17 is being held open, pending shift to Main Feed Regulating Valves. Unit 2 is at 100% power.

Turnover: G-01 EDG is out of service for annual maintenance. It was taken out of service 3 days ago and is expected to be returned to service in 3 days. G-02 is aligned to 4.16 kV buses 1A-05 and 2A-05 IAW OI-35A.

1TE-404, Loop B Hot Leg Temperature Element failed high after entry into MODE 1 and removal from service IAW 0-SOP-IC-001 Yellow has just been accomplished. I&C plans to repair the channel during 28% chemistry hold.

1RC-515, Block valve for 1RC-431C is closed due to PORV leakage. Tech Spec 3.4.11, Required Action A.1 has been completed.

IRPI is selected to alternate power (1Y02) due to planned breaker replacement on 1Y06 (Bkr 21).

Today is Sunday, present clock time is real time. An RP Tech and Chemistry Tech are on-site.

ERO Maintenance personnel are working on G01.

The objective of the shift is to raise power and roll the Main Turbine. Approved Reactivity Plan designates that power should be raised using Control Rods.

ANTICIPATED BOOTH COMMUNICATION/GUIDANCE: Scenario 3 Event 1: Raise Power and Prepare to roll the turbine No anticipated booth communications Event 2: 1FT-413 Loop flow transmitter fails high - Per Lead Examiner (PLE) activate trigger No anticipated booth communications Event 3: B Containment Accident fan trips- PLE activate trigger Crew may send AO to investigate breaker for tripped fan 1W1B1. The AO reports the breaker has tripped on high current.

Event 4: 1A05 Lock out - PLE activate trigger Per AOP-18B step 14 RNO, may contact AO to depress arming pushbutton for CR recirc fan W-13B2 at 1B52-428M.

a. Common index HVAC Control Room W13B2 Event 5: 1X04 Lockout, Reactor Trip, G03 start failure - PLE activate trigger If called, there are no indications of a lockout on 1A-06.

Per EOP-0.1 step 7 RNO, may contact AO to depress arming pushbutton for CR recirc fan W-13B2 at 1B52-428M

a. Common index HVAC Control Room W13B2 Event 6: Two rods fail to insert on trip Per EOP 0.1 step 9 ensure CVCS valves 112C open and 112B shut When crew restores charging, they may contact AO to locally shut 1CV 300A and B, RCP seal injection throttle valves

Scenario #3 Sim Setup IC-77, Unit 1 is at 7% power during a startup from a trip. Power is being raised IAW OP-1C at step 5.26. Xenon is building in.

1RC-515 Shut to isolate leaky PORV G01 Out of Service G02 Aligned to both 1 and 2A05.

TE-404 Removed from service IAW SOP. (Two Switches and yellow bistables)

B, C, E Service Water Pumps in service IRPI selected to alternate power supply due to 1Y06 Breaker 21 Breaker Replacement.

K2B IA compressor in Constant, K2A in standby.

2P-4B in Auto, 2P-4A in standby.

Ensure P99s are ON.

Ensure T-404 and T-408 are removed from scan each time you reset into this IC.

Preloads:

1. XMT1RCS029A: 1TE-404 Failed High Sev = 650

2. MAL1CRF001-E9: Stuck Rod Mal = 1

3. MAL1CRF001-I5: Stuck Rod Mal = 1

4. MAL1DSG002B: G03 Fails to Start Event Triggers:

T-1 XMT1RCS003A: 1FT-413 Loop Flow Xmtr fails high SV=110 T-3 BKR1CNM002: B Containment Accident Fan Trips MV = 1 T-5 MAL1EPS003E: Lockout of 1A05 T-7 MAL1EPS002: 1X04 Lockout (Loss of All AC)

LOA Triggers:

T-16 LOA1HVA002: Reset W13B2 when called for, then delete LOA Remote Val = Reset

Op-Test No: 2005301 Scenario No: 3 Event No: 1 Page 1 Of 2 Event

Description:

Manual SG Level Control, Raise Power and Prepare to roll the turbine.

Time Position Applicants Actions or Behavior Scenario begins at Lead Examiners discretion.

The brief may be conducted in the classroom prior to entering simulator at the discretion of the lead examiner to minimize the amount of time in the simulator. As part of the brief, the SM will inform the crew that the reactivity plan calls for pulling rods to raise power, rather than diluting.

BOP Maintain S/G narrow range level near program band with main feed bypass valves in manual (continuous)

SRO Brief crew on power escalation SRO/RO Per OP-1C Startup to power operation step 5.21, pull rods to raise power to 5 to 17%

SRO/BOP The crew has the option, per step 5.17, of transferring feed to the Main feed regulating valves when bypass flow is insufficient Ensure main feed reg valve controllers in manual Crack open main feed reg valve controllers Check S/G levels to ensure flow through the main feed reg valves Monitor main feed reg valves and slowly shut feed reg bypass controllers SRO Read caution addressing maintaining Tavg above 540F

Op-Test No: 2005301 Scenario No: 3 Event No: 1 Page 2 Of 2 Event

Description:

Manual SG Level Control, Raise Power and Prepare to roll the turbine.

Time Position Applicants Actions or Behavior SRO/RO When greater than 10% power:

Check Power above P-10 light is on Check Hi Pow Range P-10 bistable status lights are lit SRO/RO Depress Interm range logic A/B man trip block pushbuttons Check Intermed range trip blocked light is lit SRO/RO Depress Low power range logic A/B man trip block pushbuttons Check Low power range trip blocked light is lit SRO/RO Check the At power trip blocked (P-7) permissive light has cleared Once power has been raised above P-10 and at the discretion of the Lead Examiner, proceed to the next event.

Op-Test No: 2005301 Scenario No: 3 Event No: 2 Page 1 Of 3 Event

Description:

1FT-413 Loop A flow transmitter fails high Time Position Applicants Actions or Behavior Trigger activated per Lead Examiner CREW Identify failure of 1FT-413 Loop A flow transmitter indicated by PPCS alarm and board indications.

SRO Direct entry into AOP-24, Response to Instrument Malfunctions.

SRO/RO In AOP-24: Identify Failed Instrument and check if failed instrument is a controlling channel SRO Read caution regarding placing additional bistables in a tripped condition CREW Remove failed instrument channel from service per 0-SOP-IC-001

Op-Test No: 2005301 Scenario No: 3 Event No: 2 Page 2 Of 3 Event

Description:

1FT-413 Loop A flow transmitter fails high Time Position Applicants Actions or Behavior SRO Direct entry into 0-SOP-IC-001 - Blue, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service - Blue Channels.

- Obtain and implement 0-SOP-IC-001- Blue

- Review precautions and limitations

- Identify applicable Technical Specifications (reference 0-SOP-IC-002):

- LCO 3.3.1 is not met:

- Action Condition A is entered immediately - Required Action is to enter the Condition referenced in Table 3.3.1-1 for the channel.

- Condition K is referenced from Table 3.3.1-1 Function 9b. Required Action is to place the channel in trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR reduce THERMAL POWER to < P-7 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

- Conduct pre-job brief for removing FT-413 from service

- Obtain Shift Manager permission to remove channel from service

- Direct 0-SOP-IC-001 Attachment A for LT-413 removal from service RO/BOP/SRO Perform actions as directed by SRO from Attachment A for LT-413 removal.

- Place the following bistables to TRIP inside C-115: (BOP)

- Verify alarms and trip status lights are proper (RO)

1. Low Flow (proving lamp lit)

- Remove point ID F-413 from scan on PPCS SRO Inform Shift Manager LT-413 is removed from service and bypassed and that DCS and STA notifications need to be made SRO In AOP-24 Return controls to Automatic if desired

Op-Test No: 2005301 Scenario No: 3 Event No: 2 Page 3 Of 3 Event

Description:

1FT-413 Loop A flow transmitter fails high Time Position Applicants Actions or Behavior SRO In AOP-24 Check Failure for TS or TRM applicability (if not already identified)

Determine instrument channel operability requirements satisfied Inform Shift Manager of any operability requirements not satisfied SRO Exit AOP-24 At the discretion of the lead examiner, the exam team will proceed to the next event.

Op-Test No: 2005301 Scenario No: 3 Event No: 3 Page 1 Of 1 Event

Description:

B Containment accident fan 1W1B1 trips Time Position Applicants Actions or Behavior Trigger activated per Lead Examiner BOP Recognize that 1W1B1 Containment accident fan has tripped

- Board indicating lights

- Annunciators: C01B 3-4 Motor breaker trip C01B 3-3 Unit 1 Containment Recirc coolers air flow low CREW Respond to above annunciators SRO identifies LCO 3.6.6 is not met and enters TSAC 3.6.6 C, which requires inoperable accident fan to be returned to service within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

SRO/BOP May start the non-running recirc fan based on OI-72 Containment air recirculation system

- Should start 1W1A1 first, followed by 1W1A2.

SRO/BOP May secure the containment cooling fan associated with the tripped unit -

1W1B2 SRO/BOP May dispatch AO to investigate breaker. The AO will report breaker tripped on high current BOP May take switch for 1W1B1 to pullout to clear the Motor breaker tripped annunciator At the discretion of the lead examiner, the exam team will proceed to the next event.

Op-Test No: 2005301 Scenario No: 3 Event No: 4 Page 1 Of 3 Event

Description:

1A-05 Lockout Time Position Applicants Actions or Behavior Trigger activated per Lead Examiner CREW Recognize the loss of one train of safeguards power

- C02 D 3-4 Unit 1 4.16 kV lockout

- C02 bus voltage meters for 1A-05 and 1B-03 SRO Direct entry to AOP-19A, Loss of Train A Safeguards power or may directly enter AOP-18B SRO Read note regarding closing electrical breakers SRO Check plant stable per AOP-18B Unit 1, Train B Equipment Operation -

Per RNO transition to AOP-18B RO/BOP Maintain S/G level if still in manual feed control (continuous)

SRO/BOP Check bus 1A-06 energized SRO/BOP Check diesel voltage and frequency within limits: (continuous action)

Check either G03 or G04 running Per RNO go to step 3 SRO/BOP Check bus 1B-04 energized SRO/BOP Check MCC 1B-42 energized based on:

Train B equipment indications or 1B-04 to MCC 1B-42 closed

Op-Test No: 2005301 Scenario No: 3 Event No: 4 Page 2 Of 3 Event

Description:

1A-05 Lockout Time Position Applicants Actions or Behavior SRO/BOP Check blender operations to both units Power available to at least one boric acid transfer pump for each unit SRO/BOP Power available to the reactor make-up water pump aligned for blender services Ensure desired make-up established to both units - BOP should realign pumps and valves for blender services SRO Check RHR required - Per RNO go to step 8 SRO Verify CCW pumps at least one running - operator may match flags on control switches for CCW pumps SRO/BOP Check component cooling less than or equal to 3650 gpm SRO/BOP Check only one component cooling water pump running SRO Check service water header pressure greater than or equal to 40 psig - if not already done, operators may start additional SW pumps based on ARB guidance for SW header pressure alarm. May match flags on non-running pumps.

SRO Read note regarding starting tripped charging pumps

Op-Test No: 2005301 Scenario No: 3 Event No: 4 Page 3 Of 3 Event

Description:

1A-05 Lockout Time Position Applicants Actions or Behavior SRO/RO Verify charging flow:

Check charging pumps at least one running Start additional pumps and adjust speed as necessary to establish desired charging flow Adjust charging line flow controller to maintain lab seal P greater than 20 inches SRO Check if letdown should be established Check normal letdown isolated - Per RNO go to step 14 SRO/BOP Check control room fans armed Check control room recirc fan W-13B2 white light off SRO/BOP Check control room ventilation in mode one - per RNO align CR ventilation per 0-SOP-VNCR-002.

At the discretion of the lead examiner, the exam team will proceed to the next event.

Op-Test No: 2005301 Scenario No: 3 Event No: 5, 6 Page 1 Of 9 Event

Description:

1X04 Lockout, Reactor Trip due to Loss of RCS Flow, G03 fails to start, two rods fail to insert on trip Time Position Applicants Actions or Behavior Trigger activated per Lead Examiner SRO Direct entry into EOP-0, Reactor Trip and Safety Injection May enter ECA 0.0 initially if crew recognizes loss of both safeguards buses RO Performs Immediate Actions of EOP-0 (Steps 1-4) and informs SRO they are complete Verify reactor trip - RO should notice two rods not fully inserted and depress manual trip pushbuttons on 1C04 with no response

- Verify turbine trip

- Verify safeguard buses energized - May attempt to start G03 per RNO

- Check if SI is actuated SRO/RO Verify Reactor Trip

- Check reactor trip and bypass breakers OPEN

- Check all rod bottom lights LIT - manually trip the reactor if not already done during immediate actions

- Check all rod position indicators ON BOTTOM

- Check neutron flux LOWERING SRO/RO Verify Turbine Trip SRO/RO Verify Safeguard buses energized

- Check at least one 4160 Vac safeguards bus energized (1A-05 or 1A-06)

- Check at least one 480 Vac safeguards bus energized (1B-03 or 1B-04)

Op-Test No: 2005301 Scenario No: 3 Event No: 5, 6 Page 2 Of 9 Event

Description:

1X04 Lockout, Reactor Trip due to Loss of RCS Flow, G03 fails to start, two rods fail to insert on trip Time Position Applicants Actions or Behavior SRO/RO Recognize no power to safeguard buses and either attempt EDG start per EOP-0 Step 3 RNO and then transition to ECA 0.0 or immediately transition to ECA 0.0. Have STA begin monitoring Critical Safety Functions for information only.

RO Perform immediate action steps of ECA 0.0

- Verify Reactor Trip

- Verify Turbine Trip SRO/RO Verify Immediate Actions complete

- Verify Reactor Trip (reactor trip and bypass breakers open & neutron flux lowering)

- Verify Turbine Trip (stop valves shut or annunciator 1C03 1E1 4-3 lit or turbine closed bistables lit)

SRO Read note regarding implementation of CSPs Brief foldout page criteria CREW Maintain RCS Inventory

- Check PORVs shut (RO)

- Check letdown orifice valves shut (RO)

- Check letdown CI valves shut. Shuts 1CV-371/371A (RO)

- Check RCP seal return valve shut. Shuts 1CV-313A (RO)

- Check RCS Sample Valves shut. Shuts SC-966C (BOP)

- Check Head Vent System energized (RO) per RNO go to step 4 SRO Read caution regarding overcurrent on AFW pump

Op-Test No: 2005301 Scenario No: 3 Event No: 5, 6 Page 3 Of 9 Event

Description:

1X04 Lockout, Reactor Trip due to Loss of RCS Flow, G03 fails to start, two rods fail to insert on trip Time Position Applicants Actions or Behavior SRO/BOP Verify Turbine-Driven AFW pump operations

- Check 1P-29 running

- Check AFW pump discharge flow > 200gpm on 1FI-4002

- Control pumps and align valves as necessary to maintain S/G level between 29% to 65% (continuous)

SRO/BOP Verify cooling to AFW pump bearings

- Check at least one SW pump running SRO/BOP Check both 4160VAC safeguards buses not energized SRO/BOP Check emergency Diesels-ALL RUNNING

- Try to start non running EDG: G-03 (G-01 is DTO) - may choose not to try and start G03 based on previous attempt

- Ensure diesel mode selector switch in AUTO

- Place control switch to start

- Ensure generator field flash occurs automatically

- Ensure green ready to load light is energized Attempt to start G03 will be unsuccessful SRO/BOP Check Diesel Status

- Ensure SW header pressure greater to or equal to 40 psig

- Ensure frequency on running EDGs between 59.5 Hz and 60.5 Hz

- Ensure voltage on running EDGs between 4050 and 4300 VAC SRO/BOP Check Bus H-01 not energized - per RNO go to step 11

Op-Test No: 2005301 Scenario No: 3 Event No: 5, 6 Page 4 Of 9 Event

Description:

1X04 Lockout, Reactor Trip due to Loss of RCS Flow, G03 fails to start, two rods fail to insert on trip Time Position Applicants Actions or Behavior SRO/BOP Check bus 1A-05 not energized SRO/BOP Energize Bus 1A-05 from normal EDG supply G-01

- Check G-01 running, determines DTO and proceeds to step 13 SRO/BOP Energize Bus 1A-05 from alternate EDG supply G-02 Should realize that bus 1A-05 can not be energized due to lockout and proceed to energize 1A-06 from G-04 Critical Task: SRO/BOP must energize at least one AC emergency bus before placing safeguards equipment in pullout per ECA 0.0 SRO/BOP Energize Bus 1A-06 from alternate EDG supply G-04 Check G-04 running Ensure 1A-04 to 1A-06 bus tie breaker open Ensure G-03 to 1A06 bus tie breaker open and in pullout Unlock and place G-04 to bus 1A-06 breaker control switch in auto Check G-04 to bus 1A-06 breaker closed SRO/BOP Check 480 Vac Safeguard buses - at least one energized SRO/BOP Verify service water system operation Ensure service water header pressure greater than or equal to 40 psig SRO Return to procedure and step in effect Should return to EOP-0. Depending on when the crew entered ECA 0.0, the SRO may enter EOP-0 at step 3 or at step 4

Op-Test No: 2005301 Scenario No: 3 Event No: 5, 6 Page 5 Of 9 Event

Description:

1X04 Lockout, Reactor Trip due to Loss of RCS Flow, G03 fails to start, two rods fail to insert on trip Time Position Applicants Actions or Behavior SRO/RO EOP-0 step 4 Check if SI is actuated, check SI annunciators any lit.

SRO/RO Per RNO Determine appropriate recovery actions:

Check if SI is required Containment pressure greater than 5 psig Steam line A and B pressure less than 530 PZR pressure less than 1735 psig PZR level less than 10% - Pressurizer level may eventually reach 10%

requiring a manual SI and a return to step 4 of EOP-0 RCS subcooling less than 35F SRO/RO May restore charging per ARB for pressurizer level setpoint deviation SRO/RO If SI not required then:

Start monitoring Critical Safety Functions Go to EOP-0.1 Unit 1 Reactor Trip Response SRO Discuss foldout page for EOP-0.1 SI actuation criteria: Pressurizer level may eventually reach 10%

requiring a manual SI and a return to step 4 of EOP-0 RCS temperature control - adjust feedwater and steam dumps as necessary to stabilize RCS cold leg temperature less than or equal to 547F

Op-Test No: 2005301 Scenario No: 3 Event No: 5, 6 Page 6 Of 9 Event

Description:

1X04 Lockout, Reactor Trip due to Loss of RCS Flow, G03 fails to start, two rods fail to insert on trip Time Position Applicants Actions or Behavior SRO/RO Verify RCS temperature control: (continuous action)

Check RCS wide range cold leg temperatures less than or equal to 547F and stable SRO Read caution regarding inaccuracy of RTD bypass temperatures on natural circulation SRO/BOP Verify feedwater isolation Check RCS average temperature less than 554F Check feedwater reg valves both shut SRO Read caution regarding motor driven AFW pump overcurrent above 240 gpm SRO/BOP Transfer feedwater control to bypass reg valves Check main feedwater pumps at least one running - Perform RNO SRO/BOP If S/G can not be maintained using bypass, then establish AFW flow:

Ensure motor-driven AFW pumps both running (only 1 is available)

Verify AFW valve alignment Ensure Unit 1 valves open Ensure Unit 2 valves shut Ensure motor-driven AFW pump discharge maintaining discharge pressure at 1200 psig If both S/G levels less than 25% or motor-driven pumps not available then ensure steam supply valves to TD AFW pumps open SRO/BOP Stabilize S/G levels: (continuous action)

Check S/G levels greater than 29%

Control feed flow to maintain levels between 29 and 65%

Op-Test No: 2005301 Scenario No: 3 Event No: 5, 6 Page 7 Of 9 Event

Description:

1X04 Lockout, Reactor Trip due to Loss of RCS Flow, G03 fails to start, two rods fail to insert on trip Time Position Applicants Actions or Behavior SRO/BOP Verify generator trip:

Check main generator and exciter field breaker open Check auto bus transfer complete - no transfer due to 1X04 lockout SRO/BOP Ensure miscellaneous electrical loads are energized:

Ensure MCCs 1B-31 and B-43 energized - 1B31 not available Check battery chargers supplying DC buses energized restore battery chargers by closing affected battery charger supply contactor.

If contactor does not close or charger will not operate then restore per AOP 0.0 Vital DC system malfunction.

SM will direct Unit 2 operators to recover remaining charger Ensure cavity cooling fans one running Check instrument air compressors at least one running Check cable spreading room ventilation operating Check cable spreading room recirc fans one running Check CSR chilled water recirc pumps one running Start additional loads as necessary to meet current plant conditions.

Refer to AOP-22 Unit 1, EDG load management SRO/BOP Check control room fans armed:

Check control room charcoal fan filter W-14A white light off Check control room recirc fan W-13B2 white light off - Contact AO to reset fan W-13B2

Op-Test No: 2005301 Scenario No: 3 Event No: 5, 6 Page 8 Of 9 Event

Description:

1X04 Lockout, Reactor Trip due to Loss of RCS Flow, G03 fails to start, two rods fail to insert on trip Time Position Applicants Actions or Behavior SRO/BOP Check all AC buses energized by offsite power:

Restore power to all AC buses while continuing with this procedure.

Should ask SM or Unit 2 operator to address this step SRO/RO Verify charging pump suction alignment:

Check VCT level greater than 17%: If not, perform RNO Actions of RNO (if control room indications are not available, RO should contact AO to locally verify positions of MOVs)

Ensure RWST to charging pump suction MOV open - 1CV 112B Ensure VCT outlet to charging pump suction MOV shut - 1CV 112C When VCT level is greater than 17% then 1CV 112C open and 1CV 112B shut SRO/RO Verify charging flow:

Ensure RCS normal charging isolation valve open SRO/RO Check charging pumps at least one running:

If CCW to any thermal barrier lost then locally shut seal injection valves before starting charging pumps Start charging pumps as necessary to establish at least one running SRO/RO Start additional charging pumps and adjust speed to establish desired charging flow Adjust charging line flow to maintain lab seal P greater than 20 inches

Op-Test No: 2005301 Scenario No: 3 Event No: 5, 6 Page 9 Of 9 Event

Description:

1X04 Lockout, Reactor Trip due to Loss of RCS Flow, G03 fails to start, two rods fail to insert on trip Time Position Applicants Actions or Behavior Critical Task: The RO must recognize the need to emergency borate and commence emergency boration prior to exiting EOP-0.1 SRO/RO Check all control rods fully inserted - If two or more control rods not fully inserted then initiate emergency boration as follows:

SRO/BOP Record initial level for in-service BAST SRO/RO Establish maximum charging flow:

Fully open charging flow control valve Start additional charging pumps Adjust speed to maintain charging flow less than 140 gpm SRO/RO Start one boric acid transfer pump SRO/RO Open emergency borate valve SRO/RO Borate 1200 gallons for each control rod not fully inserted (2400 gal).

The scenario may be terminated at the discretion of the lead examiner. Inform examinees that they are to remain in the simulator until any evaluator follow-up questions are answered.

Appendix D Scenario Outline Form ES-D-1 Facility: Point Beach Scenario No.: 4 OP-Test No.: 2005301 Examiners: ______________________ Operators: ______________________

Initial Conditions: Unit 1 is at 28% power for chemistry hold following a startup, MOL, equilibrium xenon conditions. Boron Concentration is 1125 PPM. Unit 2 is at 100% power.

Turnover: G-01 EDG is out of service for annual maintenance. It was taken out of service 3 days ago and is expected to be returned to service in 3 days. G-02 is aligned to 4.16 kV buses 1A-05 and 2A-05 IAW OI-35A.

1TE-404, Loop B Hot Leg Temperature Element has failed high and has been removed from service IAW 1-SOP-IC-001 Yellow.

1RC-515, Block valve for 1RC-431C is closed due to PORV leakage. Tech Spec 3.4.11, Required Action A.1 has been completed.

IRPI is selected to alternate power (1Y02) due to planned breaker replacement on 1Y06 (Bkr 21).

Today is Sunday, present clock time is real time. An RP Tech and Chemistry Tech are on-site. ERO Maintenance personnel are working on G01.

The objective of the shift is to maintain stable plant conditions.

Event Malf. Event Event No. No. Type* Description 1 C - BOP 1P-75 EH Pump Trips/1P-76 EH Pump fails to auto start R - RO 2 C - BOP 1X01 Lockout / Turbine Trip SRO C - RO 3 2 Dropped Rods requiring Reactor Trip SRO One A SG Safety Valve fails open, A Non-return valve sticks open and B 4 M - ALL MSIV sticks open, depressurizing BOTH SGs C - BOP 5 A MFP fails to trip on SI/CS-466 MFRV sticks 10% open SRO

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9

Scenario #4 Initial Conditions: Unit 1 is at 28% power for chemistry hold following a startup, MOL, equilibrium xenon conditions. Boron Concentration is 1125 PPM. Unit 2 is at 100% power.

Turnover: G-01 EDG is out of service for annual maintenance. It was taken out of service 3 days ago and is expected to be returned to service in 3 days. G-02 is aligned to 4.16 kV buses 1A-05 and 2A-05 IAW OI-35A.

1TE-404, Loop B Hot Leg Temperature Element has failed high and has been removed from service IAW 1-SOP-IC-001 Yellow.

1RC-515, Block valve for 1RC-431C is closed due to PORV leakage. Tech Spec 3.4.11, Required Action A.1 has been completed.

IRPI is selected to alternate power (1Y02) due to planned breaker replacement on 1Y06 (Bkr 21).

Today is Sunday, present clock time is real time. An RP Tech and Chemistry Tech are on-site.

ERO Maintenance personnel are working on G01.

The objective of the shift is to maintain stable plant conditions.

ANTICIPATED BOOTH COMMUNICATION/GUIDANCE: Scenario 4 Event 1: 1P-75 EH Pump Trips/1P-76 EH Pump fails to auto start - Per lead examiner (PLE) activate trigger Per ARP for EH supply system AO will be asked to check EH pressure in normal band on 1PI-6017 EH fluid system pressure indicator. Acknowledge the request. If time permits, report back that accumulator load and unload times are normal and pressure is cycling between 1550 and 1950 psig.

Event 2: 1X01 Lockout / Turbine Trip - PLE activate trigger No anticipated booth communications Event 3: 2 Dropped Rods requiring Reactor Trip - PLE activate trigger No anticipated booth communications Event 4: Both S/Gs faulted Per EOP-0 Att. A step A7, crew will request AO to check shut SW-LW-61 or 62 at C-180, blowdown evap panel. Both valves are shut.

Per EOP-2 step 2, crew will ask AO to perform Attachment A of EOP-2 to locally shut MSIVs.

DO NOT shut A MSIV SHUT B MSIV (by deleting malfunction) after crew establishes 50 gpm in each S/G Per ECA-2.1 step 4, the crew will ask the AO to locally shut 1P-29 AFP/Radwaste steam isolation for both S/G, 1MS-235 and 237. Shut valves as requested.

Per EOP-2 step 4, the crew will ask the AO to locally shut main steam trap isolation for both S/G, 1MS-228 and 238. Shut valves as requested.

When the AO reports that the above valves have been shut also inform the crew that the A S/G safety is lifting.

Event 5: A MFP fails to trip on SI/CS-466 MFRV sticks 10% open Crew may ask AO to locally shut B FRV or isolation valves. Shut valves as requested

Scenario #4 Sim Setup IC-78, 28% Power, Eq Xenon, Holding power for startup IAW OP1C step 5.123.3 1RC-515 Shut to isolate leaky PORV G01 Out of Service G02 Aligned to both 1 and 2A05.

TE-404 Removed from service IAW SOP. (Two Switches and yellow bistables)

Remove 404 TH and 408 PPCS points from scan B, C, E Service Water Pumps in service IRPI selected to alternate power supply due to 1Y06 Breaker 21 Breaker Replacement.

K2B IA compressor in Constant, K2A in Standby.

2P-4B in Auto, 2P-4A BA transfer pump in pullout Ensure T-404 and T-408 are removed from scan each time IC is reset.

Preloads:

1. XMT1RCS029A: 1TE-404 Failed High Sev = 650

2. BSTMGA025: 1P-76 Fails to start on low press. (Press BST failed As Is)

Mal = 1 (As Is)

3. VLV1SGN011D: MS-2017 B MSIV Fails to Shut Sev = 1

4. VLV1SGN014: MS-2018A A Main Steam Non-Return Fails Open Mal = 1

5. BKR1CFW001: A MFP fails to trip on SI Mal = 3 (Fail Auto Trip)

Event Triggers:

T-1 BKR1MGA002: EH Pump 1P-75A Trips Mal = 6 Fail Control Fuse T-3 MAL1SWD004B: 1X01 Lockout, Auto Turbine Trip T-5 MAL1CRF002 D4: Drop Rod D4 MAL1CFR002 G7: Drop Rod G7 T-30 LOA1CFW055: CS-466 A MFRV fails to 10% open on Rx Trip.

Remote Val = 0.1 T-30 VLV1SGN008: A SG Safety Opens on Rx Trip

Mal Val = 3 (Open)

Set JCRFTR, Reactor Trip to Trigger 30 LOA Triggers:

T-16 LOA1CFW026: CS-466 Inlet Valve Shut Valve when Requested T-17 LOA1SGN0023: 1MS 235-RW Steam Isolation Shut Valve when Requested w/ 60 second Time Delay T-18 LOA1SGN025: 1MS-237 RW Steam Isolation Shut Valve when Requested w/ 60 second Time Delay

Op-Test No: 2005301 Scenario No: 4 Event No: 1 Page 1 Of 1 Event

Description:

1P-75 EH Pump Trips/1P-76 EH Pump fails to auto start Time Position Applicants Actions or Behavior Crew in chemistry hold in OP-1C step 5.123.3 Per lead examiner insert first malfunction - 1P-75 EH Pump Trips/1P-76 EH Pump fails to auto start BOP Recognize that the running EH has tripped and the standby has not started

- Annunciator 1C03 1F 1-11 EH Supply system

- Board indicating lights SRO/BOP Respond to annunciator 1C03 1F 1-11 EH Supply system per ARP BOP Ensure one EH pump is running by starting standby pump 1P-75 Check EH pressure maintained in normal band - Contact AO When plant is stable and/or per lead examiner go to next event.

Op-Test No: 2005301 Scenario No: 4 Event No: 2 Page 1 Of 2 Event

Description:

1X01 Lockout / Turbine Trip Time Position Applicants Actions or Behavior Trigger activated per Lead Examiner Crew Recognize that the main turbine has tripped

- Multiple turbine first-out annunciators SRO Direct entry into AOP-25 Turbine trip without reactor trip SRO/RO Check stable plant conditions:

Reactor power stable with condenser steam dumps Pressurizer level stable Pressurizer pressure stable S/G level stable Should decide plant is not stable, perform RNO and go to step 3 SRO/RO Check rod control in automatic SRO/BOP Verify turbine trip SRO/BOP Verify generator trip SRO/BOP Verify auto bus transfer complete CREW Stabilize Tavg and reactor power:

Check condenser steam dumps operating properly to stabilize Tavg at 547F Check rod control operating properly in automatic

Op-Test No: 2005301 Scenario No: 4 Event No: 2 Page 2 Of 2 Event

Description:

1X01 Lockout / Turbine Trip Time Position Applicants Actions or Behavior SRO/BOP Maintain mode 2: (continuous action)

Place rods in manual Place condenser steam dump mode selector switch in manual Maintain reactor critical Control reactor power between 10 E -7 amps and 5% power Maintain Tavg 540F to 550F SRO/RO Check pressurizer pressure stable at or trending to 2235 psig SRO/RO Check pressurizer level stable at or trending to 20%

SRO/BOP Transfer feedwater control to bypass regulating valves Check main feedwater pumps at least one running Control feedwater flow using bypass regulating valves Maintain steam generator levels between 60 - 75%

Place main feedwater regulating valves in manual and shut After step 11 and/or per lead examiner continue to next event

Op-Test No: 2005301 Scenario No: 4 Event No: 3,4,5 Page 1 of 12 Event -2 Dropped Rods requiring Reactor Trip

==

Description:==

-One A SG Safety Valve fails open, A Non-return valve sticks open and B MSIV sticks open, depressurizing BOTH S/Gs

-A MFP fails to trip on SI/CS-466 MFRV sticks 10% open Time Position Applicants Actions or Behavior Trigger activated per Lead Examiner Critical Task: RO must initiate a manual reactor trip prior to withdrawing rods to maintain criticality following the two dropped rods.

SRO/RO Recognize that two control rods have dropped

- Rod bottom lights illuminated

- IRPI

- Annunciators: 1C04 1A 4-5 Power range rod drop 1C04 1A 1-4 Rod bottom rod drop SRO/RO May enter AOP-6A Dropped Rod which directs tripping the reactor for more than one rod dropped or may recognize need to immediately trip the unit.

SRO Direct a Manual Reactor Trip and entry into EOP-0, Reactor Trip or Safety Injection RO Perform Immediate Actions of EOP-0 (Steps 1-4) and informs SRO they are complete

- Verify reactor trip

- Verify turbine trip

- Verify safeguard buses energized

- Check if SI is actuated - may manually actuate SI on 10% pzr level

Op-Test No: 2005301 Scenario No: 4 Event No: 3,4,5 Page 2 of 12 Event -2 Dropped Rods requiring Reactor Trip

==

Description:==

-One A SG Safety Valve fails open, A Non-return valve sticks open and B MSIV sticks open, depressurizing BOTH S/Gs

-A MFP fails to trip on SI/CS-466 MFRV sticks 10% open Time Position Applicants Actions or Behavior SRO/RO Verify Reactor Trip

- Check reactor trip and bypass breakers OPEN

- Check all rod bottom lights LIT

- Check all rod position indicators ON BOTTOM

- Check neutron flux LOWERING SRO/RO Verify Turbine Trip

-Check turbine stop valves BOTH SHUT: (either method)

- SL and SR SHUT

- Annunciator 1C03 1E1 4-3, Turbine Stop valves Two CLOSED

- Turbine Valves Closed bistable lights LIT SRO/RO Verify Safeguard buses energized Check at least one 4160 Vac safeguards bus energized (1A05 or 1A06)

Check at least one 480 Vac safeguards bus energized (1B03 or 1B04)

Op-Test No: 2005301 Scenario No: 4 Event No: 3,4,5 Page 3 of 12 Event -2 Dropped Rods requiring Reactor Trip

==

Description:==

-One A SG Safety Valve fails open, A Non-return valve sticks open and B MSIV sticks open, depressurizing BOTH S/Gs

-A MFP fails to trip on SI/CS-466 MFRV sticks 10% open Time Position Applicants Actions or Behavior SRO/RO Check if SI is actuated - Check SI annunciators any lit Check if SI is required:

Containment pressure greater than 5 psig Steam line A or B pressure less than 530 psig PZR pressure less than 1735 psig PZR level than 10% - Should manually SI if not already done RCS subcooling less than 35F SRO/RO Check SI both trains actuated SI pumps both running RHR pumps both running SRO Review foldout page criteria with the crew Crew Recognize both S/Gs faulted based on lowering S/G pressure and MSIV indicating lights. The crew may attempt to shut both MSIVs at this point.

Maintain total feed greater than or equal to 200 gpm until level in at least one is greater than 29%.

Op-Test No: 2005301 Scenario No: 4 Event No: 3,4,5 Page 4 of 12 Event -2 Dropped Rods requiring Reactor Trip

==

Description:==

-One A SG Safety Valve fails open, A Non-return valve sticks open and B MSIV sticks open, depressurizing BOTH S/Gs

-A MFP fails to trip on SI/CS-466 MFRV sticks 10% open Time Position Applicants Actions or Behavior SRO EOP-0 Attachment A Automatic Action Verification directed to be completed by the BOP operator while continuing on with EOP-0. The steps for Attachment A are included near the end of this event section.

All items of Attachment A should be as expected with the exception of:

- A SG feed pump failing to trip

- CS-466 feed reg valve sticking open

- B MSIV open

- A MSIV cycling SRO Read caution addressing motor-driven AFW pump flow > 240 gpm RO/SRO Verify Secondary Heat Sink:

- Level in at least one S/G > 29%.

- Control pumps and align valves as necessary to maintain S/G level between 29% and 65%.

Adequate Aux Feedwater will be available, > 200 gpm should be maintained until level is > 29% in one S/G SRO/RO Verify RCP Seal Cooling Check labyrinth seal delta-P > 20 inches OR Check component cooling to RCP thermal barrier normal

Op-Test No: 2005301 Scenario No: 4 Event No: 3,4,5 Page 5 of 12 Event -2 Dropped Rods requiring Reactor Trip

==

Description:==

-One A SG Safety Valve fails open, A Non-return valve sticks open and B MSIV sticks open, depressurizing BOTH S/Gs

-A MFP fails to trip on SI/CS-466 MFRV sticks 10% open Time Position Applicants Actions or Behavior SRO/RO Verify RCS temperature control (continuous action step).

- This procedure step provides actions to stop dumping steam and reducing total feed flow (if S/G levels are in the required band) with RCS temperature trending lower.

SRO/RO Check pressurizer PORVs both shut.

SRO/RO Verify pressurizer spray valves shut Both normal loop spray valves shut.

Auxiliary spray valve shut.

SRO/RO Check if RCPs should remain running - RCPs are running and subcooling is > 30 ºF SRO Start Monitoring Critical Safety Function Status trees.

The instructor SM/STA will acknowledge this report and begin monitoring.

CREW Verify Containment Sump Recirculation Not Required - sump recirc is not required.

CREW Check if secondary system is intact:

- No S/G pressure trending lower in an uncontrolled manner

- No S/G completely depressurized AND SRO should transition to EOP-2 Faulted S/G Isolation based on both S/G faulted

Op-Test No: 2005301 Scenario No: 4 Event No: 3,4,5 Page 6 of 12 Event -2 Dropped Rods requiring Reactor Trip

==

Description:==

-One A SG Safety Valve fails open, A Non-return valve sticks open and B MSIV sticks open, depressurizing BOTH S/Gs

-A MFP fails to trip on SI/CS-466 MFRV sticks 10% open Time Position Applicants Actions or Behavior SRO Read cautions and review foldout page criteria of EOP-2 SRO/RO Check RCS wide range Hot Leg Temperatures STABLE:

- Control feed and dump steam as necessary to stabilize RCS hot leg temperatures SRO/BOP Isolate both Main Steam Lines - unable to shut MSIVs Contact AO to locally shut MSIVs per Attachment A of EOP-2 SRO/BOP Check if any S/G in NOT faulted - transition to ECA 2.1 Unit 1 Uncontrolled depressurization of both S/Gs SRO/BOP Address foldout page for ECA - 2.1 If any S/G pressure rises at any time and SI has not been terminated then go to EOP-2 Note: The background document states that this step applies if the pressure boundary is restored to one steam generator and should be applied once the B MSIV is shut SRO/BOP Isolate both main steam lines Shut both MSIVs - Locally shut per Attach A if not already attempted Ensure bypass valves both shut

Op-Test No: 2005301 Scenario No: 4 Event No: 3,4,5 Page 7 of 12 Event -2 Dropped Rods requiring Reactor Trip

==

Description:==

-One A SG Safety Valve fails open, A Non-return valve sticks open and B MSIV sticks open, depressurizing BOTH S/Gs

-A MFP fails to trip on SI/CS-466 MFRV sticks 10% open Time Position Applicants Actions or Behavior SRO/BOP Isolate Feed to both S/G Ensure Feed Regulating Valve both shut May locally shut valve or isolate flow path one loop at a time Ensure Feed Regulating Bypass Valve both shut SRO/BOP Reset Loss of feedwater turbine trip SRO/BOP Isolate flow from S/Gs

- Ensure 1MS-2015 and 2016 SHUT (atmospheric dumps)

- SHUT 1MS-2019 and 2020 (turbine driven AFW steam supply)

- Ensure 1MS-5959/2045 and 5958/2042 SHUT (S/G Blowdown)

- Locally shut 1MS-237 and MS-235 (1P-29 AFP/Radwaste steam isolation)

- Locally shut 1MS-238 and MS-228 (main steam trap isolation)

SRO/BOP Control feed flow to minimize cooldown: (continuous action)

Check level in both S/G greater than 29%

Check C/D rate less than 100F - reduce feed to 50 gpm per S/G Check level in both S/G less than 65%

Check RCS wide range hot leg temperature stable or trending lower SRO/RO Check if RCPs should remain running

Op-Test No: 2005301 Scenario No: 4 Event No: 3,4,5 Page 8 of 12 Event -2 Dropped Rods requiring Reactor Trip

==

Description:==

-One A SG Safety Valve fails open, A Non-return valve sticks open and B MSIV sticks open, depressurizing BOTH S/Gs

-A MFP fails to trip on SI/CS-466 MFRV sticks 10% open Time Position Applicants Actions or Behavior SRO Once the B MSIV is shut, should transition to EOP-2 based on foldout page for one S/G no longer faulted SRO Read cautions, notes and review foldout page criteria for EOP-2 RO Check RCS wide range Hot Leg Temperatures STABLE:

- Control feed and dump steam as necessary using B S/G to stabilize RCS hot leg temperatures RO/BOP Isolate both Main Steam Lines RO/BOP Check if any S/G in NOT faulted (determine B S/G is not faulted)

RO/BOP/SRO Identify faulted S/G (determine A S/G is faulted)

RO/BOP Reset Loss of Feedwater Turbine Trip RO/BOP Isolate Feed to faulted S/G - Place P38A in pullout RO/BOP Isolate flow from faulted S/G BOP/RO Check CST Level > 8 ft

Op-Test No: 2005301 Scenario No: 4 Event No: 3,4,5 Page 9 of 12 Event -2 Dropped Rods requiring Reactor Trip

==

Description:==

-One A SG Safety Valve fails open, A Non-return valve sticks open and B MSIV sticks open, depressurizing BOTH S/Gs

-A MFP fails to trip on SI/CS-466 MFRV sticks 10% open Time Position Applicants Actions or Behavior RO Check Secondary system radiation normal Condenser air ejector S/G Blowdown Main steam line Activity samples Local surveys SRO Go to EOP-1 Unit 1 Loss of reactor or secondary coolant Scenario can be terminated at the discretion of the lead examiner

Op-Test No: 2005301 Scenario No: 4 Event No: 3,4,5 Page 10 of 12 Event -2 Dropped Rods requiring Reactor Trip

==

Description:==

-One A SG Safety Valve fails open, A Non-return valve sticks open and B MSIV sticks open, depressurizing BOTH S/Gs

-A MFP fails to trip on SI/CS-466 MFRV sticks 10% open Time Position Applicants Actions or Behavior The remainder of steps listed in this event section are those found in EOP-0 Attachment A, Automatic Action Verification. The SRO should ensure that performance of this Attachment is continued by the BOP operator, and performed in parallel with EOP-0.

Critical Task: BOP must isolate main feed to the faulted A S/G prior to the S/G level going off-scale high on narrow range level indicator BOP Verify feedwater isolation:

- Feedwater Regulating and Bypass Valves shut -CS 466 is not shut -

per RNO trip both MFPs, place condensate pumps in pull-out and stop heater drain tank pumps

- Both main feed pumps tripped.

- MFP discharge MOVs - BOTH SHUT.

BOP Verify containment isolation:

- CI Panels A and B ALL LIGHTS LIT

- RS-SA-9 SHUT.

- No other valves open under administrative control (SM may be asked to verify this).

BOP Verify AFW Actuation:

- Checks both motor driven AFW pumps running.

BOP Check both SI pumps running.

BOP Check both RHR pumps running.

Op-Test No: 2005301 Scenario No: 4 Event No: 3,4,5 Page 11 of 12 Event -2 Dropped Rods requiring Reactor Trip

==

Description:==

-One A SG Safety Valve fails open, A Non-return valve sticks open and B MSIV sticks open, depressurizing BOTH S/Gs

-A MFP fails to trip on SI/CS-466 MFRV sticks 10% open Time Position Applicants Actions or Behavior BOP Check only one CCW pump running.

BOP Verify Service Water Alignment:

- 6 service water pumps running.

- Service water isolation valves shut.

- Direct AO to locally check SW-LW-61 or SW-LW-62 shut.

BOP Verify Containment Accident Cooling Units Running

- All accident fans running.

- 1SW-2907 & 2908 OPEN.

- Unit 1 Containment Recirc Coolers Water Flow Low Alarm CLEAR.

BOP Check Control Room Ventilation IN ACCIDENT MODE:

- At least one control room recirc fan RUNNING

- Control room damper solenoid valve PURPLE LIGHT LIT BOP Check if Main Steam Lines Can Remain Open.

Should attempt to shut MSIVs if not already done

Op-Test No: 2005301 Scenario No: 4 Event No: 3,4,5 Page 12 of 12 Event -2 Dropped Rods requiring Reactor Trip

==

Description:==

-One A SG Safety Valve fails open, A Non-return valve sticks open and B MSIV sticks open, depressurizing BOTH S/Gs

-A MFP fails to trip on SI/CS-466 MFRV sticks 10% open Time Position Applicants Actions or Behavior BOP Verify proper SI valve alignment:

- Unit 1 SI active status panel ALL LIGHTS LIT

- Unit 1 SI-Spray Ready status panel NO LIGHTS LIT BOP Verify containment spray not required:

- Recognize containment pressure is rising and if > 25 psig perform continuous actions of RNO

- Containment Spray actuated, C01 B 2-6 LIT

- All containment spray discharge valves OPEN

- At least one spray pump running

- Shutdown one train of spray by placing spray pump in PULL-OUT and shutting its associated suction valve.

- After spray has been activated for greater than two minutes, one spray additive valve verified OPEN BOP Verify SI Flow:

- RCS wide range pressure <1400 psig

- Check SI pumps flow indicated

- RCS wide range pressure < [425] 200 psig This ends the steps of EOP-0 Attachment A.

ML060370466

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