Text

11-2006-Final-Operating Exam
	ML063240484
Person / Time
Site:	San Onofre
Issue date:	10/30/2006
From:	; Operations Branch IV
To:	; Southern California Edison Co
References
	50-361/06-301, 50-362/06-301, ES-301, ES-301-1 50-361/06-301, 50-362/06-301
	Download: ML063240484 (319)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: SONGS Date of Examination: 10/23/2006 Examination Level RO Operating Test Number: NRC Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant Conduct of Operations M, R operation (3.9).

JPM: Determine Shutdown Margin (J078A).

2.1.12 Ability to apply technical specifications for a system (2.9).

Conduct of Operations N, R JPM: Verify required flowpath(s) OPERABLE per Technical Specifications (New).

2.2.13 Knowledge of tagging and clearance procedures (3.6).

Equipment Control D, R JPM: Prepare a tagging clearance (J234A).

2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel N, R exposure (2.9).

Radiation Control JPM: Calculate stay time (New).

Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

Type Codes & Criteria: (C)ontrol room (D)irect from bank ( 3 for ROs; for 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams ( 1; randomly selected)

(S)imulator Class(R)oom NUREG-1021, Revision 9

Administrative Topics Outline Task Summary A.1.a The candidate will determine Shutdown Margin by manually performing a calculation given the available conditions. The set of plant conditions will include a CEA anomaly as well as a Xenon transient. The critical task will be to identify the correct Shutdown Margin. This is a modified bank JPM.

A.1.b The candidate will be required to determine the Technical Specification required Boric Acid flowpaths while in Mode 4. The critical task will be to determine the available flowpaths given current plant alignment and OPERABLE equipment. This is a new JPM.

A.2 The candidate will be required to prepare a tagging clearance for the Boric Acid Makeup Pump (2MP174). The critical tasks include identifying the necessary boundaries for the repair. This is a bank JPM.

A.3 The candidate will be required calculate stay time based on a maintenance activity. The critical task requires calculation of total dose with and without shielding for one or two operators performing the task. This is a new JPM.

A.4 N/A NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Facility: SONGS Date of Examination: 10/23/2006 Examination Level SRO(I) & (U) Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note) Code*

2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant Conduct of Operations M, R operation (4.0).

JPM: Determine Shutdown Margin (J078A).

2.1.12 Ability to apply technical specifications for a system (4.0).

Conduct of Operations N, R JPM: Verify required flowpath(s) OPERABLE per Technical Specifications (New).

2.2.22 Knowledge of limiting conditions for operations and safety limits (4.1).

Equipment Control D, R JPM: Perform a Safety Function Determination (J233A).

2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel N, R exposure (3.3).

Radiation Control JPM: Calculate stay time (New).

2.4.41 Knowledge of emergency action level thresholds and classifications (4.1).

Emergency Plan N, R JPM: Classify an emergency event (New).

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

Type Codes & Criteria: (C)ontrol room (D)irect from bank ( 3 for ROs; for 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams ( 1; randomly selected)

(S)imulator Class(R)oom NUREG-1021, Revision 9

Administrative Topics Outline Task Summary A.1.a The candidate will determine Shutdown Margin by manually performing a calculation given the available conditions. The set of plant conditions will include a CEA anomaly as well as a Xenon transient. The critical task will be to identify the correct Shutdown Margin. This is a modified bank JPM.

A.1.b The candidate will be required to determine the Technical Specification required Boric Acid flowpaths while in Mode 4. The critical task will be to determine the available flowpaths given current plant alignment and OPERABLE equipment. This is a new JPM.

A.2 The candidate will perform a Safety Function Determination per SO123-0-A5, Technical Specification LCOARs / EDMRs. The critical tasks include determining the systems and Safety functions affected. This is a bank JPM.

A.3 The candidate will be required calculate stay time based on a maintenance activity. The critical task requires calculation of total dose with and without shielding for one or two operators performing the task. This is a new JPM.

A.4 Loss of Coolant Accident and Loss of Feedwater events are in progress. The candidate will perform an EPIP classification. The critical task is to properly classify the event. This is a new JPM.

NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: SONGS Date of Examination: 10/23/2006 Exam Level (circle one): RO / SRO(I) / SRO (U) Operating Test No.: NRC Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

Type Code* Safety Function System / JPM Title S-1 061 - Auxiliary Feedwater System (J206FS) A, D, S 4-S Verify proper EFAS Actuation S-2 071 - Waste Gas Disposal System (J231S) A, M, S 9 Prepare and release a Waste Gas Decay Tank S-3 006 - ECCS (J050FS) A, D, S 2 Perform HPSI Throttle/Stop S-4 062 - AC Electrical Distribution (J054S) D, S 6 Restore Bus 2A06 from cross-tie operations S-5 004 - Chemical and Volume Control System (New) A, N, S 1 Respond to a dilution accident S-6 003 - Reactor Coolant Pump (J027FS) A, D, L, M, S 4-P Start a Reactor Coolant Pump S-7 026 - Containment Spray System (J049S) D, S 5 Terminate Containment Spray S-8 012 - Reactor Protection System (RO only) (J035S) D, S 7 Set CEAC Inoperable Flag on the Core Protection Calculator In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P-1 062 - AC Electrical Distribution (J018) D, E 6 Restore Offsite Power and transfer EDG control P-2 001 - Control Rod Drive System (J020) M, R 1 Perform actions for a CEDMCS Timer failure P-3 039 - Main and Reheat Steam System (J022) D 4-S Restore the Atmospheric Dump Valve to remote operation NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (L)ow-Power 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator 1/1/1 NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC JPM Examination Summary Description S-1 The candidate will verify EFAS-1 & 2 actuation following a Reactor trip. The alternate path requires that the candidate recognize that the AFW valve alignment is incorrect and re-aligns per SO23 2.22, ESFAS System Operation. This is a bank JPM under the Auxiliary Feedwater System -

Secondary System Heat Removal from Reactor Core safety function. This is a PRA significant action. This meets the ESF function for the SRO upgrade.

S-2 The candidate will align and commence a Waste Gas Release. The alternate path will require closing of the flow control valve when the radiation monitor goes into alarm. This is a modified JPM under the Waste Gas Disposal System - Radioactive Release safety function.

S-3 The candidate will initiate HPSI throttle / stop per SO23-12-11, EOI Supporting Attachments. The alternate path requires manual actions to restore HPSI flow once throttling is complete because the throttle / stop criteria are no longer met. This is a bank JPM under the Emergency Core Cooling System - Reactor Coolant System Inventory Control safety function.

S-4 The candidate must restore Bus 2A06 from cross-tie operations to the Reserve Auxiliary Transformer 2XR2. This is a bank JPM under the AC Electrical Distribution - Electrical Systems safety function.

S-5 The candidate will respond to an inadvertent dilution per SO23-13-11, Inadvertent Dilution or Boration. The alternate path is performed when it is determined that the Letdown Heat Exchanger outlet temperature is not being maintained at 120ºF. This is a new JPM under the Chemical and Volume Control System - Reactivity Control safety function. This is a PRA significant action.

S-6 The candidate will start a Reactor Coolant Pump. The alternate path requires an RCP trip upon receipt of abnormal RCP conditions. This is a modified JPM under the Reactor Coolant Pump -

Primary System Heat Removal from the Reactor Core safety function.

S-7 The candidate will perform actions to terminate Containment Spray per SO23-12-11, EOI Supporting Attachments. This is a bank JPM under the Containment Cooling System -

Containment Integrity safety function.

S-8 The candidate must set the CEAC Inoperable Flag on the Core Protection Calculator. This is a bank JPM under the Reactor Protection System - Instrumentation safety function.

P-1 The candidate will shutdown the Emergency Diesel Generator and transfer EDG control following a Control Room evacuation. This is a bank JPM under the AC Electrical Distribution - Electrical Systems safety function.

P-2 The candidate will perform actions for a CEDMCS Timer failure alarm SO23-15-50.A2. This is a modified JPM under the Control Rod Drive System - Reactivity Control safety function.

P-3 The candidate will restore the Atmospheric Dump Valve to remote operation per SO23-3-2.18.1, Local Manual Operation of the Atmospheric Dump Valves. This is a bank JPM under the Main and Reheat Steam System - Secondary System Heat Removal from Reactor Core safety function.

NUREG-1021, Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: San Onofre Scenario No.: 1 Op Test No.: NRC Examiners: Operators:

Initial Conditions: * ~98.7% power - RCS Boron is 1542 ppm by Chemistry Sample

Train A Component Cooling Water Pump (P-025) in service

Train A Charging Pump (P-190) OOS

Train A Saltwater Cooling Pump (P-307) OOS

Train A Low Pressure Safety Injection Pump (P-015) OOS

Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Maintain steady-state power conditions..

Critical Tasks:

Restore feedwater flow to one Steam Generator.

Restore power to 4 kV Bus A03 and/or A07.

Event No. Malf. No. Event Type* Event Description 1 Security Warning from the Security Shift Commander.

+ 5 min 2 CV22B C (CO, CRS) Charging Pump P-191 trip.

+15 min TS (CRS) 3 RC16B I (CO, CRS) Pressurizer Level Control Channel fails high (LT-0110-2).

+25 min TS (CRS) 4 CV16B I (CO, CRS) Volume Control Tank Level Instrument fails low (LT-0227).

+35 min 5 FW11 C (ACO, CRS) Condensate Pump P-050 overcurrent trip.

+40 min 6 ED04A M (ALL) Bus 2A03 overcurrent trip.

+45 min FW23 Loss of Condenser vacuum (+2 min post-trip).

Loss of Main Feedwater.

7 Bus 2A07 C (ACO) Bus 2A07 fails to transfer upon Unit trip.

+45 min XFR LP 8 FW02A C (ACO) Aux. Feedwater Pump P-141 shaft seizure (+2 min post-trip).

+45 min FW02B Aux. Feedwater Pump P-504 shaft seizure (+2 min post-trip).

FW25 Aux. Feedwater Pump P-140 overspeed trip (+1 min post-trip).

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specifications Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 SCENARIO

SUMMARY

NRC #1 The crew will assume the shift and maintain steady-state conditions per SO23-5-1.7, Power Operations.

The scenario will begin with the crew receiving a security warning from the Security Shift Commander and will enter Abnormal Operating Instruction (AOI) SO23-13-25, Operator Actions During Security Events. The crew will be required to perform security actions for a credible insider threat.

When the security event actions are complete, Charging Pump P-191 will trip and be addressed per the Annunciator Response Procedures (ARPs) and SO23-3-2.1, Chemical and Volume Control System Operations. The CRS will evaluate Technical Specifications.

After the crew has stabilized the plant, a Pressurizer Level instrument fails high and will require crew actions per the ARPs and AOI SO23-13-27, Pressurizer Pressure and Level Malfunction.

The CRS will evaluate Technical Specifications.

When the plant is stable, the VCT Level Transmitter (LT-227) will fail low. The crew will secure Charging and Letdown per the ARPs and SO23-3-2.1, CVCS Charging and Letdown Operations and/or SO23-3-2.2, Makeup Operations. The Control Operator will manually operate the Charging Pumps to control Pressurizer level.

When plant conditions are stable, a Condensate Pump will trip and the standby pump will fail to auto start. The crew will respond per the Annunciator Response Procedures.

The major event begins with a loss of Bus 2A03 and total loss of vacuum. This will require a plant trip due to a loss of Main Feedwater flow. The crew will enter SO23-12-1, Standard Post Trip Actions. This is followed by a total loss of feedwater that will necessitate entry into SO23 6, Loss of Feedwater. The ACO will be required to manually transfer Bus 2A07 during post-trip SPTAs.

Event termination will occur when Bus 2A07 power is restored and the Steam Generators are depressurized sufficiently to allow the remaining Condensate Pumps to supply feedwater flow.

Risk Significance:

Risk important components out of service: Charging P-190, LPSI P-015, SWC P-307

Risk significant core damage sequence: Loss of all feedwater

Risk significant operator actions: Depressurize and restore feedwater flow to at least one SG Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: San Onofre Scenario No.: 2 Op Test No.: NRC Examiners: Operators:

Initial Conditions:

70% power - RCS Boron is 1619 ppm by Chemistry sample

Train A Component Cooling Water Pump (P-025) in service

Train A Charging Pump (P-190) OOS

Train A Saltwater Cooling Pump (P-307) OOS

Train A Low Pressure Safety Injection Pump (P-015) OOS

Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Holding at 70% power.

Critical Tasks:

Restore flow to the CCW Non-Critical Loop (RCPs operating).

Trip any RCP not satisfying RCP operating limits.

Stabilize RCS temperature/pressure following loss of heat removal from the faulted SG.

Manually Trip the Reactor (RPS Failure).

Event No. Malf. No. Event Type* Event Description 1 CC03A C (ACO, CRS) Component Cooling Water Train A header ruptures at the SDC

+10 min TS (CRS) Heat Exchanger.

2 RC11A I (CO, ACO Reactor Coolant System Loop 1 Thot fails high (TT-0111X1).

+20 min CRS) 3 SG06A C (CO, CRS) Steam Generator tube leak on E-088 requiring plant shutdown.

+30 min TS (CRS) 4 R (CO) Rapid Power Reduction.

+45 min N (ACO, CRS) 5 SG06A M (ALL) Steam Generator Tube Rupture on E-088.

+50 min 6 RP03 C (ACO) Auto and manual Reactor trip failure (ATWS).

+50 min 7 MS03B M (ALL) Excess Steam Demand Event on E-089 inside Containment

+50 min (5 minutes post-trip).

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specifications Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 SCENARIO

SUMMARY

NRC #2 The crew will assume the watch maintaining steady state power per SO23-5-1.7, Power Operations.

When turnover is complete a Train A Component Cooling Water header rupture is initiated. The crew will respond per SO23-2-17, Component Cooling System Operation and/or Abnormal Operating Instruction (AOI) SO23-13-7, Loss of Component Cooling Water (CCW) / Saltwater Cooling (SWC). The crew will align SWC & CCW Train B per pump configuration requirements.

The ruptured header will be removed from service. The CRS will evaluate Technical Specifications.

When the CCW and SWC systems are properly aligned, a Thot instrument fails high and will require crew actions per the ARPs, Operating Instruction SO23-3-1.10, Pressurizer Pressure and Level Control and Abnormal Operating Instruction (AOI) SO23-13-27, Pressurizer Pressure and Level Malfunction.

With the plant in a stable condition, a Steam Generator tube leak will commence on E088. The crew will enter AOI SO23-13-14, Reactor Coolant System Leak and the CRS will be required to evaluate Technical Specifications. The CRS will determine that a rapid plant shutdown per the AOI is required.

When the crew has demonstrated adequate control of the downpower, the leak size will increase to that of a SGTR and be accompanied by an ATWS. The crew will respond to the ATWS by opening breakers to Buses B15 and B16. Five minutes later, an ESDE inside Containment will occur. The crew performs SO23-12-1, Standard Post Trip Actions and diagnoses an ESDE and a SGTR and transitions to SO23-12-9, Functional Recovery.

The scenario is terminated when RCS temperature and pressure are stabilized while in the Functional Recovery procedure and associated Floating Steps.

Risk Significance:

Risk important components out of service: Charging P-190, LPSI P-015, SWC P-307

Failure of risk important system prior to trip: CCW Header Rupture

Risk significant core damage sequence: SGTR and ESDE

Risk significant operator actions: Manually trip Reactor on ATWS Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: San Onofre Scenario No.: 3 Op Test No.: NRC Examiners: Operators:

Initial Conditions: * ~98.7% power - RCS Boron is 1542 ppm by Chemistry Sample

Train A Component Cooling Water Pump (P-025) in service

Train A Charging Pump (P-190) OOS

Train A Saltwater Cooling Pump (P-307) OOS

Train A Low Pressure Safety Injection Pump (P-015) OOS

Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Maintain steady-state power conditions.

Critical Tasks:

Restore flow to the CCW Non-Critical Loop (RCPs operating).

Establish minimum design SI flow rate.

Trip any RCP not satisfying RCP operating limits.

Event No. Malf. No. Event Type* Event Description 1 CC06B C (ACO, CRS) CCW Pump P-025 trip.

+5 min TS (CRS) 2 CV16A I (CO, CRS) VCT Level Instrument fails low (LT-0226).

+15 min 3 RD0403 C (CO, CRS) Dropped CEA #4.

+35 min TS (CRS) 4 R (CO) Downpower due to dropped CEA.

+45 min N (ACO, CRS) 5 FC05B I (ACO, CRS) Steam Generator E-088 Master Controller Setpoint failure.

+50 min 6 RC01C M (ALL) Large break LOCA.

+60 min 7 RP01E C (CO) LPSI Pump P-016 fails to start.

+60 min

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specifications Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 SCENARIO

SUMMARY

NRC #3 The crew will assume the shift and maintain steady-state conditions per SO23-5-1.7, Power Operations.

When turnover is complete a CCW Pump will trip. The crew will respond per AOI SO23-13-7, Loss of Component Cooling Water (CCW) / Saltwater Cooling (SWC). The crew will align SWC &

CCW Trains per pump configuration requirements. The CRS will evaluate Technical Specifications.

When the plant is stable, the VCT Level Transmitter (LT-226) will fail low. The crew will secure VCT makeup per the Annunciator Response Procedures and SO23-3-2.1, CVCS Charging and Letdown Operations. The RCS Makeup Control System will then be aligned for manual blended makeup mode.

A dropped control rod follows the transmitter failure. The crew will respond and stabilize the primary plant using Annunciator Response Procedures (ARP) and Abnormal Operating Instruction (AOI) SO23-13-13, Dropped or Misaligned CEA. The CRS will evaluate Technical Specifications. The CEA is not recoverable and a down power will be conducted per the AOI.

When the plant is stable, a Master Controller Setpoint will fail to 58% level. The crew will regain control of feedwater per Annunciator Response Procedures and/or AOI SO23-13-24, Feedwater Malfunctions.

The next event is a large break LOCA. The crew will determine that a plant trip is required and enters SO23-12-1, SPTAs, then SO23-12.3, Loss of Coolant Accident (LOCA). A LPSI Pump failure will require the operator to manually start the LPSI Pump.

Scenario is terminated when plant conditions are stable.

Risk Significance:

Risk important components out of service: Charging P-190, LPSI P-015, SWC P-307

Failure of risk important system prior to trip: CCW Pump trip

Risk significant core damage sequence: Large break LOCA with loss of LPSI

Risk significant operator actions: Restore the Non-Critical Loop Start a LPSI Pump Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: San Onofre Scenario No.: 4 Op Test No.: NRC spare Examiners: Operators:

Initial Conditions:

Reactor Critical at ~3x10-4% power - RCS Boron is 1342 ppm by Chemistry Sample

Train A Component Cooling Water Pump (P-025) in service

Train A Saltwater Cooling Pump (P-307) OOS

Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Power increase in progress to ~2% power.

Critical Tasks:

Restore flow to the CCW Non-Critical Loop (RCPs operating).

Restore power to at least one 1E 4kV Bus.

Establish Reactivity Control (> 2 FLCEAs Not Fully Inserted & No SIAS).

Event No. Malf. No. Event Type* Event Description 1 R (CO) Rod withdrawal and power increase in progress to ~2% power.

+15 min N (ACO, CRS) 2 RC15B I (CO, CRS) Pressurizer Pressure Control Channel fails high (PT-0100Y).

+25 min TS (CRS) 3 ED08B C (CO, ACO, Loss of Non-1E Instrument Bus Q0612.

+35 min CRS) 4 ED03A C (ACO, CRS) Bus 2A04 Overcurrent lockout.

+45 min TS (CRS) 5 PG24 M (ALL) Loss of Offsite Power.

+50 min 6 EG08B C (ACO) Emergency Diesel Generator 2G003 mechanical failure.

+50 min Station Blackout 7 RD8802 C (CO) Four fully stuck CEAs; Loss of Reactivity Control.

+50 min RD8902 RD9002 RD9102

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 SCENARIO

SUMMARY

NRC #4 The crew will assume the watch with the Reactor critical at ~3x10-4% power. The crew will raise power using rod withdrawal per SO23-5-1.3.1, Plant Startup from Hot Standby to Minimum Load.

After the crew has demonstrated control of the power change, a Pressurizer Pressure instrument fails high and will require crew actions per the Annunciator Response Procedures (ARPs) and Abnormal Operating Instruction (AOI) SO23-13-27, Pressurizer Pressure and Level Malfunction. The CRS will evaluate Technical Specifications.

After the crew has restored the Pressurizer Pressure instrument, a loss of Non-1E Instrument Bus Q0612 will occur and require crew actions per the ARPs and AOI SO23-13-19, Loss of Non-1E Instrument Buses.

With Letdown restoration in progress, a bus fault and lockout will occur on Bus 2A04. The crew will refer to SO23-13-26, Loss of Power to an AC Bus. The CRS will evaluate Technical Specifications.

Once the decision to shutdown is made, a Loss of Offsite Power will occur. The Reactor will trip and the crew will perform SO23-12-1, Standard Post Trip Actions. EDG 2G003 will trip. Four rods remain stuck out of the core requiring manual boration alignment on the part of the CO in preparation for Bus 2A06 power restoration.

The crew diagnoses a Loss of Reactivity Control due to a Station Blackout and enters SO23 9, Functional Recovery. The success path will require cross-tying power with Unit 3 and establishing a boration flowpath.

The scenario is terminated when Bus 2A06 is energized and boration at greater than 40 gpm is established.

Risk Significance:

Risk important components out of service: SWC P-307

Failure of risk important system prior to trip: Loss of Vital Inverter

Risk significant core damage sequence: SBO with Loss of Reactivity Control

Risk significant operator actions: Vital AC power restoration Establish boration flowpath Appendix D NUREG 1021 Revision 9

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO/SRO NRC JPM A.1.a INITIAL PLANT CONDITIONS Unit 2 is in MODE 3 following a Reactor trip from full power 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ago. The Unit was at full power for 25 EFPD.

Conditions are as follows:

Core life is BOC, 50 EFPD per Reactor Engineering.

RCS Boron Concentration is 2600 ppm via the Boronometer.

Tave is 545°F and three RCPs are running.

All CEAs are fully inserted except for CEA #44 which is untrippable and fully withdrawn.

No correction factors have been provided by Reactor Engineering for B-10 depletion.

Use OPS Table 4.4 for CEA Worths.

TASK TO BE PERFORMED The Shift Manager directs you to perform a Shutdown Margin calculation using SONGS Unit 2 Cycle 14 Operations Physics Summary Data, Revision 51 and SO23-3-3.29, Determination of Reactor Shutdown Margin.

Page 1 of 9

JOB PERFORMANCE MEASURE SONGS RO/SRO NRC JPM A.1.a SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X CLASSROOM X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR CLASSROOM ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 9

DOCUMENTATION SONGS RO/SRO NRC JPM A.1.a JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 188318 TASK DESCRIPTION Calculate the actual shutdown margin with the reactor subcritical.

KA NUMBER: 001 A4.11 KA VALUES: RO 3.5 SRO 4.1 10CFR55.45 APPLICABILITY: 4, 12

REFERENCES:

SO23-3-3.29, Determination of Reactor Shutdown Margin, Rev. 18.

M38100, Operations Physics Summary, Unit 2, Cycle 14, BOC, Rev. 51.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 2 Compared against SO23-3-3.29, LRZ 06/30/00 WLL Rev. 14. Made modifications for MOC Cycle worths.

2-1 Compared against SO23-3-3.29, RCW 11/19/03 FM Rev. 16 and M38100, Rev. 46. Added M38100 as a reference. Updated required parameter values to reflect current revision of references.

Changed core burnup to 210 EFPD to more clearly indicate MOC time in life.

2-2 Converted to an ADMIN JPM. RCW 09/29/04 MRN 2-3 Compared against SO23-3-3.29, LRZ 02/28/05 AHH Rev. 16-1 and M38100, Rev. 49.

Modified JPM by changing boron concentration and core burnup to arrive at new critical boron concentration. Made modifications for MOC Cycle worths.

3 Compared against SO23-3-3.29, LRZ 09/08/05 REV Rev. 16-1 and M38100, Rev. 49 and modified initial conditions to generate a different Shutdown Margin.

4 Compared against SO23-3-3.29, LRZ 08/08/06 REV Rev. 18 and M38100, Rev. 51 and modified all initial conditions to generate a different Shutdown Margin.

Page 4 of 9

SET-UP EXAMINER:

NOTE: This JPM was validated using M-38100, Operations Physics Summary, Unit 2, Cycle 14, BOC, Rev. 51.

Provide examinee with a copy of SO23-3-3.29, Determination of Reactor Shutdown Margin and M-38100, Operations Physics Summary, Unit 2, Cycle 14, BOC, Rev. 51.

Page 5 of 9

JPM: SONGS RO/SRO NRC JPM A.1.a TITLE: Perform a Shutdown Margin Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the examinee with a copy of SO23-3-3.29, Determination of Reactor Shutdown Margin and the Operations Physics Summary, Unit 2, Cycle 14, BOC, Rev. 51.

1 Complete Step 1.0, Prerequisites of COMPLETE Step 1.0, Prerequisites of S023- Start Time: ________

S023-3-3.29, Attachment 2. 3-3.29, Attachment 2.

2 Record present RCS boron RECORD present RCS boron concentration of concentration. 2600 ppm via Boronometer.

3 Record present RCS Tavg. RECORD RCS Tavg of 545ºF.

4 Record present cycle burnup. RECORD present cycle burnup of 50 EFPD.

5 Calculate the adjusted critical boron CALCULATE the adjusted critical boron concentration for potential reactivity concentration from OPS Fig. 2.2-1 and ADD bias. 150 ppm for B-10 depletion.

2000 ppm (CBC @ 50 EFPD)

+ 150 ppm (Correction Factor)

= 2150 ppm (Adjusted CBC) 6 Calculate the critical boron margin. CALCULATE the critical boron margin.

2600 ppm (Present Boron)

- 2150 ppm (Adjusted CBC)

= + 450 ppm (CB Margin)

Page 6 of 9

JPM: SONGS RO/SRO NRC JPM A.1.a TITLE: Perform a Shutdown Margin Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 7 Determine the inverse boron worth for DETERMINE the inverse boron worth from the present RCS Tavg and boron OPS Figure 3.3.

concentration. 144 ppm / % K/K 8 Calculate the boron reactivity defect. CALCULATE the boron reactivity defect.

450 ppm / 144 ppm / % K/K =

+ 3.125% K/K 9 Determine Total CEA worth: (Use data DETERMINE Total CEA worth from OPS listed for ARI condition.) Table 4.4 for ARI condition.

Total CEA Worth = 7.944% K/K 10 Determine Net CEA worth: (Use data DETERMINE Net CEA worth from OPS listed for ARI-WRSO condition.) Table 4.4 for ARI-WRSO condition.

Net CEA Worth = 7.535% K/K 11 Determine Available CEA Worth with DETERMINE Available CEA Worth with an an inoperable (untrippable) CEA, from inoperable (untrippable) CEA.

ONE of the following: Total CEA Worth = 7.944% K/K 1 CEA Inoperable (untrippable). - Stuck Pair Worth = 1.553% K/K

= Available CEA Worth = 6.391% K/K 12 Determine the withdrawn CEA worth. DETERMINE the withdrawn CEA worth to be zero.

Withdrawn CEA Worth = 0% K/K 13 Determine the Xenon worth based on DETERMINE the Xenon worth using OPS present cycle burnup and Xenon decay Table 7.1.

time. Xenon Worth = 1.492% K/K Page 7 of 9

JPM: SONGS RO/SRO NRC JPM A.1.a TITLE: Perform a Shutdown Margin Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 14* Calculate actual Shutdown Margin. CALCULATE actual Shutdown Margin.

3.125% K/K + 6.391% K/K + 1.492% K/K =

11.008 +/- 0.1 % K/K 15* Calculate percent shutdown of the CALCULATE percent shutdown of the Reactor. Reactor.

3.125% K/K + 1.492% K/K + 7.944% K/K +

0.0% K/K + =

12.561 +/- 0.1 % K/K 16* Determine the actual Shutdown Margin DETERMINE the actual Shutdown Margin is is greater than or equal to 5.15% K/K greater than 5.15% K/K for Mode 3 and in Mode 3. circles YES.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 8 of 9

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 9 of 9

&)(wrdW CWY p)?dwd%L=v N U C - E A R ORGANIZATI3N S U R V E I L L A N C E O P E R A T I N G INZTRUCTION 8023-3-3.29 UNITS 2 AN@ 3 R E V I S I O N 18 PAGE 1 2 OF 31 ATTACdMENT i CALCULATION OF ACTUAL SHUTDOWN MARGIN - MODES 3-6 CONTINUOUS USE OBJECTIVE To c a l c u l a t e actual S h u t d o w n Margin, Projected SDM a t some f u t u r e time taking i n t o account variable conditions (Xenon buildup and decay, e t c ) , or SDM t o meet Source Range Inoperabil i t y .

UNIT 3 MODE 3 DATE 7-D TIME k)od 1.0 PREREOUISITES P E R F . BY IN IT1ALS 1.1 Verify t h i s document i s current by checking a controlled copy or by u s i n g t h e method described i n SO123-VI-0.9.

1.2 Determine use o f t h i s SDM Calculation:

A c t u a l SDM 0 Projected SDM a t some f u t u r e time taking i n t o account variable conditions; i . e . , Xenon buildup and decay, e t c .

SDM t o meet Source Range I n o p e r a b i l i t y (LCO 3.3.13.A.2)

[Requires S h i f t l y RCS Boron Samples].

1.3 Determine a p p l i c a b i l i t y f o r Xenon Worth determination: 44-33 SRO 011s.

supv -

NOTE When c r e d i t i s taken f o r Xenon r e a c t i v i t y , then t h i s attachment f i l d be performed every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Less t h a n 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months has elapsed since the trip or s t a r t of power reduction, a n d c r e d i t i s t o be taken f o r Xenon.

a Greater t h a n 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months has elapsed s i n c e t h e t r i p or power reduction, or f o r conservatism, no c r e d i t i s t o be taken f o r Xenon.

ATTACHMENT 2 PAGE 1 OF 11 123-3-3.29

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION S O 2 3 3.29 U N I T S 2 AND 3 R E V I S I O N 18 PAGE 13 OF 3 1 ATTACHMENT 2 1.0 PREREQUISITES (Cont inued) PERF. BY I N I T 1ALS 1.4 Indicate CEA position: 3 J POSITION ACTION A L L CEAs fully Mark N/A Steps 2.6.2 a n d 2.6.3.

inserted One or more CEAs NONE NOT f u l l y inserted 1.5 J POSITION ACTION A L L CEAs are Mark N/A Step 2.6.3.

Operable (trippabl e)

One or more CEAs NONE

/ are Inoperable (untrippabl e )

1.6 Verify a l l steps in Section 1.0 are complete, and a l l steps i n Section 2.0 required t o be marked N/A, are c o r r e c t l y marked N/A.

q 5RO Ops.

supv.

END OF SECTION 1.0 ATTACHMENT 2' PAGE 2 OF 11 123-3-3.29

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SOB-3-3.29 UNITS 2 AND 3 REVISION 18 PAGE 14 OF 31 ATTACHMENT 2 2.0 PROCEDURE PERF. BY INITIALS NOTES Bracketed [steps] may use a value supplied by Reactor Engineering

( R E ) . RE values s h a l l be supplied t o Operations using SO23-XXXVII-13, Section f o r Reactor Engineering Data Transmittal, and a copy of t r a n s m i t t a l cover sheet affixed t o t h i s calculation.

Guidelines for t h e use o f Core Physics d a t a i s provided in Step 6 . 3 . 1 of the m a i n body.

2.1 Record the following d a t a :

2.1.1 Record present RCS Boron concentration:

Boronometer (per main body Step 6.3.4 g u i del i nes)

Chemical Analysis. (If verifying SDM f o r Source Ran e Inope a b i l i t y , then sample must be every 17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months .!

Sample Date T i me Present RCS Boron Concentration P Pm 2.1.2 Record present RCS average temperature (per mai n body Step 6 . 3 . 3 g u i del i nes) :

RCS Tavg 575 "F E2.1.31 Record present cycle b u r n u p and i n d i c a t e source:

Latest computer data NCO Log entry ij?J Reactor Engineering EFPD 5@

ATTACHMENT 2 PAGE 3 OF 11 123-3-3.29

NUCLEAR ORGANIZATION S U R V E I LLANC E 0 P E RAT I NG INSTRUCT I ON 5023-3-3.29 UNITS 2 AND 3 REVISION 18 PAGE 15 OF 31 ATTACHMENT 2 2.0 PROCEDURE (Continued) PERF. BY INITIALS

[2.2] Determine the adjusted Critical Boron Concentration (CBC) for the present cycle burnup using the appl icab1 e source:

G UIDELINES

1) OPS CBC figures are based on ARO, no Xe, equilibrium Sm.

2) Lf the RCS temperature i s between the temperatures o f 2 curves from OPS Figures 2 . 2 - 1 through 2 . 2 - 4 , then the curve with t h e higher c r i t i c a l Boron concentration should be used.

3) If above 545"F, then use t h e 545°F curve.

E2.2.11 Calculate adjusted CBC f o r p o t e n t i a l Reactivity Bias/Boron-10 depletion, as follows: (Use 150 ppm as t h e correction f a c t o r f o r Boron-10 depletion or a c o r r e c t i o n f a c t o r provided by Reactor Engineering.) [Ref. 2.4.3.31 PPm + P Pm CBC Correction Adjusted CBC (OPS F i g 2 . 2 ) Factor 2.3 Calculate the critical Boron margin:

PPm -

Present RCS Adjusted C B C Boron Conc ( s t e p 2.2.1)

(Step 2.1.1)

C r i t i c a l Boron Margin ATTACHMENT 2 PAGE 4 OF 11 123-3-3.29

NUCLEAR O R G A N I Z A T I O N SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.29 UNITS 2 AND 3 R E V I S I O N 18 PAGE 1 6 OF 3 1 ATTACHMENT 2 2.0 PROCEDURE (Continued) PERF. BY INITIALS

[2.4] Determine the inverse Boron worth for the present RCS Tavg and Boron concentration:

GUIDELINE Boron c o n c e n t r a t i o n s w h i c h do n o t c o i n c i d e w i t h t h e OPS c u r v e s s h o u l d be i n t e r p o l a t e d ; fi l e s s t h a n t h e l o w e s t curve, then use t h e l o w e s t c u r v e , if above t h e h i g h e s t c u r v e , then use t h e h i g h e s t c u r v e .

Data Source RE a OPS F i g u r e 3.3 I n v e r s e Boron Worth 3 ppm/%iiK/K 2 . 5 Calculate the Boron reactivity defect:

C r i t i c a l Boron M a r g i n I n v e r s e Boron Worth P Pm - ppm/%nK/K =

(Step 2.3) ( S t e p 2.4)

Boron D e f e c t 3. ~ z - J % ~ K / K e)

END OF S E C T I O N 2.5 ATTACHMENT 2 PAGE 5 OF 11 123-3-3.29

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3 2 9 U N I T S 2 AND 3 REVISION 18 PAGE 17 OF 3 1 ATTACHMENT 2 2.0 PROCEDURE (Continued) PERF. BY I N I T IALS

[2.6] Determine CEA w o r t h f o r t h e present Tavg and RCS Boron concentration:

GUIDELINE I f Tavg i s >545OF, then u s e CEA w o r t h a t 545°F.

2.6.1 D e t e r m i n e T o t a l CEA Worth:

(Use d a t a l i s t e d f o r A R I c o n d i t i o n . )

D a t a Source 113 RE OPS T a b l e 4.4 111 OPS F i g u r e 4.3 T o t a l CEA Worth 7.?YY%nK/K 2.6.2 D e t e r m i n e N e t CEA Worth:

(Use d a t a l i s t e d f o r ARI-WRSO c o n d i t i o n . )

D a t a Source [23 RE H O P S T a b l e 4.4

[23 OPS F i g u r e 4.3 N e t CEA Worth 7.S3s%nK/K 2.6.3 D e t e r m i ne Avai 1ab1 e CEA W o r t h w i t h an i n o p e r a b l e

( u n t r i p p a b l e ) CEA, f r o m ONE o f t h e f o l l o w i n g :

L7 2 o r more CEAs a r e I n o D e r a b l e ( u n t r i o o a b l e ) :

" A v a i l a b l e CEA W o r t h " 0.0 %nK/K

( c o n s e r v a t i v e l y , n o CEA c r e d i t i s t a k e n f o r SDM.)

1 CEA I n o p e r a b l e ( u n t r i m a b l e ) :

T o t a l CEA Worth %nK/K (OPS T a b l e 4.4) ( S t e p 2.6.1)

- (Minus)

S t u c k P a i r Worth /+553 %nK/K

= Available CEA Worth 6.34k %nK/K A v a i l a b l e CEA Worth p r o v i d e d b y R E Data t r a n s m i t t a l #

" A v a i l a b l e CEA Worth" %nK/K ATTACHMENT 2 PAGE 6 OF 11 123-3-3.29

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION 5023-3-3.29 U N I T S 2 AND 3 R E V I S I O N 18 PAGE 18 OF 3 1 ATTACHMENT 2 2.0 PROCEDURE (Continued) PERF. BY IN I T 1ALS P 71 D e t e r m i n e t h e w i t h d r a w n CEA w o r t h :

GUiDELiNE I f all CEAs a r e f u l l y i n s e r t e d , then record Withdrawn CEA Worth as zero, mark N/A f o r remaining d a t a spaces.

Data Source 0 RE IL] OPS Table 4 . 1 f o r Shutdown Banks, and Figure 4.4 f o r t h e Regulating Groups Banks Withdrawn md3&

Bank A CEAs Bank B CEAs Regul a t i ng Groups

@ %r\K/K + %nK/K + %nK/K =

Withdrawn CEA Worth %nK/K END OF SECTION 2.7 ATTACHMENT 2 PAGE 7 OF 11 323-3 2 9

N U C L E A R ORGANIZATION SURVEILLANCE O P E R A T I N G INSTRUCTION SO23-3-3.29 UNITS 2 AND 3 REVISION 18 PAGE 19 OF 31 ATTACHMENT 2 2.0 PROCEDURE (Conti nued) P E R F . BY I N I TI ALS

[2.8] Determine the Xenon worth based on present cycle burnup and Xenon decay time:

GUIDELINE If no c r e d i t i s being taken f o r Xenon ( s e e Step 3 . 3 ) , then record Xenon worth as zero, mark N/A for remaining d a t a spaces.

Elapsed time since t r i p or s t a r t o f power descension: 3 hours RX power level p r i o r t o trip or s t a r t o f power descension (per main body Step 6 . 3 . 2 g u i d e l i n e s ) : % power NOTES I n order t o use OPS Table 7 . 1 , o f the following conditions must be met. Otherwise, RE will provide the Xenon value or Xenon value can be obtained from COLSS (Primary or B a c k u p ) using t h e Xenon Calculator:

1) Equilibrium Xenon existed a t the above recorded previous power level.

2) The previous power level was g r e a t e r t h a n 95%.

3) The method o f shutdown was a plant t r i p .

Data Source RE Xenon Calculator pJi OPS Table 7 . 1 Xenon Worth %nK/K ATTACHMENT 2 PAGE 8 OF 11 123-3 2 9

NUCLEAR ORGANIZATION SURVEILLANCE O P E R A T I N G INSTRUCTION SO23-3-3.29 UNITS 2 AND 3 REVISION 18 PAGE 20 OF 31 ATTACHMENT 2 2.0 PROCEDURE (Continued) PERF. BY INITIALS 2 . 9 Calculate Shutdown Margin: (Tech Specs SR 3.1.1.1, SR 3 . 1 . 1 . 2 , SR 3 . 1 . 2 . 1 , and LCO 3.3.13.A.2, LCS 3.1.107, LCS 3.1.108)

GUIDELINES Equilibrium Samarium (Sm) concentration i s included i n the C r i t i c a l Boron Curves. Transient Sm r e a c t i v i t y i s always

> t r a n s i e n t Plutonium (Pu) r e a c t i v i t y ; therefore i t i s conservatively ignored in t h e calculation o f SDM. (Ref. 2.4.3.2)

When summing the following r e a c t i v i t y d e f e c t s , then t h e c o r r e c t sign must be used f o r Boron Defect.

I f a l l CEAs a r e f u l l y i n s e r t e d , then Total CEA Worth s h a l l be used.

I f any C E A i s withdrawn, a l l CEAs a r e Operable, then Net CEA Worth shall be used.

I f any CEAs a r e untrippable, then Available CEA Worth s h a l l be used.

Total /Net/Avai 1 ab1 e

( C i r c l e One)

Boron Defect C E A Worth Xenon Worth Shutdown Margin !/-mg' '&K/K 2 . 1 0 Calculate percent shutdown o f the Reactor:

(Tech Specs SR 3.1.1.1, SR 3.1.1.2, SR 3.1.2.1, and LCO 3.3.13.A.2, LCS 3.1.107, LCS 3.1.108)

NOTE Percent S h u t d o w n i s the actual amount o f r e a c t i v i t y by which t h e Reactor i s s u b c r i t i c a l i n i t s present condition.

Boron Xenon Total Withdrawn Defect Worth CEA Worth CEA Worth 2 0.B Percent S h u t d o w n ( 2 . W %nK/K 2.11 Data Values a n d Calculations f o r Section 2.0 Verified by:

ATTACHMENT 2 P A G E 9 OF 11 123-3-3.29

NUCLEAR ORGANIZATION SURVEILLANCE O P E R A T I N G INSTRUCTION 8023-3-3.29 UNITS 2 AND 3 R E V I S I O N 18 PAGE 2 1 OF 31 ATTACHMENT 2 3.0 ACCEPTANCE CRITERIA PERF. BY INITIALS 3.1 SDM c a l c u l a t i o n f o r "ACTUAL Shutdown M a r g i n " "PROJECTED Shutdown M a r g i n " i n S t e p 2.9 i s : (Tech Specs SR 3.1.1.1, S R 3.1.1.2, SR 3 . 1 . 2 . 1 , LCO 3.3.13.A.2, LCS 3.1.107, and LCS 3.1.108) d MODE SDM %nKIK SHUTDOWN MARGIN SATISFIED r -

r 4 -> 5.15%

NO I

5 ( U n i t 2) - 3.5%

6 'r 5.3% I I 3.1.1 -

I f NO f o r "ACTUAL Shutdown M a r g i n " , then: I 0 Emergency b o r a t e p e r SO23-13-11 0 NOTIFY SRO. OPS. SUPV.

0 R e f e r t o Tech. Spec. LCO 3.1.1, LCO 3.1.2, LCO 3.3.13, LCO 3 . 9 . 1 , LCS 3.1.107, and LCS 3.1.108 as a p p l i c a b l e 0 I N I T I A T E AR/LCOAR/EDMR as r e q u i r e d 0 INDICATE a c t i o n s t a k e n i n t h e Comments s e c t i o n 3.1.2 -

I f NO f o r "PROJECTED Shutdown M a r g i n " , t h e n :

0 R e f e r t o Tech. Spec. LCO 3.1.1, LCO 3.1.2, LCS 3.1.107, and LCS 3.1.108 as a p p l i c a b l e 0 I n d i c a t e a c t i o n t a k e n i n t h e Comments s e c t i o n END OF SECTION 3.0 ATTACHMENT 2 PAGE 10 OF 11

)23-3-3.29

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.29 U N I T S 2 AND 3 R E V I S I O N 18 PAGE 22 OF 3 1 ATTACHMENT 2 3 .O ACCEPTANCE C R I T E R I A (Continued)

COMMENTS :

PERF. BY INITIALS Attachment completed / and l o g entry made.

DATE TIME NCO NOTE 1

-I f c r e d i t f o r Xenon r e a c t i v i t y was taken (Step l . Z ) , then t h i s attachment should be performed every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

REVIEWED BY: DATE :

SRO Ops Supv.

F I L E DISPOSITION: F i 1 e per S 0 1 2 3 A 3 .

ATTACHMENT 2 PAGE 11 OF 11 123-3 2 9

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO/SRO NRC JPM A.1.b INITIAL PLANT CONDITIONS Unit 2 is in MODE 4 with the following conditions:

BAMU Tanks are OPERABLE per SO23-3-3.27, Once a Week Surveillance.

Charging Pump MP-191 is aligned to Train B.

Charging Pump MP-192 has been cleared for packing replacement.

HPSI Pump MP-018 is aligned to Train A.

HPSI Pump MP-017 is cleared for weld repair to the pump casing.

Bus 2B04 is de-energized due to supply breaker failure.

Charging System Back-Up Breakers are closed.

Charging System to #2 HPSI Header valves are open.

All other components/valves are in their required state.

TASK TO BE PERFORMED The Shift Manager directs you to perform Scheduled Surveillance for Boric Acid Flowpath Operability Verification per SO23-3-3.1, Boric Acid Flowpath Testing to verify adequate boration flowpaths exist.

Complete (Initial or N/A) each Step in Attachment 1, Boric Acid Flow Path Verification Valve Position Check - MODES 1 through 4.

Check (T) each associated box supporting each Step on the Attachment 1, Boric Acid Flow Path Operability Verification Diagram.

Initial and Check (T) each OPERABLE Train A and/or Train B Boric Acid Flow Path per Section 3.0, Test Acceptance Criteria.

Page 1 of 11

JOB PERFORMANCE MEASURE SONGS RO/SRO NRC JPM A.1.b SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X CLASSROOM X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR CLASSROOM ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 11

DOCUMENTATION SONGS RO/SRO NRC JPM A.1.b JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 189963 TASK DESCRIPTION Evaluate plant status against Technical Specifications requirements.

KA NUMBER: 2.1.12 KA VALUES: RO 2.9 SRO 4.0 10CFR55.45 APPLICABILITY: 12

REFERENCES:

SO23-3-3.1, Boric Acid Flow Path Testing, Rev. 14-2.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 11

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL New - - -

Page 4 of 11

SET-UP EXAMINER:

Provide the examinee with a copy of Technical Specifications.

Provide the examinee with a copy of SO23-3-3.1, Boric Acid Flow Path Testing.

Page 5 of 11

JPM: SONGS RO/SRO NRC JPM A.1.b TITLE: Boric Acid Flowpath Operability Verification

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the examinee with a copy of SO23-3-3.1, Boric Acid Flow Path Testing.

1 Complete Section 1.0, Prerequisites. COMPLETE Section 1.0, Prerequisites by Start Time: _______

performing the following:

INITIAL Step 1.1.

INITIAL Step 1.2 and CHECK the box for Scheduled Surveillance.

MARK Step 1.3 N/A.

NOTE: Components which are Out of Service (de-energized, cleared, etc.) are marked as N/A.

2 Review Section 2.1, Performance REVIEW Section 2.1, Performance Requirements. Requirements.

NOTE: Components in Section 2.2 are OPERABLE and in their required position based on Initial Plant Conditions.

3 Complete Section 2.2, RWST to DETERMINE each component in Section 2.2, Charging Pump Suction. RWST to Charging Pump Suction is OPERABLE and in its required position per Initial Plant Conditions and PERFORM the following:

INITIAL Steps 2.2.1 through 2.2.4.

CHECK applicable boxes on Boric Acid Flow Path Operability Verification Diagram.

NOTE: Components in Section 2.3 are OPERABLE and in their required position based on Initial Plant Conditions with the exception of BAMU Pumps (2MP-174and 2MP-175) and 2HV-9247 which are powered from de-energized MCC 2BY via Bus 2B04.

Page 6 of 11

JPM: SONGS RO/SRO NRC JPM A.1.b TITLE: Boric Acid Flowpath Operability Verification

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 4 Complete Section 2.3, BAMU to DETERMINE each component in Section 2.3, Charging Pump Suction. BAMU to Charging Pump Suction is OPERABLE and in its required position (except for BAMU Pumps and 2HV-9247 which are de-energized) per Initial Plant Conditions and PERFORM the following:

INITIAL Steps 2.3.1 through 2.3.4.

MARK Steps 2.3.5 through 2.3.7 N/A.

INITIAL Step 2.3.8.

CHECK applicable boxes on Boric Acid Flow Path Operability Verification Diagram.

NOTE: Components in Section 2.4 are OPERABLE and in their required position based on Initial Plant Conditions with the exception of swing Charging Pump 2MP-191 which is aligned to Train B and Train B Charging Pump 2MP-192 which is cleared for packing replacement.

Page 7 of 11

JPM: SONGS RO/SRO NRC JPM A.1.b TITLE: Boric Acid Flowpath Operability Verification

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5 Complete Section 2.4, Charging Pump. DETERMINE each component in Section 2.4, Charging Pump is OPERABLE and in its required position (except for Train A 2MP-190 and 2MP-191 and Train B 2MP-192) per Initial Plant Conditions and PERFORM the following:

INITIAL Step 2.4.3.

MARK Steps 2.4.1, 2.4.2 and 2.4.4 N/A.

CHECK applicable boxes on Boric Acid Flow Path Operability Verification Diagram.

NOTE: Components in Section 2.5 are OPERABLE and in their required position based on Initial Plant Conditions.

6 Complete Section 2.5, Charging to RCS. DETERMINE each component in Section 2.5, Charging to RCS is OPERABLE and in its required position per Initial Plant Conditions and PERFORM the following:

INITIAL Steps 2.5.1 through 2.5.5.

CHECK applicable boxes on Boric Acid Flow Path Operability Verification Diagram.

NOTE: Components in Section 2.6 are OPERABLE and in their required position based on Initial Plant Conditions.

Page 8 of 11

JPM: SONGS RO/SRO NRC JPM A.1.b TITLE: Boric Acid Flowpath Operability Verification

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 7 Complete Section 2.6, Charging to #2 DETERMINE each component in Section 2.6, HPSI Header. Charging to #2 HPSI Header is OPERABLE and in its required position per Initial Plant Conditions and PERFORM the following:

INITIAL Steps 2.6.1 and 2.6.2.

CHECK applicable boxes on Boric Acid Flow Path Operability Verification Diagram.

NOTE: Components in Section 2.7 are OPERABLE and in their required position based on Initial Plant Conditions with the exception of HPSI Train A Loop Isolation Valves which are inoperable (de-energized).

8 Complete Section 2.7, HPSI to RCS. DETERMINE each component in Section 2.7, HPSI to RCS is OPERABLE and in its required position (except for HPSI Train A Loop Isolation Valves) per Initial Plant Conditions and PERFORM the following:

INITIAL Step 2.7.1 and CIRCLE MP-018.

INITIAL Step 2.7.2.

INITIAL Steps 2.7.3 and 2.7.4

MARK Steps 2.7.5 through 2.7.8 N/A.

INITIAL Steps 2.7.9 through 2.7.12.

CHECK applicable boxes on Boric Acid Flow Path Operability Verification Diagram.

Page 9 of 11

JPM: SONGS RO/SRO NRC JPM A.1.b TITLE: Boric Acid Flowpath Operability Verification

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 9* Complete Step 3.1: DETERMINE there is NO OPERABLE Select the Operable Train A Boric Acid Train A Boric Acid Flow Path per Step 3.1.

Flow Paths as documented in Section 2.0.

10* Complete Step 3.2: DETERMINE there is an OPERABLE Select the Operable Train B Boric Acid Train B Boric Acid Flow Path and CHECK; Flow Paths as documented in Section

One Boric Acid Make Up Tank 2.0. and/or Two Boric Acid Makeup Tanks AND

RWST via Charging Pump and/or RWST via HPSI Pump as the OPERABLE flowpaths per Step 3.2.

11 Complete Steps 3.3.1 and 3.3.2 for Test CHECK Step 3.3.1 Train A Acceptance Criteria. UNSATISFACTORY box and CHECK Step 3.3.2 Train B SATISFACTORY box.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 10 of 11

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 11 of 11

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 U N I T S 2 AND 3 R E V I S I O N 14 TCN 14-2 PAGE 1 O F 22 E F F E C T I V E DATE 01/03/2003 BORIC A C I D FLOW PATH T E S T I N G T A B L E O F CONTENTS SECTION -

PAGE i.0 OBJECTIVES .... . ........... ..... .. .. .... z

2.0 REFERENCES

. . . . . ........... ..... . .. . . .... 2 3.0 PREREQUISITES . . . . ........... ..... . .. .. .... 3 4.0 PRECAUTIONS . . . . . ...... ..... ..... . .. .. .... 3 5.0 CHECKLIST(S) ... . ........... ..... . ..

.. .... 3 6.0 PROCEDURE.. . . . . ....., ..... ..... ..... .... 3 7.0 ACCEPTANCE C R I T E R I A . ........... ..... ..... .. . . 3 8.0 RECORDS.. ..... .. ......... ......... . .... 3 ATTACHMENTS 1 B o r i c A c i d Flow P a t h Verification Valve P o s i t i o n Check

- M o d e s 1 through 4 .............. ........ . 4 2 B o r i c A c i d Flow P a t h V e r i f i c a t i o n Valve P o s i t i o n Check

- M o d e s 5 and 6 . ... ....................

, 14 CONTINUOUS USE f 1-14. w p d QA PROGRAM AFFECTING H. Fazardo 50.59 DNA/72.48 DNA

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 UNITS 2 AND 3 REVISION 14 TCN 14-2 PAGE 2 OF 22 BORIC ACID FLOW PATH TESTING 1.0 OBJECTIVES 1.1 To v e r i f y monthly t h e o p e r a b i l i t y of 2 Boron i n j e c t i o n flow p a t h s i n Modes 1-4 or 1 Boron i n j e c t i o n flow p a t h i n Modes 5 and 6. This will be accomplished by verifying t h a t each valve (manual, power operated, or automatic) t h a t i s not locked, s e a l e d , or otherwise secured i n position i s i n i t s c o r r e c t p o s i t i o n , and Operable.

(Tech. Specs. SR 3.1.9.3 and SR 3.1.10.4)

2.0 REFERENCES

2.1 L i censi nq Commi tment 2.1.1 Technical S p e c i f i c a t i o n s 2.1.2 Licensee Controlled S p e c i f i c a t i o n s ( L C S ) .

2.2 Procedure 2.2.1 SO123-VI-0.9, Author's Guide f o r t h e Preparation of Orders, Procedures and I n s t r u c t i o n s 2.3 Operatinq I n s t r u c t i o n s 2.3.1 S0123-0-A3, Procedure Use 2.3.2 SO23-5-1.3, Plant S t a r t u p from Cold Shutdown t o Hot Stand by 2.3.3 SO23-3-3.27, Once a Week Surveil lances (Modes 1-4) 2.3.4 SO23-3-3.27.1, Once a Week Survei 1 1 ances (Modes 5-6) 2.4 Other 2.4.1 P i p i n q a n d Instrumentation Drawinqs

.I 40112, Safety I n j e c t i o n System Sheet 1

.2 40113, Safety I n j e c t i o n System, Sheet 2

.3 40122, Fuel Pool Cooling System, Sheet 2

.4 40123, Chemical a n d Volume Control System, Sheet 1

.5 40124, Chemical and Volume Control System, Sheet 2

-6 40125, Chemical a n d Volume Control System, Sheet 3

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 UNITS 2 AND 3 REVISION 14 TCN 14-2 PAGE 3 OF 22 3.0 PREREQUISITES 3.1 Verify this document i s current by checking a controlled copy or by using the method described in SO123-VI-0.9.

4.0 PRECAUTIONS 4.1 The Operable Boron injection flow path must be associated with an Operable borated water source, and in Modes 5 and 6 with an Operable emergency power source.

5.0 CHECKLIST(S) 5.1 None.

6.0 PROCEDURE 6.1 None.

? .O ACCEPTANCE CRITERIA 7.1 Acceptance criteria delineated in each attachment.

8.0 RECORDS 8.1 File completed Attachments per S0123-0-A3.

E i c w l a copy NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 UNITS 2 AND 3 REVISION 14 TCN 14-2 PAGE 4 OF 22 ATTACHMENT 1 BORIC ACID FLOW PATH VERIFICATION VALVE POSITION CHECK - MODES 1 THROUGH 4 CONTINUOUS USE OBJECTIVE To Verify t h a t two Boron i n j e c t i o n flowpaths (except locked valves) t o t h e RCS using the Charging Pumps a r e Operable. One flow p a t h shall be from Train A Components and the other f l o w p a t h s h a l l be from Train B Components.

(Tech. Spec. LCO 3.1.9 and Bases)

UNIT a MODE 4 1.0 PREREQUISITES PERF .BY I N I TI ALS Verify t h i s document i s current by checking a controlled 1.1 copy or by u s i n g t h e method described i n SO123-VI-0.9. 4 1.2 Determine t h e performance requirements of t h i s attachment: 3 IB Scheduled surveillance (Mark N/A f o r S t e p 1.3) I 0 This Attachment i s b e i n g performed prior t o entering Mode 4 as d i r e c t e d by SO23-5-1.3. (Mark N / A f o r Post Maintenance: WAR #

0 Part ia1 Schedul ed Survei 1 1 ance.

Iz] Other: (e.g., Defueled, SDC Secured, etc.):

1i I I-TEST COMPONENT(S) iI n PERFORM MARK N/A STEPS I I

MARK N/A f o r Unused Steps (Unused poges BOY be discorded) 1 1.3 Verify a l l steps i n Section 1.0 are complete, and a l l steps in Section 2.0 required t o be marked N/A, a r e c o r r e c t l y marked N/A. dk SRO Ops.

supv.

ATTACHMENT 1 PAGE 1 OF 10

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 UNITS 2 AND 3 REVISION 14 TCN 14-2 PAGE 5 OF 22 ATTACHMENT 1 20 PROCEDURE 2 . 1 Performance requirements 2.1.1 Power must be available to components to meet the operability requirements of this surveillance.

.1 Availability of power t o a valve can be verified by observation of Control Room handswitch position indication light.

2.1.2 This is an Alignment Verification only. Do not reposition components using this Attachment.

2.1.3 As this attachment is completed mark the associated boxes on Figure 1.

2.1.4 Mark N/A if the component is Out of Service.

2 . 2 RWST t o Charging Pump Suction NUMBER OF REQUIRED PERF. BY STEP COMPONENT NOUN NAME NOTE POSITION INITIALS 2.2.1 MT-005/MT-006 Refuel ing Water Storage Tanks 0P ERAB LE 2-2.2.2 52 (3) 1218MU054 Bori c Aci d B1 ending Tee to Charging Pump Suction/RWST Block Valve (9' Radwaste) CLOSED 9 2.2.3 2(3)LV-O227C RWST or Blending Tee CLOSED/

to Charging Pumps OPERABLE 3 2.2.4 2(3)LV-02276 VCT Outlet Valve [l] OPERABLE 53

[l] LV-0227B VCT Outlet Valve is not in the Boration Flow Path; however it i s required to close during use of the Gravity Feed Boration Flow Paths.

LV-0227B may be Closed if charging and letdown are secured.

ATTACHMENT 1 PAGE 2 OF 10

NUCLEAR ORGAN I ZAT ION SURVEILLANCE OPERATING I N S T R U C T I O N SO23-3-3.1 UNITS 2 AND 3 R E V I S I O N 14 TCN 14-2 PAGE 6 OF 22 ATTACHMENT 1 2 .O PROCEDURE (Continued) 2 . 3 BAMU t o Charging Pump Suction NUMBER OF REQUIRED PERF. BY STEP COMPONENT NOUN NAME NOTE P O S I T I O N INITIALS 2.3.1 2(3)MT-071 BAMU Tank [2] OPERABLE 2.3.2 2 (3)MT-072 BAMU Tank [2] OPERABLE 3 2.3.3 2 (3) HV-9240 MT-071 G r a v i t y Feed t o [2] CLOSED/

Charging Pumps OPERABLE 3 2.3.4 Z(3) HV-9235 MT-072 G r a v i t y Feed t o [2] CLOSED/

Charging Pumps OPERABLE &

2.3.5 2 (3)MP-174 BAMU Pump [2] OPERABLE o/dk 2.3.6 2(3)MP-175 BAMU Pump [2] OPERABLE d(n 2.3.7 Z(3) HV-9247 BAMU Pumps D i s c h a r g e t o CLOSED/

Charging Pumps S u c t i o n OPERABLE dfa 2.3.8 Z(3) FV-9253 Blended Makeup t o VCT [lo] CLOSED/ &

I s 0 1 a t ion OPERABLE 2 . 4 Charging Pumps NUMBER OF REQUIRED PERF. BY STEP COMPONENT NOUN NAME NOTE POSITION INITIALS 2.4.1 2(3)MP-190 Charging Pump OPERABLE uin 2.4.2 2(3)MP-191 T r a i n A Charging Pump OPERABLE dl&

2.4.3 2 (3)MP- 191 T r a i n B Charging Pump OPERABLE 8 2.4.4 2 (3)MP-192 Charging Pump 0 P ERABLE AJ /a

[2] R e f e r t o S e c t i o n 3.0 t o d e t e r m i n e t h e t a n k , v a l v e , and pump a l l o w a b l e combinations t o meet t h e s i n g l e BAMU f l o w p a t h .

[lo] 2(3)FV-9253, Blended Makeup t o VCT I s o l a t i o n Valve i s n o t i n t h e B o r a t i o n Flow Path; however i t i s r e q u i r e d t o be c l o s e d d u r i n g use o f t h e T r a i n A B o r a t i o n Flow Path t o p r e v e n t f l o w d i v e r s i o n t o t h e VCT.

ATTACHMENT 1 PAGE 3 OF 10

NUCLEAR O R G A N I Z A T I O N SURVEILLANCE O P E R A T I N G I N S T R U C T I O N SO23-3-3.1 UNITS 2 AND 3 R E V I S I O N 14 TCN 14-2 PAGE 7 OF 22 ATTACHMENT 1 2.0 PROCEDURE (Cont inued) 2.5 Charging t o RCS NUMBER OF REQUIRED PERF. BY STEP COMPONENT NOUN NAME NOTE POSITION INITIALS 2.5.1 2 (3) Hi'-9200 Charging Pump I s o l a t i o n t o RCS l o o p s OPEN/

0 P E RAB LE G-2.5.2 2 ( 3 ) Hi'-9202 Charging Pump I s o l a t i o n t o RCS l o o p 2A [4] OPEN +

2.5.3 Z(3) BLP1206 HV-9202 P e n e t r a t i o n Back-up B r e a k e r ( 6 3 ' Pen.) [3] CLOSED +

2.5.4 2(3)HV-9203 Charging Pump I s o l a t i o n t o RCS l o o p 1 A [4] OPEN +

2.5.5 Z(3) BLP0807 HV-9203 P e n e t r a t i o n Back-up Breaker ( 4 5 ' Pen.) [3] CLOSED a-2 . 6 Charging t o #2 H P S I Header NUMBER OF REQUIRED PERF. BY STEP COMPONENT NOUN NAME NOTE POSITION INITIALS 2.6.1 S2(3)1208MU005 Charging Pumps t o ECCS T r a i n B I n j e c t i o n Header B l o c k Valve (Room 209 a c r o s s f r o m Pen 49)

[7] OPEN/CLOSED

( c i r c l e one)

'2.6.2 S2(3)1208MU065 Charging Pumps t o H P S I Header [7] OPEN/CLOSED

( 9 ' Radwaste i n MP-190 room) ( c i r c l e one) 2.7 H P S I t o RCS NUMBER OF REQUIRED PERF. BY STEP c _ _ _ COMPONENT NOUN NAME POS IT I ON IN I T 1ALS T r a i n A H P S I Pump (Swing H P S I Pump i f A l i g n e d ) OPERABLE 59-T r a i n B H P S I Pump (Swing H P S I Pump i f A l i g n e d ) OPERABLE &-

[31 Backup Breaker P o s i t i o n must be checked l o c a l l y . C o n t r o l S w i t c h I n d i c a t i o n L i g h t does n o t c o r r e s p o n d t o Backup B r e a k e r P o s i t i o n .

[4] Powered f r o m a non-1E source; v a l v e i s n o t Operable when c l o s e d .

[7] Normally CLOSED, p o s i t i o n may be OPEN i f used as a T r a i n B f l o w p a t h i n Mode 4.

ATTACHMENT 1 PAGE 4 OF 10

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 U N I T S 2 AND 3 R E V I S I O N 14 TCN 14-2 PAGE 8 OF 22 ATTACHMENT 1 2.0 PROCEDURE (Continued) 2.7 H P S I t o RCS (Continued)

NUMBER OF REOUIRED PERF. BY STEP 7

COMPONENT NOUN NAME NOTE POSITION INITIALS RWST t o Train A HPSI I s o l a t i o n Valve 2.7.3 2(3)HV-9300 RUST MT-005 O u t l e t V a l v e (MT-005 Tank Room) OPEN .a-RWST t o Train 8 HPSI I s o l a t i o n Valve

'2.7.4 2(3)HV-9301 RWST MT-006 O u t l e t Valve (MT-006 Tank Room) OPEN e HPSI Train A Loop I s o l a t i o n Valves 2.7.5 2(3)HV-9324 Loop 1A H P S I Header I s o l a t i o n CLOSED/

OPERABLE Ib-2.7.6 2(3)HV-9327 Loop 1 B H P S I Header I s o l a t i o n CLOSED/

OPERABLE IJ(*

2.7.7 2(3)HV-9330 Loop 2A H P S I Header I s o l a t i o n CLOSED/

OPERABLE d(k 2.7.8 2(3)HV-9333 Loop 2B H P S I Header I s o l a t i o n CLOSED/ (cr(w OPERABLE HPSI Train B Loop I s o l a t i o n Valves 2.7.9 2(3)HV-9323 Loop 1 A H P S I Header I s o l a t i o n CLOSED/

OPERABLE &

2.7.10 2(3)HV-9326 Loop 1 B H P S I Header I s o l a t i o n CLOSED/

OPERABLE %

2.7.11 2(3)HV-9329 Loop 2A H P S I Header I s o l a t i o n CLOSED/

0 P E RAB LE 3 2.7.12 2(3)HV-9332 Loop 2B H P S I Header I s o l a t i o n CLOSED/

OPERABLE a

ATTACHMENT 1 PAGE 5 OF 10

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 U N I T S 2 AND 3 R E V I S I O N 14 TCN 14-2 PAGE 9 OF 22 ATTACHMENT 1 3.0 TEST ACCEPTANCE C R I T E R I A PERF .BY IN I T IALS 3.1 S e l e c t t h e Operable T r a i n A B o r i c A c i d Flow Paths as documented i n S e c t i o n 2.0. a TRAIN A FLOWPATHS TO RCS One B o r i c Acid Make Up Tank (MT-071 o r MT-072) w i t h t h e c o n t e n t s o f t h e t a n k Operable e r Tech. Spec. LCO 3.1.9 and LCS 3.1.104 w i t h f l o w p a t h components: [8 P A s s o c i a t e d B o r i c A c i d Makeup Pump (MP-174 o r MP-175),

TO Charging Pump S u c t i o n (HV-9247)

TO One Operable T r a i n A Charging Pump (MP-190 o r MP-191 a l i g n e d t o T r a i n A),

TO

- The RCS (HV-9200 AND EITHER HV-9202 E HV-9203 OPEN).

~ or Two Boric Acid Muke Up Tunks (MT-071 and MT-072) w i t h t h e combined c o n t e n t s o f t h e t a n k s Operable p e r Tech. Spec. LCO 3.1.9 and LCS 3.1.104, w i t h f l o w p a t h components: [8]

FROM B o r i c A c i d Make Up Pumps (MP-174 and MP-175),

TO Charging Pump S u c t i o n (HV-9247)

TO One Operable T r a i n A Charging Pump (MP-190 o r MP-191 a l i g n e d t o T r a i n A),

TO The RCS (HV-9200 EITHER HV-9202 HV-9203 OPEN).

AND RWST (MT-005, MT-006) Operable p e r Tech. Spec. LCO 3.1.9, w i t h f l o w p a t h components: [6] RWST t o T r a i n A H P S I Pumps (HV-9300),

H P S I Pump (MP-017 o r MP-018 a l i g n e d t o T r a i n A ) ,

TO

- The RCS (HV-9324, HV-9327, HV-9330, o r HV-9333)

CONTINUED ON NEXT PAGE Refer t o SO23-3-3.27 t o determine RWST O p e r a b i l i t y Requirements.

R e f e r t o SO23-3-3.27 t o determine BAMU Tank O p e r a b i l i t y Requirements.

ATTACHMENT 1 PAGE 6 OF 10

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 UNITS 2 AND 3 R E V I S I O N 14 TCN 14-2 PAGE 10 OF 22 ATTACHMENT 1 3.0 TEST ACCEPTANCE CRITERIA (Continued) PERF .BY IN I T 1ALS 3.2 S e l e c t t h e Operable T r a i n 6 B o r i c A c i d Flow Paths as documented i n S e c t i o n 2.0. 3-

- One B o r i c A c i d Make Up TankTRAIN J B FLOWPATH TO RCS (MT-071 o r MT-072) w i t h t h e c o n t e n t s o f the t a n k Operable p e r Tech. Spec. LCO 3.1.9 and LCS 3.1.104 w i t h f l o w p a t h components: [8]

Associated g r a v i t y f e e d c o n n e c t i o n (HV-9240 o r HV-9235) ,

J TO

- One Operable T r a i n B Charging Pump (MP-192 o r M P - 1 9 1 a l i g n e d t o T r a i n 6), [9]

TO The RCS: (HV-9200 HV-9202 & HV-9203 OPEN).

OR The RD: (SZ(3) 1208MU005 OPEN & SZ(3) 1208MU065 OPEN) [lo]

AND (HV-9323, HV-9326, HV-9329, o r HV-9332 OPERABLE)

~~~ ~~

Two Boric Acid Make Up Tanks (MT-071 and MT-072) w i t h t h e combined c o n t e n t s o f t h e t a n k s Operable p e r Tech. Spec. LCO 3.1.9 and LCS 3.1.104, w i t h f l o w p a t h components: [8]

J -TO G r a v i t y Feed c o n n e c t i o n s (HV-9240 and HW-9235),

One Operable T r a i n B Charging Pump (MP-192 o r MP-191 a l i g n e d t o T r a i n B), [9]

TO The RCS: (HV-9200 and HV-9202 & HV-9203 open).

OR The RCS: ( S 2 (3) 1208MU005 OPEN S2 (3) 1208MU065 OPEN) [ 101 AND (HV-9323, HV-9326, HV-9329, o r HV-9332 OPERABLE)

AND (CONTINUED ON NEXT PAGE)

[8] R e f e r t o SO23-3-3.27 t o d e t e r m i n e BAMU Tank O p e r a b i l i t y Requirements.

[9] LV-0227B must be Operable CLOSED f o r O p e r a b i l i t y o f t h i s f l o w p a t h .

[lo] These valves, i f opened, a r e c r e d i t e d f o r t h e T r a i n B f l o w p a t h o n l y .

(AR 020602015)

ATTACHMENT 1 PAGE 7 OF 10

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 UNITS 2 AND 3 REVISION 14 TCN 14-2 PAGE 11 OF 22 ATTACHMENT 1 3.0 TEST ACCEPTANCE CRITERIA (Cont i nued) PERF . B Y IN IT I ALS

_ _ _ _ ~

I J I TRAIN B FLOWPATH TO RCS (CONTINUED FROM PREVIOUS PAGE)-]

RWST (MT-005, MT-006) Operable per Tech. Spec. LCO 3 . 1 . 9 w i t h flowpath components : [6]

I J- FROM RWST t o Charging Pumps (LV-O227C),

1 1-I I

TO IT0 One Operable Train B Charging Pump (MP-192 or MP-191 a l i g n e d t o Train B),

The RCS (HV-9200 and HV-9202 HV-9203 OPEN) I RWST (MT-005, MT-006) Operable p e r Tech. Spec. LCO 3.1.9, w i t h f l o w p a t h components: [6] FROM RWST t o T r a i n B HPSI Pumps (HW-9301),

J HPSI Pump (MP-019 or MP-018 a l i g n e d t o Train B),

I -

TO The RCS (HV-9323, HV-9326, HV-9329, or HV-9332)

[6] Refer t o SO23-3-3.27 t o d e t e r m i n e RWST Operabil i t y Requirements.

ATTACHMENT 1 PAGE 8 OF 10

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 UNITS 2 AND 3 REVISION 14 TCN 14-2 PAGE 1 2 OF 22 ATTACHMENT 1 3.0 TEST ACCEPTANCE CRITERIA (Continued) PERF .BY IN I T IALS 3.3 Two OPERABLE t r a i n s of boron i n j e c t i o n flow p a t h s a r e required while operating in Modes I, 2, 3, and 4. Each train consists of two flow paths from borated water sources t o t h e RCS v i a charging pumps and/or HPSI pumps. (TS Bases 3.1.9).

T h i s t e s t i s considered s a t i s f a c t o r y i f the following Train A and Train B Boron I n j e c t i o n Flowpaths are Operable: (Tech. Spec. SR 3.1.9.3) 3.3.1 Train A Boric Acid Flowpaths required i n Section 3.1 a r e Operable as documented in Section 2.0.

SAT IS FACTORY UNSATISFACTORY 3.3.2 Train B Boric Acid Flowpaths required in Section 3.2 are Operable as documented in Section 2.0.

SATISFACTORY 17 UNSATISFACTORY 3.3.3 -If Unsatisfactory, then:

.I Notify the SRO Ops. Supervisor.

.2 Refer t o Tech. Spec. LCO 3.1.9, a n d LCS 3.1.104,

-.-?- I n i t i a t e a LCOAR/EDMR as required.

.4 Record actions taken i n t h e comments s e c t i o n .

COMMENTS :

PERF . B Y IN IT1ALS Survei 1 1 ance compl eted / a n d 1 og e n t r y made.

DATE TIME NCO 1 REVIEWED BY: DATE :

SRO Ops. Supv.

FILE DISPOSITION: F i 1 e per S0123-0-A3 ATTACHMENT 1 PAGE 9 OF 10

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NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 U N I T S 2 AND 3 R E V I S I O N 14 TCN 14-2 PAGE 14 OF 22 ATTACHMENT 2 D O R I C A C I D FLOW PATH V E R I F I C A T I O N VALVE P O S I T I O N CHECK - MODES 5 AND 6 CONTINUOUS USE OBJECTIVE To V e r i f y t h a t one Boron i n j e c t i o n f l o w p a t h ( e x c e p t l o c k e d v a l v e s ) be Operable and capable o f b e i n g powered f r o m an Operable emergency power source.

UNIT MOD E DATE TIME 1.O PREREQUISITES PERF .BY I N ITIALS 1.1 V e r i f y t h i s document i s c u r r e n t by c h e c k i n g a c o n t r o l l e d copy o r by u s i n g t h e method d e s c r i b e d i n SO123-VI-0.9.

1.2 Determine t h e performance r e q u i r e m e n t s o f t h i s a t t a c h m e n t :

Scheduled s u r v e i l l a n c e (Mark N/A f o r S t e p 1.3)

Cl P a r t i a1 Schedul ed S u r v e i 11ance.

I I c] Other: (e.g., D e f u e l e d , SDC Secured, e t c . ) :

I I i I Cl PERFORM 0 MARK N/A STEPS i

I I MARK N/A f o r Unused Steps (Unused pages may be d i s c a r d e d ) I 1.3 V e r i f y a l l s t e p s i n S e c t i o n 1.0 a r e complete, and a l l s t e p s i n S e c t i o n 2.0 r e q u i r e d t o be marked N/A, a r e c o r r e c t l y marked N/A.

SRO Ops.

supv.

ATTACHMENT 2 PAGE 1 OF 9

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 UNITS 2 AND 3 REVISION 14 TCN 14-2 PAGE 15 OF 22 ATTACHMENT 2 2 .O PROCEDURE 2 . 1 Performance requirements 2.1.1 Power must be a v a i l a b l e t o components t o meet t h e o p e r a b i l i t y requirements of t h i s s u r v e i l l a n c e .

.1 A v a i l a b i l i t y of power t o a valve can be v e r i f i e d by observation of Control Room handswitch p o s i t i o n indication l i g h t .

2.1.2 This i s an Alignment Verification only. Do not r e p o s i t i o n components using t h i s Attachment.

2.1.3 As t h i s attachment i s completed mark the associated boxes on Figure 1.

2.1.4 Mark N/A i f the component i s O u t of Service.

2 . 2 RWST t o Charging Pump Suction NUMBER OF REQUIRED PERF. BY STEP COMPONENT NOUN NAME NOTE POSITION INITIALS 2.2.1 MT-005/MT-006 Refueling Water Storage Tanks OPERABLE 2.2.2 S2(3)1218MU054 Boric Acid Blending Tee t o Charging Pump Suction/RWST Block Valve (9' Radwaste) C LOS ED 2.2.3 2(3)LV-O227C RWST o r Blending Tee CLOSED/

t o C h a r g i n g Pumps OPERABLE 2.2.4 2(3)LV-O227B VCT Outlet Valve [l] OPERABLE 2 . 3 B1 ending Tee A1 i gnment (Mark steps c

N A i f Section 2 . 2 i s being credited as a B.A.

F owpath)

NUMBER OF REQUIRED PERF. BY STEP COMPONENT NOUN NAME POSITION INITIALS 2.3.1 S2(3)1218MU054 Boric Acid Blending Tee t o Charging

( 9 ' Radwaste i Pump Suction RWST Block Valve OPEN 2.3.2 S2(3)1219MU054 Mi-006 Gravity Drain t o Charging CLOSED

[l] LV-0227B VCT Outlet Valve i s not i n the Boration Flow P a t h ; however i t i s required t o close during use of the Gravity Feed Boration Flow Paths.

LV-0227B may be Closed i f c h a r g i n g a n d letdown are secured.

ATTACHMENT 2 PAGE 2 OF 9

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING I N S T R U C T I O N 5023-3-3.1 UNITS 2 AND 3 R E V I S I O N 14 TCN 14-2 PAGE 16 OF 22 ATTACHMENT 2 2.9 PROCEDURE (Cont inued) 2.3 61 endi ng Tee A1 i gnment (Continued)

NUMBER OF REQUIRED PERF. BY STEP COMPONENT NOUN NAME POSIT ION I N I T IALS 2.3.3 SZ(3) 1218MU037 FE-0210Y I n 1 e t OPEN 2.3.4 S 2 (3) 1218MU038 FE-0210Y O u t l e t OPEN 2.3.5 FW-210Y B o r a t i o n C o n t r o l Valve CLOSED/

OPERABLE 2.4 BAMU t o Charging Pump S u c t i o n NUMBER OF REQUIRED PERF. BY STEP COMPONENT NOUN NAME NOTE POSITION INITIALS 2.4.1 2 (3) MT-07 1 BAMU Tank [Z] OPERABLE 2.4.2 2(3)MT-072 BAMU Tank [Z] OPERABLE 2.4.3 2 (3) HV-9240 MT-071 G r a v i t y Feed t o [Z] CLOSED/

Charging Pumps OPERABLE 2.4.4 2 (3) HV-9235 Mi-072 G r a v i t y Feed t o [Z] CLOSED/

Charging Pumps OPERABLE 2.4.5 2 (3) MP- 174 BAMU Pump [2] OPERABLE 2.4.6 2(3)MP-175 BAMU Pump [Z] OPERABLE 2.4.7 2 (3) HV-9247 BAMU Pumps Discharge t o CLOSED/

Charging Pumps S u c t i o n OPERABLE 2.4.8 2 (3) FV-9253 Blended Makeup t o VCT [8] CLOSED/

Isolation OPERABLE 2.5 Charging Pumps NUMBER OF REQUIRED PERF. BY COMPONENT NOUN NAME NOTE POSITION INITIALS 2.5.1 2(3)MP-190 Charging Pump OPERABLE 2.5.2 2 (3)MP-191 Charging Pump OPERABLE 2.5.3 2 (3)MP-192 Charging Pump OP ERAB LE

[2] R e f e r t o S e c t i o n 3.0 t o d e t e r m i n e t h e tank, v a l v e , and pump a l l o w a b l e combinations t o meet t h e s i n g l e BAMU f l o w p a t h .

[e] 2(3)FV-9253, Blended Makeup t o VCT I s o l a t i o n V a l v e i s n o t i n t h e B o r a t i o n Flow Path; however i t i s r e q u i r e d t o be c l o s e d d u r i n g u s e o f t h e T r a i n A B o r a t i o n Flow Path t o p r e v e n t f l o w d i v e r s i o n t o t h e VCT.

ATTACHMENT 2 PAGE 3 OF 9

NUCLEAR O R G A N I Z A T I O N SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 UNITS 2 AND 3 R E V I S I O N 14 TCN 14-2 PAGE 17 OF 22 ATTACHMENT 2 2.0 PROCEDURE (Continued) 2.6 Charging t o RCS NUMBER OF REQUIRED PERF. BY STEP COMPONENT NOUN NAME NOTE P O S I T I O N INITIALS 2.6.1 2(3)HV-9200 C h a r g i n g Pump I s o l a t i o n t o OPEN/

RCS l o o p s 0 P ERAB LE 2.6.2 2 (3)HV-9202 Charging Pump I s o l a t i o n t o RCS l o o p 2A [4] OPEN 2.6.3 2 ( 3 ) BLP1206 HV-9202 P e n e t r a t i o n Back-up B r e a k e r ( 6 3 ' Pen.) [3] CLOSED 2.6.4 2 ( 3 ) HV-9203 Charging Pump I s o l a t i o n t o RCS l o o p 1A [4] OPEN 2.6.5 2 ( 3 ) BLP0807 HV-9203 P e n e t r a t i o n Back-up B r e a k e r (45' Pen.) [31 CLOSED 2.6.6 2(3)XCV-9219 Charging t o Loop 1 A S p r i n g Loaded Check Valve OP ERAB LE 2.7 HPSI t o RCS NUMBER OF REQUIRED PERF. BY STEP COMPONENT NOUN NAME POSIT I O N INITIALS 2.7.1 MP-017 T r a i n A H P S I Pump (MP-018) (Swing H P S I Pump i f A l i g n e d ) OPERABLE 2.7.2 MP-039 T r a i n B H P S I Pump (MP-0 18) (Swing H P S I Pump i f A l i g n e d ) OPERABLE 2.7.3 S2 (3) 1208MU065 Chargi ng Pumps t o H P S I Header

( 9 ' Radwaste i n MP-190 room) OPEN 2.7.4 S2(3)1204MU154 C h a r g i n g Pumps t o RCS Loop 2 Hot Leg I n j e c t i o n B l o c k Valve OPEN RWST t o Train A HPSI I s o l a t i o n Valve 2.7.5 2 (3)HV-9300 RWST MT-005 Out1 e t Valve (MT-005 Tank Room) OPEN RWST t o Train B HPSI I s o l a t i o n Valve 2.7.6 2 (3)HV-9301 RWST MT-006 O u t l e t Valve (MT-006 Tank Room) OPEN

[3] Backup Breaker P o s i t i o n must be checked l o c a l l y . C o n t r o l S w i t c h I n d i c a t i o n L i g h t does n o t c o r r e s p o n d t o Backup Breaker P o s i t i o n .

[4] Powered f r o m a non-1E source; v a l v e i s n o t Operable when c l o s e d . Valve may be Closed, when 2(3)XCV-9219 i s t h e B o r i c A c i d Flowpath.

ATTACHMENT 2 PAGE 4 OF 9

NUCLEAR O R G A N I Z A T I O N SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 UNITS 2 AND 3 R E V I S I O N 14 TCN 14-2 PAGE 18 OF 22 ATTACHMENT 2 2.0 PROCEDURE (Continued)

NUMBER OF REQUIRED PERF. BY STEP COMPONENT NOUN NAME NOTE P O S I T I O N INITIALS H P S I Train A Loop I s o l a t i o n Valves 2.7.7 2(3)HV-9324 Loop 1 A H P S I Header I s o l a t i o n [6] CLOSED/

0 P E RAB LE 2.7.8 2(3)HV-9327 Loop 1 B H P S I Header I s o l a t i o n [6] CLOSED/

OPERABLE 2.7.9 2(3)HV-9330 Loop 2A H P S I Header I s o l a t i o n [6] CLOSED/

0 P ERAB LE 2.7.10 2(3)HV-9333 Loop 2B H P S I Header I s o l a t i o n [6] CLOSED/

0 P ERAB LE 2.7.11 2(3)HV-9420 Loop 2 H P S I Hot Leg I s o l a t i o n CLOSED/

0 P ERAB LE 2.7.12 BY-29 HV-9420 Power Supply CLOSED 2.7.13 S2(3)1208MU005 Charging Pumps t o ECCS T r a i n B I n j e c t i o n Header B1 ock V a l v e (Room 209 across f r o m Pen 49) OPEN H P S I Train B Loop I s o l a t i o n Valves 2.7.14 2(3)HV-9323 Loop 1 A H P S I Header I s o l a t i o n [6] CLOSED/

0 P ERAB LE 2.7.15 2(3)HV-9326 Loop 1 B H P S I Header I s o l a t i o n [6] CLOSED/

0 P ERAB LE 2.7.16 2(3)HV-9329 Loop 2A H P S I Header I s o l a t i o n [6] CLOSED/

OPERABLE 2.7.17 2(3)HV-9332 Loop 2B H P S I Header I s o l a t i o n [6] CLOSED/

OPERABLE 2.7.18 2(3)HV-9434 Loop 1 Hot Leg I s o l a t i o n CLOSED/

OPERABLE 2.7.19 BZ-39 HV-9434 Power Supply CLOSED

[6] A v a i l a b i l i t y o f power t o v a l v e can be v e r i f i e d b y o b s e r v a t i o n o f C o n t r o l Room handswitch p o s i t i o n i n d i c a t i o n l i g h t .

ATTACHMENT 2 PAGE 5 O F 9

NUCLEAR ORGAN I ZATI ON S U R V E I L L A N C E OPERATING INSTRUCTION SO23-3-3.1 UNITS 2 AND 3 REVISION 14 TCN 14-2 PAGE 19 OF 22 ATTACHMENT 2 3.0 TEST ACCEPTANCE CRITERIA PERF .BY INITIALS 3.1 This t e s t i s considered S a t i s f a c t o r y i f t h e component status i n Section 2.0 meets t h e o p e r a b i l i t y requirements of one of the following three Boron i n j e c t i o n flowpaths t o the RCS and i s c a p a b l e o f being powered from an Operable emergency power source: (Tech. Spec. SR 3.1.10.4)

[3 SATISFACTORY UNSATISFACTORY 3.1.1 -I f Unsatisfactory, then:

.1 Notify the SRO Ops. Supervisor.

-2 Refer t o Tech. Spec. LCO 3.1.10, and LCS 3.1.104,

.3 I n i t i a t e a LCOAR/EDMR as required.

.4 Record a c t i o n s taken in the comments section.

I TO Any Operable Charging Pump (MP-190, MP-191, MP-192),

TO The RCS (HV-9200 a n d HV-9202, and/or HV-9203),

OR T h e RCS (HV-9200 and XCV-9219),

OR T h e RCS v i a S2(3) 1208MU065, S2 (3) 1208MU005, and HV-9323 , HV-9326 , HV-9329, HV-9332, and/or HV-9434, OR The RCS v i a S2(3)1208MU065, S2(3)1204MU154 and HV-9420, AND Capable of being powered from an Operable Emergency Power Source.

[7] Refer t o SO23-3-3.27.1 t o determine BAMU Tank/RWST Operability Requirements, ATTACHMENT 2 PAGE 6 OF 9

NUCLEAR O R G A N I Z A T I O N SURVEILLANCE OPERATING INSTRUCTION SO23-3-3.1 UNITS 2 AND 3 R E V I S I O N 14 TCN 14-2 PAGE 20 OF 22 ATTACHMENT 2 3.8 TEST ACCEPTANCE C R I T E R I A (Continued)

RMST (MT-005, MT-006) Operable p e r Tech. Spec. LCO 3.1.10, with flowpath components: [5], [7] FRoM RWST t o H P S I Pumps (HV-9300, HV-9301),

mHPSI Pump (MP-019, MP-018, MP-017),

TO The RCS (HV-9323, HV-9324, HV-9326, HV-9327, HV-9329, HV-9330, HV-9332, HV-9333, HV-9420, HV-9434),

AND Capabl e o f b e i n g powered from an Operabl e Emergency Power Source.

RWST (MT-005, MT-006 components: [5], [7 1 Operable p e r Tech. Spec. LCO 3.1.10, w i t h flowpath RWST t o Charging Pumps (LV-O227C),

TO Any Operable Charging Pump (MP-190, MP-191, MP-192),

TO The RCS (HV-9200 and HV-9202 and/or HV-9203),

OR The RCS (HV-9200 and XCV-9219),

OR The RCS v i a S2( 3) 1208MU065, S2 (3) 1208MU005, and HV-9323, HV-9326, HV-9329, HV-9332, and/or HV-9434 OR The RCS v i a S 2 ( 3 ) 1208MU065, S2(3)1204MU154, and HV-9420, AND Capabl e o f b e i n g powered f r o m an Operabl e Emergency Power Source.

~ ~ ~~

CONTINUED ON NEXT PAGE

[5] I f RWSTs a r e S p l i t ( x - t i e c l o s e d ) and G r a v i t y f e e d t o Charging i s t h e c r e d i t e d BAFP, t h e n ONLY TO06 can be used as B o r a t e d Source as i t s u p p l i e s t h e Charging Pumps (40122B). H P S I b o r a t e d source becomes T r a i n s p e c i f i c w i t h T-005 a s s o c i a t e d w i t h T r a i n A and T-006 a s s o c i a t e d w i t h T r a i n B.

[7] R e f e r t o SO23-3-3.27.1 t o d e t e r m i n e RWST O p e r a b i l i t y Requirements.

ATTACHMENT 2 PAGE 7 OF 9

NUCLEAR ORGANIZATION SURVEILLANCE OPERATING I N S T R U C T I O N SO23-3-3.1 U N I T S 2 AND 3 R E V I S I O N 14 TCN 14-2 PAGE 2 1 OF 22 ATTACHMENT 2 3.0 TEST ACCEPTANCE C R I T E R I A (Continued)

COMMENTS :

PERF .BY IN IT IALS SiiWei11 a n c e c o m p l e t e d / a n d log e n t r y made.

DATE TIME NCO I REVIEWED BY:

SRO Ops. S u p v .

DATE: -

F I L E DISPOSITION: F i l e per S 0 1 2 3 A 3 .

ATTACHMENT 2 PAGE 8 O F 9

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Document Number SO23-3-3.1, TCN 14-2 PAGE __ OF ~

COMMITMENT 50.59 SUPP. DESCRIPTION OF CHANGES PAGE(s)

NUMBER REVIEW Added B o r i c A c i d V a l v e HV9247 t o 9, 19 Acceptance C r i t e r i a f o r T r a i n A B o r i c A c i d Flow Path.

OPGWG I DNA I NO I n c o r p o r a t e changes t o C o n t r o l Room Personnel t i t l e changes as d i r e c t e d by 12, 2 1 OPGWG

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO NRC JPM A.2 INITIAL PLANT CONDITIONS The Unit 2 Boric Acid Makeup Pump 2MP175 requires an overhaul and is ready to be aligned for maintenance. The BAMU Pump is stopped.

A Work Authorization Request (WAR) must be prepared to allow repairs to the pump.

TASK TO BE PERFORMED The Shift Manager directs you to identify the Clearance boundaries required to allow overhaul of Unit 2 Boric Acid Makeup Pump 2MP175. Sequencing is NOT required at this time, it will be performed by the Work Process Control Operator (51) during WAR review.

Page 1 of 8

JOB PERFORMANCE MEASURE SONGS RO NRC JPM A.2 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X CLASSROOM X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR CLASSROOM ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 8

DOCUMENTATION SONGS RO NRC JPM A.2 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 30 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 182153 TASK DESCRIPTION Prepare a Work Authorization Record tagout.

KA NUMBER: 2.2.13 KA VALUES: RO 3.6 SRO 3.8 10CFR55.45 APPLICABILITY: 12, 13

REFERENCES:

SO123-XX-5, Work Authorizations, Revision 14.

SO23-3-2.2, Makeup Operations, Revision 19-4.

Boric Acid Makeup P&ID #40125A, Revision 14.

Boric Acid Makeup P&ID #40125B, Revision 18.

480 V Load Center Bus 2BY One Line Diagram #30162, Revision 33.

480 V Load Center Bus 2BZ One Line Diagram #30164, Revision 39.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

0-1 Compared against SO123-XX-5, Rev LRZ 06/05/06 14 and SO23-3-2.2, Rev 19-4 with no changes required. Compared against latest One-Line Diagrams and P&IDs with no changes required to P&IDs and minor changes to One-Line Diagrams. Changed Clearance to BAMU Pump P-175 from P-174.

Page 4 of 8

SET-UP EXAMINER:

Obtain P&IDs for:

Boric Acid Makeup Pump #40125A

Boric Acid Makeup Pump #40125B Obtain One-Line Diagram for:

480 V Load Center Bus 2BY #30162

480 V Load Center Bus 2BY #30164 The P&IDs may be prepared by the examinee as follows:

Highlight in BLUE the problem area(s).

Highlight in YELLOW the Cleared line(s).

Highlight in RED the isolation area(s).

Provide the examinee with a blank Work Authorization Record Tag Installation sheet (Attachment 4) and colored highlighters to outline the flowpath.

Provide the examinee with a copy of SO123-XX-5, Work Authorizations, SO23-3.2.2, Makeup Operations and the applicable P&IDs and electrical prints.

Page 5 of 8

JPM: SONGS RO NRC JPM A.2 TITLE: Prepare a Work Authorization Record (WAR) Tagout

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the examinee with a copy of SO123-XX-5, Work Authorizations, SO23-3.2.2, Makeup Operations and copies of P&IDs and electrical prints.

1 Review P&IDs and One-Line Diagram REVIEW P&IDs for: Start Time: _______

for the Boric Acid Makeup Pump.

Unit 2 Reactor Coolant CVCS System

1218 - #40125A

Unit 2 Reactor Coolant CVCS System

1218 - #40125B OBTAIN One-Line Diagram for:

Unit 2 One-Line Diagram 480 V Motor Control Center 2BY #30162

Unit 2 One-Line Diagram 480 V Motor Control Center 2BZ #30164 2 Locate the component to be isolated. LOCATE the Boric Acid Makeup Pump on P&ID #40125B.

3* Determine the BAMU Pump P-175 DETERMINE BAMU Pump P-175 clearance clearance boundaries to be used to boundaries to be:

isolate the repair area.

S21218MU034 discharge CLOSED.

S21218MU078 discharge flush OPEN.

S21218MU079 suction flush OPEN.

S21218MU005 suction valve CLOSED.

4 Locate the component to be isolated. LOCATE the Boric Acid Makeup Pump Recirculation Valves on P&ID #40125A.

Page 6 of 8

JPM: SONGS RO NRC JPM A.2 TITLE: Prepare a Work Authorization Record (WAR) Tagout

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5* Determine the BAMU Pump P-175 DETERMINE BAMU Pump P-175 Recirc.

clearance boundaries to be used to Valve clearance boundaries to be:

isolate the repair area.

S21218MU042 recirc valve CLOSED.

S21218MU043 recirc valve CLOSED.

6 Locate the component to be isolated. LOCATE the Boric Acid Makeup Pump power supply on One-Line Diagram 30162.

7* Determine the BAMU Pump P-175 DETERMINE BAMU Pump P-175 power power supply clearance boundaries to be supply clearance boundaries to be:

used to isolate the repair area.

Pump breaker 2BY15 OPEN.

NOTE: The examinee may list all, some, or none of the components in Step 8. They are shown as potential examples of additional tags that may be hung.

8 Determine the optional clearance DETERMINE the optional clearance boundaries to be used to isolate the boundaries to be:

repair area.

Motor enclosure heater 2BY40D OFF.

2HV-9231 alternate recirc valve CLOSED.

S21218MR078 recirc vent OPEN.

S21218MR155 root valve Uncapped OPEN.

2P-175 Control Room Switch in OFF.

TERMINATING CUE: Stop Time: _______

This JPM is complete.

Page 7 of 8

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 8 of 8

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 SRO NRC JPM A.2 INITIAL PLANT CONDITIONS Unit 2 is in Mode 1 at 100% power. Saltwater Cooling System Pump P-112 is out-of-service for maintenance. The breaker for Saltwater Cooling System Pump P-307 has just tripped on overcurrent.

Two hours later, Maintenance Engineering contacts the Control Room to report that a review of radiographs performed during the last outage to LPSI Pump P-016 have revealed a series of hairline cracks.

TASK TO BE PERFORMED Perform a Safety Function Determination Program (SFDP) analysis per SO123-0-A5, Technical Specification LCOAR/EDMR for the LPSI System and identify the following parameters:

1. Inoperable Equipment:

2. Previously Inoperable Equipment:

3. Safety Function Affected:

4. Redundant System(s):

5. Support System(s):

6. Supported System(s):

7. SFDP Assessment (SAT / UNSAT):

8. SFDP Rules and Logic Applied to reach SFDP Determination:

Page 1 of 8

JOB PERFORMANCE MEASURE SONGS SRO NRC JPM A.2 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X CLASSROOM X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR CLASSROOM ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 8

DOCUMENTATION SONGS SRO NRC JPM A.2 JPM LEVEL: SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CRS TASK SYS ID: 189963 TASK DESCRIPTION Evaluate plant status against Technical Specification requirements.

KA NUMBER: 2.2.22 KA VALUES: RO 3.4 SRO 4.1 10CFR55.45 APPLICABILITY: 13

REFERENCES:

SO123-0-A5, Technical Specification LCOAR/EDMR, Rev. 2-2.

Unit 2 Technical Specifications.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

0-1 Compared against SO123-0-A5, Rev. LRZ 08/18/06 2-2 with no changes required.

Page 4 of 8

SET-UP EXAMINER:

Provide the examinee with a copy of SO123-0-A5, Technical Specification LCOAR/EDMR and Unit 2 Technical Specifications.

Definitions:

LCOAR - Limiting Condition for Operation ACTION Requirement EDMR - Equipment Deficiency MODE Restraint Page 5 of 8

JPM: SONGS SRO NRC JPM A.2 TITLE: Complete a Safety Function Determination

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: When located, provide the examinee with a copy of SO123-0-A5, Technical Specification LCOAR/EDMR and Technical Specifications.

1 Determine the inoperable system or DETERMINE that the Train B LPSI System Start Time: ________

component. is the inoperable equipment.

2 Determine the previously inoperable DETERMINE that the Train A SWC System system or component. is the previously inoperable equipment.

NOTE: Either Safety Function identified in Step 3 will be considered full credit.

3* Determine the Safety Function impacted DETERMINE that a loss of injected borated by the inoperable system or component. water on SIAS signal or removal of decay heat is the Safety Function impacted.

4* Determine the Redundant System(s) DETERMINE that the Train A LPSI System impacted by the inoperable system or is the Redundant System impacted by the component. inoperable system or component.

5 Determine the Support System(s) DETERMINE that CCW, SWC, and AC impacted by the inoperable system or Distribution are the Support Systems component. impacted by the inoperable system or component.

6 Determine the Supported System(s) DETERMINE that ECCS is the Supported impacted by the inoperable system or System impacted by the inoperable system or component. component.

7* Determine the SFDP Assessment for the DETERMINE that the SFDP Assessment for inoperable system or component. the inoperable system or component is UNSAT.

Page 6 of 8

JPM: SONGS SRO NRC JPM A.2 TITLE: Complete a Safety Function Determination

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 8 Determine the SFDP Rules and Logic DETERMINE the SFDP Rules and Logic Applied to reach SFDP Determination Applied to reach SFDP Determination:

for the inoperable system or component.

Train B LPSI Pump is inoperable affecting Train B ECCS Safety Function.

Train A SWC is inoperable affecting Train A ECCS Safety Function.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 7 of 8

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 8 of 8

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO/SRO NRC JPM A.3 INITIAL PLANT CONDITIONS A high dose maintenance activity is scheduled in the Unit 3 Penetration Building.

The general dose rate in the area is 75 mrem/hour but can be reduced to 30 mrem/hour if lead shielding is installed.

It will take Operators A & B two (2) hours to install the shielding if desired.

Independent of the shielding, it will take Operator A five and a half (5.5) hours or Operators A &

B three (3) hours to perform the maintenance.

TASK TO BE PERFORMED The Work Process Supervisor has directed you to select the condition with the lowest total dose to perform the maintenance (CIRCLE your answer):

1. Operator A without shielding.

2. Operators A & B without shielding.

3. Operator A with shielding.

4. Operators A & B with shielding.

Page 1 of 8

JOB PERFORMANCE MEASURE SONGS RO/SRO NRC JPM A.3 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X CLASSROOM X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR CLASSROOM ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 8

DOCUMENTATION SONGS RO/SRO NRC JPM A.3 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 7 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 113888 TASK DESCRIPTION Calculate stay time given a dose rate, current exposure, and an exposure limit.

KA NUMBER: 2.3.10 KA VALUES: RO 2.9 SRO 3.3 10CFR55.45 APPLICABILITY: 10

REFERENCES:

SO123-VII-20.4.3, ALARA Job Reviews, Rev. 4-1.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

Page 4 of 8

SET-UP EXAMINER:

Provide the examinee with a calculator.

Page 5 of 8

JPM: SONGS RO/SRO NRC JPM A.3 TITLE: Determine Total Dose Due to Maintenance

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide examinee with a calculator.

1 Determine total dose to Operator A DETERMINE total dose to Operator A Start Time: _______

without shielding. without shielding as follows:

75 mrem/hr x 5.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months =

412.5 mrem total dose.

2 Determine total dose to Operators DETERMINE total dose to Operators A & B A & B without shielding. without shielding as follows:

75 mrem/hr x 3.0 hour0 days 0 hours 0 weeks 0 months s/operator x 2 operators = 450 mrem total dose.

3 Determine total dose to install shielding. DETERMINE total dose to install shielding as follows:

75 mrem/hr x 2.0 hour0 days 0 hours 0 weeks 0 months s/operator x 2 operators = 300 mrem to install.

4 Determine total dose to Operator A with DETERMINE total dose to Operator A with shielding. shielding as follows:

30 mrem/hr x 5.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months + 300 mrem =

465 mrem total dose.

5 Determine total dose to Operators DETERMINE total dose to Operators A & B A & B with shielding. with shielding as follows:

30 mrem/hr x 3.0 hour0 days 0 hours 0 weeks 0 months s/operator x 2 operators + 300 mrem =

480 mrem total dose.

Page 6 of 8

JPM: SONGS RO/SRO NRC JPM A.3 TITLE: Determine Total Dose Due to Maintenance

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6* Select the appropriate individual. DETERMINE total dose to Operator A without shielding at a total dose of 412.5 mrem is the most desirable selection.

TERMINATING CUE: Stop Time: _______

This JPM is complete.

Page 7 of 8

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 2.5 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 8 of 8

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 SRO NRC JPM A.4 INITIAL PLANT CONDITIONS Given the following plant conditions:

The Unit has experienced a small break LOCA following a Reactor trip.

The leak rate is estimated at 60 gpm.

A loss of offsite power occurred and 2G003 EDG Output Breaker will not close.

2G002 is running and providing necessary loads.

All swing equipment was aligned to Train A prior to the trip.

ECCS has not actuated, nor does its actuation appear imminent.

All other ESF functions have actuated successfully.

AFW Pump P-140 has tripped on overspeed and AFW Pump P-141 appears to be cavitating with discharge pressure fluctuating between 250 and 1000 psig TASK TO BE PERFORMED The Shift Manager directs you to determine the Event Classification and the appropriate Event Code using SO123-VIII-1, Recognition and Classification of Emergencies.

THIS IS A TIME CRITICAL JPM Page 1 of 7

JOB PERFORMANCE MEASURE SONGS SRO NRC JPM A.4 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X CLASSROOM X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR CLASSROOM ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 7

DOCUMENTATION SONGS SRO NRC JPM A.4 JPM LEVEL: SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: YES CRITICAL TIME: 15 minutes POSITION: SM TASK SYS ID: 192840 TASK DESCRIPTION Classify emergency events requiring emergency plan implementation.

KA NUMBER: 2.4.41 KA VALUES: RO 2.3 SRO 4.1 10CFR55.45 APPLICABILITY: 11

REFERENCES:

SO123-VIII-1, Recognition and Classification of Emergencies, Revision 25.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: A. Hagemeyer DATE:

APPROVED BY: M. Jones DATE:

Page 3 of 7

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

Page 4 of 7

SET-UP EXAMINER:

Provide the Examinee with a copy of SO123-VIII-1, Recognition and Classification of Emergencies.

Page 5 of 7

JPM: SONGS SRO NRC JPM A.4 TITLE: Classification and Reporting Requirement for an Emergency Event

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO123-VIII-1, Recognition and Classification of Emergencies.

NOTE: The following steps can be performed in any order.

1 Determine the Event Category. DETERMINE the event to be a Loss of Safety Critical Start Time:

Equipment Event. ________

2 Match plant conditions with the EALs REVIEW EAL descriptions to determine the listed in the selected Event Category EAL that most closely matches the plant tabs. conditions.

3 Review the notes preceding/following REVIEW notes preceding / following the the selected EAL to find the highest EAL.

level applicable EAL.

4* Classify the emergency using the CLASSIFY event as a Site Area Emergency highest applicable Event Code. per Event Code Tab D3-7.

TERMINATING CUE: Critical Stop Time:

This JPM is complete. ________

Page 6 of 7

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 7 of 7

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO/SRO NRC JPM S-1 INITIAL PLANT CONDITIONS A Unit 2 Reactor trip occurred 15 minutes ago.

SG pressures are approximately 1000 psia.

Steam Generator E-089 and Steam Generator E-088 levels are increasing through 35%.

The Control Room team is preparing to verify EFAS-1 and EFAS-2 actuation.

SO23-3-2.22, EFAS System Operation, Attachment 13, Prerequisites have been completed.

TASK TO BE PERFORMED The Control Room Supervisor directs you to verify proper EFAS-1 and 2 actuation per SO23-3-2.22, EFAS System Operation, Attachment 13.

Page 1 of 9

JOB PERFORMANCE MEASURE SONGS RO/SRO NRC JPM S-1 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 9

DOCUMENTATION SONGS RO/SRO NRC JPM S-1 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 186173 TASK DESCRIPTION Verify the proper actuation, reset and restoration of the auxiliary feedwater system following automatic actuation of EFAS or DEFAS.

KA NUMBER: 013 A3.02 KA VALUES: RO 4.1 SRO 4.2 10CFR55.45 APPLICABILITY: 5, 7

REFERENCES:

SO23-3-2.22, Engineered Safety Features Actuation System Operation, Rev. 15-3.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 Compared against SO23-3-2.22, Rev. LRZ 06/19/06 15-3 with minor changes required.

Page 4 of 9

SET-UP MACHINE OPERATOR:

Use IC #171 for the 2006 NRC JPM Exam.

Otherwise use any 100% IC and establish the following Simulator conditions:

$ Reactor tripped.

$ E088 SG level approximately 40% and rising.

$ E089 SG level approximately 35% and rising.

$ Two (2) malfunctions:

RP_K211A TRUE EXAMINER:

Provide the Examinee with a copy of SO23-3-2.22, ESFAS System Operation, Attachment 13, EFAS/DEFAS Actuation Verification, with the Prerequisites completed.

NOTE: Maintain the simulator in freeze until the Examinee is ready to start the JPM. This will assist in keeping the level low in the Steam Generators.

Page 5 of 9

JPM: SONGS RO/SRO NRC JPM S-1 TITLE: Verify the Proper Operation of the AFW System Following an EFAS

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-3-2.22, Attachment 13, EFAS/DEFAS Actuation Verification, with the Prerequisites completed.

1 Ensure P-141 Motor Driven AFW Pump VERIFY 2HS-4707-1, AFWP 2P141 running Start Time: _______

started. with red START light illuminated and ~130 amps indicated.

2 Ensure HV-4713, 2P-141 Flow Control VERIFY 2HV-4713, AFWP 2P141 to SG Valve to 2E-089, is closed. E089 Discharge Valve closed and OBSERVE green JOG CLOSE light illuminated.

3 Ensure HV-4731, S/G E-089 VERIFY 2HV-4731, AFW to SG E089 Iso Containment Isolation Valve, is Valve closed and OBSERVE green CLOSE CLOSED. light illuminated.

4 Ensure HV-8200, Main Steam to P-140 OBSERVE 2HV-8200, Main Steam to Isolation, is OPEN. AFWPT 2K007 SG 2E089 Iso Valve red OPEN light illuminated.

5 Ensure HV-4706, P-140 Flow Control OBSERVE 2HV-4706, AFWP 2P140 to SG Valve to 2E-089, is CLOSED. 2E089 Disch Valve green JOG CLOSE light illuminated.

6 Ensure HV-4715, SG 2E-089 OBSERVE 2HV-4715, AFW to SG 2E-089 Containment Isolation Valve, is Iso Valve green JOG CLOSE light CLOSED. illuminated.

7 Ensure HV-4053, SG 2E-089 OBSERVE 2HV-4053-2, SG 2E089 Blowdown Isolation Valve, is Blowdown Iso Valve green CLOSE light CLOSED. illuminated.

Page 6 of 9

JPM: SONGS RO/SRO NRC JPM S-1 TITLE: Verify the Proper Operation of the AFW System Following an EFAS

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 8 Ensure HV-4763, P-141 Discharge OBSERVE 2HV-4763, AFWP 2P141 to SG Bypass Valve to 2E-089, is CLOSED. 2E089 Disch Valve Bypass green CLOSE light illuminated.

9 Ensure HV-4716, Main Steam Valve to OBSERVE 2HV-4716, AFWPT 2K007 Steam 2P-140, is OPEN. Inlet Valve red OPEN light illuminated.

10 Ensure Motor Driven AFW Pump P-504 OBSERVE 2HS-4733-2, AFWP 2P504 red STARTED. START light illuminated.

11 Ensure HV-4712, P-504 flow control OBSERVE 2HV-4712, AFWP 2P504 to SG valve to E088, CLOSED. E088 Disch Valve green JOG CLOSE light illuminated.

12 Ensure HV-4714, SG E088 OBSERVE 2HV-4714, AFW to SG E088 Iso Containment Isolation Valve, CLOSED. Valve green CLOSE light illuminated.

13 Ensure HV-8201, Main Steam to P-140 OBSERVE 2HV-8201, Main Steam to Isolation, OPEN. AFWPT 2K007 SG E088 Iso Valve red OPEN light illuminated.

NOTE: The following two steps represent the alternate path of this JPM. Examinee will be required to evaluate Steam Generator level and determine that SO23-3-2.22 requires the following two (2) valves to be closed.

14* Ensure HV-4705, P-140 Flow Control OBSERVE 2HV-4705 is open, DETERMINE Valve to E088, CLOSED. the valve should be closed and DEPRESS and HOLD JOG CLOSE pushbutton on 2HV-4705, AFWP 2P140 to SG E088 Disch Valve until green JOG CLOSE light illuminated.

Page 7 of 9

JPM: SONGS RO/SRO NRC JPM S-1 TITLE: Verify the Proper Operation of the AFW System Following an EFAS

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 15* Ensure HV-4730, SG E088 containment OBSERVE 2HV-4730 is open, DETERMINE isolation valve, CLOSED. the valve should be closed and DEPRESS and HOLD JOG CLOSE pushbutton 2HV-4730, AFW to SG E088 Iso Valve until green JOG CLOSE light illuminated.

16 Ensure HV-4054, SG E088 BD OBSERVE 2HV-4054, SG E088 Blowdown Isolation Valve, CLOSED. Iso Valve green CLOSE light illuminated.

17 Ensure HV-4762, P-504 discharge OBSERVE 2HV-4762, AFWP 2P504 to SG bypass valve to E088, CLOSED. E088 Disch Valve Bypass green CLOSE light illuminated.

18 Ensure HV-4716, Main Steam Valve to OBSERVE 2HV-4716, AFWPT 2K007 Steam 2P-140, is OPEN. Inlet Valve red OPEN light illuminated.

19 Ensure A-443, AFW Pump Room Fan, OBSERVE 2HS-9532-2, AFW Pump Area is STARTED. Fan 2A443 red START light illuminated.

20 Ensure A-394, AFW Pump Room Fan, VERIFY 2HS-9581-1, AFW Pump Area Fan is STARTED. 2A394 running and OBSERVE red START light illuminated.

21 Verify E-128, Pressurizer Backup OBSERVE 2HS-0100F1, Backup Heaters Heater on CR-50, is OFF. Bank 128 from 2B0402 green OFF light illuminated.

22 Verify E-129, Pressurizer Backup OBSERVE 2HS-0100I2, Backup Heaters Heater on CR-50, is OFF. Bank 129 from 2B0602 green OFF light illuminated.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 8 of 9

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 9 of 9

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO/SRO NRC JPM S-2 INITIAL PLANT CONDITIONS Chemistry informs you that T-084, Waste Gas Decay Tank is ready for release. The Gaseous Effluent Release Permit Cover Sheet for T-084 is complete per SO123-III-5.1.23, Units 2(3)

Effluent Sampling and Analysis.

TASK TO BE PERFORMED The Control Room Supervisor directs you to prepare and release Waste Gas Decay Tank T-084 per SO23-8-15, Radwaste Gas Discharge, Attachment 1, starting at Step 1.7.

Page 1 of 13

JOB PERFORMANCE MEASURE SONGS RO/SRO NRC JPM S-2 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 13

DOCUMENTATION SONGS RO/SRO NRC JPM S-2 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 186269 TASK DESCRIPTION Coordinate radioactive gas releases.

KA NUMBER: 2.3.11 KA VALUES: RO 2.7 SRO 3.2 10CFR55.45 APPLICABILITY: 8, 12

REFERENCES:

SO23-8-15, Radwaste Gas Discharge, Rev. 16-1.

CH(123) 5-90, Gaseous Effluent Release Permit Cover Sheet, Rev. 3.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 13

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

1 Compared against SO23-8-15, Rev LRZ 06/19/06 REV 16-1 with no changes required.

Modified this JPM to include steps for isolating the waste gas release upon receipt of a high radiation alarm.

Page 4 of 13

SET-UP MACHINE OPERATOR:

Use IC #172 for the 2006 NRC JPM Exam and perform the following:

Place 2/3FIC-7202 in MANUAL.

Select and lower OPERATOR SETPOINT (OSP) to a value less than 50%.

Place 2/3FIC-7202 in the OUT (output) Mode.

Using a blank yellow magnetic CAUTION tag and a white board marker CREATE a CAUTION tag reading WASTE GAS RELEASE IN PROGRESS, DO NOT RESET and place near 2/3FIC-7202.

Ensure 2/3FV-7202, Waste Gas Decay Tank Header Vent Valve, is closed.

Reboot and reload DAS to remove previous examinees trend.

Place DAS on Home Page.

Otherwise, use any 100% IC and perform the following:

Insert malfunction RM04V to 100,000 µci/sec.

EXAMINER:

Provide a partially completed copy of SO23-8-15, Radwaste Gas Discharge Attachment 1 up to and including Prerequisite Step 1.6. Also ensure the Gaseous Effluent Release Permit Cover Sheet for T-084 (located at the end of this JPM) box for Weather Evaluation is marked N/A.

Ensure the following actions are completed each time the JPM is performed:

Place 2/3FIC-7202 in MANUAL.

Select and lower OPERATOR SETPOINT (OSP) to a value less than 50%.

Leave 2/3FIC-7202 in the OUT (output) Mode.

Ensure 2/3FV-7202, Waste Gas Decay Tank Header Vent Valve, is closed.

Reboot and reload DAS to remove previous examinees trend.

Place DAS on Home Page.

Page 5 of 13

JPM: SONGS RO/SRO NRC JPM S-2 TITLE: Prepare and Release a Waste Gas Decay Tank

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Ensure that setup page is completed before each examinee performs this JPM.

NOTE: Provide the examinee with a copy of SO23-8-15, Radwaste Gas Discharge, Attachment 1 (completed up to and including Prerequisite Step 1.6) and Gaseous Effluent Release Permit Cover Sheet for T-084 (located at the end of this JPM). Ensure box for Weather Evaluation is marked N/A.

1 Perform a Channel Check on PERFORM a Channel Check on 2/3FIT-7202. Start Time: ________

2/3FIT-7202.

2 Verify no outstanding LCOAR/EDMRs VERIFY no outstanding LCOAR/EDMRs related to 2/3FIT-7202. related to 2/3FIT-7202 by CHECKING the Radiation Monitoring Panel and/or LCOAR Book.

CUE: No outstanding LCOAR/EDMRs related to 2/3FIT-7202 currently exist.

3* Verify 2/3FIC-7202 = 0.0 SCFM. DEPRESS SEL on 2/3 FIC-7202, Waste Gas Decay Tanks HDR Vent Control and VERIFY 2/3FIC-7202 process flow reading is 0.0 SCFM.

4 Verify 2/3FIT-7202 < 5 SCFM. VERIFY 2/3FIT-7202 < 5 SCFM.

(63' Radwaste - LOCAL). at the 63' Radwaste local indication.

CUE: Radwaste Operator reports 2/3FIT-7202 is reading 0 SCFM.

5 Document that the Channel Check was DOCUMENT that the Channel Check was completed satisfactorily. completed satisfactorily by CHECKING YES and MARK Steps 1.7.1 and 2.3.4 N/A.

Page 6 of 13

JPM: SONGS RO/SRO NRC JPM S-2 TITLE: Prepare and Release a Waste Gas Decay Tank

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6 Ensure 2/3 RIC-7808G, PVS Radiation ENSURE 2/3 RIC-7808G, PVS Radiation Monitor is Operable. Monitor is OPERABLE:

2/3 RIC-7808G Channel Check;

VERIFY 2/3 RIC-7808G, Green Green OPERATE LED OPERATE LED illuminated in illuminated. Control Room Hallway.

2/3 RIC-7808G Channel Check;

VERIFY 2/3 RIC-7808G, Red TEST Red TEST LED extinguished. LED extinguished in Control Room

2/3 RIC-7808G Channel Check; Hallway (amber in Simulator).

Normal channel behavior on

VERIFY 2/3 RIC-7808G, Normal DAS. channel behavior on DAS.

7 Ensure 2/3 RIC-7808G, PVS Radiation ENSURE 2/3 RIC-7808G, PVS Radiation Monitor is Operable. Monitor is OPERABLE:

2/3 RIC-7808G Source Check;

VERIFY 2/3 RIC-7808G, Green Green OPERATE LED OPERATE LED illuminated in illuminated. Control Room Hallway.

CUE: Source Check for 2/3RIC-7808G is satisfactory.

Page 7 of 13

JPM: SONGS RO/SRO NRC JPM S-2 TITLE: Prepare and Release a Waste Gas Decay Tank

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 8 Ensure 2/3 RIC-7808G, PVS Radiation ENSURE 2/3 RIC-7808G, PVS Radiation Monitor is Operable. Monitor is OPERABLE:

DAS Channel Check; Clock on

VERIFY clock on Data Acquisition DAS Home page is updating. System (DAS) Home page is updating.

Status of 2/3RIC-7808G on DAS

VERIFY status of 2/3RIC-7808G on Home page matches DAS Home page matches LCOAR/EDMR book. LCOAR/EDMR book.

2/3RIC-7808G on DAS Trend

VERIFY 2/3RIC-7808G on DAS page shows NORMAL status. Trend page shows NORMAL status.

DAS Trend page matches RDU

VERIFY DAS Trend page matches trend. RDU trend.

CUE: DAS Home page matches LCOAR/EDMR book.

CUE: DAS Trend page matches RDU trend.

9 Circle YES for 2/3RIC-7808G Channel CIRCLE YES for 2/3RIC-7808G Channel Check, Source Check and DAS Channel Check, Source Check and DAS Channel Check. Check.

10 Verify that all Steps in Section 1.0 are VERIFY that all Steps in Section 1.0 are complete and all Steps in Section 1.0 complete and all Steps in Section 1.0 and 2.0 and 2.0 required to be marked N/A, are required to be marked N/A, are correctly correctly marked N/A. marked N/A.

CUE: SRO Operations Supervisor acknowledges that all steps are complete or marked N/A and initials Step 1.9.

11 Verify the Release Permit Setpoint is COMPARE 2/3 RIC-7808G on DAS with less than the Rad Monitor HI-HI Release Permit and VERIFY the Release setpoint. Permit Setpoint is less than the Rad Monitor HI-HI setpoint.

Page 8 of 13

JPM: SONGS RO/SRO NRC JPM S-2 TITLE: Prepare and Release a Waste Gas Decay Tank

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 12 Verify CLOSED 2/3 FV-7202 Header VERIFY CLOSED 2/3FV-7202 Waste Gas Vent Valve. Decay TK HDR Vent Valve by OBSERVING green CLOSE light illuminated.

13* RESET 2/3 FQI-7202, Waste Gas RESET 2/3 FQI-7202, Waste Gas Disch HDR Discharge Totalizer. Total Flow by DEPRESSING the Totalizer Reset pushbutton.

14 Install a Caution Tag on 2/3FQI-7202 INSTALL a Caution Tag on 2/3FQI-7202 which states "Waste Gas release in which states "Waste Gas release in progress, progress, do not reset." do not reset."

15 Align the WGDT selected in Step 1.2. PREPARE to align WGDT T-084 by CIRCLING valves SA1902MU076 and SA1902MU032.

16 Close the Waste Gas N2 Valve. CLOSE the Waste Gas N2 Valve SA1902MU076.

CUE: Radwaste Operator reports that Waste Gas N2 Valve SA1902MU076 is closed.

17 Open the Waste Gas Outlet Valve. OPEN the Waste Gas Outlet Valve SA1902MU032.

CUE: Radwaste Operator reports that Waste Gas Outlet Valve SA1902MU032 is open.

18 Transfer the numeric identifier of the TRANSFER the numeric identifier of the valve positioned in Step 2.2.3.1 to Steps valve positioned in Step 2.2.3.1 to Steps 2.4.4.2 and 2.5.1. 2.4.4.2 and 2.5.1.

19 Transfer the numeric identifier of the TRANSFER the numeric identifier of the valve positioned in Step 2.2.3.2 to Step valve positioned in Step 2.2.3.2 to Step 2.5.2.

2.5.2.

Page 9 of 13

JPM: SONGS RO/SRO NRC JPM S-2 TITLE: Prepare and Release a Waste Gas Decay Tank

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 20 ENSURE 2/3PV-7814, Waste Gas ENSURE 2/3PV-7814, Waste Gas Discharge Discharge Header Control Valve, Header Control Valve, is aligned.

is aligned.

CUE: Radwaste Operator reports that Step 2.2.4 is complete.

21* In AUTO, ADJUST 2/3FIC-7202 SELECT 2/3FIC-7202, Waste Gas Decay TK Operator Setpoint (OSP) to 50 (100% of HDR Vent Control to AUTO and PRESS OSP controller scale). (Operator Setpoint) and RAISE setpoint to 50% (100% of controller scale).

22* OPEN 2/3FV-7202 by depressing the DEPRESS 2/3FV-7202, Waste Gas Decay TK OPEN Pushbutton. HDR Vent Control OPEN pushbutton and OBSERVE the red OPEN light illuminated.

23 Record the Release Start Time. RECORD the Release Start Time on the Gaseous Effluent Release Permit Cover Sheet.

24 SLOWLY THROTTLE OPEN DIRECT the Radwaste Operator to SLOWLY SA1902MU089, WGDT to Exhaust THROTTLE OPEN SA1902MU089, WGDT Plenum. to Exhaust Plenum.

MO CUE: EXECUTE remote function WD55 to OPEN the Waste Gas Decay Tank Valve.

CUE: Radwaste Operator acknowledges to slowly throttle open SA1902MU089.

25 As required, ADJUST 2/3 PIC-7814 to DIRECT the Radwaste Operator to ADJUST establish stable flow and pressure. 2/3 PIC-7814 to establish stable flow and pressure.

CUE: Radwaste Operator reports stable flow and pressure on 2/3PIC-7814.

NOTE: The following steps represent the alternate path of this JPM.

Page 10 of 13

JPM: SONGS RO/SRO NRC JPM S-2 TITLE: Prepare and Release a Waste Gas Decay Tank

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 26 Verify 2/3 RIC-7808G, PVS OBSERVE 2/3 RIC-7808G, PVS Radmonitor Radmonitor is responding as expected to on DAS and DETERMINE that 2/3 RIC-release. 7808G is above alarm setpoint with a Unit 2 Critical Parameter Problem alarm (63B02) and NOT responding as expected.

27* CLOSE 2/3FV-7202, WGDT Header DEPRESS 2/3 FV-7202, Waste Gas Decay Vent Valve. TK HDR Vent Valve CLOSE pushbutton and OBSERVE green CLOSE light illuminated.

28 IMMEDIATELY notify the Shift Immediately NOTIFY the Shift Manager.

Manager.

TERMINATING CUE: Stop Time: ________

The Shift Manager has been notified.

This JPM is complete.

Page 11 of 13

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (does not meet threshold criterion of K/A 3.0 or greater for the RO, however performance of this evolution is required).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 12 of 13

REFERENCES:

SO123-III-5.9 Gaseous Effluent Release Permit Cover Sheet Gaseous Permit # U2-029-06 Prerelease Data (Prepared by Chemistry)

Unit . . . . . . . . . . 2 . . . . . . . . . . __________ / ___________

Source . . . . . . . . . T-084 . . . . . . . . . . __________ / ___________

Type . . . . . . . . . . Gas . . . . . . . . . . __________ / ___________

Release must start by:. . . . Tonight Date / Time . . . . . __________ / ___________

Permit expires on: :. . . . . Tomorrow Date / Time . . . . . __________ / ___________

Maximum release flow rate . 50 CFM . . . . . . . __________ / ___________

Number of fans required: . . 2 . . . . . . . . . . __________ / ___________

Monitor ID: . . . . . . . 2/3 RIC-7808G . . . . . . . . . . __________ / ___________

Recommended setpoint: . . . 3.04E+4 ci / sec __________ / ___________

ODCM Maximum Limit: . . 1.75E+5 ci / sec __________ / ___________

RELEASE PERMIT PREREQUISITES Initials Weather Evaluation Required DESIRABLE UNDESIRABLE (Note reason for release) ______________________________

N/A if continuous release LRZ N/A (Met. Tower unavailable)

CURRENT X / Q ___________________

COMMENTS:______________________________________________________________

Actual release data (Performed by Operations) Initials Setpoint installed for release 5.26 E+4 ci / sec LRZ Number of fans running . . . 2 . . . . . . . . . . LRZ Release start . . . . . . . ____________________ Date / Time . . . . . _______________

Monitor reading during release ____________________ ______ (Units or INOP) _______________

Release stop . . . . . . . ____________________ Date / Time . . . . . _______________

Maximum actual release rate . ____________________ CFM . . . . . . . _______________

Monitor returned to pre-release [ ] YES [ ] NO [ ] . . . . . . . . . . _______________

COMMENTS: ___________________________________________________________________________________________

REVIEWED BY: (SRO OPS SUPV) _______________________________________ DATE __________________

REVIEWED BY: (CHEMISTRY SUPV) _______________________________________ DATE __________________

REVIEWED BY: (EFFLUENT ENG) _______________________________________ DATE __________________

Ch(123) 5-90, Rev. 3 (12/01) Page 13 of 13

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO/SRO NRC JPM S-3 INITIAL PLANT CONDITIONS The plant has experienced a small break LOCA. The Control Room team has entered SO23-12-3, Loss of Coolant Accident.

TASK TO BE PERFORMED The Control Room Supervisor directs you to initiate SO23-12-11, EOI Supporting Attachments, , FS-7, Verify SI Throttle/Stop Criteria.

Page 1 of 11

JOB PERFORMANCE MEASURE SONGS RO/SRO NRC JPM S-3 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 11

DOCUMENTATION SONGS RO/SRO NRC JPM S-3 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 192210 TASK DESCRIPTION Perform HPSI Throttle / Stop action.

KA NUMBER: EA2.11 KA VALUES: RO 3.9 SRO 4.3 10CFR55.45 APPLICABILITY: 6, 7, 8, 12, 13

REFERENCES:

SO23-12-11, EOI Supporting Attachments, Attachment 2, FS-7 Verify SI Throttle / Stop, Rev. 4.

AUTHOR: Clark F. Baker DATE: 09/04/00 OPERATIONS REVIEW: R. Clement DATE: 09/05/00 APPROVED BY: W. Lyke DATE: 09/06/00 Page 3 of 11

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 2 Compared against SO23-12-3, Rev. 16 CFB 09/04/00 WLL and made corrections as required for established standards. Added changes to cause lowering of PZR level following initial throttle/stop response to drive Examinee to reestablish SI flow (RNO actions).

2-1 Changed setup page to establish the JJM 10/25/00 WLL final severity of the leak at 0% and set the future severity of the leak at 50%

that is triggered from the STOP pushbuttons of the Charging Pumps.

2-2 Compared against SO23-12-11, Rev. RCW 08/26/04 MRN

2. Updated set-up page. Added several new steps and CUEs. Minor wording changes.

2-3 Modified Initial Plant Conditions. RCW 09/13/04 AH 2-4 Minor modifications to Set-up page RCW 09/30/04 MRN and to JPM step 21 standard.

2-5 Compared against SO23-12-11, Rev. 4 LRZ 06/19/06 with minor wording changes required.

Page 4 of 11

SET-UP MACHINE OPERATOR:

Use IC #173 for 2006 NRC JPM exam.

Ensure Auxiliary Feedwater is set for 140 gpm to each SG with SG levels ~40% and slowly trending upward, with SBCS in AUTO.

This IC uses an event file for automatically adjusting break flow. Go to RUN after the JPM brief has taken place. Activate the event file after going to RUN.

Otherwise, use any at power IC, and perform the following:

Insert RC03 at 25% and allow to proceed until approximately 1345 psia, then reduce the severity of the malfunction to 0%. Ensure RCPs are stopped.

If HPSI P-018 is operating on Train A then HPSI P-019 should be operating on Train B.

If HPSI P-018 is operating on Train B then HPSI P-017 should be operating on Train A.

Ensure Auxiliary Feedwater is set for 140 gpm to each S/G with S/G levels ~40% and slowly trending upward, and ADVs set for MANUAL and 0% output.

Ensure Pressurizer level greater than 30% and not lowering.

After examinee has initially throttled SI flow to control PZR level, increase leak rate to ~50%.

This should be triggered from the OVERRIDE pushbuttons of Charging Pumps P-190, P-191, and P-192.

EXAMINER:

Provide examinee with a copy of SO23-12-11, EOI Supporting Attachments, Attachment 2, FS-7, Verify SI Throttle / Stop Criteria.

Page 5 of 11

JPM: SONGS RO/SRO NRC JPM S-3 TITLE: Verify SI Throttle / Stop Criteria

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide examinee with a copy of SO23-12-11, EOI Supporting Attachments, Attachment 2, FS-7, Verify SI Throttle / Stop Criteria.

1 VERIFY at least one S/G operating: OBSERVE Steam Generators have Steam Start Time: _______

SBCS - available OR ADV - available Bypass Control System operating and AND Feedwater - available. feedwater is available to both SGs.

2 VERIFY Pressurizer Level - greater OBSERVE Pressurizer Level instruments than 30% AND - NOT lowering. 2LIC-0110, 2LR-0110A/B, 2LI-0110A1/A2 or 2LI-0103 and VERIFY level greater than 30% and not lowering.

3 VERIFY Core Exit Saturation Margin OBSERVE Core Exit Saturation Margin on greater than or equal to 20EF: QSPDS (page 611) or CFMS (page 311) and QSPDS page 611 VERIFY Core Exit Saturation Margin greater CFMS page 311 than 20EF.

4 VERIFY Reactor Vessel level - greater OBSERVE Reactor Vessel level on QSPDS than or equal to 100% (Plenum): (page 622) or CFMS (page 312) or use QSPDS page 622 Attachment 4 and VERIFY Reactor Vessel CFMS page 312 level $ 100% (Plenum).

Attachment 4 5 RCS Cooldown not in progress. VERIFY RCS Cooldown not in progress.

CUE: There is no cooldown in progress.

NOTE: To satisfy the critical nature of stopping/throttling HPSI flow, each train must have, at a minimum, the valves throttled or the pump stopped. Additionally, it may be required to stop one or all Charging Pumps to stabilize PZR level. Sequence of steps is NOT critical, however, injection flow must be re-established for the examinee to be successful.

Page 6 of 11

JPM: SONGS RO/SRO NRC JPM S-3 TITLE: Verify SI Throttle / Stop Criteria

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Mark N/A the steps below that were not required to be performed.

6 VERIFY SI pumps - NOT operating per VERIFY SI pumps NOT operating per SO23-12-9, Attachment FR-1, SO23-12-9, Attachment FR-1, RECOVERY -

RECOVERY - REACTIVITY REACTIVITY CONTROL to satisfy RC-3 CONTROL to meet RC-3 Success Path. Success Path.

CUE: Safety Injection Pumps are NOT operating to satisfy RC-3 Success Path.

NOTE: Examinee may elect to either stop HPSI Pumps and/or close HPSI Loop Isolation Valves.

7* OVERRIDE and CLOSE HV-9333. DEPRESS white OVERRIDE pushbutton, then DEPRESS 2HV-9333, HDR 1 to Loop 2B JOG CLOSE pushbutton until green JOG CLOSE light is illuminated and red JOG OPEN light is extinguished.

8* OVERRIDE and CLOSE HV-9324. DEPRESS white OVERRIDE pushbutton, then DEPRESS 2HV-9324, HDR 1 to Loop 1A JOG CLOSE pushbutton until green JOG CLOSE light is illuminated and red JOG OPEN light is extinguished.

9* OVERRIDE and CLOSE HV-9327. DEPRESS white OVERRIDE pushbutton, then DEPRESS 2HV-9327, HDR 1 to Loop 1B JOG CLOSE pushbutton until green JOG CLOSE light is illuminated and red JOG OPEN light is extinguished.

Page 7 of 11

JPM: SONGS RO/SRO NRC JPM S-3 TITLE: Verify SI Throttle / Stop Criteria

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 10* OVERRIDE and CLOSE HV-9330. DEPRESS white OVERRIDE pushbutton, then DEPRESS 2HV-9330, HDR 1 to Loop 2A JOG CLOSE pushbutton until green JOG CLOSE light is illuminated and red JOG OPEN light is extinguished.

11* OVERRIDE and STOP the Train A DEPRESS white OVERRIDE pushbutton, HPSI pump. then DEPRESS 2HS-9393-1, HPSI Pump 2P-018 STOP pushbutton and OBSERVE green STOP light illuminated and ammeter at zero.

12* OVERRIDE and CLOSE HV-9332. DEPRESS white OVERRIDE pushbutton, then DEPRESS 2HV-9332, HDR 2 to Loop 2B JOG CLOSE pushbutton until green JOG CLOSE light is illuminated and red JOG OPEN light is extinguished.

13* OVERRIDE and CLOSE HV-9323. DEPRESS white OVERRIDE pushbutton, then DEPRESS 2HV-9323, HDR 2 to Loop 1A JOG CLOSE pushbutton until green JOG CLOSE light is illuminated and red JOG OPEN light is extinguished.

14* OVERRIDE and CLOSE HV-9326. DEPRESS white OVERRIDE pushbutton, then DEPRESS 2HV-9326, HDR 2 to Loop 1B JOG CLOSE pushbutton until green JOG CLOSE light is illuminated and red JOG OPEN light is extinguished.

Page 8 of 11

JPM: SONGS RO/SRO NRC JPM S-3 TITLE: Verify SI Throttle / Stop Criteria

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 15* OVERRIDE and CLOSE HV-9329. DEPRESS white OVERRIDE pushbutton, then DEPRESS 2HV-9329, HDR 2 to Loop 2A JOG CLOSE pushbutton until green JOG CLOSE light is illuminated and red JOG OPEN light is extinguished.

16* OVERRIDE and STOP the Train B DEPRESS white OVERRIDE pushbutton, HPSI pump. then DEPRESS 2HS-9394-2, HPSI Pump 2P-019 STOP pushbutton and OBSERVE green STOP light illuminated and ammeter at zero.

17 VERIFY Charging pumps - NOT VERIFY Charging pumps - NOT operating operating per SO23-12-9, Attachment per SO23-12-9, Attachment FR-1, FR-1, RECOVERY - REACTIVITY RECOVERY - REACTIVITY CONTROL to CONTROL to meet RC-2 Success Path. meet RC-2 Success Path.

CUE: Charging pumps are NOT operating to satisfy RC-2 Success Path.

18 VERIFY Pressurizer level - less than VERIFY Pressurizer level less than 80%.

80%.

NOTE: Charging pumps may be stopped in any order.

19* STOP Charging Pumps as required one DEPRESS white OVERRIDE pushbutton, at a time. then DEPRESS 2P-190, Charging Pump STOP pushbutton and OBSERVE green STOP light illuminated.

20* STOP Charging Pumps as required one DEPRESS white OVERRIDE pushbutton, at a time. then DEPRESS 2P-191, Charging Pump STOP pushbutton and OBSERVE green STOP light illuminated.

Page 9 of 11

JPM: SONGS RO/SRO NRC JPM S-3 TITLE: Verify SI Throttle / Stop Criteria

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 21* STOP Charging Pumps as required one DEPRESS white OVERRIDE pushbutton, at a time. then DEPRESS 2P-192, Charging Pump STOP pushbutton and OBSERVE green STOP light illuminated.

NOTE: When the first Charging Pump is stopped, RCS leakage will increase to ~50%.

NOTE: The following steps represent the alternate path of this JPM.

22 MAINTAIN criteria of steps a through RECOGNIZE lowering PZR level and e - satisfied. IMPLEMENT RNO actions for Steps

b. through d.

NOTE: After the Examinee has recognized the changing plant condition and has taken action(s) to raise SI flow, the JPM can be terminated when a HPSI Pump is started and one (1) HPSI Loop Injection Valve is throttle opened.

23* IF any criteria of steps b through d - PERFORM one (1) or all of the following:

NOT satisfied,

START Charging Pumps as required.

OPERATE Charging and SI systems as necessary to maintain

START any HPSI Pump and Throttle /Stop criteria - satisfied. THROTTLE OPEN at least one (1) HPSI Loop Injection Valve.

THROTTLE Loop Injection Valves - as required.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 10 of 11

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 11 of 11

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO/SRO NRC JPM S-4 INITIAL PLANT CONDITIONS Bus 2A06 is cross-tied to Bus 3A06 due to a recent electrical transient resulting in a transfer to the bus tie.

TASK TO BE PERFORMED The Control Room Supervisor directs a Restoration from 1E 4 kV Bus 2A06 to Bus 3A06 Cross-Tie Operations by aligning Bus 2A06 to the Reserve Auxiliary Transformer 2XR2.

Page 1 of 10

JOB PERFORMANCE MEASURE SONGS RO/SRO NRC JPM S-4 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 10

DOCUMENTATION SONGS RO/SRO NRC JPM S-4 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 271 TASK DESCRIPTION Manually transfer 1E 4KV bus power source.

KA NUMBER: 062 A4.07 KA VALUES: RO 3.1 SRO 3.1 10CFR55.45 APPLICABILITY: 6

REFERENCES:

SO23-6-2, Transferring of 4 kV Buses, Rev 10-4.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 10

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 Compared against SO23-6-2, Rev. 7 LRZ 06/15/00 WLL with minor changes required. Updated format.

2 Updated SO23-6-2 Revision and JGA 08/04/03 KR changed JPM to reflect A06 vice A04.

2-1 Compared against SO23-6-2, Rev. 7 LRZ 08/04/03 MRN with minor changes required. Updated format.

3 Compared against SO23-6-2, Rev. 10- LRZ 06/19/06 REV 4 with changes required. Steps were deleted / replaced and re-ordered as necessary for the updated procedure.

Page 4 of 10

SET-UP MACHINE OPERATOR:

Use IC #172 for the 2006 NRC JPM Exam.

Otherwise, use any 100% power IC and cross-tie Bus 2A06 to Unit 3 Bus 3A06, using SO23 2, Section 6.2.

EXAMINER:

Provide the examinee with a copy of SO23-6-2, Transferring of 4 kV Buses.

Page 5 of 10

JPM: SONGS RO/SRO NRC JPM S-4 TITLE: Restore from Bus 2A06 to Bus 3A06 Cross-Tie Operations

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the examinee with a copy of SO23-6-2, Transferring of 4 kV Buses.

1 Ensure the affected Switchgear Room DISPATCH PEO to clear personnel from is clear of all unnecessary personnel Unit 2 and 3 Train B Switchgear Rooms and maintain it clear until after 4kV and MAINTAIN them clear.

bus transfer is complete.

CUE: Unit 2 and 3 Train B Switchgear Rooms are clear.

2* SELECT 2HS-1627-2, ESF B Sync. PLACE synchroscope, 2/3SI-1627A, in Master Control, to ON. service by TURNING key operated Train B SYNC CKT Control, 2HS-1627-2 ESF B SYNC Master Control switch to ON.

3* DEPRESS the SYNC pushbutton for DEPRESS white SYNC pushbutton for the INCOMING Transformer breaker Incoming Breaker 2HS-1637-2, RES AUX to energize the synchronizing circuit: XFMR 2XR2 FDR Breaker 2A0618.

2A0618, 2XR2 Reserve Aux.

Transformer 4 VERIFY ILLUMINATED the OBSERVE white SYNC light illuminated incoming Transformer breaker SYNC on 2HS-1637-2, RES AUX XFMR 2XR2 pushbutton. FDR Breaker 2A0618.

5 VERIFY ILLUMINATED the SYNC OBSERVE white SYNC IN MODE light IN MODE light. illuminated on Train B SYNC CKT Control, 2HS-1627-2 ESF B SYNC Master Control Switch.

Page 6 of 10

JPM: SONGS RO/SRO NRC JPM S-4 TITLE: Restore from Bus 2A06 to Bus 3A06 Cross-Tie Operations

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6 VERIFY EXTINGUISHED the VERIFY amber SYNC RELAYS SYNC RELAYS TROUBLE light. TROUBLE light extinguished on Train B SYNC CKT Control, 2HS-1627-2 ESF B SYNC Master Control Switch.

7 VERIFY the synchroscope moves to VERIFY synchroscope 2/3SI-1627A moves the straight up (12 o'clock) position. to straight up (12 o'clock) position.

8 If synchronizing circuit does not DETERMINE that the synchronizing circuit respond correctly, then remove the has responded correctly.

synchronizing circuit from service, and contact Electrical Test.

9 VERIFY MATCHED Incoming and VERIFY Incoming and Running voltages Running voltages. matched on 2/3EI-1627A, Running Volts &

2/3EI-1627B, Incoming Volts.

10 VERIFY MATCHED Incoming and VERIFY Incoming and Running Running frequencies. frequencies matched on 2/3SI-1627C, Running Hertz & 2/3SI-1627D, Incoming Hertz.

11* CLOSE the INCOMING Transformer DEPRESS 2HS-1637-2, RES AUX XFMR breaker: 2XR2 FDR Breaker 2A0618 CLOSE

2A0618, 2XR2 Reserve Aux. pushbutton and OBSERVE red CLOSE Transformer light illuminated.

12 VERIFY ANNUNCIATED OBSERVE 2UA63C58 - 2A06 / 3A06 2UA63C58 2A06 / 3A06 PARALLELED alarm on Unit 2 Panel 63C.

PARALLELED.

Page 7 of 10

JPM: SONGS RO/SRO NRC JPM S-4 TITLE: Restore from Bus 2A06 to Bus 3A06 Cross-Tie Operations

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 13 VERIFY 3UA63C58 3A06 / 2A06 OBSERVE 3UA63C58 - 3A06 / 2A06 PARALLELED REMAINS PARALLELED is still in alarm on Unit 3 ANNUNCIATED. Panel 63C.

CUE: 3UA63C58 - 3A06 / 2A06 PARALLELED is still in alarm.

14* OPEN (TRIP) 2A0619, Bus Tie 2A06 DEPRESS 2HS-1639A2, Bus Tie 2A06 to to 3A06 Feeder Breaker. 3A06 FDR BKR 2A0619 TRIP pushbutton and OBSERVE green TRIP light illuminated.

15 VERIFY RESET 2UA63C58 2A06 / RESET 2UA63C58 - 2A06 / 3A06 3A06 PARALLELED. PARALLELED alarm on Unit 2 Panel 63C.

16 VERIFY RESET 3UA63C58 3A06 / RESET 3UA63C58 - 3A06 / 2A06 2A06 PARALLELED. PARALLELED alarm on Unit 3 Panel 63C.

CUE: 3UA63C58 - 3A06 / 2A06 PARALLELED alarm is reset.

17* DEPRESS the SYNC pushbutton for DEPRESS white SYNC pushbutton for the INCOMING Transformer breaker Incoming Breaker 2HS-1637-2, RES AUX to de-energize the synchronizing XFMR 2XR2 FDR Breaker 2A0618.

circuit:

2A0618, 2XR2 Reserve Aux.

Transformer 18 VERIFY EXTINGUISHED the OBSERVE white SYNC light extinguished INCOMING Transformer breaker on 2HS-1637-2, RES AUX XFMR 2XR2 SYNC pushbutton. FDR Breaker 2A0618.

Page 8 of 10

JPM: SONGS RO/SRO NRC JPM S-4 TITLE: Restore from Bus 2A06 to Bus 3A06 Cross-Tie Operations

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 19* SELECT 2HS-1627-2, ESF B Sync. REMOVE synchroscope, 2/3SI-1627A, Master Control, to OFF. from service by TURNING key operated Train B SYNC CKT Control, 2HS-1627-2 ESF B SYNC Master Control switch to OFF.

20 Verify bus 2A06 voltage is stable. OBSERVE 2EI-1641-2, 4.16 KV Bus 2A06 Volts and VERIFY Bus voltage indication is stable.

21* OPEN (TRIP) 3A0603, Bus Tie 3A06 DEPRESS 3HS-1639A2, Bus Tie 3A06 to to 2A06 Feeder Breaker 2A06 FDR BKR 3A0603 TRIP pushbutton and OBSERVE green TRIP light illuminated.

22* Return Bus Tie Breakers transfer DEPRESS 3HS-1639B2, Bus Tie 3A06 to controls to automatic, as follows: 2A06 FDR BKR 3A0603 AUTO Selector SELECT 3HS-1639B2, 3A06 to 2A06 pushbutton and OBSERVE amber AUTO Tie Breaker 3A0603 AUTO / light illuminated.

MANUAL Transfer Switch, to AUTO.

23* Return Bus Tie Breakers transfer DEPRESS 2HS-1639B2, Bus Tie 2A06 to controls to automatic, as follows: 3A06 FDR Breaker 2A0619 Selector SELECT 2HS-1639B2, 2A06 to 3A06 AUTO pushbutton and OBSERVE amber Tie Breaker 2A0619 AUTO / AUTO light illuminated.

MANUAL Transfer Switch, to AUTO.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 9 of 10

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 10 of 10

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO/SRO NRC JPM S-5 INITIAL PLANT CONDITIONS Unit 2 is at 98.7% power.

RCS Boron Concentration is 1538 ppm via Chemistry sample. BAMU tanks are 5750 ppm in T-071 and 5749 ppm in T-072.

The plant is experiencing an identified rise in RCS temperature and an inadvertent dilution event is confirmed.

TASK TO BE PERFORMED The Control Room Supervisor directs you to perform SO23-13-11, Emergency Boration of the RCS / Inadvertent Dilution or Boration to mitigate the effects of an inadvertent dilution.

Page 1 of 11

JOB PERFORMANCE MEASURE SONGS RO/SRO NRC JPM S-5 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 11

DOCUMENTATION SONGS RO/SRO NRC JPM S-5 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: NO POSITION: CO TASK SYS ID: 252607 TASK DESCRIPTION Respond to an inadvertent dilution / emergency boration of the RCS.

KA NUMBER: 004 A2.06 KA VALUES: RO 4.2 SRO 4.3 10CFR55.45 APPLICABILITY: 5, 6, 7, 10

REFERENCES:

SO23-13-11, Emergency Boration of the RCS/Inadvertent Dilution or Boration, Rev. 8.

SO23-3-2.2, Makeup Operations, Rev. 19-4.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 11

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

Page 4 of 11

SET-UP MACHINE OPERATOR:

Use IC #172 for the 2006 NRC JPM Exams.

Otherwise use any 100% IC and perform the following:

Ensure Primary Water Pump 2P-200 Discharge Valve is circled on CR-56.

Lower 2TIC-0223 OSP to 110°F.

Set the Operator Setpoint (OSP) to 28 for PMW flow controller and 15 for BA flow controller, respectively.

EXAMINER:

Provide the Examinee with a copy of SO23-13-11, Emergency Boration of the RCS/Inadvertent Dilution or Boration and SO23-3-2.2, Makeup Operation.

Prior to repeating the JPM, perform the following with the Simulator in RUN:

Depress 2TV-0224B, Ion Exchanger Bypass Valve blue MANUAL pushbutton followed by the green ION EXCH pushbutton and then the amber AUTO pushbutton. This sets up 2TV-0224B for appropriate actions in Step 5e of SO321-13-11.

Ensure local PMS page MAIN MENU is double selected to preclude history use of previous examinee.

Ensure Operator Setpoint (OSP) set to 28 for PMW flow controller and 15 for BA flow controller, respectively.

Page 5 of 11

JPM: SONGS RO/SRO NRC JPM S-5 TITLE: Respond to an Inadvertent Dilution

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Ensure the setup page information for 2TV-0224B, PMS Main Menus is complete.

NOTE: Provide the examinee with a copy of SO23-13-11, Emergency Boration of the RCS/Inadvertent Dilution or Boration.

1 VERIFY Refueling NOT in progress. DETERMINE Refueling NOT in progress Start Time: _______

with Unit at power.

2* PLACE Makeup Mode Selector to PLACE 2HS-0210, Makeup Mode Selector to MANUAL. MANUAL.

3 ENSURE Primary Makeup Water OBSERVE 2P-200 and 2P-201 Primary Pumps STOPPED. Makeup Water Pumps green STOP lights illuminated.

4 ENSURE Letdown Heat Exchanger DEPRESS SEL pushbutton on 2TIC-0223, Outlet temperature maintaining at 120°F Letdown HX 2E062 Temp Control and with TIC-0223, CCW Temperature OBSERVE TIC-0223 < 120°F or OBSERVE Controller, in AUTO. 2TI-0224, Letdown HX 2E062 Outlet Temp <

120°F on CR58.

NOTE: The following step represents the alternate path of this JPM.

5* PLACE TIC-0223 in MANUAL and DEPRESS A/M pushbutton on 2TIC-0223 adjust as necessary. Letdown HX 2E062 Temp Control to place in MANUAL then PUSH () pushbutton to bring controller output to 120ºF or SELECT OSP and PUSH () pushbutton to RAISE setpoint in AUTO to 120ºF.

Page 6 of 11

JPM: SONGS RO/SRO NRC JPM S-5 TITLE: Respond to an Inadvertent Dilution

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6* PLACE 2(3)TV-0224B, CVCS Ion DEPRESS the MANUAL pushbutton then the Exchanger in BYPASS BYPASS pushbutton on 2TV-0224B, Ion Exchanger Bypass Valve and OBSERVE blue MANUAL light and red BYPASS lights illuminated with amber AUTO and green ION EXCH lights extinguished.

7 VERIFY Deborating Ion Exchanger VERIFY Deborating Ion Exchanger NOT in NOT in service. service by OBSERVING the CVCS Ion Exchanger Operator Aid on CR-56 or REQUEST this information from Chemistry or Radwaste Operator.

CUE: Chemistry reports the Deborating Ion Exchanger is not in service.

8 ENSURE dilution flow paths isolated: CONTACT the Radwaste Operator to CLOSE S21901MU589, Demineralized Water to

CLOSE S2(3)1901MU589, Charging Pump Suction in Room 410A.

Demineralized Water to Charging Pump Suction [RM 410A(B)].

CUE: Radwaste Operator reports that valve S2-1901-MU589 is closed.

9 ENSURE dilution flow paths isolated: CONTACT the Radwaste Operator to CLOSE S21415MU152, Nuclear Condensate to

CLOSE S2(3)1415MU152, Nuclear Purification Ion Exchanger ME-074 in Room Condensate to Purification Ion 305G.

Exchanger ME-074

[RM 305G(CC)].

CUE: Radwaste Operator reports that valve S2-1415-MU152 is closed.

Page 7 of 11

JPM: SONGS RO/SRO NRC JPM S-5 TITLE: Respond to an Inadvertent Dilution

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 10 ENSURE dilution flow paths isolated: CONTACT the Radwaste Operator to CLOSE S21415MU439, Nuclear Condensate to

CLOSE S2(3)1415MU439, Nuclear Purification Ion Exchanger ME-075 in Room Condensate to Purification Ion 305H.

Exchanger ME-075

[RM 305H (DD)].

CUE: Radwaste Operator reports that valve S2-1415-MU439 is closed.

11 ENSURE dilution flow paths isolated: CONTACT the Radwaste Operator to CLOSE S21415MU151, Nuclear Condensate to

CLOSE S2(3)1415MU151, Nuclear Purification Ion Exchanger ME-078 in Room Condensate to Purification Ion 305F.

Exchanger ME-078.

[RM 305F (BB)]

CUE: Radwaste Operator reports that valve S2-1415-MU151 is closed.

12 ENSURE FIC-0210X, PMW Flow ENSURE FIC-0210X, PMW Flow Controller, Controller, and FIC-0210Y, BAMU and FIC-0210Y, BAMU Flow Controller, are Flow Controller, are set for correct set for correct blended makeup per SO23 blended makeup per SO23-3-2.2, 2.2, Section to Establish Automatic Makeup Section to Establish Automatic Makeup Mode.

Mode.

NOTE: Provide the examinee with a copy of SO23-3-2.2, Makeup Operations.

13 LOCATE Section 6.3 Establish LOCATE Section 6.3 Establish Automatic Automatic Makeup Mode in SO23 Makeup Mode in SO23-3-2.2, Makeup 2.2, Makeup Operations. Operations.

CUE: If necessary, direct the examinee to use the PMS Computer for the RCS Makeup calculation.

Page 8 of 11

JPM: SONGS RO/SRO NRC JPM S-5 TITLE: Respond to an Inadvertent Dilution

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 14 Determine the existing RCS boron On any PMS Computer Terminal, SELECT concentration from the most recent Main Menu / User Function / Coolant chemistry sample analysis. System to access RCS Calculation.

15 Enter selected BAMU Tank PPM value ENTER 5750 ppm for BAMU Tank T-071 or and the current RCS PPM value into 5749 ppm for BAMU Tank T-072 for BAMU PMS. Tank Concentration into PMS Computer Terminal.

16 Enter selected BAMU Tank PPM value ENTER 1538 ppm as the Current RCS Boron and the current RCS PPM value into Concentration into PMS Computer Terminal.

PMS.

CUE: The CRS directs you to set Total Flowrate for 44 gpm.

17 Enter TOTAL desired Makeup flowrate ENTER 44 gpm desired Makeup flowrate into into PMS to obtain the required BAMU PMS and OBSERVE the required BAMU and and PMW flowrates for this blend. PMW flowrates for this blend.

18* POSITION 2FIC-0210Y, BAMU Flow POSITION 2FIC-0210-Y, Flow Control to Controller to AUTOMATIC and SET AUTO and SET to 11.8 gpm.

to the required flowrate.

19* POSITION 2FIC-0210-X, Flow Control POSITION 2FIC-0210-X, Flow Control to to AUTOMATIC and SET to the AUTO and SET to 32.2 gpm.

required flowrate.

20 Ensure the selected BAMU Pump is ENSURE the selected BAMU Pump is associated with the BAMU Tank PPM associated with the BAMU Tank PPM value value entered into PMS. entered into PMS.

NOTE: If examinee entered 5750 ppm, then ensure BAMU Tank T-071 and BAMU Pump 2P-174 is selected. If examinee entered 5749 ppm, then ensure BAMU Tank T-072 and BAMU Pump 2P-175 is selected.

Page 9 of 11

JPM: SONGS RO/SRO NRC JPM S-5 TITLE: Respond to an Inadvertent Dilution

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 21 Ensure the Discharge Valve is circled VERIFY PMW Pump P-200 is circled.

Open for the PMW Pump selected.

22 SELECT FV-9253, Blended Makeup to SELECT 2FV-9253, Blended Makeup to VCT VCT Isolation for AUTOMATIC Block Valve to AUTO.

operation.

23* SELECT HS-0210, Makeup Mode SELECT 2HS-0210, Makeup Mode Selector Selector to AUTOMATIC. to AUTO.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 10 of 11

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 11 of 11

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO/SRO NRC JPM S-6 INITIAL PLANT CONDITIONS Unit 2 is in MODE 3.

A Unit heat up is in progress to the point of starting the fourth Reactor Coolant Pump (RCP) P-001.

All actions of SO23-3-1.7, Reactor Coolant Pump Operation, through Step 6.1.17 are complete.

An Operator is stationed at the Reactor Coolant Pump (RCP) in Containment.

TASK TO BE PERFORMED The Control Room, Supervisor directs you to start RCP P-001 using SO23-3-1.7, Reactor Coolant Pump Operation, beginning with Step 6.1.18.

Page 1 of 12

JOB PERFORMANCE MEASURE RO/SRO NRC JPM S-6 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 12

DOCUMENTATION RO/SRO NRC JPM S-6 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 12 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 192368 TASK DESCRIPTION Startup a Reactor Coolant Pump.

KA NUMBER: 003 A4.06 KA VALUES: RO 2.9 SRO 2.9 10CFR55.45 APPLICABILITY: 5, 6, 7, 8

REFERENCES:

SO23-3-1.7, Reactor Coolant Pump Operation, Rev. 27.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 12

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 Compared against SO23-3-1.7, Rev. LRZ 06/19/06 REV 27 with minor changes required.

Modified JPM to identify different conditions that require tripping the RCP.

Page 4 of 12

SET-UP MACHINE OPERATOR:

Use IC #176 for 2006 NRC Exam and display PMS Trend Group Data page for RCP P001 by performing the following:

Go to MAIN MENU on PMS.

Select MAIN POINTS.

Select POINT I.

Point Type Selected to SERVER GROUP.

Select RCP 1 ARMS.

Otherwise, perform the following using any MODE 4 IC with RCS temperature > 400ºF:

DISPLAY PMS Trend Group Data page for RCP P001 per instructions above.

INSERT Key #38, CPC A Trip Bypass to ON.

INSERT Key #42, CPC B Trip Bypass to ON.

INSERT Key #46, CPC C Trip Bypass to ON.

INSERT Key #50, CPC D Trip Bypass to ON.

Override Annunciator 56C34 one minute after starting P-001.

EXAMINER:

Provide the Examinee with a copy of SO23-3-1.7, Reactor Coolant Pump Operation completed to Step 6.1.17.

Page 5 of 12

JPM: SONGS RO/SRO NRC JPM S-6 TITLE: Startup a Reactor Coolant Pump

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Ensure the setup page information for PMS Trend Group Data is complete.

NOTE: Provide the examinee with a copy of SO23-3-1.7, Reactor Coolant Pump Operation completed to Step 6.1.17.

1* START one Oil Lift Pump by selecting DEPRESS the NORMAL pushbutton on Start Time: _______

the NORMAL mode. either 2HS-9108A, 2P001 Oil Lift Pump 2P260, or 2HS-9109A, 2P001 Oil Lift Pump 2P261 and VERIFY the amber NORMAL light is illuminated.

NOTE: Annunciator alarm 56C33 will come in and reset. This is an expected alarm.

2 ENSURE the second oil lift pump DEPRESS the STANDBY pushbutton on selected to STANDBY either 2HS-9108A, 2P001 Oil Lift Pump 2P260 or 2HS-9109A, 2P001 Oil Lift Pump 2P261, whichever was not started in the previous step and VERIFY the amber STANDBY light is illuminated.

CUE: Two minutes has elapsed.

3* After the Oil Lift System has run DEPRESS the NORMAL pushbutton on approximately 2 minutes, then START either 2HS-9166, 2P001 ARRD Pump 2P399 one ARRD Lube Oil Pump by selecting or 2HS-9167, 2P001 ARRD Pump 2P400 and the NORMAL mode. VERIFY the amber NORMAL light is illuminated.

Page 6 of 12

JPM: SONGS RO/SRO NRC JPM S-6 TITLE: Startup a Reactor Coolant Pump

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 4 ENSURE the second ARRD pump is DEPRESS the STANDBY pushbutton on available by selecting the STANDBY either 2HS-9166, 2P001 ARRD Pump 2P399 mode. or 2HS-9167, 2P001 ARRD Pump 2P400, whichever was not started in the previous step and VERIFY the amber STANDBY light is illuminated.

Page 7 of 12

JPM: SONGS RO/SRO NRC JPM S-6 TITLE: Startup a Reactor Coolant Pump

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5 VERIFY the following alarms on Panel OBSERVE alarms on Panel CR56 are clear CR56 are clear prior to starting the prior to starting the RCP:

RCP:

RCP P001 THRUST BEARINGS

56C03 - RCP P001 THRUST BRG TEMP HI, 56C03 TEMP HI

RCP P001 LUBE OIL FLOW LO,

56C13 - RCP P001 LUBE OIL FLOW 56C13 LO

RCP P001 REVERSE ROTATION,

56C14 - RCP P001 REVERSE 56C14 ROTATION

RCP P001 OIL LIFT FLOW LO,

56C23 - RCP P001 OIL LIFT FLOW LO 56C23

RCP P001 OIL LIFT PRESS LO,

56C33 - RCP P001 OIL LIFT PRESS LO 56C33

RCP P001 CCW FLOW LO,

56C34 - RCP P001 CCW FLOW LO 56C34

RCP P001 ARRD LUBE OIL

56C43 - RCP P001 ARRD LUBE OIL FLOW LO, 56C43 FLOW LO 6 Verify PMS Points selected in Step OBSERVE the following alarms on PMS:

6.1.6 not in alarm:

Computer Trend Groups

Computer Trend Groups

RCP Controlled Bleed-off Flow

RCP Controlled Bleed-off Flow

CCW Seal Heat Exchanger

CCW Seal Heat Exchanger Temperature Temperature Hi Hi Page 8 of 12

JPM: SONGS RO/SRO NRC JPM S-6 TITLE: Startup a Reactor Coolant Pump

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

CUE: There are NO PMS points in alarm for the RCPs.

7 Verify RCP CONTROLLED BLEED- VERIFY RCP Controlled Bleed-Off Flow OFF FLOW (PMS) is clear or proper (PMS) is clear or proper RCP CBO flow for RCP CBO flow for the existing RCS the existing RCS pressure (~1.5 gpm).

pressure.

8 Verify CCW SEAL EXCHANGER VERIFY CCW Seal Exchanger Temperature TEMPERATURE HI(PMS) alarm is HI (PMS) alarm is clear.

clear.

9 Final configuration check is to PERFORM final configuration check:

VERIFY:

One Oil Lift Pump selected to

VERIFY one Oil Lift Pump, 2P260 and/or NORMAL 2P261 selected to NORMAL.

One Oil Lift Pump selected to

VERIFY one Oil Lift Pump, 2P260 and/or STANDBY 2P261 selected to STANDBY.

One ARRD Pump selected to

VERIFY one ARRD Pump, 2P399 and/or NORMAL 2P400 selected to NORMAL.

One ARRD Pump selected to

VERIFY one ARRD Pump, 2P399 and/or STANDBY 2P400 selected to STANDBY.

Vibration Alarm reset

VERIFY Vibration Alarm reset on 2HS-0151, Vibration Monitor Reset.

10 VERIFY RCP Zero Speed lamp OBSERVE 2SL-9107, RCP P001 Zero Speed illuminated. indication white light illuminated.

Page 9 of 12

JPM: SONGS RO/SRO NRC JPM S-6 TITLE: Startup a Reactor Coolant Pump

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 11 ANNOUNCE pump start using local ANNOUNCE pump start using local area area page. page.

12* START the Reactor Coolant Pump DEPRESS 2HS-9160A, 2P001 START P001. pushbutton and OBSERVE the red START light illuminated.

13 Verify motor amps stabilize between OBSERVE RCP P001 Motor Ammeter and 470 and 800 amps. VERIFY motor amps stabilize between 470 and 800 amps on 2HS-9160A handswitch.

NOTE/CUE: Annunciator alarm 50A51, Vibration and Loose Parts Monitor System Trouble will come in and reset.

This is an expected alarm when starting the RCP. If examinee attempts to research cause of the alarm, state that another operator is at 2L-194 verifying alarm was due to starting the RCP.

14 Closely MONITOR RCS pressure. Using any combination of Control Board, CFMS, QSPDS or PMS indicators, OBSERVE RCS pressure is satisfactory.

15 Verify the Oil Lift and ARRD Pumps OBSERVE:

automatically stop and Zero Speed lamp

Oil Lift Pump indicators for 2P001 Oil extinguishes.

Lift Pump 2P266 and 2P267, green STOP indicating lights illuminated.

ARRD Pump Indicators for 2P001 ARRD Pump 2P405 and 2P406, green STOP indicating lights illuminated.

Zero Speed white light extinguished.

16 Check RCP Oil Reservoir levels SAT. DIRECT an Operator to OBSERVE RCP P001 Oil Reservoir levels.

Page 10 of 12

JPM: SONGS RO/SRO NRC JPM S-6 TITLE: Startup a Reactor Coolant Pump

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

CUE: Operator at the pump reports oil levels are satisfactory.

17 Acknowledge Annunciator 56C34, RCP ACKNOWLEDGE annunciator 56C34, RCP P001 CCW FLOW LO. P001 CCW FLOW LO and REFER to 56C34 Annunciator Response Procedure.

CUE: If the applicant checks PMS tends for P001 CCW Flow Low, REPORT that CCW flow is low and temperature is rising.

NOTE: The following guidance is provided in Annunciator Response Procedure for 56C34.

18 If in Modes 3-5, then stop 2(3) MP-001, RECOGNIZE operation in Mode 3 and RCP. DETERMINE RCP P001 must be stopped.

NOTE: The following steps represent the alternate path of this JPM.

19* Trip RCP P001. DEPRESS 2HS-9160A, P001 STOP Pushbutton and VERIFY green STOP light illuminated.

20 ENSURE the Oil Lift Pump and ARRD Oil Lift Pump indicators for 2P001 Oil Lift Pump START. Pump 2P260 and 2P261, red START indicating lights illuminated.

21 ENSURE the Oil Lift Pump and ARRD ARRD Pump Indicators for 2P001 ARRD Pump START. Pump 2P399 and 2P400, red START indicating lights illuminated.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

Page 11 of 12

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (K/A is < 3.0, however, task is infrequently performed).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 12 of 12

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO/SRO NRC JPM S-7 INITIAL PLANT CONDITIONS The plant has experienced a LOCA inside Containment.

Containment pressure had risen to 18 psig and is now 10 psig and decreasing.

The Control Room Team is performing SO23-12-11, EOI Supporting Attachments, Attachment 2, Floating Steps and SO23-12-3, LOCA.

TASK TO BE PERFORMED The Control Room Supervisor directs you to initiate SO23-12-11, EOI Supporting Attachments, , FS-14, Terminate Containment Spray Operation.

Page 1 of 9

JOB PERFORMANCE MEASURE SONGS RO/SRO NRC JPM S-7 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 9

DOCUMENTATION SONGS RO/SRO NRC JPM S-7 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 2628 TASK DESCRIPTION Terminate Containment Spray.

KA NUMBER: 09 EA-2.11 KA VALUES: RO 3.1 SRO 3.7 10CFR55.45 APPLICABILITY: 6, 7, 8 and 12

REFERENCES:

SO23-12-11, EOI Supporting Attachments, Attachment 2, FS-14, Terminate Containment Spray Operation, Rev. 4.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1-2 Compared against SO23-12-11, LRZ 06/19/06 Rev. 4, with no changes required.

Page 4 of 9

SET-UP MACHINE OPERATOR:

Use IC #177 for the 2006 NRC JPM exam.

Otherwise, use a full power IC, insert a steam line break inside Containment (MS03A@1.5%)

until 14 psig in Containment then MS03A to 0%. Then insert RC03, small break LOCA at 20%.

Ensure RCPs are stopped and reduce break sized to ~1%.

EXAMINER:

Provide the Examinee with a copy of SO23-12-11, EOI Supporting Attachments, , FS-14, Terminate Containment Spray Operation.

NOTE: Verify that the CCW to Letdown Heat Exchanger valve is re-opened when repeating this JPM.

Page 5 of 9

JPM: RO-SRO NRC JPM S-7 TITLE: Terminate Containment Spray Operation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the examinee with a copy of SO23-12-11, EOI Supporting Attachments, Attachment 2, FS-14, Terminate Containment Spray Operation.

NOTE: Verify that the CCW to Letdown Heat Exchanger valve is re-opened when repeating this JPM.

1 Verify Containment pressure less than On CR-57 OBSERVE Containment Pressure Start Time: _______

14 psig and stable or lowering. Narrow Range PI-0351-1, 2, 3, and 4, Containment Pressure Wide Range PI-0352-1, 2, 3, and 4, Containment Pressure Wide-Wide Range PI-0353-1 or PI-0354-2 or QSPDS, page 503 less than 14 psig and stable or lowering.

2 Verify at least two Containment For Train A ECU E-399:

Emergency Cooling Units operating. OBSERVE 2HS-9953-1, Containment ECU 2E399(SW) red START light illuminated and Train A Train B 2HV-6370, CCW to CNTMT ECU 2E399 and E-399 E-400 2HV-6371, CCW from CNTMT ECU 2E399 E-401 E-402 red OPEN lights illuminated.

3 Verify at least two Containment For Train A ECU E-401:

Emergency Cooling Units operating. OBSERVE 2HS-9947-1, Containment ECU 2E401(NW) red START light illuminated and Train A Train B 2HV-6366, CCW to CNTMT ECU 2E401 and E-399 E-400 2HV-6367, CCW from CNTMT ECU 2E401 E-401 E-402 red OPEN lights illuminated.

Page 6 of 9

JPM: RO-SRO NRC JPM S-7 TITLE: Terminate Containment Spray Operation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 4 Verify at least two Containment For Train B ECU E-400:

Emergency Cooling Units operating. OBSERVE 2HS-9939-2, Containment ECU 2E400(SE) red START light illuminated and Train A Train B 2HV-6368, CCW to CNTMT ECU 2E400 and E-399 E-400 2HV-6369, CCW from CNTMT ECU 2E400 E-401 E-402 red OPEN lights illuminated.

5 Verify at least two Containment For Train B ECU E-402:

Emergency Cooling Units operating. OBSERVE 2HS-9955-2, Containment ECU 2E402(NE) red START light illuminated and Train A Train B 2HV-6372, CCW to CNTMT ECU 2E402 and E-399 E-400 2HV-6373, CCW from CNTMT ECU 2E402 E-401 E-402 red OPEN lights illuminated.

6 Request Shift Manager or Operations REQUEST this information from Shift Leader to evaluate Containment Spray - Manager or Operations Leader.

NOT required for:

1. Containment Iodine Removal.

2. Decay heat removal post-RAS.

CUE: Shift Manager reports Containment Spray is not required for Containment iodine removal or decay heat removal post-RAS.

7* Override and stop Containment Spray DEPRESS white OVERRIDE pushbutton, pump P-012. then DEPRESS 2HS-9395-1, Containment Spray Pump 2P-012 STOP pushbutton and OBSERVE green STOP light illuminated and ammeter at zero.

Page 7 of 9

JPM: RO-SRO NRC JPM S-7 TITLE: Terminate Containment Spray Operation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 8* Override and stop Containment Spray DEPRESS white OVERRIDE pushbutton, pump P-013. then DEPRESS 2HS-9396-2, Containment Spray Pump 2P-013 STOP pushbutton and OBSERVE green STOP light illuminated and ammeter at zero.

9* Override and close Containment Spray DEPRESS white OVERRIDE pushbutton, Pump Discharge valve 2HV-9367. then DEPRESS 2HV-9367, Cntmt Spray Hdr No 1 Control Valve JOG CLOSE pushbutton and OBSERVE green JOG CLOSE light illuminated and 0% indication on positioner.

10* Override and close Containment Spray DEPRESS white OVERRIDE pushbutton, Pump Discharge valve 2HV-9368. then DEPRESS 2HV-9368, Cntmt Spray Hdr No 2 Control Valve JOG CLOSE pushbutton and OBSERVE green JOG CLOSE light illuminated and 0% indication on positioner.

11 RESET CSAS per SO23-3-2.22, ESFAS RESET CSAS per SO23-3-2.22, ESFAS OPERATION. Operation.

TERMINATING CUE: Stop Time: ________

Another operator will reset CSAS.

This JPM is complete.

Page 8 of 9

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 9 of 9

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO NRC JPM S-8 INITIAL PLANT CONDITIONS A computer technician is preparing to perform investigative work on CPC Channel B.

CEAC No. 2 is OPERABLE.

CEAC No. 1 INOP flags are to be set in all 4 CPCs per direction of the Control Room Supervisor.

Shift Manager approval has been given.

TASK TO BE PERFORMED The Control Room Supervisor directs you to set CEAC No. 1 INOP flag in CPC Channel D per SO23-3-2.13, Core Protection/Control Element Assembly Calculator Operation starting at Step 6.3.10.

Page 1 of 10

JOB PERFORMANCE MEASURE SONGS RO NRC JPM S-8 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 10

DOCUMENTATION SONGS RO NRC JPM S-8 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 6 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 185094 TASK DESCRIPTION Change the value of a CPC addressable constant.

KA NUMBER: 012 A4.05 KA VALUES: RO 3.6 SRO 3.6 10CFR55.45 APPLICABILITY: 2, 4

REFERENCES:

SO23-3-2.13, Core Protection/Control Element Assembly Calculator Operation, Rev. 14.

SO23-XXXVII-4.7, Control of Core Protection Calculator Addressable Constants, Rev. 1-1.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 10

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 3 Compared against SO23-3-2.13, LRZ 16/19/06 REV Rev. 14 with changes required due to re-positioning of steps in procedure.

Page 4 of 10

SET-UP MACHINE OPERATOR:

Use IC-172 for 2006 NRC Exam.

Otherwise, use any 100% IC.

EXAMINER:

Provide Key #52 for the CPC D FUNCTION keylock, when located.

Provide examinee with a copy of SO23-3-2.13, Core Protection/Control Element Assembly Calculator Operation and a copy of ACEANOP@ Log page (from SO23-XXXVII-4.7), with the following items filled in:

Top of the page:

Unit CPC Channel CPC Point ID Program Label 2 D 062 CEANOP On the first (or last filled in) line:

Installer Initials: NFC Date: 10/20/06 Time: 0400 Before and After PID 406: 2.04 Before and After PID 179: 11.96 Value Entered: 0 CPC Readout Value: 0.0000 CPC Readout n: 0 Indep. Verif. Initials: HFD SM or CRS Initials: EMS Type I Notif. Comp.: Leave Blank Page 5 of 10

JPM: SONGS RO NRC JPM S-8 TITLE: Set CEAC No. 1 Inoperable Flag in CPC Channel D

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide examinee with a copy of SO23-3-2.13, Core Protection/Control Element Assembly Calculator Operation as well as the ACEANOP@ Log Page with appropriate information filled out.

CUE: All Addressable Constant changes will be documented using the Addressable Constant Change Log provided by the examiner.

CUE: Another operator has initiated SO23-3-3.25, Attachment for CEA Position Verification - Four Hour Monitoring.

CUE: If asked, report PID 334 and PID 406 are both greater than 1.70 and CEA INOP flag PID 062 will be changed without installing the DNBR and LPD trip bypasses per the Shift Manager.

1 SELECT CPC mode on the Operator PLACE the Calculator Select switch to the Module. CPC position and OBSERVE white CPC light ON.

2 If changing Addressable Constant Point DEPRESS the DISPLAY pushbutton and then IDs 060 through 104, then RECORD 1, 7, 9 on the keypad. RECORD the resulting the initial values for point IDs 179 and value in the appropriate column of the CPC 406 in the CPC Addressable Constants Addressable Constants Change Log.

Change Log.

3 If changing Addressable Constant Point DEPRESS the DISPLAY pushbutton and then IDs 060 through 104, then RECORD 4, 0, 6 on the keypad. RECORD the resulting the initial values for point IDs 179 and value in the appropriate column of the CPC 406 in the CPC Addressable Constants Addressable Constants Change Log.

Change Log.

4* TURN the FUNCTION keylock to ON OBTAIN Key #52 for CPC D FUNCTION (allows the operation of the function keylock, INSERT and TURN the FUNCTION keys). KEYS keylock to ON and OBSERVE amber FUNCTION KEYS light illuminated.

Page 6 of 10

JPM: SONGS RO NRC JPM S-8 TITLE: Set CEAC No. 1 Inoperable Flag in CPC Channel D

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5* DEPRESS CHANGE VALUE. DEPRESS the CHANGE VALUE pushbutton.

6* ENTER the 3-digit Point ID number; DEPRESS 0, 6, and 2 on the keypad.

leading zeros maybe required to make Point ID number three digits.

7 VERIFY the value for Point ID REFER to CPC Addressable Change displayed matches the value in the CPC Constants Log and VERIFY current PID 062 Addressable Change Constants Log. display matches the last entry in the log (0).

8* DEPRESS the ENTER key. DEPRESS the ENTER key.

9* ENTER the new value for the point DEPRESS 0, 0, 1 or 1 on the keypad. (Either being changed. method works.)

10* PRESS EXECUTE to complete the DEPRESS the EXECUTE key.

value change.

11 VERIFY that VALUE displayed on OBSERVE the VALUE display and VERIFY CPC Readout is correct. that it is 1.

12 TURN the FUNCTION keylock to OFF. TURN the FUNCTION KEYS keylock to the OFF position.

13 When all constants have been changed CONTACT another operator to PERFORM an for a given channel, then Operations Independent Verification.

INDEPENDENTLY VERIFY the FUNCTION keylock switch in OFF and make a log entry documenting status.

CUE: Another operator will perform the Independent Verification.

Page 7 of 10

JPM: SONGS RO NRC JPM S-8 TITLE: Set CEAC No. 1 Inoperable Flag in CPC Channel D

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 14 If changing Addressable Constant Point DEPRESS the DISPLAY pushbutton and then IDs 060 through 104, then RECORD 1, 7, 9 on the keypad. RECORD the resulting the final values for Point ID 179 and value in the appropriate column of the CPC 406 in the CPC Addressable Constants Addressable Constants Change Log.

Change Log.

15 If changing Addressable Constant Point DEPRESS the DISPLAY pushbutton and then IDs 060 through 104, then RECORD 4, 0, 6 on the keypad. RECORD the resulting the final values for Point ID 179 and value in the appropriate column of the CPC 406 in the CPC Addressable Constants Addressable Constants Change Log.

Change Log.

16 If changing Point ID 062 (CEAC INOP OBSERVE the CEAC INOP light illuminated Flag) to a value of 1, 2, or 3, then on the CPC Operators Module.

VERIFY the CEAC INOP light illuminates on the CPC Operators Module.

17 If changing Addressable Constant Point RECORD the value A1" in the @Value IDs 060 through 104, then ENSURE Entered@ Column of CPC Addressable that the CPC Addressable Constants Constants Change Log and RECORD the Change Log has been updated for the CPC Readout on the CPC Addressable Point ID that was changed, and that the Constants Change Log.

value recorded was actually entered into the CPC.

18 ENSURE Addressable Constant Point DEPRESS the DISPLAY pushbutton and then ID 419 is reset to 0. 419 on the keypad and OBSERVE the value for Point ID 419 is zero (0).

Page 8 of 10

JPM: SONGS RO NRC JPM S-8 TITLE: Set CEAC No. 1 Inoperable Flag in CPC Channel D

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 19 If a Type I Addressable Constant was CONTACT the Control Room Supervisor to changed, then ENSURE the TYPE I DETERMINE if a TYPE I Constant Change Constant Change Notification has been Notification has been completed.

completed.

TERMINATING CUE: Stop Time: ________

The TYPE I Constant Change Notification is being addressed by the CRS.

This JPM is complete.

Page 9 of 10

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 10 of 10

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO/SRO NRC JPM P-1 INITIAL PLANT CONDITIONS You are the Unit 2 (Unit 3) Primary ACO.

The Control Room has been evacuated due to dense smoke. All operators are stationed at plant locations required for this condition, and are available to perform actions at their locations.

The fire has resulted in a loss of offsite power. Bus 2A04 (Bus 3A04) is energized by Diesel Generator 2G002 (3G002).

Offsite power is now available and the Control Room is habitable.

The process of returning the Control Room command function to the Control Room is in progress using SO23-13-2, Shutdown from Outside the Control Room, Attachment 18.

TASK TO BE PERFORMED Transfer 1E 4 kV Bus 2A04 (Bus 3A04) from 2G002 (3G002) Diesel Generator to the Reserve Auxiliary Transformer per SO23-13-2, Shutdown from Outside the Control Room, Attachment 18, using Step 3.4.

When complete, shutdown Diesel Generator 2G002 (3G002) locally and transfer control back to the Control Room using SO23-2-13, Diesel Generator Operation, Attachment 2, Step 2.9.

Page 1 of 12

JOB PERFORMANCE MEASURE SONGS RO/SRO NRC JPM P-1 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 12

DOCUMENTATION SONGS RO/SRO NRC JPM P-1 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 11 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: PPEO TASK SYS ID: 705, 2802 TASK DESCRIPTION Perform Primary ACO assigned actions during shutdown of the unit from outside the Control Room.

Restore offsite power during response to an emergency event.

KA NUMBER: 068 AA1.31 KA VALUES: RO 3.9 SRO 4.0 10CFR55.45 APPLICABILITY: 6, 8

REFERENCES:

SO23-13-2, Shutdown From Outside the Control Room, Rev. 8-1.

SO23-2-13, Diesel Generator Operation, Rev. 26-3.

AUTHOR: L. Zilli DATE: 08/15/01 OPERATIONS REVIEW: W. Reeves DATE: 09/28/01 APPROVED BY: A. Hagemeyer DATE: 10/08/01 Page 3 of 12

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 2 Updated to current rev of procedure and LRZ 08/10/01 REV corrected Attachment numbers.

Incorporated new procedure SO23-3-3.23 used to shutdown the EDG and added critical steps as necessary to comply with procedure steps. Modified JPM so that it can be performed on either unit.

2-1 Updated SO23-13-2 Revision number and JGA 08/04/03 KR compared steps in JPM to updated references. Added more details to Initial Plant Condition. Added Cues at beginning of SO23-2-13 actions. Changed DG reference to reflect different procedure usage (SO23-2-13) 2-1 Compared against SO23-13-2, Rev. 8-1 LRZ 07/14/06 and SO23-2-13, Rev. 26-3 with changes required to address procedure revisions.

Page 4 of 12

SET-UP EXAMINER:

NOTE: Circle the unit on which this JPM will be performed and inform the examinee.

Provide the examinee with a copy of SO23-13-2, Shutdown From Outside the Control Room, Attachment 18, Returning the Control Room Command Function to the Control Room.

Provide the examinee with a copy of SO23-2-13, Diesel Generator Operation, Attachment 2, Diesel Generator Operation, with Section 1.0 and appropriate N/As filled in for a local stop from idle speed.

Page 5 of 12

JPM: SONGS RO/SRO NRC JPM P-1 TITLE: Transfer 4 kV Bus from EDG to the RAT then to the Control Room

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Circle the unit on which this JPM will be performed and inform the Examinee.

NOTE: Provide the examinee with a copy of SO23-13-2, Shutdown from Outside the Control Room, Attachment 18.

CUE: You have Safe Shutdown Kit 23 (33).

CUE: All steps in this JPM will be simulated.

1* ENSURE all Mode Select and Fire PLACE 2(3)HS-1670A1, Fire ISO. Switch Start Time: _______

Isolation Switches aligned to allow control DG Control on 2(3)L-160, in REM & LOC from the Control Room: position.

G-002 D/G Control on L-160 is selected to REMOTE & LOCAL.

CUE: The switch is in the Remote & Local position.

2* ENSURE all Mode Select and Fire PLACE 2(3)HS-1669A1, Fire ISO. Switch Isolation Switches aligned to allow control GOV. & EXCT. CONT on 2(3)L-160, in from the Control Room: REM & LOC position.

G-002 Gov. and Exct. Cont. on L-160 is selected to REMOTE & LOCAL.

CUE: The switch is in the Remote & Local position.

3* ENSURE all Mode Select and Fire PLACE 2(3)HS-9537E1, Fire ISO. Switch Isolation Switches aligned to allow control DG BLDG Fans on 2(3)L-160, in REM &

from the Control Room: LOC position.

G-002 D/G Building Fans on L-160 is selected to REMOTE & LOCAL.

CUE: The switch is in the Remote & Local position.

Page 6 of 12

JPM: SONGS RO/SRO NRC JPM P-1 TITLE: Transfer 4 kV Bus from EDG to the RAT then to the Control Room

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 4* ENSURE all Mode Select and Fire PLACE Fuel Oil Transfer Pump switches on Isolation Switches aligned to allow control 2L-160A (3L-161A) in the CONTROL from the Control Room: ROOM position:

Fuel Oil Transfer Pumps on L-160A

2(3)HS-5901B1 for Pump P093 (L-161A) selected to C.R.

2(3)HS-5902B1 for Pump P096 CUE: The switches are in the Control Room position.

5 ENSURE all Mode Select and Fire CONTACT Operator at ESF Switchgear Isolation Switches aligned to allow control Room to obtain status of A0413 breaker from the Control Room: control at 2(3)L-412.

D/G G-002 Output Breaker A0413 on L-412 selected to REMOTE.

CUE: G-002 Output Breaker A0413 on 2(3)L-412 is selected to Remote.

6 ENSURE all Mode Select and Fire CONTACT Control Room to verify LOCAL Isolation Switches aligned to allow control CONTROL Mode Selector 2HS-1665-1 from the Control Room: (3HS-1664-2) on CR-63 Backlight is LOCAL Mode Select HS-1665-1 (HS- extinguished.

1664-2) on CR-63 Backlight extinguished.

CUE: Control Room reports 2HS-1665-1 (3HS-1664-2) on CR-63 Local Control backlight extinguished.

7 Ensure CLOSED DC control power CONTACT Control Room or local Operator breaker for the associated 1E 4 kV Bus to VERIFY DC control power breaker for Supply Breaker: 2(3)A0418, Reserve Auxiliary Transformer A04-18, Reserve Aux. Transformer. is closed.

CUE: The 22 (32) reports 2(3)A0418 DC control power breaker closed.

Page 7 of 12

JPM: SONGS RO/SRO NRC JPM P-1 TITLE: Transfer 4 kV Bus from EDG to the RAT then to the Control Room

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 8 Transfer 1E loads to the Reserve Aux. TRANSFER 1E loads to the Reserve Aux.

Transformer per SO23-2-13, Attachment Transformer per SO23-2-13, Attachment for for Diesel Generator Operation, by Diesel Generator Operation, by performing performing the following Sections: the following Sections:

Paralleling a Diesel Supplied Bus

Paralleling a Diesel Supplied Bus to to the RAT the RAT

Unloading the Diesel Generator

Unloading the Diesel Generator

Stopping the Diesel Generator

Stopping the Diesel Generator CUE: The Control Room has energized Bus 2(3)A04 from Reserve Aux Transformer 2(3)XR1.

CUE: The Control Room has unloaded DG 2(3)G002 and opened the output breaker. DG 2(3)G002 is running at 900 RPM. The Control Room Supervisor directs you to stop the Diesel Generator using SO23-2-13, Section 2.9.

NOTE: Provide the Examinee with a copy of SO23-2-13, Diesel Generator Operations, Attachment 2, Diesel Generator Operation.

9 Transfer Diesel Control to LOCAL as NOTIFY Control Room to transfer Diesel follows: Control to LOCAL CONTROL at CR-63.

TRANSFER HS-1665-1(HS-1644-2),

MODE SELECTOR to LOCAL CONTROL at CR-63.

CUE: The Control Room has transferred the 2(3)G002 Diesel to LOCAL.

10 Transfer Diesel Control to LOCAL as OBSERVE LOCAL CONTROL light follows: 2(3)ZL-E918 on Panel 2(3)L-160 VERIFY ILLUMINATED ZL-E918 illuminated.

(ZL-E968), LOCAL CONTROL light.

[L-160(L-161)]

Page 8 of 12

JPM: SONGS RO/SRO NRC JPM P-1 TITLE: Transfer 4 kV Bus from EDG to the RAT then to the Control Room

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

CUE: The LOCAL CONTROL light is ON.

11* Reduce speed to idle, as follows: DEPRESS 2(3)HS-1701A, IDLE SPEED DEPRESS HS-1701A(B), IDLE SPEED ON red pushbutton on 2(3)L-160.

ON pushbutton. [L-160(L-161)]

CUE: Diesel generator sound changes to indicate a reduction in speed.

12 Reduce speed to idle, as follows: OBSERVE 2(3)ZL-1700A IDLE SPEED VERIFY ILLUMINATED ZL-1700A(B), indicator white light illuminated on 2(3)L-IDLE SPEED light. [L-160(L-161)] 160.

CUE: The IDLE SPEED light is ON.

13 Reduce speed to idle, as follows: OBSERVE 2(3)G002 Diesel fuel rack Verify the Diesel at idle speed. movement and/or INDICATE the sound of the Diesel speed lowering would be heard.

CUE: The Diesel was loaded. It is now running at idle speed.

14 Allow to run at idle for at least: (Check CHECK 15 minute block and VERIFY one.) diesel runs at idle speed for at least 15 Diesel was loaded: 15 minutes minutes.

CUE: 15 minutes have passed.

15 Ensure both AC Lube Oil Circulating OBSERVE indicating lights on:

Pumps and both Turbocharger Pumps are

2(3)ZL-E925B Engine 1 AC Lube Oil operating.

Circ Pump/Turbocharger Pump on 2(3)L-160.

2(3)ZL-E925A Engine 2 AC Lube Oil Circ Pump/Turbocharger Pump on 2(3)L-160.

Page 9 of 12

JPM: SONGS RO/SRO NRC JPM P-1 TITLE: Transfer 4 kV Bus from EDG to the RAT then to the Control Room

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

CUE: The red lights for both sets of pumps are ON.

16 Verify the Air Start Manifolds > 185 psig OBSERVE pressure indicators for the Air as indicated on PI-5958A(C) & PI- Start Manifolds greater than 185 psig on:

5958B(D).

2(3)PI-5958A on 2(3)L-286, Engine 2.

2(3)PI-5958B on 2(3)L-287, Engine 1.

CUE: Both Air Start Manifolds indicate 200 psig.

17* Locally Shut Down the Diesel as follows: NOTIFY the Control Room that the Diesel After notifying the Control Room that the has run for 15 minutes then ROTATE Diesel has run in idle for >15 minutes or 2(3)HS-5995-1, Local Engine Control

>5 minutes, as required, or if locally Switch to the STOP position and RECORD stopping from 900 rpm, then ROTATE the time.

HS-5995-1(2), Local Engine Control, to STOP and RECORD time.

CUE: Control Room acknowledges securing of the Diesel. The Diesel is stopped.

18* Return Diesel Control to Control Room, as DEPRESS 2(3)HS-1702A, IDLE SPEED follows: OFF green pushbutton on 2(3)L-160.

DEPRESS HS-1702A(B), IDLE SPEED OFF. [L-160(L-161)].

19 Return Diesel Control to Control Room, as VERIFY 2(3)ZL-1700A, IDLE SPEED follows: indicator light extinguished on 2(3)L-160.

VERIFY EXTINGUISHED ZL-1700A (B), IDLE SPEED light. [L-160(L-161)].

CUE: The Idle Speed light is off.

Page 10 of 12

JPM: SONGS RO/SRO NRC JPM P-1 TITLE: Transfer 4 kV Bus from EDG to the RAT then to the Control Room

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 20 Return Diesel Control to Control Room, as NOTIFY the Control Room that Diesel follows: Control is ready to be transferred to the DEPRESS HS-1665-1(HS-1644-2), Control Room.

MODE SELECTOR, LOCAL CONTROL pushbutton at CR-63 to transfer Diesel Control to the Control Room.

CUE: The Control Room has transferred the 2(3) G002 Diesel to Remote.

21 Return Diesel Control to Control Room, as OBSERVE LOCAL CONTROL light follows: 2(3)ZL-E918 on Panel 2(3)L-160 is OFF.

VERIFY EXTINGUISHED ZL-E918 (ZL-E968), LOCAL CONTROL light. [L-160(L-161)].

TERMINATING CUE: Stop Time: ________

The Local Control light is OFF.

This JPM is complete.

Page 11 of 12

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 12 of 12

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO/SRO NRC JPM P-2 INITIAL PLANT CONDITIONS As a Radwaste Operator, you have been notified by the Unit 2 (Unit 3) Control Room of a "CEDMCS TIMER FAILURE" alarm and directed to investigate the problem.

TASK TO BE PERFORMED The Control Room Supervisor directs you to perform the actions of Unit 2 (Unit 3) Annunciator Response Procedure SO23-15-50.A2, CEDMCS TIMER FAILURE (50A40) using the locally posted instructions.

Page 1 of 8

JOB PERFORMANCE MEASURE SONGS RO/SRO NRC JPM P-2 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 8

DOCUMENTATION SONGS RO/SRO NRC JPM P-2 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 14 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: RWOP TASK SYS ID: 1076 TASK DESCRIPTION Transfer a CEA to the hold bus.

KA NUMBER: 001 A2.14 KA VALUES: RO 3.7 SRO 3.9 10CFR55.45 APPLICABILITY: 3, 13

REFERENCES:

SO23-15-50.A2, CEDMCS Timer Failure, Rev. 10-1.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 2 Compared against SO23-15-50.A2, LRZ 07/10/00 WLL Rev. 6, TCN 6-3 with major changes required. Deleted steps no longer required to place a CEA on the hold bus.

2-1 Compared against SO23-15-50.A2, RCW 11/4/03 AHH Rev. 8, TCN 8-4, 50A40. Added one non-critical step and one cue to reflect changes in procedure.

3 Compared against SO23-15-50.A2, LRZ 07/19/06 REV Rev. 10-1, 50A40. Modified JPM as follows: Deleted one critical step and replaced with a different critical step to comply with the procedure change for a CEDMCS Timer failure.

Page 4 of 8

SET-UP EXAMINER:

NOTE: Circle the unit on which this JPM will be performed and inform the examinee.

Provide the examinee with a copy of SO23-15-50.A2, CEDMCS Timer Failure.

Page 5 of 8

JPM: SONGS RO/SRO NRC JPM P-2 TITLE: CEDMCS Timer Failure Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Circle the unit on which this JPM will be performed and inform the examinee.

NOTE: Provide the examinee with a copy of SO23-15-50.A2, CEDMCS Timer Failure.

CUE: All steps in this JPM will be simulated.

1 Proceed to Unit 2(3) CEDMCS Room. PROCEED to Unit 2(3) CEDMCS Room. Start Time: _______

NOTE: Provide the next two cues as the examinee reads the posted instructions.

2 Verify the alarm is solid. CONTACT the Control Room to Start Time: _______

DETERMINE if the 50A40, CEDMCS Timer Failure alarm is solid.

CUE: The 50A40, CEDMCS Timer Failure alarm in the Control Room is in solid.

3 DETERMINE CEA(s) affected by DETERMINE CEA(s) affected by observing the CEA Timer Failure Alarm OBSERVING the CEA Timer Failure Alarm lamps lit on 2(3)L-038(C-4). lamps lit on 2(3)L-038(C-4), on Panel 2(3)UI-J120.

CUE: CEA #22 Timer Failure lamp is illuminated on Panel 2(3)L-038(C-4).

4 Verify the Holding Bus is available as OBSERVE AHOLDING BUS FAILURE@ and indicated by the following lamps ASUBGROUP MAINT@ lamps for C2 on extinguished (on appropriate Maintenance Supply Lamp Panel 2(3)UI-Maintenance Supply Lamp Panel): J122.

HOLDING BUS FAILURE

SUBGROUP MAINTENANCE CUE: HOLDING BUS FAILURE and SUBGROUP MAINTENANCE lamps for C2 are extinguished.

Page 6 of 8

JPM: SONGS RO/SRO NRC JPM P-2 TITLE: CEDMCS Timer Failure Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5 Notify the Control Room of the Holding NOTIFY the Control Room that the Holding Bus / Subgroup Maintenance Lamps Bus Failure and Subgroup Maintenance status and intentions of performing Lamps are extinguished and intention to Step1.3.3. PERFORM Step1.3.3.

CUE: The Control Room acknowledges the performance of Step 1.3.3.

6* SELECT the Subgroup Maintenance PLACE Subgroup Maintenance switch in UP switch to the UP position for the position for Subgroup 05, Supplied From affected Subgroup. Hold Bus C2 on Panel 2(3)UI-J122.

CUE: Subgroup lamp for Subgroup 05 is illuminated.

7* ACTUATE the MAN TRANS switch ACTUATE the MAN TRANS switch on on the respective ACTM. ACTM 22 located behind Panel 2(3)UY-J133C, Card Status Monitor.

8* OPEN the circuit breaker(s) to the OPENING CEA #22 individual disconnect CEAs that have their CEA Timer circuit breaker on 2(3)UI-J131C, Power Failure Alarm Lamps illuminated. Switch Assembly for Subgroup 05.

9 Initiate an AR for I&C to troubleshoot / INITIATE an Action Report for I&C to investigate. troubleshoot / investigate.

CUE: Another operator will initiate the Action Request.

10 Verify 50A40 alarm is clear in the CONTACT the Control Room and VERIFY Control Room. 50A40 alarm has cleared.

TERMINATING CUE: Control Room Stop Time: ________

reports that the 50A40 alarm has cleared.

This JPM is complete.

Page 7 of 8

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: R. Hampton DATE: 10/04/06 Page 8 of 8

JPM INFORMATION SHEET JPM NUMBER SONGS Oct 2006 RO/SRO NRC JPM P-3 INITIAL PLANT CONDITIONS You are the Auxiliary Operator.

Unit 2 (Unit 3) is in MODE 3, Hot Standby.

The Unit 2 (Unit 3) Atmospheric Dump Valve, 2HV-8419 (3HV-8419), was operated locally during the last shift and is currently 10% open.

TASK TO BE PERFORMED The Control Room Supervisor directs you to restore Unit 2 (Unit 3) Atmospheric Dump Valve, 2HV-8419 (3HV-8419), to remote operation per SO23-3-2.18.1, Attachment 4, Step 2.2, Local Manual Operation of the Atmospheric Dump Valves.

Page 1 of 10

JOB PERFORMANCE MEASURE SONGS RO/SRO NRC JPM P-3 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Page 2 of 10

DOCUMENTATION SONGS RO/SRO NRC JPM P-3 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 8 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: PPEO TASK SYS ID: 141183 TASK DESCRIPTION Operate the Atmospheric Dump Valve in Local Manual.

KA NUMBER: 039 A2.04 KA VALUES: RO 3.4 SRO 3.7 10CFR55.45 APPLICABILITY: 6

REFERENCES:

SO23-3-2.18.1, Atmospheric Dump Valve Operation, Rev. 13.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

Page 3 of 10

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 Updated the JPM to the current New GLM 09/13/93 MJK Format, separated combined steps, isolated the cues fro 1-1 Changed setup page; minor editorial HJW 03/17/94 N/A corrections for clarity; changed estimated time from 15 to 8 minutes based on history.

1-2 Corrected KA number. HJW 08/04/95 N/A 1-3 Compared to SO23-13-2.18.1, Rev. 8. SGA 06/27/97 N/A No changes required. Updated KA to NUREG-1122, Rev. 1.

1-4 Compared against SO23-3-2.18.1, JJM 09/22/00 WLL Rev. 10 with no changes required.

Changed old task number to VISION SYS ID and updated the KA designation.

1-5 Compared against SO23-3-2.18.1, LRZ 05/11/01 WLL Rev. 10 with minor editorial changes required.

1-6 Compared against SO23-3-2-18.1, JJM 11/28/01 KR TCN 11-1 and changed the number of the attachment to 4 from 6.

1-7 Compared against SO23-3-2-18.1, RCW 09/01/04 AH TCN 12-1. Made minor editorial changes. Updated Task Sys ID.

2 Compared against SO23-3-2-18.1, LRZ 07/19/06 REV Rev. 13. Added step required by procedure revision.

Page 4 of 10

SET-UP EXAMINER:

NOTE: Circle the unit on which this JPM will be performed and inform the examinee.

Provide the examinee with a copy of SO23-3-2.18-1, Atmospheric Dump Valve Operation, .

Page 5 of 10

JPM: SONGS RO/SRO NRC JPM P-3 TITLE: Operate the Atmospheric Dump Valve in Local-Manual

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Circle the unit on which this JPM will be performed and inform the examinee.

NOTE: Provide examinee with a copy of SO23-3-2.18.1, Atmospheric Dump Valve Operation, Attachment 4.

CUE: All steps in this JPM will be simulated.

1* MANUALLY CLOSE HV-8419. TURN 2(3)HV-8419, S/G 2E088 Main Steam Start Time: _______

Dump to Atmosphere Train A handwheel in the clockwise direction.

CUE: The valve is closed.

2* ROTATE the Handwheel back and forth ROTATE 2(3)HV-8419 S/G 2E088 Main until pressure is relieved from the clevis. Steam Dump to Atmosphere Train A handwheel BACK and FORTH until pressure is relieved from the clevis.

CUE: The pressure is relieved from the clevis.

3* REMOVE the clevis from the detent in REMOVE the clevis from the detent in the the Actuator Shaft. actuator shaft on 2(3)HV-8419, S/G 2E088 Main Steam Dump to Atmosphere Train A.

CUE: The clevis is removed.

4* FULLY EXTEND the Manual Override FULLY EXTEND the Manual Override Shaft Shaft by TURNING the Handwheel on 2(3)HV-8419, S/G 2E088 Main Steam Counter-Clockwise until resistance is Dump to Atmosphere Train A by TURNING encountered. the handle counter-clockwise until resistance is encountered.

CUE: You feel resistance.

Page 6 of 10

JPM: SONGS RO/SRO NRC JPM P-3 TITLE: Operate the Atmospheric Dump Valve in Local-Manual

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5* When the Manual Override Shaft is SCREW the clevis into the Manual Override fully extended, then SCREW the clevis Shaft on 2(3)HV-8419, S/G 2E088 Main fully into the Manual Override Shaft. Steam Dump to Atmosphere Train A.

CUE: The clevis is in the Manual Override Shaft.

6 ENSURE 2(3)PIC-8419-1, HV-8419 CONTACT the Control Room to VERIFY Controller, is adjusted to FULL that 2(3)PIC-8419-1, HV-8419 Atmospheric CLOSED (0%) (CR-52). Dump Valve Position Controller is adjusted to FULL CLOSED 0% position at CR-52 in Control Room.

CUE: The positioner is at zero.

7 ENSURE 2(3) HS-8419-A1, HV-8419 CONTACT the Control Room to VERIFY Handswitch, selected to CLOSE that the 2(3) HS-8419-A1, HV-8419 (CR-52). Atmospheric Dump Valve Control Switch is selected to CLOSE at CR-52 in Control Room.

CUE: The hand switch is selected to CLOSE.

8 ENSURE 2(3)HIC-8419-1, HV-8419 CONTACT the Control Room to VERIFY Controller, is adjusted to FULL that 2(3)HIC-8419-1, HV-8419 Atmospheric CLOSED (0%) (L-042). Dump Valve Position Controller is adjusted to FULL CLOSED (0%) at L-042, Remote Shutdown Panel.

CUE: The positioner is at zero.

Page 7 of 10

JPM: SONGS RO/SRO NRC JPM P-3 TITLE: Operate the Atmospheric Dump Valve in Local-Manual

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 9 ENSURE 2(3)HS-8419-B1, HV-8419 CONTACT the Control Room to VERIFY Handswitch, selected to CLOSE that the 2(3)HS-8419-B1, HV-8419 (L-042). Atmospheric Dump Valve Control Handswitch is selected to CLOSE at L-042, Remote Shutdown Panel.

CUE: The hand switch is selected to CLOSE.

10* CLOSE S2(3)1301MU1264, HV-8419 CLOSE the Atmospheric Dump Valve Controller Equalizing Valve. 2(3)HV-8419, Valve Actuator Equalizing Valve, S2(3)1301MU1264.

CUE: The equalizing valve is CLOSED.

11* OPEN S2(3)1301MU1304, HV-8419 OPEN the ADV Controller Instrument Air Controller Instrument Air Isolation Isolation Valve, S2(3)1301MU1304, Valve. Instrument Air Header Inlet ISO Valve to 2(3)HV-8419 Actuator Train A.

CUE: The valve is OPEN.

12* OPEN S2(3)1301MU1328, HV-8419 OPEN the Atmospheric Dump Valve Positioner Nitrogen Isolation Valve. 2(3)HV-8419 Positioner Nitrogen Isolation Valve S2(3)1301MU1328, 2(3)HV-4819 Backup N2 Supply block Valve Train A.

CUE: The valve is OPEN.

13 PERFORM Remote Functional Stroke CONTACT the Control Room to INFORM Test of HV-8419 Atmospheric Dump them that the Atmospheric Dump Valve is Valve. aligned for remote operation and ready for remote functional stroke testing after independent verification.

Page 8 of 10

JPM: SONGS RO/SRO NRC JPM P-3 TITLE: Operate the Atmospheric Dump Valve in Local-Manual

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

TERMINATING CUE: Stop Time: ________

The Control Room has been contacted.

This JPM is complete.

Page 9 of 10

JPM CHECKLIST

1. The JPM is:

a. X Supported by facilitys job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 10/04/06 Page 10 of 10

NRC Scenario #1 SR-5 Unit 2(3) Control Board Operator l Shift Relief Status Sheet REVISION 7 Approved by: Dennis Wilcockson Date: 05/22/06

REVISION 7 SR-5 PAGE 1 OF 4 UNIT 2(3) CONTROL BOARD OPERATOR l SHIFT RELIEF STATUS SHEET POSITION: 22 32 DATE: Today NIGHTS: DAYS:

(Name) (Name)

Part I - Review prior to assuming the shift.

1. GENERAL PLANT STATUS Mode of Operation 1 Rx Power 98.7% MWe 1171 Inserted Rods ARO RCS Boron 1542 Sample/Meter Boration Gallons: Per percent 22 Per degree 20 Dilution Gallons: Per percent 61 Per degree 58 VCT Blend Set points: BA 11.8 PMW 32.2 SHUTDOWN MODES: (leave blank if not applicable)

DID Sheet # Time to Boil Rx Head: ON OFF RCS Loops: FILLED NOT FILLED RIC Boration Flowpath:

Containment Integrity: (indicate open/unlocked hatches)

Main Equipment Emergency Parameter Limits: RCS Level: RCS Press:

RCS Temp: SDC Flow:

2. ACTIVITIES PERFORMED/IN PROGRESS:

PMW Gallons added: NIGHTS DAYS Boric Acid Gallons added: NIGHTS DAYS General Information/Comments:

Maintain steady-state power conditions.

NRC Scenario #1 Turnover Sheet.wpd

REVISION 7 SR-5 PAGE 2 OF 4

3. ENGINEERED SAFETY FEATURES:

List INOP/OOS ESF Equipment and Comments:

Train A Charging Pump P-190 Train A Saltwater Cooling Pump P-307 Train A Low Pressure Safety Injection Pump P-015

4. REACTOR SUPPORT:

(B-Bypassed, I-In Test, T-Tripped, S-Simulated Signal, INOP-INOPERABLE)

PPS: A B C D CPC: A B C D CEAC: 1 2 PPS Points in Bypass or Trip:

A C B D Critical Parameters: (QSPDS A or B page 502 and 611)

T-Cold S/G E089 S/G E088 PZR PZR RCS Level Level Level Pressure Subcooling 541EF 68% 68% 57% 2253 27EF ASI: -0.0216 ESI: -0.0216 COLSS Power Margin: +1.29

5. BALANCE OF PLANT:

Main XFMR Neutral Amps: 100 BPS flow to: Condenser Outfall E071 aligned to: SFP RWST List Out of Service / INOP Rad Monitors:

Condenser Air Ejector Low Range Radiation Monitor RM-7818 List New Compensatory Actions and Setpoint Changes:

REVISION 7 SR-5 PAGE 3 OF 4 5.1 List additional comments, unusual conditions, and any SO123-0-A3 actions for the watch:

6. Activities scheduled or expected during oncoming shifts:

DAYS: Maintain steady-state power conditions.

NIGHTS:

REVISION 7 SR-5 PAGE 4 OF 4 INITIALS DAYS NIGHTS

7. The Control Boards been walked down and accepted:

(Oncoming CBO) l

8. I hereby assume the position of Control Board Operator: l DAYS: DATE: TIME:

(Signature)

NIGHTS: DATE: TIME:

(Signature)

PART II - To Be Reviewed/Performed as Early in the Shift as Possible.

1. I have reviewed/performed (check boxes):

DAYS NIGHTS C The NCO Log C The LCOAR/EDMR Books C The Annunciator Status Book C The Annunciator Checks per SO23-6-29 C A complete status check of Control Board indicators to verify indications are within expected ranges for current plant conditions (Ref. LER 3-90-14)

[Modes 1 and 2 only (Ref. LER 3-90-10)]

C Valve positions on CR-57 and CCW boards aligned per position dots; any discrepancies understood.

C All annunciators in alarm are understood C PMS Alarms (print out) and CFMS alarm l page checked and all valid alarms are l understood. Forward reviewed PMS l alarm print out to Equipment Control. l

[Modes 5 and 6 only]

C During Outages: System Status Drawings have been reviewed (ECCS, CVCS, CCW) N/A (ACE 041100534)

(Initials)

2. Reviewed by Control Room Supervisor:

DAYS: DATE: TIME:

(Signature)

NIGHTS: DATE: TIME:

(Signature)

DISPOSITION: File per SO123-0-A3

Appendix D Scenario Outline Form ES-D-1 Facility: San Onofre Scenario No.: 1 Op Test No.: NRC Examiners: Operators:

Initial Conditions: * ~98.7% power - RCS Boron is 1542 ppm by Chemistry Sample

Train A Component Cooling Water Pump (P-025) in service

Train A Charging Pump (P-190) OOS

Train A Saltwater Cooling Pump (P-307) OOS

Train A Low Pressure Safety Injection Pump (P-015) OOS

Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Maintain steady-state power conditions..

Critical Tasks:

Restore feedwater flow to one Steam Generator.

Restore power to 4 kV Bus A03 and/or A07.

Event No. Malf. No. Event Type* Event Description 1 Security Warning from the Security Shift Commander.

+ 5 min 2 CV22B C (CO, CRS) Charging Pump P-191 trip.

+15 min TS (CRS) 3 RC16B I (CO, CRS) Pressurizer Level Control Channel fails high (LT-0110-2).

+25 min TS (CRS) 4 CV16B I (CO, CRS) Volume Control Tank Level Instrument fails low (LT-0227).

+35 min 5 FW11 C (ACO, CRS) Condensate Pump P-050 overcurrent trip.

+40 min 6 ED04A M (ALL) Bus 2A03 overcurrent trip.

+45 min FW23 Loss of Condenser vacuum (+2 min post-trip).

Loss of Main Feedwater.

7 Bus 2A07 C (ACO) Bus 2A07 fails to transfer upon Unit trip.

+45 min XFR LP 8 FW02A C (ACO) Aux. Feedwater Pump P-141 shaft seizure (+2 min post-trip).

+45 min FW02B Aux. Feedwater Pump P-504 shaft seizure (+2 min post-trip).

FW25 Aux. Feedwater Pump P-140 overspeed trip (+1 min post-trip).

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specifications Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 SCENARIO

SUMMARY

NRC #1 The crew will assume the shift and maintain steady-state conditions per SO23-5-1.7, Power Operations.

This section redacted per SUNSI requirements When the security event actions are complete, Charging Pump P-191 will trip and be addressed per the Annunciator Response Procedures (ARPs) and SO23-3-2.1, Chemical and Volume Control System Operations. The CRS will evaluate Technical Specifications.

After the crew has stabilized the plant, a Pressurizer Level instrument fails high and will require crew actions per the ARPs and AOI SO23-13-27, Pressurizer Pressure and Level Malfunction.

The CRS will evaluate Technical Specifications.

When the plant is stable, the VCT Level Transmitter (LT-227) will fail low. The crew will secure Charging and Letdown per the ARPs and SO23-3-2.1, CVCS Charging and Letdown Operations and/or SO23-3-2.2, Makeup Operations. The Control Operator will manually operate the Charging Pumps to control Pressurizer level.

When plant conditions are stable, a Condensate Pump will trip and the standby pump will fail to auto start. The crew will respond per the Annunciator Response Procedures.

The major event begins with a loss of Bus 2A03 and total loss of vacuum. This will require a plant trip due to a loss of Main Feedwater flow. The crew will enter SO23-12-1, Standard Post Trip Actions. This is followed by a total loss of feedwater that will necessitate entry into SO23 6, Loss of Feedwater. The ACO will be required to manually transfer Bus 2A07 during post-trip SPTAs.

Event termination will occur when Bus 2A07 power is restored and the Steam Generators are depressurized sufficiently to allow the remaining Condensate Pumps to supply feedwater flow.

Risk Significance:

Risk important components out of service: Charging P-190, LPSI P-015, SWC P-307

Risk significant core damage sequence: Loss of all feedwater

Risk significant operator actions: Depressurize and restore feedwater flow to at least one SG Appendix D NUREG 1021 Revision 9

Scenario Event Description NRC Scenario 1 SONGS 2006 Facility NRC Initial License Examination Simulator Scenario Setup Scenario 1 MACHINE OPERATORS INSTRUCTIONS SETUP IC: Use IC #181 and see attached Event File for NRC Scenario #1.

Appendix D NUREG 1021 Revision 9

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 4 of 22 Event

Description:

Security Event Time Position Applicants Actions or Behavior Machine Operator: EXECUTE IC #181 and NRC Scenario #1 SETUP file to align components.

ENSURE Control Board Tags are hung on P-190, P-015 and P-307.

ENSURE Operator Aid Tags #029 (CVCS) and #005-4 (CVCS Ion Exchanger) reflect the scenario boron concentration.

ENSURE procedures in progress are on the CO desk:

- Copy of SO32-5-1.7, Power Operations, open to Section 6.4, Guidelines for Steady State Operation.

Control Room Annunciators in Alarm at 100%:

57A51 - SI / ECW SYS TRAIN A INOPERABLE 58A51 - CHARGING PUMP P-190 OVERRIDE / NOT IN AUTO Machine Operator: redacted per SUNSI requirements Indications available:

None

+1 min CRS redacted per SUNSI requirements CRS redacted per SUNSI requirements

+2 min CRS redacted per SUNSI requirements CRS redacted per SUNSI requirements CRS redacted per SUNSI requirements

+5 min CRS redacted per SUNSI requirements

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 5 of 22 Event

Description:

Security Event Time Position Applicants Actions or Behavior When the AOI actions are addressed, or at Lead Evaluators discretion, PROCEED to Event 2.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 6 of 22 Event

Description:

Charging Pump P-191 Trip Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE CV22B, Charging Pump P-191 trip.

Indications available:

58A42 - CHARGING PUMP P191 TRAIN A OC 58A12 - CHARGING HEADER FLOW LO

+30 secs CO REFER to Annunciator Response Procedures.

DETERMINE Charging Pump P-191 is tripped and INFORM CO the CRS.

CRS DIRECT placing a Standby Charging Pump P-192 in service.

START Charging Pump P-192 and PLACE P-192 as the Lead CO Pump in Auto.

CO PLACE Charging Pump P-191 in MANUAL and STOP.

+2 min DISPATCH a PEO to the 50 Control Building to determine the CRS cause of the trip and DIRECT performance of SO23-3-2.1, CVCS Operations to align systems to normal.

M.O. Cue: If directed to check Charging Pump 2P-191, WAIT 3 minutes, then REPORT that the motor is hot and has an odor of burnt insulation.

If directed to rack out Charging Pump 2P-191 breaker, WAIT 2 minutes, then EXECUTE remote functions CV77B, DC power on Train A and CV78B, P-191 Breaker, and REPORT that P-191 breaker is racked out.

+4 min CRS CONTACT Maintenance to investigate Charging Pump P-191.

+4 min DIRECT performance of SO23-6-9, Section 6.9 kV, 4kV and CRS/CO 480V Bus And Feeder Faults for P-191.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 7 of 22 Event

Description:

Charging Pump P-191 Trip Time Position Applicants Actions or Behavior

+10 min CRS EVALUATE Technical Specifications.

3.1.9.A, Boration Systems - Operating (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ACTION).

Restore boron injection flowpath to OPERABLE.

When systems are re-aligned to normal and Technical Specifications are addressed, PROCEED to Event 3.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 8 of 22 Event

Description:

PZR Level Control Channel LT-0110-2 Fails High Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE RC16B, PZR Level Controlling Channel Y LT-0110-2 fails high.

Indications available:

50A22 - PZR LVL ERROR HI 50A12 - PZR LVL HI-HI Letdown flow INCREASING

+1 min CO REFER to Annunciator Response Procedures.

OBSERVE minimum Charging flow and maximum Letdown CO flow.

DETERMINE Letdown and Charging systems are NOT CO responding as desired and PERFORM the following:

DEPRESS the A/M button on LIC-0110, PZR Level Controller, to place PZR level control in MANUAL.

START Charging Pumps to match Letdown flow as closely as possible.

ADJUST LIC-0110, PZR Level Controller, to match Letdown and Charging flows.

SECURE PZR heaters as necessary to control RCS pressure.

MONITOR PZR level and maintain stable.

+2 min DETERMINE that PZR Level Channel Y (LI-0110A2) is cause CO of failure and INFORM the CRS AOI SO23-13-27 entry required.

DIRECT performance of SO23-13-27, Pressurizer Pressure CRS and Level Malfunction, to transfer PZR Level Control to the operable transmitter.

CO VERIFY Level Channel X (LI-0110X) is OPERABLE.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 9 of 22 Event

Description:

PZR Level Control Channel LT-0110-2 Fails High Time Position Applicants Actions or Behavior CO ENSURE LIC-0110 is in MANUAL with stable Letdown flow.

+5 min POSITION HS-0110, PZR Level Channel Select switch, to CO Channel X.

On LIC-0110 (page 1), MATCH actual level (middle column)

CO with the Pressurizer Level setpoint (left column) by ADJUSTING the output (right column) to within 2%.

TRANSFER LIC-0110 PZR Level Controller to AUTO by CO depressing the A/M pushbutton.

DEPRESS HS-0100C, PZR Lo-Lo Level Heater Cutout CO Channel selector, selecting OPERABLE Level Transmitter X.

CO RESET PZR heaters by depressing OFF, then AUTO.

CO RESTORE Backup Charging Pumps to AUTO.

NOTE: Crew may elect to switch the CFMS point display for PZR level from Channel Y to Channel X.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 10 of 22 Event

Description:

PZR Level Control Channel LT-0110-2 Fails High Time Position Applicants Actions or Behavior

+10 min CRS EVALUATE Technical Specifications.

3.3.11.A, Post Accident Monitoring Instrumentation (30 day ACTION).

Restore required channel to OPERABLE status.

3.4.9.B, Pressurizer Heaters (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ACTION).

Restore required group of Pressurizer Heaters to OPERABLE status.

When Technical Specifications are addressed, or at Lead Evaluators discretion, PROCEED to Event 4.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 Page 11 of 22 Event

Description:

VCT Level Transmitter LT-0227 Fails Low Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE CV16B, VCT Level Transmitter, LT-0227 fails low.

Indications available:

58A04 - VCT LEVEL LO/LO VCT Level Indicator LI-0227A lowering (on PMS)

VCT Outlet Valve LC-0227B closes RWST to Charging Pump Suction Valve LV-0227C opens

+30 sec CO REFER to Annunciator Response Procedures.

DETERMINE that VCT suction has shifted from the VCT to the CO RWST and INFORM the CRS that ARP SO23-15.58A entry required.

CHECK VCT Level indicator LI-0226 and DETERMINE that CO level is normal.

CO IDENTIFY that VCT level indicator LI-0227 has failed low.

+1 min CRS DIRECT securing of Charging and Letdown.

CO STOP any operating Charging Pumps.

ISOLATE Letdown by CLOSING TV-0221 or HV-9204 or HV-CO 9205 or HV-9267.

OPERATE Charging Pumps as necessary to control CO Pressurizer level.

+5 min DIRECT performance of SO23-3-2.2, Makeup Operations to CRS ensure proper CVCS alignment is achieved.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 Page 12 of 22 Event

Description:

VCT Level Transmitter LT-0227 Fails Low Time Position Applicants Actions or Behavior

+10 min CRS REQUEST I&C assistance.

When Charging Pump control is established and Letdown is isolated, or at Lead Evaluators discretion, PROCEED to Event 5.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 5 Page 13 of 22 Event

Description:

Condensate Pump P-050 Trip Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE FW11, Condensate Pump P-050 trip.

Indications available:

53B44 - CONDENSATE PUMP OC 53B47 - CONDENSATE PRESSURE LO 52A13 - FWCS TROUBLE

+1 min ACO REFER to Annunciator Response Procedures.

DETERMINE that Condensate Pump P050 has tripped on ACO overcurrent and INFORM the CRS that ARP SO23-15.53A entry required.

DETERMINE that Condensate Pump P053 has NOT auto ACO started and recommend starting Condensate Pump P053.

CRS DIRECT starting of Condensate Pump P053.

START Condensate Pump P053 and OBSERVE normal ACO running current.

OBSERVE Condensate and Feedwater System operation for CRS/ACO any abnormal conditions.

+5 min NOTIFY Electrical Maintenance to troubleshoot tripping of CRS P050.

When the AOI actions are addressed, or at Lead Evaluators discretion, PROCEED to Events 6, 7 and 8.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 14 of 22 Event

Description:

Loss of Bus 2A03 / Loss of Vacuum / Bus 2A07 Fails to Transfer / Loss of Feedwater Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE ED04A, Bus 2A03 Trip, Failure of Bus 2A07 to transfer, FW25, P-140 trip (+1 minute post-trip),

FW02A and FW02B, P-141 and P-504 trip (+2 minutes post-trip) and FW23, Loss of Vacuum at 100% severity (+2 minutes post-trip).

Indications available:

53A03 - MFWP TURBINE K006 TRIP 53A08 - MFWP NPSH LO TRIP 53B03 - MFWP TURBINE K005 TRIP 53B05 - CONDENSATE PUMP P050 FLOW LO 53B06 - CONDENSATE PUMP P051 FLOW LO

+30 secs RECOGNIZE loss of both Main Feed Pumps and INFORM the ACO CRS that reactor trip is required.

DIRECT a Reactor trip and DIRECT crew to perform actions of CRS SO23-12-1, Standard Post Trip Actions.

TRIP the Reactor and ENTER SO23-12-1, Standard Post Trip CO/ACO Actions.

NOTE: Crew may take all action required during SPTAs prior to reporting status.

CRS INITIATE Administrative Actions:

RECORD time of Reactor trip.

ANNOUNCE Reactor trip via PA System.

INITIATE Attachment 4, WORKSHEET.

INITIATE Attachment 5, ADMINISTRATIVE ACTIONS.

CO VERIFY Reactivity Control criteria satisfied:

VERIFY Reactor trip circuit breakers (8) open

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 15 of 22 Event

Description:

Loss of Bus 2A03 / Loss of Vacuum / Bus 2A07 Fails to Transfer / Loss of Feedwater Time Position Applicants Actions or Behavior

VERIFY maximum of one full length CEA - NOT fully inserted.

VERIFY Reactor power lowering and startup rate negative.

CRS DIRECT initiation of EFAS 1 and 2 due to loss of feedwater.

ACO INITIATE EFAS 1 and 2 due to loss of feedwater.

ACO VERIFY Vital Auxiliaries functioning properly:

VERIFY Main Turbine tripped.

HP and LP Stop and Governor Valves - closed.

MWE output - lowering.

VERIFY both Unit Output Breakers - open.

VERIFY Main Turbine speed - less than 2000 RPM OR -

lowering.

VERIFY CCW Pump aligned to Non-Critical Loop (NCL) and Letdown Heat Exchanger.

VERIFY both 1E 4 kV Buses - energized.

VERIFY both 1E 480 V Buses B04 and B06 - energized.

VERIFY all 6.9 kV and Non-1E Buses - energized.

DETERMINE Bus 2A03 and Bus 2A07 both de-energized.

VERIFY all Class 1E DC Buses - energized.

CRITICAL Manually TRANSFER Bus 2A07 to the Reserve Auxiliary ACO TASK Transformer.

CO VERIFY RCS Inventory Control criteria satisfied:

VERIFY PZR level:

Between 10% and 70%.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 16 of 22 Event

Description:

Loss of Bus 2A03 / Loss of Vacuum / Bus 2A07 Fails to Transfer / Loss of Feedwater Time Position Applicants Actions or Behavior

Trending to between 30% and 60%.

VERIFY Core Exit Saturation Margin greater than or equal to 20°F

QSPDS page 611

CFMS page 311 CO VERIFY RCS Pressure Control criteria satisfied:

VERIFY PZR pressure (WR and NR):

Between 1740 and 2380 psia and controlled.

TRENDING to between 2025 psia and 2275 psia.

CO VERIFY Core Heat Removal criteria satisfied:

VERIFY at least one RCP - operating.

VERIFY core loop T (TH - TC) - less than 10°F.

VERIFY Core Exit Saturation Margin - greater than or equal to 20°F:

QSPDS page 611

CFMS page 311.

ACO DETERMINE RCS Heat Removal criteria NOT satisfied:

DETERMINE SG levels are NOT between 21% and 80%

NR.

DETERMINE AFW is NOT available to restore SG levels.

PREVENT SG High level:

CLOSE MFW Block Valves HV-4047 and HV-4051.

VERIFY heat removal adequate.

Tc less than 555°F.

SG Pressures approximately 1000 psia.

VERIFY Tc greater than 545°F or controlled.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 17 of 22 Event

Description:

Loss of Bus 2A03 / Loss of Vacuum / Bus 2A07 Fails to Transfer / Loss of Feedwater Time Position Applicants Actions or Behavior

VERIFY SG pressures greater than 740 psia.

CRS DIRECT outside Operator to reset AFW Pump P-140.

PLACE AFW Pump P-140 HV-4716 hand switch to ACO OVERRIDE, then CLOSE.

M.O. Cue: If directed to reset AFW Pump P140, WAIT 4 minutes then REPORT that AFW Pump P140 HV-4716 linkage is broken and cannot be reset.

M.O. Cue: If directed to inspect P141 and P504 breaker, WAIT 3 minutes then REPORT both breakers are tripped on overcurrent (151 flags dropped on Phases A & C).

M.O. Cue: If requested to inspect P141 and P504 pumps, WAIT 3 minutes then REPORT both motors have an odor of burned insulation.

CO VERIFY Containment Isolation criteria satisfied:

VERIFY Containment pressure less than 1.5 psig.

VERIFY Containment Radiation monitors energized, AND not alarming or trending to alarm.

VERIFY secondary plant radiation monitors energized, AND not alarming or trending to alarm.

VERIFY Containment Temperature, Pressure and Combustible CO Gas Control criteria satisfied:

VERIFY Containment average temperature less than 120°F.

VERIFY Containment pressure less than 1.5 psig.

+15 min CRS DIAGNOSE event in progress:

DETERMINE all safety function criteria are NOT met per Attachment 4, Worksheet.

COMPLETE Attachment 1, Recovery Diagnostic.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 18 of 22 Event

Description:

Loss of Bus 2A03 / Loss of Vacuum / Bus 2A07 Fails to Transfer / Loss of Feedwater Time Position Applicants Actions or Behavior

DIAGNOSE event as Loss of Feedwater.

NOTIFY personnel of event in progress.

DESIGNATE SRO in Charge.

DIRECT initiation Steps 11-14.

CRS DIRECT performance of SO23-12-6, Loss of Feedwater.

CRS VERIFY Loss of Feedwater diagnosis:

INITIATE SO23-12-10, Safety Function Status Checks.

INITIATE Foldout Page.

DIRECT performance of FS-18, Establish Secondary Plant Protection.

DIRECT performance of Attachment 22, Non-Qualified Loads Restoration (post-SIAS initiation).

DIRECT performance of FS-11, Reset P-140 Overspeed Trip.

ENSURE EFAS 1 and 2 actuated.

VERIFY loss of feedwater diagnosis.

INITIATE Administrative Actions.

CRS DIRECT stopping all RCPs.

CO STOP all RCPs.

CRS DIRECT closing SG Blowdown and Sample valves.

DETERMINE Condensate Pumps P-052 and P-053 available CRS for low pressure feedwater with restoration of power to Bus A07.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 19 of 22 Event

Description:

Loss of Bus 2A03 / Loss of Vacuum / Bus 2A07 Fails to Transfer / Loss of Feedwater Time Position Applicants Actions or Behavior DIRECT bypassing Full Flow Condensate Polishing CRS Demineralizers (FFCPD).

ENSURE FFCPD Bypassed: FV-4902A open; HV-4900A and ACO HV-4900B closed.

DIRECT outside Operator to unlock and initiate OPENING CRS 1305MU024, MFW Pump Bypass Valve.

M.O. Cue: When directed to unlock/open MFW Pump Bypass Valve 1305MU024, EXECUTE remote function FW57, MFWP Bypass MU024

@ 100%.

DIRECT outside Operator to adjust Condensate Pump Mini-CRS flow Controller FIC-3294 to 3000 gpm.

M.O. Cue: When directed to adjust Condensate Pump Mini-flow Controller, EXECUTE remote function FW79, FIC-3294 Condensate Pump Mini-Flow @ 3000 gpm.

DIRECT placing MFW Regulator Bypass Valves HV-1105 and CRS HV-1106 in LOCAL and CLOSE.

PLACE MFW Regulator Bypass Valves in LOCAL at 0%

ACO demand.

ACO ENSURE FFCPD Inlet/Outlet valves closed and Bypass valve open.

+30 min CRS DIRECT manual initiation of SIAS and CCAS.

CO/ACO Manually ACTUATE SIAS and CCAS.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 20 of 22 Event

Description:

Loss of Bus 2A03 / Loss of Vacuum / Bus 2A07 Fails to Transfer / Loss of Feedwater Time Position Applicants Actions or Behavior CRS DIRECT overriding and operating Charging Pumps as necessary to maintain Pressurizer level.

CO OPERATE Charging Pumps to maintain Pressurizer level.

CRS DIRECT initiation of Attachment 22, Non-Qualified Load Restoration.

M.O. Cue: When directed to restore Non-Qualified Loads, WAIT 3 minutes, then CALL the Control Room and state that you are ready to restore.

When directed, EXECUTE Remote Function ED85, Non-Qualified Loads Restoration. When complete, INFORM the Control Room that you have restored Non-Qualified Loads.

CO VERIFY boration flow 40 gpm.

CRS DIRECT raising steaming rate on both SGs to lower SG pressures to < 500 psia.

ACO RAISE steaming rate on both SGs using ADVs.

CRS DIRECT resetting MSIS setpoint as cooldown proceeds.

CO RESET MSIS setpoint during cooldown.

ACO ENSURE MFW Pumps tripped and MFW Mini-flow Valves closed.

ACO VERIFY intact feedwater flowpath available.

CO VERIFY CIAS not actuated.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 21 of 22 Event

Description:

Loss of Bus 2A03 / Loss of Vacuum / Bus 2A07 Fails to Transfer / Loss of Feedwater Time Position Applicants Actions or Behavior ACO VERIFY MFW Isolation Valves HV-4048 and HV-4052 OPEN.

CRS DIRECT starting at least one Condensate Pump.

ACO START Condensate Pump(s) as directed.

CRS DIRECT opening MFW Regulator Bypass valves to 20% open.

ACO OPEN MFW Regulator Bypass Valves to 20% open.

CRS If MSIS actuates during cooldown, then DIRECT MSIS reset.

M.O. Cue: If directed to reset MSIS, EXECUTE Events as follows:

(NOTE: SG pressure must be > MSIS setpoint for reset to function.)

EVENT: MSIS Reset on Channel B and D @ PPS Cabinets.

L032 Key Lock Channel B (RP61A to Unlock)

L032 MSIS Channel B Reset (RP62F to Reset)

L032 Key Lock Channel B (RP61A to Lock)

L032 Key Lock Channel D (RP61B to Unlock)

L032 MSIS Channel D Reset (RP63F to Reset)

L032 Key Lock Channel D (RP61B to Lock)

EVENT: Floor Action - Reset A and C MSIS @ PPS Cabinets.

(Floor Operator to accomplish this action.)

M.O. Cue: If directed to reset MSIS, EXECUTE the following Events after MSIS reset has been completed at the PPS Cabinets:

EVENT: MSIS L/O Reset - L034/L035 (Aux Relay Cabinets).

L034 MSIS Train A Lockout Reset (RP57D to Reset)

L034 MSIS Train A Lockout Reset (RP57D to Normal)

L035 MSIS Train B Lockout Reset (RP59D to Reset)

L035 MSIS Train B Lockout Reset (RP59D to Normal)

CRS If MSIS actuated and reset, DIRECT opening MFW Isolation V l HV 4048 d HV 4052

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 22 of 22 Event

Description:

Loss of Bus 2A03 / Loss of Vacuum / Bus 2A07 Fails to Transfer / Loss of Feedwater Time Position Applicants Actions or Behavior Valves HV-4048 and HV-4052.

ACO If MSIS actuated and reset, OPEN MFW Isolation Valves.

CRITICAL ACO CONTINUE cooldown and SG depressurization until feedwater TASK flow to SGs is established (SG pressure ~ 600 psia).

+40 min CRS DIRECT maintaining reduced MFW flow for 5 minutes.

When feedwater is restored to any Steam Generator, or at Lead Evaluators discretion, TERMINATE the scenario.

NRC Scenario #2 SR-5 Unit 2(3) Control Board Operator l Shift Relief Status Sheet REVISION 7 Approved by: Dennis Wilcockson Date: 05/22/06

REVISION 7 SR-5 PAGE 1 OF 4 UNIT 2(3) CONTROL BOARD OPERATOR l SHIFT RELIEF STATUS SHEET POSITION: 22 32 DATE: Today NIGHTS: DAYS:

(Name) (Name)

Part I - Review prior to assuming the shift.

1. GENERAL PLANT STATUS Mode of Operation 1 Rx Power 70% MWe 809 Inserted Rods PLCEAs @ 130" RCS Boron 1619 Sample/Meter Boration Gallons: Per percent 22 Per degree 20 Dilution Gallons: Per percent 61 Per degree 58 VCT Blend Set points: BA 12.4 PMW 31.6 SHUTDOWN MODES: (leave blank if not applicable)

DID Sheet # Time to Boil Rx Head: ON OFF RCS Loops: FILLED NOT FILLED RIC Boration Flowpath:

Containment Integrity: (indicate open/unlocked hatches)

Main Equipment Emergency Parameter Limits: RCS Level: RCS Press:

RCS Temp: SDC Flow:

2. ACTIVITIES PERFORMED/IN PROGRESS:

PMW Gallons added: NIGHTS DAYS Boric Acid Gallons added: NIGHTS DAYS General Information/Comments:

Maintaining steady-state conditions at 70% power.

NRC Scenario #2 Turnover Sheet.wpd

REVISION 7 SR-5 PAGE 2 OF 4

3. ENGINEERED SAFETY FEATURES:

List INOP/OOS ESF Equipment and Comments:

Train A Charging Pump P-190 Train A Saltwater Cooling Pump P-307 Train A Low Pressure Safety Injection Pump P-015

4. REACTOR SUPPORT:

(B-Bypassed, I-In Test, T-Tripped, S-Simulated Signal, INOP-INOPERABLE)

PPS: A B C D CPC: A B C D CEAC: 1 2 PPS Points in Bypass or Trip:

A C B D Critical Parameters: (QSPDS A or B page 502 and 611)

T-Cold S/G E089 S/G E088 PZR PZR RCS Level Level Level Pressure Subcooling 542EF 68% 68% 49% 2246 48EF ASI: -0.049 ESI: -0.049 COLSS Power Margin: +28.38

5. BALANCE OF PLANT:

Main XFMR Neutral Amps: 100 BPS flow to: Condenser Outfall E071 aligned to: SFP RWST List Out of Service / INOP Rad Monitors:

Condenser Air Ejector Low Range Radiation Monitor RM-7818 List New Compensatory Actions and Setpoint Changes:

REVISION 7 SR-5 PAGE 3 OF 4

6. List additional comments, unusual conditions, and any SO123-0-A3 actions for the watch:

7. Activities scheduled or expected during oncoming shifts:

DAYS: Maintaining steady-state conditions at 70% power.

NIGHTS:

REVISION 7 SR-5 PAGE 4 OF 4 INITIALS DAYS NIGHTS

8. The Control Boards been walked down and accepted:

(Oncoming CBO) l

9. I hereby assume the position of Control Board Operator: l DAYS: DATE: TIME:

(Signature)

NIGHTS: DATE: TIME:

(Signature)

PART II - To Be Reviewed/Performed as Early in the Shift as Possible.

1. I have reviewed/performed (check boxes):

DAYS NIGHTS C The NCO Log C The LCOAR/EDMR Books C The Annunciator Status Book C The Annunciator Checks per SO23-6-29 C A complete status check of Control Board indicators to verify indications are within expected ranges for current plant conditions (Ref. LER 3-90-14)

[Modes 1 and 2 only (Ref. LER 3-90-10)]

C Valve positions on CR-57 and CCW boards aligned per position dots; any discrepancies understood.

C All annunciators in alarm are understood C PMS Alarms (print out) and CFMS alarm l page checked and all valid alarms are l understood. Forward reviewed PMS l alarm print out to Equipment Control. l

[Modes 5 and 6 only]

C During Outages: System Status Drawings have been reviewed (ECCS, CVCS, CCW) N/A (ACE 041100534)

(Initials)

2. Reviewed by Control Room Supervisor:

DAYS: DATE: TIME:

(Signature)

NIGHTS: DATE: TIME:

(Signature)

DISPOSITION: File per SO123-0-A3

Appendix D Scenario Outline Form ES-D-1 Facility: San Onofre Scenario No.: 2 Op Test No.: NRC Examiners: Operators:

Initial Conditions:

70% power - RCS Boron is 1619 ppm by Chemistry sample

Train A Component Cooling Water Pump (P-025) in service

Train A Charging Pump (P-190) OOS

Train A Saltwater Cooling Pump (P-307) OOS

Train A Low Pressure Safety Injection Pump (P-015) OOS

Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Holding at 70% power.

Critical Tasks:

Restore flow to the CCW Non-Critical Loop (RCPs operating).

Trip any RCP not satisfying RCP operating limits.

Stabilize RCS temperature/pressure following loss of heat removal from the faulted SG.

Manually Trip the Reactor (RPS Failure).

Event No. Malf. No. Event Type* Event Description 1 CC03A C (ACO, CRS) Component Cooling Water Train A header ruptures at the SDC

+10 min TS (CRS) Heat Exchanger.

2 RC11A I (CO, ACO Reactor Coolant System Loop 1 Thot fails high (TT-0111X1).

+20 min CRS) 3 SG06A C (CO, CRS) Steam Generator tube leak on E-088 requiring plant shutdown.

+30 min TS (CRS) 4 R (CO) Rapid Power Reduction.

+45 min N (ACO, CRS) 5 SG06A M (ALL) Steam Generator Tube Rupture on E-088.

+50 min 6 RP03 C (ACO) Auto and manual Reactor trip failure (ATWS).

+50 min 7 MS03B M (ALL) Excess Steam Demand Event on E-089 inside Containment

+50 min (5 minutes post-trip).

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specifications Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 SCENARIO

SUMMARY

NRC #2 The crew will assume the watch maintaining steady state power per SO23-5-1.7, Power Operations.

When turnover is complete a Train A Component Cooling Water header rupture is initiated. The crew will respond per SO23-2-17, Component Cooling System Operation and/or Abnormal Operating Instruction (AOI) SO23-13-7, Loss of Component Cooling Water (CCW) / Saltwater Cooling (SWC). The crew will align SWC & CCW Train B per pump configuration requirements.

The ruptured header will be removed from service. The CRS will evaluate Technical Specifications.

When the CCW and SWC systems are properly aligned, a Thot instrument fails high and will require crew actions per the ARPs, Operating Instruction SO23-3-1.10, Pressurizer Pressure and Level Control and Abnormal Operating Instruction (AOI) SO23-13-27, Pressurizer Pressure and Level Malfunction.

With the plant in a stable condition, a Steam Generator tube leak will commence on E088. The crew will enter AOI SO23-13-14, Reactor Coolant System Leak and the CRS will be required to evaluate Technical Specifications. The CRS will determine that a rapid plant shutdown per the AOI is required.

When the crew has demonstrated adequate control of the downpower, the leak size will increase to that of a SGTR and be accompanied by an ATWS. The crew will respond to the ATWS by opening breakers to Buses B15 and B16. Five minutes later, an ESDE inside Containment will occur. The crew performs SO23-12-1, Standard Post Trip Actions and diagnoses an ESDE and a SGTR and transitions to SO23-12-9, Functional Recovery.

The scenario is terminated when RCS temperature and pressure are stabilized while in the Functional Recovery procedure and associated Floating Steps.

Risk Significance:

Risk important components out of service: Charging P-190, LPSI P-015, SWC P-307

Failure of risk important system prior to trip: CCW Header Rupture

Risk significant core damage sequence: SGTR and ESDE

Risk significant operator actions: Manually trip Reactor on ATWS Appendix D NUREG 1021 Revision 9

Scenario Event Description NRC Scenario 2 SONGS 2006 Facility NRC Initial License Examination Simulator Scenario Setup Scenario 2 MACHINE OPERATORS INSTRUCTIONS SETUP IC: Use IC #182 and see attached Event File for NRC Scenario #2.

Appendix D NUREG 1021 Revision 9

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 1 Page 4 of 23 Event

Description:

CCW Train A Header Rupture Time Position Applicants Actions or Behavior Machine Operator: EXECUTE IC #182 and NRC Scenario #2 SETUP file to align components.

ENSURE Control Board Tags are hung on P-190, P-015 and P-307.

ENSURE Operator Aid Tags #029 (CVCS) and #005-4 (CVCS Ion Exchanger) reflect the scenario born concentration.

ENSURE procedures in progress are on the CO desk:

- Copy of SO32-5-1.7, Power Operations open to Section 6.4, Guidelines for Steady State Operation.

ENSURE SBCS is selected to Loop #1.

Control Room Annunciators in Alarm at 70%:

57A51 - SI / ECW SYS TRAIN A INOPERABLE 58A51 - CHARGING PUMP P-190 OVERRIDE / NOT IN AUTO Machine Operator: When directed, EXECUTE CC03A, CCW Train A Header rupture at the SDC Heat Exchanger E004 @ 500 gpm.

Indications available:

64A07 - CCW PUMP TRAIN A DISCH PRESS LO 64A45 - CCW HX TRAIN A OUTLET PRESS LO 64A26 - CCW SURGE TANK TRAIN A LEVEL HI/LO (on time delay) 64A17 - CCW TRAIN A RETURN FLOW LO 56C58 - SAFETY EQPT BLDG SUMP LEVEL HI-HI (on time delay)

+30 sec ACO REFER to Annunciator Response Procedures.

RECOGNIZE lowering surge tank level and CCW Pump ACO discharge pressure and INFORM the CRS AOI SO23-13-7 entry required.

+1 min CRS DIRECT performance of AOI SO23-13-7, Loss of SWC/CCW.

ACO ISOLATE Radwaste by closing 2HV-6465 and 3HV-6465.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 1 Page 5 of 23 Event

Description:

CCW Train A Header Rupture Time Position Applicants Actions or Behavior CRS/ACO DETERMINE that the leak is not isolated.

M.O. Cue: If contacted to report status of Unit 3 CCW Surge Tank Level, REPORT that Train A CCW Surge Tank level is stable and unchanged.

CRS DIRECT placing Train B CCW in service.

START CCW Pump P-026 and VERIFY that SWC P-114 ACO automatically starts.

+3 min CRS DIRECT transfer of the CCW Non-Critical Loop to Train B.

CRITICAL TASK ACO TRANSFER the CCW Non-Critical Loop to Train B.

CRS DIRECT transfer of Letdown HX to Train B.

ACO TRANSFER Letdown HX to Train B.

CRS/CO DISPATCH PEO to investigate flooding alarms.

CRS DIRECT securing CCW Pump P-025.

ACO STOP CCW Pump P-025 and SWC Pump P-112.

M.O. Cue: If directed to rack out breaker for CCW Pump P-024, WAIT 3 minutes and EXECUTE remote functions CC57A (DC to P-024) and CC58A (P-024 Breaker). If directed to rack out breaker for CCW Pump P-025, WAIT 3 minutes and EXECUTE remote functions CC57B (DC to P-025) and CC58B (P-025 Breaker).

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 1 Page 6 of 23 Event

Description:

CCW Train A Header Rupture Time Position Applicants Actions or Behavior DISPATCH PEO to close Loop A CCW Surge Tank Outlet, HV-CRS/ACO 6225.

M.O. Cue: If directed to close HV-6225, Loop A CCW Surge Tank Outlet, WAIT 3 minutes and EXECUTE remote function CC60.

+10 min CRS EVALUATE Technical Specifications.

LCO 3.7.7.A, Component Cooling Water System (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ACTION).

Restore CCW Train to OPERABLE status.

LCO 3.7.8.A, Saltwater Cooling System (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ACTION).

Restore SWC Train to OPERABLE status.

NOTE: The crew may decide to place CCW pumps P-024 and P-025 OOS, swap CCW Pump P-025 to Train B, and/or place Train A HPSI and CS Pumps OOS. Crew may remove DC Control Power for Train A HPSI and CS pumps to avoid damage due to lack of cooling water.

M.O. Cues: If directed to open the DC power supply breaker for the Train A ESF Pumps, ACKNOWLEDGE the order but do not perform (Time restriction).

If directed to transfer Emergency Chiller E-336 to Unit 3, ACKNOWLEDGE the order but do not perform (Time restriction).

If directed to transfer CCW Pump P-025 from Train A to Train B, ACKNOWLEDGE the order but do not perform (Time restriction).

CRS ENSURE ECCS is not required.

HPSI, LPSI, CS pumps are stopped.

When Technical Specifications are addressed, or at Lead Evaluators discretion, PROCEED to Event 2.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 2 Page 7 of 23 Event

Description:

Control Channel Thot Transmitter Fails High Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE RC11A @ 625°F, Loop 1B NR Thot TT-0111X1 fails high.

Indications Available:

50A02 - COLSS ALARM 50A05 - TAVG HI 50A15 - HOT LEG LOOP 1 TEMP HI Letdown lowers to minimum TI-0111AX indication rising

+30 sec CO REFER to Annunciator Response Procedures.

RECOGNIZE Thot failure and INFORM the CRS OI SO23 CO 1.10 or AOI SO23 27 entry required.

DIRECT performance of SO23-13-27, Pressurizer Pressure CRS and Level Malfunction.

DETERMINE Charging and Letdown systems are NOT CO responding as desired.

+1 min DEPRESS the A/M button on LIC-0110, PZR Level Controller, CO to place PZR level control in MANUAL.

STOP Charging pumps to match Letdown flow as closely as CO possible.

POSITION SBCS Tavg Selector Switch to Tavg 2 to restore ACO control of SBCS.

+2 min ADJUST LIC-0110, PZR Level Controller, to match Letdown CO and Charging flows.

CO MONITOR PZR level and maintain stable.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 2 Page 8 of 23 Event

Description:

Control Channel Thot Transmitter Fails High Time Position Applicants Actions or Behavior DETERMINE that a Loop 1 Thot transmitter, TT-0111X1, has CO/CRS failed high.

CRS DIRECT transfer of Pressurizer Level Remote Setpoint.

SELECT (TAG) to page 2 on LIC-0110 controller and CO OBSERVE IN1 displayed.

CO DEPRESS SEL pushbutton to display IN2.

CO DETERMINE IN2 will be selected to control PZR level.

DISPLAY the PZR level Remote Setpoint currently selected CO and DEPRESS SEL until the Selected Indicating Light is extinguished.

CO SELECT the new Remote Setpoint:

To select IN2, DEPRESS the RAISE () pushbutton once.

+5 min CO RETURN PZR level controller LIC-0110 to AUTO:

SELECT (TAG) to page 1 on the controller.

Manually ADJUST the output (right column) until the actual level (middle column) is matched with the generated setpoint (left column).

When within 2%, DEPRESS the A/M pushbutton to transfer LIC-0110 to AUTO.

OBSERVE Letdown flow and pressure to ensure no unusual oscillations.

RESTORE PZR heaters to service as required to control RCS pressure.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 2 Page 9 of 23 Event

Description:

Control Channel Thot Transmitter Fails High Time Position Applicants Actions or Behavior

+10 min CO RESTORE Backup Charging Pump P-192 to AUTO.

When PZR Level Control is returned to Auto, or at Lead Evaluators discretion, PROCEED to Event 3.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 3 Page 10 of 23 Event

Description:

SG Tube Leak on E088 @ 50 gpm Requiring Plant Shutdown Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE SG06A @ 0.14%, SG E088 Tube Leak of ~50 gpm.

Indications available:

60A46 - SECONDARY RADIATION HI 63B02 - UNIT 2 CRITICAL PARAMETERS PROBLEM CO/ACO REFER to Annunciator Response Procedures.

RECOGNIZE increasing radiation levels and INFORM the CRS ACO AOI SO23-13-14 entry required.

+1 min DIRECT performance of SO23-13-14, RCS Leak, Section for CRS Primary to Secondary leakage.

REQUEST Chemistry to confirm and quantify the Steam Generator tube leak by sampling the Condenser Air Ejector discharge.

M.O. Cue: When contacted as Chemistry, WAIT 5 minutes and REPORT that a frisk of the SG sample indicates high activity in SG E088. WAIT another 5 minutes, and then REPORT that high activity in SG E088 is verified.

CREW DETERMINE Radiation Monitor status:

Air Ejector High Range 7870 in alarm.

Main Steam Line 7874A1 (E088) in alarm.

SG Blowdown 6759 (E088) in alarm after a time delay.

DETERMINE that high radiation is due to a SG Tube Leak on CRS SG E088.

CRS/CO VERIFY PZR level is lowering.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 3 Page 11 of 23 Event

Description:

SG Tube Leak on E088 @ 50 gpm Requiring Plant Shutdown Time Position Applicants Actions or Behavior VERIFY VCT level is being maintained within programmed CRS/CO band.

CRS/CO DETERMINE RCS leak is greater than 25 gpm.

CRS DIRECT a rapid shutdown per SO23-5-1.7.

NOTE: Depending on crew actions, they may identify the leak at >25 gpm and go to the RNO which requires a Rapid Power Reduction (see Event 4) per SO23-5-1.7, otherwise, this will occur later in the AOI.

+5 min CRS/CO DETERMINE PZR level NOT stable or rising.

VERIFY that the SG Tube Leak is large enough to be CRS/CO confirmed by:

A mismatch in Charging and Letdown indications, AND

Air Ejector, Steam Generator Blowdown, or Main Steam Line Rad Monitor indications.

ACO Manually INITIATE Train B of CRIS.

CREW CONFIRM leakage using all available indications.

CRS DETERMINE leak rate and action from Step 4.p table:

Leakage is > 720 GPD (1/2 gpm).

DIRECT performance of Attachment 3, Minimizing Contamination During a SG Tube Leak.

Concurrently DIRECT a rapid shutdown per SO23-5-1.7 to be < 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and in Mode 3 within next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 3 Page 12 of 23 Event

Description:

SG Tube Leak on E088 @ 50 gpm Requiring Plant Shutdown Time Position Applicants Actions or Behavior PERFORM Attachment 3, Minimizing Contamination During a ACO SG Tube Leak.

PLACE Vacuum Pump P054 in service.

PLACE A-361, Air Ejector Unit in DIRECT.

ISOLATE Blowdown to E088.

PLACE LV-3245, Condenser Draw Off Valve to DISABLE.

NOTIFY Chemistry to sample Condenser Draw Off line.

PLACE Condenser Hotwell Overboarding System in MANUAL.

BYPASS the Full Flow Condensate Polishers.

+10 min CRS EVALUATE Technical Specifications.

LCO 3.4.13.A, RCS Operational Leakage (4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ACTION).

Reduce LEAKAGE to within limits.

When Technical Specifications are addressed, or at Lead Evaluators discretion, PROCEED to Event 4.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 4 Page 13 of 23 Event

Description:

Rapid Power Reduction Time Position Applicants Actions or Behavior Machine Operator: If contacted as Grid Control Center, ACKNOWLEDGE Rapid Power Reduction due to SG tube leak.

Indications available:

None DIRECT performance of actions in SO23-5-1.7, Power CRS Operations, Rapid Power Reduction.

IMPLEMENT Attachment 8 to determine the amount of CO/ACO Boration and CEAs to be used (located on Control Board).

A combination of CEA insertion and/or Boron will be used.

LOWER Turbine load (to raise Tc) until SBCS permissives are ACO in.

CO BORATE to the Charging Pump suction (Borate Mode).

CO USE CEAs for power reduction and ASI control.

STOP CEA insertion any time the PPDIL alarm is received.

CO Proceed after PPDIL alarm has reset.

+15 min FORCE Pressurizer Normal Spray flow using both spray CO valves.

When power level is lowered 3-5%, or at Lead Evaluators discretion, PROCEED to Events 5, 6, and 7.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5, 6, and 7 Page 14 of 23 Event

Description:

SGTR on E088 / ATWS / ESDE on E089 Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE SG06A, SGTR on E088 to 1.4%

(~500 gpm), RP03, ATWS, MS03B, SG E089 ESDE inside Containment @ 1.2% (5 minutes post-trip).

Indications Available:

56A55 - CONTAINMENT SUMP LEVEL HI 56A56 - CONTAINMENT SUMP LEVEL HI-HI 60A02 - CONTAINMENT HUMIDITY HI 60A03 - CONTAINMENT / FHB TEMP HI 60A12 - REACTOR CAVITY TEMP HI (time delay)

COLSS alarm Reactor Power rising RCS temperature lowering

+1 min RECOGNIZE uncontrollable increase in RCS leakrate along CREW with a post-trip increase in Containment pressure and sump level.

CRS DIRECT isolation of Letdown.

CO ISOLATE Letdown by closing TV-0221 or HV-9204.

+2 min DIRECT a Reactor trip and DIRECT performance of SO23 CRS 1, Standard Post Trip Actions.

NOTE: Crew may take all action required during SPTAs prior to reporting status.

CRS INITIATE Administrative Actions:

RECORD time of Reactor trip.

ANNOUNCE Reactor trip via PA System.

INITIATE Attachment 4, WORKSHEET.

INITIATE Attachment 5, ADMINISTRATIVE ACTIONS.

CO DETERMINE Reactivity Control criteria is NOT satisfied:

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5, 6, and 7 Page 15 of 23 Event

Description:

SGTR on E088 / ATWS / ESDE on E089 Time Position Applicants Actions or Behavior

DETERMINE Reactor trip circuit breakers (8) are NOT open.

DETERMINE more than one full length CEA - NOT fully inserted.

DETERMINE Reactor power is NOT lowering and startup rate is NOT negative.

CO REPORT Reactor fails to AUTO or MANUAL trip.

CRS DIRECT opening B15 and B16 Load Center supply breakers.

CRITICAL TASK ACO OPEN B15 and B16 Load Center supply breakers.

CO VERIFY Reactor trip.

ACO VERIFY Vital Auxiliaries functioning properly:

VERIFY Main Turbine tripped.

HP and LP Stop and Governor Valves closed.

MWe output lowering.

VERIFY both Unit Output Breakers open.

VERIFY Main Turbine speed less than 2000 rpm or lowering.

VERIFY CCW pump aligned to Non-Critical Loop and Letdown - Operating.

VERIFY both 1E 4 kV Buses energized.

VERIFY both 1E 480 V Buses B04 and B06 energized.

VERIFY all 6.9 kV and Non-1E 4 kV Buses energized.

VERIFY all Class 1E DC buses energized.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5, 6, and 7 Page 16 of 23 Event

Description:

SGTR on E088 / ATWS / ESDE on E089 Time Position Applicants Actions or Behavior M.O. Cue: When directed to check Main Steam Safety Valve status, REPORT as the 25 (Full Flow Operator) that all safety valves appear to be seated with no steam coming from the MSIV roof.

CO DETERMINE RCS Inventory Control criteria is NOT satisfied:

DETERMINE PZR level:

Is NOT between 10% and 70%.

Is NOT trending to between 30% and 60%.

VERIFY Core Exit Saturation Margin greater than or equal to 20°F.

QSPDS page 611.

CFMS page 311.

ENSURE PZR Level Control System operating in AUTO.

CO DETERMINE RCS Pressure Control criteria is NOT satisfied:

DETERMINE PZR pressure (WR and NR) is NOT between 1740 and 2380 psia and NOT controlled and NOT trending to between 2025 psia and 2275 psia.

ENSURE Auxiliary Spray Valve closed.

DETERMINE PZR pressure (WR) is less than 1740 psia and ENSURE SIAS actuated.

CRS RECORD time of SIAS.

CO DETERMINE Core Heat Removal criteria is NOT satisfied:

CRITICAL TASK

STOP all RCPs due to CIAS.

DETERMINE no RCPs are operating.

RECORD time of all RCPs off.

VERIFY operating loop Delta T (Th-Tc) less than 58°F.

VERIFY Th and Tc not rising.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5, 6, and 7 Page 17 of 23 Event

Description:

SGTR on E088 / ATWS / ESDE on E089 Time Position Applicants Actions or Behavior

VERIFY Core Exit Saturation Margin greater than or equal to 20°F.

QSPDS page 611.

CFMS page 311.

VERIFY operating loop Th and REP CET within 16°F.

QSPDS page 611.

CFMS page 311.

VERIFY Reactor Vessel level greater than or equal to 100% (plenum).

QSPDS page 622.

CFMS page 312.

NOTE: It is acceptable for CO to report Monitoring for Natural Circulation.

ACO DETERMINE RCS Heat Removal criteria is NOT satisfied:

DETERMINE E089 SG level is NOT between 21% and 80%

NR.

DETERMINE AFW available to restore E088 SG level between 40% NR and 80% NR.

PREVENT SG High level:

CLOSE MFW Block Valves HV-4047 and HV-4051.

VERIFY heat removal adequate:

Tc less than 555°F.

DETERMINE SG Pressures are NOT ~1000 psia.

DETERMINE E089 is affected SG for ESDE and E088 is affected SG for SGTR.

DETERMINE Tc less than 545°F and NOT controlled.

ENSURE SBCS valves closed.

ENSURE ADVs closed.

ENSURE SG Blowdown valves closed.

ENSURE Main Steam to Reheater valves closed.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5, 6, and 7 Page 18 of 23 Event

Description:

SGTR on E088 / ATWS / ESDE on E089 Time Position Applicants Actions or Behavior

DETERMINE E089 SG pressures less than 740 psia.

ENSURE MSIS Actuation.

RECORD time of MSIS.

CO DETERMINE Containment Isolation criteria is NOT satisfied:

DETERMINE Containment pressure exceeds 3.4 psig, and ENSURE the following actuated:

SIAS, CIAS, CCAS, CRIS

ENSURE all RCPs stopped.

VERIFY Containment Radiation monitors energized and not alarming or trending to alarm.

DETERMINE secondary plant radiation monitors energized and alarming or trending to alarm.

RECORD status of radiation monitors.

DETERMINE Containment Temperature, Pressure and CO Combustible Gas Control criteria NOT satisfied:

DETERMINE Containment average temperature greater than 120°F.

ENSURE proper functioning of Normal Containment Cooling.

CO DETERMINE Containment pressure greater than 14 psig:

ENSURE CSAS actuated.

ENSURE all available Containment Spray header flows are greater than 1600 GPM.

CRS RECORD time of CSAS.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5, 6, and 7 Page 19 of 23 Event

Description:

SGTR on E088 / ATWS / ESDE on E089 Time Position Applicants Actions or Behavior CRS DIAGNOSE event in progress:

DETERMINE all safety function criteria are NOT met per Attachment 4, Worksheet.

COMPLETE Attachment 1, Recovery Diagnostic.

DIAGNOSE feed break/ESDE on SG E089 inside Containment and SGTR on E088.

NOTIFY personnel of event in progress.

DESIGNATE SRO in Charge.

DIRECT initiation of Steps 11 - 14.

CRS DIRECT performance of SO23-12-9, Functional Recovery.

CRS RECORD time of EOI entry.

+15 min CRS VERIFY FR diagnosis:

INITIATE SO23-12-10, Safety Function Status Checks.

INITIATE Foldout Page.

DIRECT performance of FS-7, SI Throttle/Stop Criteria.

DIRECT performance of SO23-12-11, Attachment 3, Cooldown Depressurization.

DIRECT performance of SO23-12-11, Attachment 22, Non-Qualified Load Restoration.

DIRECT performance of SO23-12-11, Attachment 28, Isolation of SG with ESDE.

DIRECT performance of FS-30, Establish Stable RCS Temperature During ESDE.

DIRECT Chemistry to sample both SGs for radioactivity and boron.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5, 6, and 7 Page 20 of 23 Event

Description:

SGTR on E088 / ATWS / ESDE on E089 Time Position Applicants Actions or Behavior M.O. Cue: If directed to sample SGs, WAIT 10 minutes and then REPORT that E089 has activity near background and E088 activity is elevated with high boron levels. If the SG sample valves are closed, REPORT unable to establish sample flow.

CRS INITIATE Administrative Actions:

NOTIFY Shift Manager/Operations Leader of SO23-12-9, Functional Recovery.

ENSURE Emergency Plan is initiated.

IMPLEMENT Placekeeper.

CO VERIFY ESF actuation:

VERIFY SIAS actuation required.

PZR pressure less than SIAS setpoint.

ENSURE the following actuated:

SIAS/CCAS/CRIS M.O. Cue: If directed to energize Auxiliary Spray Valve, EXECUTE remote functions CV76 for MU130, CV55 for BE-17 Auxiliary Spray Valve power and CV75 for MU084 as required for the Charging Header Isolation Valve.

ACO STOP all unloaded Diesel Generators.

INITIATE SO23-12-11, Attachment 22, Non-Qualified Load ACO Restoration.

M.O. Cue: When directed to restore Non-Qualified Loads, WAIT 3 minutes, then CALL the Control Room and state that you are ready to restore.

When directed, EXECUTE Remote Function ED85, Non-Qualified Loads Restoration. When complete, INFORM the Control Room that you have restored Non-Qualified Loads.

CO ESTABLISH optimum SI alignment.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5, 6, and 7 Page 21 of 23 Event

Description:

SGTR on E088 / ATWS / ESDE on E089 Time Position Applicants Actions or Behavior

ESTABLISH two train operation

VERIFY all Charging Pumps operating.

DETERMINE two HPSI trains and two LPSI trains operating.

VERIFY all Cold leg flow paths aligned.

VERIFY SI flow required:

SI flow indicated or RCS pressure >1250 psia

RCS pressure greater than 1250 psia, OR VERIFY FS-7, Verify HPSI Throttle/Stop criteria satisfied.

CRS EVALUATE Immediate Safety Function Recovery Actions:

VERIFY any Safety Function Recovery Attachments (FR-1 through FR-8) indicated by any optimal EOI.

IMPLEMENT precautionary actions:

DIRECT Boration at greater than 40 gpm.

CO/ACO VERIFY SI Throttle/Stop Criteria NOT met:

VERIFY at least one SG operating

DETERMINE SBCS is NOT Available.

DETERMINE ADV available and Feedwater available.

DETERMINE PZR level <30% and NOT rising.

+35 min CO/ACO

DETERMINE RCS Cooldown is in progress.

CO MAINTAIN boration at least 40 gpm.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5, 6, and 7 Page 22 of 23 Event

Description:

SGTR on E088 / ATWS / ESDE on E089 Time Position Applicants Actions or Behavior DIRECT performance of FS-30, Establish Stable RCS CRS Temperature during ESDE.

ACO DETERMINE SG E088 affected by SGTR.

OBTAIN approval from the Shift Manager/Operations Leader to steam the isolated SG and NOTIFY Shift Manager/Operations CRS Leader to monitor radiological release rates and applicable area dose rates.

CRITICAL OPERATE ADV on SG E088 to stabilize RCS temperatures as ACO TASK faulted SG level lowers.

SG E089 at 10% WR, positions SG E088 ADV, HV-8419 to 10% open.

SG E089 at 5% WR, set SG E088 ADV, HV-8419, at Psat for lowest Tc.

SG E089 initial dryout, adjust SG E088 ADV, HV-8419, at Psat for lowest Tc attained as SG boils dry.

ACO STABILIZE least affected SG E088 pressure.

OPERATE ADV in automatic.

STABILIZE AFW flow.

DIRECT Initiation of SO23-12-11, Attachment 28, Isolation of CRS SG with ESDE.

ACO IDENTIFY SG E089 as most affected by ESDE.

VERIFY SG E088 available for heat removal AND affected by ACO SGTR.

REQUEST Shift Manager/Operations Leader to evaluate CRS radiological releases from that SG.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5, 6, and 7 Page 23 of 23 Event

Description:

SGTR on E088 / ATWS / ESDE on E089 Time Position Applicants Actions or Behavior Floor Cue: DIRECT the CRS to isolate Steam Generator E089.

ACO ISOLATE affected SG E089.

CLOSE/STOP the following:

MSIV HV-8204

MSIV Bypass HV-8202

ADV HV-8421 and PIC-8421 in MANUAL

MFIV HV-4052

AFW valves HV-4731 and HV-4715

Steam to AFW P-140 HV-8200

SG Blowdown isolation HV-4053

SG Water Sample Isolation HV-4057

+30 min

Electric AFW Pump P-141 When SG E089 is isolated, or at Lead Evaluators discretion, TERMINATE the scenario.

NRC Scenario #3 SR-5 Unit 2(3) Control Board Operator l Shift Relief Status Sheet REVISION 7 Approved by: Dennis Wilcockson Date: 05/22/06

REVISION 7 SR-5 PAGE 1 OF 4 UNIT 2(3) CONTROL BOARD OPERATOR l SHIFT RELIEF STATUS SHEET POSITION: 22 32 DATE: Today NIGHTS: DAYS:

(Name) (Name)

Part I - Review prior to assuming the shift.

1. GENERAL PLANT STATUS Mode of Operation 1 Rx Power 98.7% MWe 1171 Inserted Rods ARO RCS Boron 1542 Sample/Meter Boration Gallons: Per percent 22 Per degree 20 Dilution Gallons: Per percent 61 Per degree 58 VCT Blend Set points: BA 11.8 PMW 32.2 SHUTDOWN MODES: (leave blank if not applicable)

DID Sheet # Time to Boil Rx Head: ON OFF RCS Loops: FILLED NOT FILLED RIC Boration Flowpath:

Containment Integrity: (indicate open/unlocked hatches)

Main Equipment Emergency Parameter Limits: RCS Level: RCS Press:

RCS Temp: SDC Flow:

2. ACTIVITIES PERFORMED/IN PROGRESS:

PMW Gallons added: NIGHTS DAYS Boric Acid Gallons added: NIGHTS DAYS General Information/Comments:

Maintain steady-state power conditions.

NRC Scenario #3 Turnover Sheet.wpd

REVISION 7 SR-5 PAGE 2 OF 4

3. ENGINEERED SAFETY FEATURES:

List INOP/OOS ESF Equipment and Comments:

Train A Charging Pump P-190 Train A Saltwater Cooling Pump P-307 Train A Low Pressure Safety Injection Pump P-015

4. REACTOR SUPPORT:

(B-Bypassed, I-In Test, T-Tripped, S-Simulated Signal, INOP-INOPERABLE)

PPS: A B C D CPC: A B C D CEAC: 1 2 PPS Points in Bypass or Trip:

A C B D Critical Parameters: (QSPDS A or B page 502 and 611)

T-Cold S/G E089 S/G E088 PZR PZR RCS Level Level Level Pressure Subcooling 541EF 68% 68% 57% 2253 27EF ASI: -0.0216 ESI: -0.0216 COLSS Power Margin: +1.29

5. BALANCE OF PLANT:

Main XFMR Neutral Amps: 100 BPS flow to: Condenser Outfall E071 aligned to: SFP RWST List Out of Service / INOP Rad Monitors:

Condenser Air Ejector Low Range Radiation Monitor RM-7818 List New Compensatory Actions and Setpoint Changes:

REVISION 7 SR-5 PAGE 3 OF 4

6. List additional comments, unusual conditions, and any SO123-0-A3 actions for the watch:

7. Activities scheduled or expected during oncoming shifts:

DAYS: Maintain steady-state power conditions.

NIGHTS:

REVISION 7 SR-5 PAGE 4 OF 4 INITIALS DAYS NIGHTS

8. The Control Boards been walked down and accepted:

(Oncoming CBO) l

9. I hereby assume the position of Control Board Operator: l DAYS: DATE: TIME:

(Signature)

NIGHTS: DATE: TIME:

(Signature)

PART II - To Be Reviewed/Performed as Early in the Shift as Possible.

1. I have reviewed/performed (check boxes):

DAYS NIGHTS C The NCO Log C The LCOAR/EDMR Books C The Annunciator Status Book C The Annunciator Checks per SO23-6-29 C A complete status check of Control Board indicators to verify indications are within expected ranges for current plant conditions (Ref. LER 3-90-14)

[Modes 1 and 2 only (Ref. LER 3-90-10)]

C Valve positions on CR-57 and CCW boards aligned per position dots; any discrepancies understood.

C All annunciators in alarm are understood C PMS Alarms (print out) and CFMS alarm l page checked and all valid alarms are l understood. Forward reviewed PMS l alarm print out to Equipment Control. l

[Modes 5 and 6 only]

C During Outages: System Status Drawings have been reviewed (ECCS, CVCS, CCW) N/A (ACE 041100534)

(Initials)

2. Reviewed by Control Room Supervisor:

DAYS: DATE: TIME:

(Signature)

NIGHTS: DATE: TIME:

(Signature)

DISPOSITION: File per SO123-0-A3

Appendix D Scenario Outline Form ES-D-1 Facility: San Onofre Scenario No.: 3 Op Test No.: NRC Examiners: Operators:

Initial Conditions: * ~98.7% power - RCS Boron is 1542 ppm by Chemistry Sample

Train A Component Cooling Water Pump (P-025) in service

Train A Charging Pump (P-190) OOS

Train A Saltwater Cooling Pump (P-307) OOS

Train A Low Pressure Safety Injection Pump (P-015) OOS

Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Maintain steady-state power conditions.

Critical Tasks:

Restore flow to the CCW Non-Critical Loop (RCPs operating).

Establish minimum design SI flow rate.

Trip any RCP not satisfying RCP operating limits.

Event No. Malf. No. Event Type* Event Description 1 CC06B C (ACO, CRS) CCW Pump P-025 trip.

+5 min TS (CRS) 2 CV16A I (CO, CRS) VCT Level Instrument fails low (LT-0226).

+15 min 3 RD0403 C (CO, CRS) Dropped CEA #4.

+35 min TS (CRS) 4 R (CO) Downpower due to dropped CEA.

+45 min N (ACO, CRS) 5 FC05B I (ACO, CRS) Steam Generator E-088 Master Controller Setpoint failure.

+50 min 6 RC01C M (ALL) Large break LOCA.

+60 min 7 RP01E C (CO) LPSI Pump P-016 fails to start.

+60 min

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specifications Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 SCENARIO

SUMMARY

NRC #3 The crew will assume the shift and maintain steady-state conditions per SO23-5-1.7, Power Operations.

When turnover is complete a CCW Pump will trip. The crew will respond per AOI SO23-13-7, Loss of Component Cooling Water (CCW) / Saltwater Cooling (SWC). The crew will align SWC &

CCW Trains per pump configuration requirements. The CRS will evaluate Technical Specifications.

When the plant is stable, the VCT Level Transmitter (LT-226) will fail low. The crew will secure VCT makeup per the Annunciator Response Procedures and SO23-3-2.1, CVCS Charging and Letdown Operations. The RCS Makeup Control System will then be aligned for manual blended makeup mode.

A dropped control rod follows the transmitter failure. The crew will respond and stabilize the primary plant using Annunciator Response Procedures (ARP) and Abnormal Operating Instruction (AOI) SO23-13-13, Dropped or Misaligned CEA. The CRS will evaluate Technical Specifications. The CEA is not recoverable and a down power will be conducted per the AOI.

When the plant is stable, a Master Controller Setpoint will fail to 58% level. The crew will regain control of feedwater per Annunciator Response Procedures and/or AOI SO23-13-24, Feedwater Malfunctions.

The next event is a large break LOCA. The crew will determine that a plant trip is required and enters SO23-12-1, SPTAs, then SO23-12.3, Loss of Coolant Accident (LOCA). A LPSI Pump failure will require the operator to manually start the LPSI Pump.

Scenario is terminated when plant conditions are stable.

Risk Significance:

Risk important components out of service: Charging P-190, LPSI P-015, SWC P-307

Failure of risk important system prior to trip: CCW Pump trip

Risk significant core damage sequence: Large break LOCA with loss of LPSI

Risk significant operator actions: Restore the Non-Critical Loop Start a LPSI Pump Appendix D NUREG 1021 Revision 9

Scenario Event Description NRC Scenario 3 SONGS 2005 Facility NRC Initial License Examination Simulator Scenario Setup Scenario 3 MACHINE OPERATORS INSTRUCTIONS SETUP IC: Use IC #185 and see attached Event File for NRC Scenario #3.

Appendix D NUREG 1021 Revision 9

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 1 Page 4 of 19 Event

Description:

CCW Pump Trip Time Position Applicants Actions or Behavior Machine Operator: EXECUTE IC #185 and NRC Scenario #3 SETUP file to align components.

ENSURE Control Board Tags are hung on P-190, P-015 and P-307.

ENSURE Operator Aid Tags #029 (CVCS) and #005-4 (CVCS Ion Exchanger) reflect the scenario born concentration.

ENSURE procedures in progress are on the CO desk:

- Copy of SO32-5-1.7, Power Operations open to Section 6.4, Guidelines for Steady State Operation.

Control Room Annunciators in Alarm at 100%:

57A51 - SI / ECW SYS TRAIN A INOPERABLE 58A51 - CHARGING PUMP P-190 OVERRIDE / NOT IN AUTO Machine Operator: When directed, EXECUTE CC06B, CCW Pump P-025 OC Trip.

Indications Available:

64A21 - CCW PUMP TRAIN A OC 64A07 - CCW PUMP TRAIN A DISCH PRESS LO 64A10 - CCW NON-CRITICAL LOOP RETURN FLOW LO

+30 sec ACO REFER to Annunciator Response Procedures.

RECOGNIZE CCW Pump P025 trip and INFORM the CRS ACO CCW Pump P024 is available for starting.

CRS DIRECT starting CCW Pump P-024 (within 5 minutes).

CRITICAL RESTORE flow to the Component Cooling Water Non-Critical ACO TASK Loop (RCPs operating).

START CCW Pump P-024 and VERIFY SWC Pump P-112 is ACO running.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 1 Page 5 of 19 Event

Description:

CCW Pump Trip Time Position Applicants Actions or Behavior

+1 min May DIRECT performance of AOI SO23-13-7, Loss of CRS SWC/CCW.

ENSURE CCW aligned to the Train A Non-Critical Loop and ACO Letdown Heat Exchanger

+5 min CRS EVALUATE Technical Specifications.

LCO 3.7.7.A, Component Cooling Water System (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ACTION).

Restore CCW Train to OPERABLE status.

NOTE: The CRS may request that CCW Pump P-025 be racked out to restore the CCW Train to OPERABLE status.

When Technical Specifications are addressed, or at Lead Evaluators discretion, PROCEED to Event 2.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 2 Page 6 of 19 Event

Description:

VCT Level Transmitter LT-0226 Fails Low Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE CV16A, VCT Level Transmitter, LT-0226 fails low.

Indications available:

58A04 - VCT LEVEL HI/LO VCT Level Indicator LI-0226A lowering VCT Auto Makeup initiation CO REFER to Annunciator Response Procedures.

CO DETERMINE that VCT Auto Makeup has started.

CHECK VCT Level indicator LI-0227 on PMS and DETERMINE CO that level is normal (~51% and trending up due to auto makeup initiation).

CO IDENTIFY that VCT level indicator LI-0226 has failed low.

CO PLACE Makeup Mode Selector, HS-0210, to MANUAL.

NOTE: When Makeup Control is placed in MANUAL, the following alarms will illuminate (on short time delay):

58A06 - BORIC ACID TO VCT FLOW HI/LO (100 sec TD)

58A07 - DEMIN WATER TO VCT FLOW HI/LO (45 sec TD)

DIRECT performance of SO23-3-2.2, CVCS Operations to CRS ensure proper CVCS alignment is achieved.

+10 min CRS REQUEST I&C assistance.

When VCT Makeup is in Manual or at Lead Evaluators discretion, PROCEED to Events 3 and 4.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 and 4 Page 7 of 19 Event

Description:

Dropped CEA #4 and Power Descension Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE RD0403, Dropped CEA #4.

Indications Available:

50A28 - CEA DEVIATION 50A38 - CEA GROUP DEVIATION 50A10 - CEDMCS CEA WITHDRAWAL PROHIBIT 56B06 - PPS CH 1 TROUBLE 56A03 - LOCAL POWER DENSITY HI CHANNEL TRIP 56A04 - DNBR LO CHANNEL TRIP 56A13 - LOCAL POWER DENSITY HI PRETRIP 56A14 - DNBR LO RPS PRETRIP CEA #4 Rod Bottom indication

+10 sec RECOGNIZE that Regulating Group 1, CEA 4 has dropped and CO INFORM the CRS AOI SO23-13-13 entry required.

DIRECT performance of AOI SO23-13-13, Misaligned or CRS Immovable Control Element Assembly.

CO VERIFY that no more than one CEA is misaligned > 7 inches.

CO ENSURE CEDMCS Mode Selector Switch in OFF.

+10 min REDUCE Turbine load to restore RCS Tcold to the pre-CEA ACO drop value and BLOCK load changes.

M.O. Cues: If sent as Radwaste PEO to investigate CEDMCS, WAIT 3 minutes and REPORT no observable problems. If sent as I&C to investigate, WAIT 5 minutes and REPORT that a CEDMCS Card requires replacement. The estimated repair time is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

CO VERIFY Reactor is critical.

RECORD initial and stabilized reactor power for subsequent CRS SDM calculation.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 and 4 Page 8 of 19 Event

Description:

Dropped CEA #4 and Power Descension Time Position Applicants Actions or Behavior Within 15 minutes, DIRECT monitoring of DNBR and LPD per CRS SO23-3-3.6, Attachment 1.

Floor Cue: The Work Control Supervisor will complete the DNBR and LPD monitoring in accordance with SO23-3-3.6, Attachment 1.

DIRECT performance of Attachment 3, Misaligned CEA CRS checklist.

Within 15 minutes of discovery, DIRECT initiation of Reactor CRS power reduction.

For Non Group 6 Full Length CEA, REDUCE power 10%

within 60 minutes.

NOTE: CRS should recognize that power reduction due to dropped CEA

(~3%) satisfies the 15 minute requirement to initiate a power reduction. The remaining power reduction must be accomplished within 60 minutes.

COMMENCE lowering Turbine Generator load using CVOL ACO while maintaining Tcold per SO23-5-1.7.

DIRECT initiation of boration of the RCS per SO23-3-2.2 to CRS achieve target power level.

CO COMMENCE attempting to control ASI near full power ESI.

CRS REQUEST Reactor Engineering to report to the Control Room.

CRS INITIATE recovery of affected CEA per Attachment 1.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 and 4 Page 9 of 19 Event

Description:

Dropped CEA #4 and Power Descension Time Position Applicants Actions or Behavior CO VERIFY CEA position indications agree:

COMPARE affected CEA PIDs from CEAC No. 1 and 2 at CPC Operator Console.

COMPARE affected CEA PIDs from CEAC No. 1 and 2 at Secondary Rod Position CRT.

CHECK UEL and LEL lights.

VERIFY one CEA has not been misaligned >7 inches for an CO/CRS unknown duration.

+20 min CRS EVALUATE Technical Specifications.

LCO 3.1.5.A, Control Element Assembly Alignment (2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ACTION).

Restore the misaligned CEA to within 7 inches of its group.

When a 3-5% power reduction is completed, or at Lead Evaluators discretion, PROCEED to Event 5.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 10 of 19 Event

Description:

SG E088 Master Controller Setpoint Failure Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE FC05B, E088 Master Controller Setpoint failure to 58% level.

Indications available:

52A02 - FWCS SG2 E088 LEVEL DEVIATION 52A13 - FWCS TROUBLE 53B23 - CONDENSATE FLOW BALANCE TROUBLE SG E088 Feedwater Control Valve modulating closed then open SG E088 level lowering

+30 sec ACO REFER to Annunciator Response Procedure.

RECOGNIZE E088 Master Controller Setpoint at 58% and ACO INFORM the CRS AOI SO23-13-24 entry required.

DIRECT performance of AOI SO23-13-24, Feedwater Control CRS System Malfunctions.

CRS DIRECT use of AOI SO23-13-24, Attachment 1.

ACO DETERMINE that SG E088 level is low.

DETERMINE that SG E088 Master Controller output is ACO lowering.

+5 min PLACE SG E088 Master Controller in PREFERRED MANUAL ACO and raise output.

Floor CUE: REPORT as Shift Manager to maintain SG level at 68%.

ACO DETERMINE that SG E088 Feed Control Valve is opening.

DETERMINE that Main Feedwater Pumps K-005 and K-006 ACO speed is rising.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 11 of 19 Event

Description:

SG E088 Master Controller Setpoint Failure Time Position Applicants Actions or Behavior

+10 min VERIFY SG E088 level is stable at or near program level with ACO SG E088 Master Controller in MANUAL.

When SG level is restored, or at Lead Evaluators discretion, PROCEED to Events 6 and 7.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 and 7 Page 12 of 19 Event

Description:

Large Break LOCA / LPSI Pump Failure Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE RC01 @ 100%, RCS LOCA and RP01E, LPSI Pump P-016 failure.

Indications Available:

60A02 - CONTAINMENT HUMIDITY HIGH 57C10 - CONTAINMENT RADIATION HIGH 57C20 - RCS LEAKAGE DETECTION ACTIVITY HI 57C43 - RCS LEAKAGE ABNORMAL/RECIRC SYS VV MISALIGNED Unidentified RCS leak rate 1 gpm Charging flow > Letdown flow with plant conditions stable VCT level lowering Containment Sump inlet flow 1 gpm on the CFMS

+30 sec CREW RECOGNIZE RCS pressure decreasing rapidly.

VERIFY Reactor trip and DIRECT crew to perform actions of CRS SO23-12-1, Standard Post Trip Actions.

NOTE: Crew may take all action required during SPTAs prior to reporting status.

CRS INITIATE Administrative Actions:

RECORD time of Reactor trip.

ANNOUNCE Reactor trip via PA System.

INITIATE Attachment 4, WORKSHEET.

INITIATE Attachment 5, ADMINISTRATIVE ACTIONS.

CO VERIFY Reactivity Control criteria satisfied:

VERIFY Reactor Trip Circuit Breakers (8) open.

VERIFY maximum of one full length CEA - NOT fully inserted.

VERIFY Reactor power lowering and startup rate negative.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 and 7 Page 13 of 19 Event

Description:

Large Break LOCA / LPSI Pump Failure Time Position Applicants Actions or Behavior ACO VERIFY Vital Auxiliaries functioning properly:

VERIFY Main Turbine tripped.

HP and LP Stop and Governor Valves closed.

MWe output lowering.

VERIFY both Unit Output Breakers - open.

VERIFY Main Turbine speed less than 2000 rpm or lowering.

VERIFY both 1E 4KV buses A04 and A06 - energized.

VERIFY both 1E 480V buses B04 and B06 - energized.

VERIFY all 6.9KV and Non-1E 4KV buses are energized.

VERIFY all Class 1E DC buses - energized.

CO DETERMINE RCS Inventory Control criteria NOT satisfied:

DETERMINE PZR level:

Is NOT between 10% and 70%.

Is NOT trending to between 30% and 60%.

DETERMINE Core Exit Saturation margin NOT greater than or equal to 20°F.

QSPDS page 611.

CFMS page 311.

CO DETERMINE RCS Pressure Control criteria NOT satisfied:

DETERMINE PZR pressure (WR and NR) NOT between 1740 and 2380 psia and is NOT controlled.

Is NOT trending to between 2025 psia and 2275 psia.

If PZR pressure less than PZR pressure control system setpoint and lowering, then ENSURE Normal and Auxiliary Spray Valves - closed

If PZR pressure (WR) is less than 1740 psia, ENSURE SIAS actuated.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 and 7 Page 14 of 19 Event

Description:

Large Break LOCA / LPSI Pump Failure Time Position Applicants Actions or Behavior CRITICAL TASK CO DETERMINE LPSI Pump did NOT start and START P-015.

CRS RECORD time of SIAS.

CO DETERMINE Core Heat Removal criteria is NOT satisfied:

CRITICAL

DETERMINE RCPs operating criteria not met (CIAS) and TASK TRIP all RCPs.

RECORD time of all RCPs off.

VERIFY operating loop Delta T (Th-Tc) less than 58°F.

VERIFY Th and Tc not rising.

VERIFY operating loop Th and REP CET within 16°F.

QSPDS page 611.

CFMS page 311.

VERIFY Core Exit Saturation Margin 20°F.

QSPDS page 611.

CFMS page 311.

VERIFY Reactor Vessel level 100% (plenum).

QSPDS page 622.

CFMS page 312.

NOTE: It is acceptable for CO to report Monitoring for Natural Circulation.

ACO DETERMINE RCS Heat Removal criteria NOT satisfied:

VERIFY both SGs level - greater than 21% NR.

VERIFY both SGs level - less than 80% NR.

VERIFY the following:

Auxiliary feedwater available to restore both SGs level -

between 40% NR and 80% NR.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 and 7 Page 15 of 19 Event

Description:

Large Break LOCA / LPSI Pump Failure Time Position Applicants Actions or Behavior

Main feedwater available to restore both SGs level -

between 40% NR and 80% NR with flow to each SG:

At least one MFW Pump - operating.

RTO - actuated to both SGs.

PREVENT SG high level:

CLOSE MFW Block Valves:

E-088 E-089 HV-4047 HV-4051

VERIFY heat removal adequate:

TC - less than 555°F.

SG pressures - approximately 1000 PSIA.

DETERMINE Tc less than 545°F and NOT controlled.

VERIFY SG pressures greater than 740 psia.

CO DETERMINE Containment Isolation criteria NOT satisfied:

DETERMINE Containment pressure exceeds 3.4 psig, ENSURE the following actuated

SIAS, CIAS, CCAS, CRIS CRS RECORD time of SIAS, CIAS, CCAS, CRIS.

DETERMINE Containment Radiation monitors energized CO and alarming or trending to alarm.

VERIFY Secondary Plant Radiation Monitors energized CO/ACO and not alarming or trending to alarm.

DETERMINE Containment Temperature, Pressure and CO Combustible Gas Control criteria NOT satisfied:

DETERMINE Containment average temperature >120°F.

DETERMINE Containment pressure >1.5 psig.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 and 7 Page 16 of 19 Event

Description:

Large Break LOCA / LPSI Pump Failure Time Position Applicants Actions or Behavior ENSURE at least one Containment Dome Air Circulator CO operating.

If Containment pressure is greater than 3.4 psig, ENSURE the CO following are actuated:

SIAS, CIAS, CCAS, CRIS ENSURE all available Containment Emergency Cooling Units CO are operating.

CO If Containment pressure greater than 14 psig, then:

ENSURE CSAS actuated.

ENSURE all available containment spray header flows are greater than 1625 GPM.

CRS RECORD time of CSAS.

CRS DIAGNOSE event in progress:

DETERMINE all safety function criteria are NOT met per Attachment 4, Worksheet.

COMPLETE Attachment 1, Recovery Diagnostic.

LOCA inside Containment.

NOTIFY personnel of event in progress.

DESIGNATE SRO in Charge.

INITIATE Steps 11 - 14.

CRS DIRECT performance of SO23-12-3, LOCA.

RECORD EOI entry time.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 and 7 Page 17 of 19 Event

Description:

Large Break LOCA / LPSI Pump Failure Time Position Applicants Actions or Behavior

+15 min CRS VERIFY LOCA diagnosis:

INITIATE SO23-12-10, LOCA Safety Function Status Checks.

INITIATE Foldout Page.

DIRECT initiation of FS-7, HPSI Throttle/Stop.

DIRECT initiation of Attachment 22, Non-Qualified Loads Restoration.

VERIFY LOCA diagnosis, using Figure 1, Break Identification Chart.

INITIATE sampling of both Steam Generators for radioactivity and boron.

M.O. Cue: If directed to sample SGs, WAIT 10 minutes and then REPORT that E088 and E089 both have activity near background, and normal boron levels. If the SG sample valves are closed, REPORT unable to establish sample flow.

CRS INITIATE Administrative actions:

NOTIFY Shift Manager/Operations Leader of SO23-12-3, Loss of Coolant Accident initiation.

ENSURE Emergency Plan is initiated.

IMPLEMENT PLACEKEEPER.

CO VERIFY ESF actuation:

VERIFY SIAS actuation required:

PZR Pressure less than SIAS setpoint OR

Containment pressure greater than 3.4 psig

ENSURE SIAS, CCAS, CRIS are actuated.

INITIATE SO23-12-11, Attachment 22, Non-Qualified Load ACO Restoration.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 and 7 Page 18 of 19 Event

Description:

Large Break LOCA / LPSI Pump Failure Time Position Applicants Actions or Behavior M.O. Cue: When directed to restore Non-Qualified Loads, WAIT 3 minutes, then CALL the Control Room and state that you are ready to restore.

When directed, EXECUTE Remote Function ED85, Non-Qualified Loads Restoration. When complete, INFORM the Control Room that you have restored Non-Qualified Loads.

CO ESTABLISH Optimum SI Alignment:

ESTABLISH two train operation.

All Charging Pumps operating.

Two HPSI trains and one LPSI train operating.

All Cold leg flow paths aligned.

VERIFY SI flow required:

SI flow indicated.

DETERMINE FS-7, VERIFY SI Throttle/Stop Criteria is CO NOT satisfied.

CO VERIFY PZR pressure:

DETERMINE RCP NPSH requirements of SO23-12-11, Attachment 29 NOT satisfied.

VERIFY all RCPs stopped.

INITIATE FS-3, Monitor Natural Circulation.

CO VERIFY Letdown isolated.

VERIFY outside Containment radiation alarms - NOT alarming CO or trending to alarm.

VERIFY outside Containment sump levels - NOT abnormally CO rising.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 and 7 Page 19 of 19 Event

Description:

Large Break LOCA / LPSI Pump Failure Time Position Applicants Actions or Behavior VERIFY RCS sample valves, RCS and PZR head vents are CO closed.

CO VERIFY CCW parameters are normal.

CO VERIFY PZR safety valves are closed.

CRS/CO DETERMINE RCS is not isolated.

+30 min CRS DIRECT initiation of RCS cooldown.

When the RCS cooldown is initiated, or at Lead Evaluators discretion, TERMINATE the scenario.

NRC Scenario #4 SR-5 Unit 2(3) Control Board Operator l Shift Relief Status Sheet REVISION 7 Approved by: Dennis Wilcockson Date: 05/22/06

REVISION 7 SR-5 PAGE 1 OF 4 UNIT 2(3) CONTROL BOARD OPERATOR l SHIFT RELIEF STATUS SHEET POSITION: 22 32 DATE: Today NIGHTS: DAYS:

(Name) (Name)

Part I - Review prior to assuming the shift.

1. GENERAL PLANT STATUS Mode of Operation 2 Rx Power 3x10-4% MWe N/A Inserted Rods Gr.5@125" Gr.6@23" PLCEAs@75" RCS Boron 1342 Sample/Meter Boration Gallons: Per percent 22 Per degree 24 Dilution Gallons: Per percent 71 Per degree 79 VCT Blend Set points: BA 10.3 PMW 33.7 SHUTDOWN MODES: (leave blank if not applicable)

DID Sheet # Time to Boil Rx Head: ON OFF RCS Loops: FILLED NOT FILLED RIC Boration Flowpath:

Containment Integrity: (indicate open/unlocked hatches)

Main Equipment Emergency Parameter Limits: RCS Level: RCS Press:

RCS Temp: SDC Flow:

2. ACTIVITIES PERFORMED/IN PROGRESS:

PMW Gallons added: NIGHTS DAYS Boric Acid Gallons added: NIGHTS DAYS General Information/Comments:

Raise power to ~ 2% in preparation for placing Main Feedwater in service per Section 6.5 and 6.6 of SO23-3-1.3.1.

Unit is in a Xenon-free, middle of life (MOC) condition.

NRC Scenario #4 Turnover Sheet.wpd

REVISION 7 SR-5 PAGE 2 OF 4

3. ENGINEERED SAFETY FEATURES:

List INOP/OOS ESF Equipment and Comments:

Train A Saltwater Cooling Pump P-307

4. REACTOR SUPPORT:

(B-Bypassed, I-In Test, T-Tripped, S-Simulated Signal, INOP-INOPERABLE)

PPS: A B C D CPC: A B C D CEAC: 1 2 PPS Points in Bypass or Trip:

A C B D Critical Parameters: (QSPDS A or B page 502 and 611)

T-Cold S/G E089 S/G E088 PZR PZR RCS Level Level Level Pressure Subcooling 546EF 55% 55% 38% 2255 106EF ASI: -0.0216 ESI: -0.0216 COLSS Power Margin: +99.72

5. BALANCE OF PLANT:

Main XFMR Neutral Amps:

BPS flow to: Condenser Outfall E071 aligned to: SFP RWST List Out of Service / INOP Rad Monitors:

Condenser Air Ejector Low Range Radiation Monitor RM-7818 List New Compensatory Actions and Setpoint Changes:

REVISION 7 SR-5 PAGE 3 OF 4

6. List additional comments, unusual conditions, and any SO123-0-A3 actions for the watch:

7. Activities scheduled or expected during oncoming shifts:

DAYS:

Raise power to ~ 2% in preparation for placing Main Feedwater in service per Section 6.5 and 6.6 of SO23-3-1.3.1.

Unit is in a Xenon-free, middle of life (MOC) condition.

NIGHTS:

REVISION 7 SR-5 PAGE 4 OF 4 INITIALS DAYS NIGHTS

8. The Control Boards been walked down and accepted:

(Oncoming CBO) l

9. I hereby assume the position of Control Board Operator: l DAYS: DATE: TIME:

(Signature)

NIGHTS: DATE: TIME:

(Signature)

PART II - To Be Reviewed/Performed as Early in the Shift as Possible.

1. I have reviewed/performed (check boxes):

DAYS NIGHTS C The NCO Log C The LCOAR/EDMR Books C The Annunciator Status Book C The Annunciator Checks per SO23-6-29 C A complete status check of Control Board indicators to verify indications are within expected ranges for current plant conditions (Ref. LER 3-90-14)

[Modes 1 and 2 only (Ref. LER 3-90-10)]

C Valve positions on CR-57 and CCW boards aligned per position dots; any discrepancies understood.

C All annunciators in alarm are understood C PMS Alarms (print out) and CFMS alarm l page checked and all valid alarms are l understood. Forward reviewed PMS l alarm print out to Equipment Control. l

[Modes 5 and 6 only]

C During Outages: System Status Drawings have been reviewed (ECCS, CVCS, CCW) N/A (ACE 041100534)

(Initials)

2. Reviewed by Control Room Supervisor:

DAYS: DATE: TIME:

(Signature)

NIGHTS: DATE: TIME:

(Signature)

DISPOSITION: File per SO123-0-A3

Appendix D Scenario Outline Form ES-D-1 Facility: San Onofre Scenario No.: 4 Op Test No.: NRC spare Examiners: Operators:

Initial Conditions:

Reactor Critical at ~3x10-4% power - RCS Boron is 1342 ppm by Chemistry Sample

Train A Component Cooling Water Pump (P-025) in service

Train A Saltwater Cooling Pump (P-307) OOS

Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Power increase in progress to ~2% power.

Critical Tasks:

Restore flow to the CCW Non-Critical Loop (RCPs operating).

Restore power to at least one 1E 4kV Bus.

Establish Reactivity Control (> 2 FLCEAs Not Fully Inserted & No SIAS).

Event No. Malf. No. Event Type* Event Description 1 R (CO) Rod withdrawal and power increase in progress to ~2% power.

+15 min N (ACO, CRS) 2 RC15B I (CO, CRS) Pressurizer Pressure Control Channel fails high (PT-0100Y).

+25 min TS (CRS) 3 ED08B C (CO, ACO, Loss of Non-1E Instrument Bus Q0612.

+35 min CRS) 4 ED03A C (ACO, CRS) Bus 2A04 Overcurrent lockout.

+45 min TS (CRS) 5 PG24 M (ALL) Loss of Offsite Power.

+50 min 6 EG08B C (ACO) Emergency Diesel Generator 2G003 mechanical failure.

+50 min Station Blackout 7 RD8802 C (CO) Four fully stuck CEAs; Loss of Reactivity Control.

+50 min RD8902 RD9002 RD9102

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Appendix D NUREG 1021 Revision 9

Appendix D Scenario Outline Form ES-D-1 SCENARIO

SUMMARY

NRC #4 The crew will assume the watch with the Reactor critical at ~3x10-4% power. The crew will raise power using rod withdrawal per SO23-5-1.3.1, Plant Startup from Hot Standby to Minimum Load.

After the crew has demonstrated control of the power change, a Pressurizer Pressure instrument fails high and will require crew actions per the Annunciator Response Procedures (ARPs) and Abnormal Operating Instruction (AOI) SO23-13-27, Pressurizer Pressure and Level Malfunction. The CRS will evaluate Technical Specifications.

After the crew has restored the Pressurizer Pressure instrument, a loss of Non-1E Instrument Bus Q0612 will occur and require crew actions per the ARPs and AOI SO23-13-19, Loss of Non-1E Instrument Buses.

With Letdown restoration in progress, a bus fault and lockout will occur on Bus 2A04. The crew will refer to SO23-13-26, Loss of Power to an AC Bus. The CRS will evaluate Technical Specifications.

Once the decision to shutdown is made, a Loss of Offsite Power will occur. The Reactor will trip and the crew will perform SO23-12-1, Standard Post Trip Actions. EDG 2G003 will trip. Four rods remain stuck out of the core requiring manual boration alignment on the part of the CO in preparation for Bus 2A06 power restoration.

The crew diagnoses a Loss of Reactivity Control due to a Station Blackout and enters SO23 9, Functional Recovery. The success path will require cross-tying power with Unit 3 and establishing a boration flowpath.

The scenario is terminated when Bus 2A06 is energized and boration at greater than 40 gpm is established.

Risk Significance:

Risk important components out of service: SWC P-307

Failure of risk important system prior to trip: Loss of Vital Inverter

Risk significant core damage sequence: SBO with Loss of Reactivity Control

Risk significant operator actions: Vital AC power restoration Establish boration flowpath Appendix D NUREG 1021 Revision 9

Scenario Event Description NRC Scenario 4 SONGS 2006 Facility NRC Initial License Examination Simulator Scenario Setup Scenario 4 MACHINE OPERATORS INSTRUCTIONS SETUP IC: Use IC #184 and see attached Event File for NRC Scenario #4.

Appendix D NUREG 1021 Revision 9

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 4 of 20 Event

Description:

Rod Withdrawal and Power Increase in Progress to ~2% power Time Position Applicants Actions or Behavior Machine Operator: EXECUTE IC #184 and NRC Scenario #4 SETUP file to align components.

ENSURE Control Board Tags are hung on P-307.

ENSURE Operator Aid Tags #029 (CVCS) and #005-4 (CVCS Ion Exchanger) reflect the scenario born concentration.

ENSURE procedures in progress are on the CO desk:

- Copy of SO23-5-1.3.1 completed through Step 6.4.

ENSURE that Control Rods are in the appropriate position.

PLACE the MOC Operations Physics Summary Book on the CO Desk.

PLACE the MOC Attachment 8 from SO23-5-1.7 in the Plexiglas holder next to Rod Control.

Control Room Annunciators in Alarm at 3x10-4%:

50A02 - COLSS ALARM 50A07 - SBCS DEMAND PRESENT 52A12 - FWCS SG2 E088 AUTO XFR TO MANUAL 52A17 - FWCS SG1 E089 AUTO XFR TO MANUAL 53A03 - MFWP TURBINE K006 TRIP 53A27 - MFWP P062 DISCH PRESS LO 53A28 - MFWP P062 FLOW LO 53A47 - 3rd POINT HEATER DRAIN TANK LEVEL HI/LO 53B03 - MFWP TURBINE K005 TRIP 53B27 - MFWP P063 DISCH PRESS LO 53B28 - MFWP P063 FLOW LO 56A30/40/50/60 - LOSS OF LOAD CHANNEL 1/2/3/4 TRIP DISABLED 63E10 - SCE CB TRIP 99A02 - EMERGENCY PUSHBUTTON TURBINE TRIP 99A24 - TURBINE TRIP RELAY TRIPPED 99B01 - GENERATOR TRIP 99B19 - VACUUM PROTECTION PLC TROUBLE 99B41 - AVR CH A FAULT 99B42 - AVR CH B FAULT

+1 min DIRECT performance of SO23-5-1.3.1, Plant Startup from Hot CRS Standup to Minimum Load.

REFER to LCS Figure 3.1.102-1 and commence maintaining CO the Control Rods in the proper sequence of overlap.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 5 of 20 Event

Description:

Rod Withdrawal and Power Increase in Progress to ~2% power Time Position Applicants Actions or Behavior CO POSITION Group Select switch to the CEA Group 6.

POSITION Mode Select Switch to MG (Manual Group) or MS CO (Manual Sequential).

When directed by the CRS, WITHDRAW Control Rods as CO/CRS required.

When CEA positioning is complete, PLACE the Mode Select CO Switch to OFF.

+15 min MAINTAIN Tcold within required band by monitoring the Steam ACO Bypass Control System operation.

When power has been raised to ~2%, or at Lead Evaluators discretion, PROCEED to Event 2.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 2 Page 6 of 20 Event

Description:

PZR Pressure Transmitter PT-0100Y Fails High Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE RC15B, Pressurizer Pressure Control Channel PT-0100Y fails high.

Indications available:

50A04 - PZR PRESS DEVIATION HI/LO 50A14 - PZR PRESS HI/LO PZR Heaters Trip OFF PZR Spray valves modulate OPEN if control channel drifts high enough prior to action

+1 min CO REFER to Annunciator Response Procedures.

CO DETERMINE which channel initiated the alarm using PR-100.

RECOGNIZE Channel Y (PR-0100B) has failed high and NOTIFY CRS that SO23-13-27 entry required.

If desired, SELECT PIC-100 to MANUAL, and return pressure CO to the normal band and ensure Spray Valves close and PZR pressure trending to normal.

DIRECT PERFORMANCE OF SO23-13-27 to place PZR CRS Pressure Control to the unaffected channel.

CO VERIFY PI-0100X is OPERABLE.

POSITION HS-0100A, Pressurizer Pressure Channel Select CO Switch to Channel X.

If required, TRANSFER PIC-0100, PZR Pressure Controller, to CO AUTO by DEPRESSING the A/M pushbutton and VERIFY proper system response.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 2 Page 7 of 20 Event

Description:

PZR Pressure Transmitter PT-0100Y Fails High Time Position Applicants Actions or Behavior CO RESTORE PZR heaters to normal configuration.

PLACE heater control switches to OFF, then AUTO (May wait until PZR pressure has been returned to the normal band).

RECOGNIZE and REPORT SBCS Permissives are active.

ACO (Not recoverable or controllable.)

+10 min CRS EVALUATE Technical Specifications.

LCO 3.4.1.A, RCS DNB Limits (2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ACTION).

Restore Pressurizer pressure to within limit.

When Technical Specifications are addressed, or at Lead Evaluators discretion, PROCEED to Event 3.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 3 Page 8 of 20 Event

Description:

Loss of Instrument Bus Q0612 Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE ED08B, Loss of Instrument Bus Q0612.

Indications Available:

63B34 - 2Q0612 INST BUS 2 POWER SUPPLY FAILURE Non-1E Pressurizer Heaters de-energize SBCS Automatic operation is lost Charging Pump P-191 (in AUTO) will stop Loss of Letdown due to closure of 2TV-9267, Letdown Regen HX outlet 58A01 - REGEN HX TSH-9267 LETDOWN TEMP HI 50A05 - TAVG HI 50A06 - TAVG LO 58A04 - VCT LEVEL HI/LO 58A05 - VCT LEVEL LO/LO VCT Outlet Valve LV-0227B will close RWST Outlet Valve LV-0227C will open

+30 sec CO/ACO REFER to Annunciator Response Procedures.

DETERMINE that Non-1E Instrument Bus Q0612 has de-ACO energized and INFORM the CRS SO23-13-19, Loss of Non-1E Instrument Buses entry required.

DIRECT performance of SO23-13-19, Loss of Non-1E CRS Instrument Buses.

DISPATCH PEO to transfer Instrument Bus #2 (Q0612) to CRS Emergency Source per SO23-6-17.1.

M.O. Cue: When directed to transfer Q0612 to the Emergency Source, WAIT two (2) minutes, then REPORT you are ready for transfer. When directed, EXECUTE remote function ED81, Transfer Q0612 to Emergency Source and DELETE malfunction ED08B. Ensure that SBCS Master Controller is placed in Manual prior to transfer.

+1 min ACO PLACE SBCS Master Controller in MANUAL.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 3 Page 9 of 20 Event

Description:

Loss of Instrument Bus Q0612 Time Position Applicants Actions or Behavior MAINTAIN PZR pressure at 2250 psia using 1E pressurizer CO heaters.

+5 min STOP Charging Pump P190 then MANUALLY operate CO Charging Pumps as necessary to maintain Pressurizer level.

NOTE: If a Charging Pump is started, a boration will occur due to the valve alignment changes for Charging Pump suction source on loss of Q0612.

ACO MAINTAIN Tcold by adjusting SBCS as necessary.

+10 min Upon restoration of Bus Q0612, DIRECT restoration of CRS automatic control.

NOTE: The CO will make preparations to restore Letdown, however, restoration is not required prior to proceeding to the next event.

(Scenario time restriction).

When Instrument Bus Q0612 has been re-energized, or at Lead Evaluators discretion, PROCEED to Event 4.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 4 Page 10 of 20 Event

Description:

Bus 2A04 Overcurrent Lockout Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE ED03A, Bus 2A04 overcurrent.

Indications Available:

63B05 - 2A04 VOLTAGE LO 63B06 - 2B04 VOLTAGE LO 63B25 - 2A04 SUPPLY BREAKER 2A0418 OC 63B40 - DIESEL GEN 2G002 DAY TANK TROUBLE

+30 sec CO/ACO REFER to Annunciator Response Procedures.

RECOGNIZE low bus voltage and INFORM the CRS AOI CO/ACO SO23-13-26 entry required.

DIRECT performance of SO23-13-26, Loss of Power to an AC CRS Bus.

CRS DIRECT aligning of Train B CCW and SWC.

+1 min ACO START the Train B CCW Pump (within 5 minutes of loss).

CRITICAL TASK

TRANSFER the Non-Critical Loop to Train B.

TRANSFER the Letdown Heat Exchanger to Train B.

VERIFY loss of the 1E 4 kV Bus is NOT due to a fire in the 1E ACO Switchgear Room.

ACO DETERMINE overcurrent annunciators are alarming on 2A04.

DIRECT initiation of SO23-6-9, 6.9 kV, 4 kV and 480V Bus and CRS Feeder Faults, to return Bus A04 to service.

DIRECT initiation of Equipment Actions for Loss of the 1E 4 kV CRS Bus 2A04.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 4 Page 11 of 20 Event

Description:

Bus 2A04 Overcurrent Lockout Time Position Applicants Actions or Behavior

+5 min STOP G002 Diesel Generator by placing in MAINTENANCE ACO LOCKOUT.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , DIRECT performance of SO23-3-3.23, CRS Attachment for AC Sources Verification, for both Units.

SELECT HS-0210, Makeup Mode Selector Switch to MANUAL CO and PLACE a Caution Tag at the switch to prevent inadvertent dilution.

CO ALIGN Feedwater flow to SG E-089.

START P-140 and ALIGN AFW Valves.

+15 min CRS EVALUATE Technical Specifications.

LCO 3.0.3, Due to loss of two 1E Battery Chargers.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , place the Unit in MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

M.O. Cue: When the crew decides to place Channel A in Bypass, EXECUTE remote functions RP51, 52C, and 52D, then DELETE remote function RP51.

CRS DIRECT Bypassing Channel A DNBR and LPD trips.

+15 min DIRECT setting CEAC 2 INOP Flags in all CPCs by changing CRS each CPC Addressable Constant Point ID 062 to 2.

When Technical Specifications have been addressed, or at Lead Evaluators discretion, PROCEED to Events 5, 6, and 7.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5, 6, and 7 Page 12 of 20 Event

Description:

Loss of Offsite Power / Four Stuck CEAs / 2G003 Failure Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE PG24, Loss of Offsite Power, EG08B, 2G003 EDG Mechanical Failure, RD8802/8902/9002/9102, Stuck CEAs, and PG57, Loss of SDGE Switchyard (+5 minutes) trip.

Indications available:

Numerous Loss Of Offsite Power Related Alarms

+10 secs RECOGNIZE Reactor trip and Loss of Offsite Power and CO/ACO INFORM the CRS SO23-12-11 entry required.

DIRECT performance of SO23-12-1, Standard Post Trip CRS Actions.

NOTE: Crew may take all action required during SPTAs prior to reporting status.

CRS INITIATE Administrative Actions:

RECORD time of Reactor trip.

ANNOUNCE Reactor trip via PA System.

INITIATE Attachment 4, WORKSHEET.

INITIATE Attachment 5, ADMINISTRATIVE ACTIONS.

CO DETERMINE Reactivity Control criteria NOT satisfied:

VERIFY Reactor Trip Circuit Breakers (8) - open.

DETERMINE four full length CEAs - NOT fully inserted.

VERIFY Reactor power lowering and startup rate negative.

When available, COMMENCE emergency boration at > 40 CO gpm.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5, 6, and 7 Page 13 of 20 Event

Description:

Loss of Offsite Power / Four Stuck CEAs / 2G003 Failure Time Position Applicants Actions or Behavior ACO DETERMINE Vital Auxiliaries NOT functioning properly:

VERIFY Main Turbine tripped.

VERIFY both Unit Output Breakers - open.

DETERMINE CCW Pump NOT aligned to Non-Critical Loop (NCL) and Letdown Heat Exchanger.

DETERMINE both 1E 4 kV Buses A04 and A06 de-energized.

DETERMINE both 1E 480 V Buses B04 and B06 de-energized.

DETERMINE all 6.9 kV and Non-1E Buses de-energized.

VERIFY all Class 1E DC Buses - energized.

ACO PLACE DG G003 in Maintenance Lockout.

INITIATE Attachment 6, DG Failure Followup Actions for Buses ACO 2A04 and 2A06.

M.O. Cue: If directed to investigate 2G003, WAIT 3 minutes and REPORT it is shutdown and there is a large amount of oil on the DG room floor.

CO DETERMINE RCS Inventory Control criteria NOT satisfied:

DETERMINE PZR level between 10% and 70% and NOT trending to between 30% and 60%.

VERIFY Core Exit Saturation Margin - greater than or equal to 20°F:

QSPDS page 611.

CFMS page 311.

CO DETERMINE RCS Pressure Control criteria NOT satisfied:

DETERMINE PZR pressure (WR and NR) between 1740 PSIA and 2380 PSIA and NOT controlled AND trending to between 2025 PSIA and 2275 PSIA.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5, 6, and 7 Page 14 of 20 Event

Description:

Loss of Offsite Power / Four Stuck CEAs / 2G003 Failure Time Position Applicants Actions or Behavior CO DETERMINE Core Heat Removal criteria is NOT satisfied:

DETERMINE no RCPs are operating.

RECORD time of all RCPs off.

VERIFY operating loop Delta T (Th-Tc) less than 58°F.

VERIFY Th and Tc not rising.

VERIFY operating loop Th and REP CET within 16°F.

QSPDS page 611.

CFMS page 311.

VERIFY Core Exit Saturation Margin 20°F.

QSPDS page 611.

CFMS page 311.

VERIFY Reactor Vessel level 100% (plenum).

QSPDS page 622.

CFMS page 312.

NOTE: It is acceptable for CO to report Monitoring for Natural Circulation.

ACO DETERMINE RCS Heat Removal criteria NOT satisfied:

VERIFY both SGs level - greater than 21% NR.

VERIFY both SGs level - less than 80% NR.

VERIFY Auxiliary feedwater available to restore both SGs level - between 40% NR and 80% NR.

PREVENT SG high level:

CLOSE MFW Block Valves:

E-088 E-089 HV-4047 HV-4051

VERIFY heat removal adequate:

TC - less than 555°F.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5, 6, and 7 Page 15 of 20 Event

Description:

Loss of Offsite Power / Four Stuck CEAs / 2G003 Failure Time Position Applicants Actions or Behavior

SG pressures - approximately 1000 PSIA.

DETERMINE TC - less than 545°F and NOT controlled.

ACO

CLOSE MSIVs due to loss of offsite power.

VERIFY SG pressures - greater than 740 PSIA.

CO VERIFY Containment Isolation criteria satisfied:

VERIFY Containment pressure - less than 1.5 PSIG.

DETERMINE some Containment Area Radiation Monitors energized and NOT alarming or trending to alarm.

DETERMINE some Secondary Plant Radiation Monitors energized and NOT alarming or trending to alarm.

DETERMINE Containment Temperature, Pressure and CO Combustible Gas Control criteria NOT satisfied:

DETERMINE Containment average temperature - greater than 120°F.

VERIFY Containment pressure - less than 1.5 PSIG.

+15 min CRS DIAGNOSE Event in Progress:

DETERMINE all safety function criteria are NOT met per Attachment 4, WORKSHEET.

COMPLETE Attachment 1, Recovery Diagnostic.

DIAGNOSE loss of Reactivity Control and Station Blackout.

o NOTIFY personnel of event in progress.

o DESIGNATE SRO-in-charge.

o DIRECT initiation of Steps 11 through 14.

M.O. Cue: If SC&E GCC is contacted for grid status, REPORT that cause of grid loss is unknown and field crews are investigating. No estimate on time to restore a line.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5, 6, and 7 Page 16 of 20 Event

Description:

Loss of Offsite Power / Four Stuck CEAs / 2G003 Failure Time Position Applicants Actions or Behavior M.O. Cue: If Unit 3 status is requested, REPORT that Bus 3A06 is energized from EDG 3G003 and Bus 3A04 is energized from EDG 3G002.

CRS DIRECT performance of SO23-12-9, Functional Recovery.

M.O. Cue: When SO23-12-9 is initiated, CALL as SDG&E GCC and REPORT that SONGS Switchyard appears to have several faults and will not be available until a crew can be dispatched to determine the problem.

CRS VERIFY Functional Recovery diagnosis:

INITIATE SO23-12-10, Safety Function Status Checks.

INITIATE Foldout Page.

DIRECT performance of FS-3, Monitor Natural Circulation.

DIRECT performance of SO23-12-11, Attachment 19, Non-1E DC Load Reduction.

DIRECT performance of SO23-12-11, Attachment 20, Class1E Battery Load Reduction.

DIRECT performance of FS-18, Secondary Plant Protection.

DIRECT performance of SO23-12-11, Attachment 24, Supply 1E 4 kV Bus with Opposite Unit Diesel.

DIRECT performance of SO23-12-11, Attachment 6, Diesel Generator Failure Follow-up Actions.

DIRECT Chemistry to sample both SGs for radioactivity and boron.

M.O. Cue: If directed to sample SGs, WAIT 10 minutes and REPORT that E088 and E089 sample lines were frisked, and both have activity near background. If the SG sample valves are closed, REPORT that you are unable to establish sample flow.

M.O. Cue: When directed to initiate Non-1E DC Load Reduction, ACKNOWLEDGE and STATE you will report when complete.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5, 6, and 7 Page 17 of 20 Event

Description:

Loss of Offsite Power / Four Stuck CEAs / 2G003 Failure Time Position Applicants Actions or Behavior M.O. Cue: When directed to initiate Class 1E Battery Load Reduction, ACKNOWLEDGE and STATE you will report when complete.

DIRECT performance of SO23-12-11, Attachment 24, CRS Supplying 1E 4 kV Bus with Opposite Unit Diesel.

CRS DETERMINE Train B is available.

OBTAIN approval of Shift Manager to cross connect Train B CRS using 10 CFR 50.54(x) on both units to supply 1E 4 kV Bus 2A06 with the opposite unit Diesel Generator.

REQUEST SM initiates NRC notification within one hour CRS regarding actions per this attachment.

NOTIFY opposite unit SRO that automatic sequencing of ESF CRS loads onto opposite Unit 1E 4kV Bus 3A06 will be blocked.

ENSURE 1E 4kV Bus Tie breaker AUTO/MANUAL transfer ACO switches selected to MANUAL.

2A0619 (2HS-1639B2) and 3A0603 (3HS-1639B2).

ACO ENSURE 1E 4kV Bus Tie breakers open.

2A0619 and 3A0603.

ENSURE 2G003 Diesel Generator selected to MAINTENANCE ACO LOCKOUT.

DIRECT performance of Train B Diesel Generator Cross-Tie CRS Permissive switch alignment on 50' Elevation.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5, 6, and 7 Page 18 of 20 Event

Description:

Loss of Offsite Power / Four Stuck CEAs / 2G003 Failure Time Position Applicants Actions or Behavior CONTACT the PPEO and INITIATE Unit 2 Train A Diesel ACO Generator Cross-Tie Permissive switch alignment on 50' Elevation.

VERIFY feeder faults NOT indicated by relay flags on:

2A0616 - Unit Aux Transformer

2A0618 - Reserve Aux Transformer

2A0619 - 2A06 Bus Tie

2A0613 - 2G003 EDG M.O. Cue: When asked, REPORT no feeder faults on breakers.

DIRECT the PPEO to SELECT both Unit 2 Train B Diesel ACO Generator Cross-Tie Permissive switches on Fire Isolation Panel 2L-413 to 50.54X.

2HS-5054XA2 and 2HS-5054XB2 M.O. Cue: When directed, PERFORM remote functions EG62A and EG62B and REPORT that the Unit 2 50.54X switches have been aligned.

CONTACT the PPEO and INITIATE Unit 3 Train B Diesel ACO Generator Cross-Tie Permissive switch alignment on 50' Elevation.

VERIFY feeder faults NOT indicated by relay flags on:

3A0603 - 3A06 Bus Tie M.O. Cue: When asked, REPORT no feeder faults on breakers.

DIRECT the PPEO to SELECT both Unit 3 Train B Diesel ACO Generator Cross-Tie Permissive switches on Fire Isolation Panel 3L-413 to 50.54X.

3HS-5054XA2 and 3HS-5054XB2

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5, 6, and 7 Page 19 of 20 Event

Description:

Loss of Offsite Power / Four Stuck CEAs / 2G003 Failure Time Position Applicants Actions or Behavior M.O. Cue: When directed PERFORM remote functions EG62C and EG62D and REPORT that the Unit 3 50.54X switches have been aligned.

ACO VERIFY 3G003 Diesel Generator loading less than 3.4 MW.

ACO VERIFY Bus 2A06 NOT energized.

ACO VERIFY Unit 2 overcurrent/ground alarms reset.

63C15 SUPPLY BKR A0616 OC

63C25 SUPPLY BKR A0618 OC VERIFY 1E DC bus voltages 2D2 and 3D2 greater than ACO 108 VDC.

M.O. Cue: When asked, REPORT 3D2 voltage at 129 VDC.

ACO ESTABLISH final Train B configuration.

ACO ENSURE 1E 4kV Bus 2A06 supply breakers open.

2A0616 - Unit Aux Transformer

2A0618 - Reserve Aux Transformer

2A0613 - 2G003 EDG ACO ENSURE 1E 4kV Bus A06 tie breakers open.

2A0619 - 2A06 Bus Tie

3A0603 - 3A06 Bus Tie ACO ENSURE 1E 4kV Bus 2A06 load breakers open.

Emergency Chillers

Containment Spray Pumps

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5, 6, and 7 Page 20 of 20 Event

Description:

Loss of Offsite Power / Four Stuck CEAs / 2G003 Failure Time Position Applicants Actions or Behavior

HPSI Pumps

LPSI Pumps

AFW Pumps

CCW Pumps

SWC Pumps VERIFY Train B Diesel Generator Cross-Tie Permissive ACO switches on both units are in the 50.54X position.

(Total of 4 switches).

ACO CLOSE Unit 3 Bus Tie breaker 3A0603.

VERIFY Unit 3 Diesel Generator 3G003 output breaker remains ACO closed.

CRITICAL Restore power to at least one 1E 4kv Bus; CLOSE Unit 2 Bus ACO TASK Tie breaker 2A0619.

ACO VERIFY Unit 2 1E buses 2A06 and 2B06 energized.

ACO START CCW Pump P-026 on Train B.

CRITICAL Establish Reactivity Control (> 2 FLCEAs Not Fully Inserted &

CO TASK No SIAS)

START Charging Pump P-192 on Train B and COMMENCE CO boration at >40 gpm.

OPEN HV-9245 and HV-9240 Gravity Feed Valves.

+35 min

CLOSE LV-227B VCT Outlet Block Valve.

When power is restored to Bus 2A06 and emergency boration is started, or at Lead Evaluators discretion, TERMINATE the scenario.

ML063240484

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