ML12346A246

SO-2012-10-Final Operating Test

ML12346A246
Person / Time
Site:	San Onofre
Issue date:	11/01/2012
From:	Apger G Operations Branch IV
To:	Southern California Edison Co
laura hurley
References
50-361/12-010, 50-362/12-010
Download: ML12346A246 (290)

Text

Administrative Topics Outline Facility: SONGS Units 2 and 3 Date of Examination: 10/12/12 Examination Level RO Operating Test Number: NRC Administrative Topic Type Code* Describe Activity to be Performed (see Note) 2.1.25 Ability to interpret reference materials, such as Conduct of Operations graphs, curves, tables, etc. (3.9)

M, R (A1)

JPM: Determine Time to Boil (J213A).

2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, Conduct of Operations oxygen, and hydrogen). (3.4)

N, R (A2)

JPM: Perform Receiving Chemicals Independent Verification (New).

2.2.12 Knowledge of surveillance procedures. (3.7)

Equipment Control N, R (A3) JPM: Perform a Manual Water Inventory Balance (New).

Radiation Control - -

2.4.27 Knowledge of fire in the plant procedures.

Emergency Plan (3.4)

(A4) N, S JPM: Perform Local Area Evacuation actions (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 all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

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

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

SONGS NRC 2012 ES-301-1 RO Admin JPM Outline Rev c.docc

Administrative Topics Outline Task Summary A1 The applicant will use data provided to perform a Time to Boil calculation using SO23-5-1.8.1, Shutdown Nuclear Safety. This is a modified bank JPM.

A2 The applicant will use provided data to perform an independent chemical receiving calculation and determine if chemicals can be accepted under current conditions per SO23-4-4, Receiving and Storing Chemicals. This is a new JPM.

A3 The applicant will use provided data to manually calculate a water inventory balance per SO23-3-3.37, Reactor Coolant System Water Inventory Balance. This is a new JPM.

A4 The applicant will perform a Local Area Evacuation per SO23-13-1, Local Area Evacuation, due to a fire inside Containment. This JPM will be conducted in the simulator. This is a new JPM.

SONGS NRC 2012 ES-301-1 RO Admin JPM Outline Rev c.docc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM A-1 Task # 176136 K/A # G 2.1.25 3.9 / 4.2

Title:

Calculate RCS Time-To-Boil Margin Examinee (Print):

Testing Method:

Simulated Performance: Classroom: x Actual Performance: x Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions during a refueling outage on Unit 3:

• The Reactor was tripped 45 days ago.

• RCS level is 30 above the bottom of the hot leg.

• Core Exit Temperature (Thot) is 95ºF.

• Fuel is loaded into the core.

• There are 72 new fuel assemblies.

• No Time to Boil transmittal has been provided by Reactor Engineering.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Calculate RCS Time to Boil margin using SO23-5-1.8.1, Shutdown Nuclear Safety, Attachment 7, Calculation of RCS Time-To-Boil Margin/Boil-Off Rate.

• Document the Time to Boil margin on the Cue Sheet.

Task Standard: Calculated the RCS Time to Boil.

Required Materials: SO23-5-1.8.1, Shutdown Nuclear Safety, Attachment 7, Calculation of RCS Time-To-Boil Margin/Boil-Off Rate.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 5 SONGS NRC 2012 JPM A-1 Rev c.doc c

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of SO23-5-1.8.1, Shutdown Nuclear Safety, , Calculation of RCS Time-To-Boil Margin/Boil-Off Rate.

Page 2 of 5 SONGS NRC 2012 JPM A-1 Rev c.doc c

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Record the Time-to-Boil Margin (BMref) based on a reference Hot Leg 1.1 level of 26 inches from Table A. (If an outage specific Time-to-Boil Margin Data Transmittal has been prepared by Reactor Engineering (located in the Ops. Physics Summary book), then that Time-to-Boil Margin value should be used.

Standard: RECORDED 48.12 minutes (acceptable range 48.1 - 48.2)

Interpolation required for 45 days since Reactor trip.

(45.18 + 51.06) / 2 = 48.12 Comment: SAT UNSAT Perform Step: 2 Record the Level Correction Factor (Lcf) based on the level to which you 1.2 are draining from Table B.

Standard: RECORDED 1.031 from Table B, corresponding to a level of 30 above the bottom of the hot leg.

Comment: SAT UNSAT Perform Step: 3 Record the Temperature Correction Factor (Tcf) based on one of the 1.3, 1.3.1 following temperature correction equations:

For TE levels: Use: Tcf = (212 - THOT) / 92 Standard: RECORDED Tcf as 1.27 (acceptable range 1.270 - 1.272)

Tcf = (212 - 95) / 92 Tcf = 1.2717 Comment: SAT UNSAT Page 3 of 5 SONGS NRC 2012 JPM A-1 Rev c.doc c

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 Record the New Fuel Correction Factor (Ncf). Use the following decay 1.4, 1.4.2 heat correction factor which represents the reload Reactor Core status:

For New Fuel Assemblies (Not Irradiated) less than or greater than 108, Use:

Ncf = 217 Irradiated Assemblies 217 Irradiated Assemblies - # of New Assemblies Standard: RECORDED Ncf of 1.50 (acceptable range 1.49 - 1.50)

Ncf = 217 / (217 - 72)

Ncf = 1.4965 Comment: SAT UNSAT Perform Step: 5 Calculate the RCS Actual Time-To-Boil Margin (BMact) as follows:

BMact = (BMref) X (Lcf) X (Tcf) X (Ncf)

1.5 Standard

CALCULATED BMact of 94.51 minutes BMact = (48.12) x (1.031) x (1.2717) x (1.4965)

BMact = 94.416 minutes (acceptable range 93.8 - 94.8 minutes)

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 SONGS NRC 2012 JPM A-1 Rev c.doc c

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions during a refueling outage on Unit 3:

• The Reactor was tripped 45 days ago.

• RCS level is 30 above the bottom of the hot leg.

• Core Exit Temperature (Thot) is 95ºF.

• Fuel is loaded into the core.

• There are 72 new fuel assemblies.

• No Time to Boil transmittal has been provided by Reactor Engineering.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Calculate RCS Time to Boil margin using SO23-5-1.8.1, Shutdown Nuclear Safety, Attachment 7, Calculation of RCS Time-To-Boil Margin/Boil-Off Rate.

• Document the Time to Boil margin on the Cue Sheet.

Time to Boil margin: _______________

Page 5 of 5 SONGS NRC 2012 JPM A-1 Rev c.doc c

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM A-2 Task # 182119 K/A # G 2.1.26 3.4 / 3.6

Title:

Perform Receiving Chemicals Independent Verification Examinee (Print):

Testing Method:

Simulated Performance: Classroom: x Actual Performance: x Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions:

• A PEO is preparing to receive acid for Sulfuric Acid Storage Tank T-194.

• Current level in Tank T-194 is 56%.

• The driver has 54,000 pounds of Sulfuric Acid and wants to unload the entire volume into T-194.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Calculate an independent verification of final expected volume in Sulfuric Acid Storage Tank T-194 using SO23-4-4, Receiving and Storing Chemicals, Attachment 1, Receiving Acid for Sulfuric Acid Storage Tank T-194.

• Determine if T-194 can accept the full chemical offload.

• Document final expected volume in T-194 AND whether or not T-194 is ready to receive the full chemical offload on the Cue Sheet.

Task Standard: CALCULATED final expected volume of T-194 and DETERMINED that the full chemical offload cannot be accepted do the administrative limit of 90%.

Required Materials: SO23-4-4, Receiving and Storing Chemicals, Attachment 1, Receiving Acid for Sulfuric Acid Storage Tank T-194.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 5 SONGS NRC 2012 JPM A-2 Rev a.doc

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a blank copy and the PEOs marked up copy of SO23-4-4, Receiving and Storing Chemicals, Attachment 1, Receiving Acid for Sulfuric Acid Storage Tank T-194.

Page 2 of 5 SONGS NRC 2012 JPM A-2 Rev a.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 DETERMINE the weight of chemicals being delivered from the initial 1.3 conditions.

Standard: IDENTIFIED 54,000 lbs as the weight of chemicals being delivered (from the initial conditions).

Comment: SAT UNSAT Perform Step: 2 RECORD T-194 Initial Volume.

2.1 Standard

RECORDED T-194 Initial Volume as 56% (from initial conditions) and CONVERTED to 5600 gallons (100% = 10,000 gallons).

Comment: SAT UNSAT Perform Step: 3 RECORD quantity of Sulfuric Acid to be added.

2.1 Standard

CONVERTED 54,000 lbs to gallons and RECORDED 3529 gallons as the quantity to be added.

(acceptable range = 3529 - 3530 gallons)

Comment: SAT UNSAT Perform Step: 4 CALCULATE T-194 expected final volume.

2.1 Standard

CALCULATED a final volume of 9129 gallons and CONVERTED to 91.29% final volume and DOCUMENTED on the Cue Sheet.

(acceptable range = 9129 - 9130 gallons, 91 - 91.3%)

Comment: SAT UNSAT Page 3 of 5 SONGS NRC 2012 JPM A-2 Rev a.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 VERIFY tank expected volume is 90%.

2.1.1 Standard

DETERMINED tank expected volume is > 90%.

Comment: SAT UNSAT Perform Step: 6 To allow space for liquid expansion, tanks should not be filled > 90%.

L&S 3.2 Standard: DETERMINED that T-194 is NOT ready to receive chemicals and DOCUMENTED on the Cue Sheet.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 SONGS NRC 2012 JPM A-2 Rev a.doc

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions:

• A PEO is preparing to receive acid for Sulfuric Acid Storage Tank T-194.

• Current level in Tank T-194 is 56%.

• The driver has 54,000 pounds of Sulfuric Acid and wants to unload the entire volume into T-194.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Calculate an independent verification of final expected volume in Sulfuric Acid Storage Tank T-194 using SO23-4-4, Receiving and Storing Chemicals, Attachment 1, Receiving Acid for Sulfuric Acid Storage Tank T-194.

• Determine if T-194 can accept the full chemical offload.

• Document final expected volume in T-194 AND whether or not T-194 is ready to receive the full chemical offload on the Cue Sheet.

Final expected volume in T-194: __________

T-194 can receive the full chemical offload: Yes / No Page 5 of 5 SONGS NRC 2012 JPM A-2 Rev a.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM A-3 Task # 185300 K/A # G 2.2.12 3.7 / 4.1

Title:

Manual Water Inventory Balance Calculation Examinee (Print):

Testing Method:

Simulated Performance: Classroom: x Actual Performance: x Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions on Unit 2 at full power:

Initial Data Final Data Time 0200 0400 VCT Level 51.6% 48.1%

PZR Level 53.0% 52.7%

Tavg 577.0ºF 578.0ºF SIT-008 79.1% 79.1%

SIT-007 79.4% 79.4%

SIT-009 79.6% 80.0%

SIT-010 79.8% 79.8%

Quench Tank (QT) Level 77% 78%

• There is no known in-leakage to the RCS.

• RCS Pressure is 2250 psig.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Perform a manual leak rate calculation per SO23-3-3.37, Reactor Coolant System Water Inventory Balance, Attachment 2, Manual Leak Rate Calculation.

• Start at step 2.7.

• Stop after step 3.1 is completed.

• Independent verification has been suspended for the performance of this attachment.

• Document results on the Cue Sheet.

Task Standard: CALCULATED RCS leak rate.

Page 1 of 10 SONGS NRC 2012 JPM A-3 Rev c.docc

Appendix C JPM WORKSHEET Form ES-C-1 Required Materials: SO23-3-3.37, Reactor Coolant System Water Inventory Balance, Attachment 2, Manual Leak Rate Calculation.

Validation Time: 20 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 10 SONGS NRC 2012 JPM A-3 Rev c.docc

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of SO23-3-3.37, Reactor Coolant System Water Inventory Balance, Attachment 2, Manual Leak Rate Calculation.

INFORM applicant of typo on SO23-3-3.37, page 26, step 2.10.1. Refers to Table 4 but should say Table 3.

Page 3 of 10 SONGS NRC 2012 JPM A-3 Rev c.docc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Record all final data and perform calculations on Table 1.

2.7 Standard

RECORDED all final data and PERFORMED calculations on Table 1.

Comment: SAT UNSAT Perform Step: 2 Table 1 Calculation Independently Verified by:

2.8 Standard

MARKED step N/A (from initial conditions)

Comment: SAT UNSAT Examiner Note: From note at bottom of step 2.9.1:

A 1°F change in TAVG will change RCS volume as shown on Table 2.

With SDC in service, the volume change is multiplied 1.2 times the value obtained in Table 2. The final TAVG value is used to determine conversion value.

The volume change is multiplied by a factor of 1.01702 in order to account for the Replacement Steam Generator's (RSG's) slight increase to the RCS volume.

Perform Step: 3 Determine gal TAVG:

2.9.1 gal TAVG (From Table 1) (+) (-) ________ gal x 1.01702 for RSG's = (+) (-) ________ gal If SDC is in Service then Multiply by 1.2. (Multiply by 1 if SDC is Not in Service) = (+) (-) ________ gal Standard: DETERMINED gal TAVG = 92.51 gal from Table 1. (acceptable range 92.5 - 92.51 gal)

(92.51 gal x 1.01702) = 94.08 gal DETERMINED SDC not in service from initial conditions (unit operating at full power).

Comment: SAT UNSAT Page 4 of 10 SONGS NRC 2012 JPM A-3 Rev c.docc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 Add Volume Changes (Algebraic Sum):

2.9.2 gal VCT (From Table 1) (+) (-) _______ gal gal PZR (From Table 1) (+) (-) _______ gal gal TAVG (From Final Gallonage Step 2.9.1) (+) (-) _______ gal Subtotal = _______ gal Standard: CALCULATED subtotal of volume changes to be 244.7 gal.

gal VCT = 134.75 gal (acceptable range 134 - 135 gal) gal PZR = 15.87 gal (acceptable range 15.8 - 16.0 gal) gal Tavg = 94.08 gal (acceptable range 94.0 - 94.1 gal) 134.75 gal + 15.87 gal + 94.08 gal = 244.7 gal (acceptable range 243.8

- 245.1 gal)

Comment: SAT UNSAT Perform Step: 5 Calculate (divide):

2.9.3 Subtotal ________ gal Test Duration ÷ ________ min Calculated Total Leak Rate ________ gpm Calculate to the nearest hundredth (e.g., .01)

Identified In-leakage + ________ gpm TOTAL LEAK RATE = ________ gpm Standard: CALCULATED total leak rate of 2.04 gpm. (acceptable range 2.03 -

2.05 gpm)

Subtotal from step 2.9.2 was 244.7 gal.

Test duration was 120 minutes (from initial conditions).

Calculated total leak rate was 2.04 gpm.

No identified in-leakage (from initial conditions).

TOTAL LEAK RATE = 2.04 gpm.

Comment: SAT UNSAT Page 5 of 10 SONGS NRC 2012 JPM A-3 Rev c.docc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 6 Total Leak Rate Calculation Independently Verified by:

2.9.4 Standard

MARKED step N/A (from initial conditions)

Comment: SAT UNSAT Perform Step: 7 If Total Leak Rate, Step 2.9.3, is < 1 gpm, then Mark N/A 2.9.5 Sections 2.10 and 2.11, and Circle N/A for Identified Leak Rate and Unidentified Leak Rate in Step 3.1. (Mark N/A if Total Leak Rate > 1 gpm.)

Standard: DETERMINED leak rate to be > 1gpm, MARKED step 2.9.5 N/A and PROCEEDED to step 2.10.

Comment: SAT UNSAT Perform Step: 8 Using final and initial Tank level from Table 1 and conversion 2.10.1 values from Table 3, Calculate Quench Tank Volume Change.

Standard: CALCULATED Quench Tank volume change to be 22 gpm.

78% = 1876 gal 77% = 1854 gal 1876 gal - 1854 gal = 22 gal Comment: SAT UNSAT Page 6 of 10 SONGS NRC 2012 JPM A-3 Rev c.docc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 Add volume changes from Table 1 and Step 2.10.1:

2.10.2 T-008 ________ gal T-007 ________ gal T-009 ________ gal T-010 ________ gal Quench Tank ________ gal Subtotal ________ gal Standard: CALCULATED subtotal volume changes to be 82.12 gal. (acceptable range 82.0 - 82.2 gal)

SIT T-009 level increased 0.4% (60.12 gal).

Quench Tank volume change = 22 gal (from step 2.10.1).

60.12 gal + 22 gal = 82.12 gal Comment: SAT UNSAT Perform Step: 10 Calculate (divide):

2.10.3 Subtotal ________ gal

÷ Test Duration ________ min

=

IDENTIFIED LEAK RATE ________ gpm Standard: CALCULATED identified leak rate to be .684 gpm. (acceptable range

.68 - .69 gpm)

Subtotal = 82.12 gal (from step 2.10.2).

Test duration = 120 min (from initial conditions).

82.12 gal / 120 min = 0.684 gpm.

Comment: SAT UNSAT Page 7 of 10 SONGS NRC 2012 JPM A-3 Rev c.docc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 11 Identified Leak Rate Calculation Independently Verified by:

2.10.4 Standard: MARKED step N/A (from initial conditions)

Comment: SAT UNSAT Perform Step: 12 Determine difference between Total and Identified volume:

2.11.1 TOTAL LEAK RATE ________ gpm (Step 2.9.3)

IDENTIFIED LEAK RATE ________ gpm (Step 2.10.3)

=

UNIDENTIFIED LEAK RATE ________ gpm Standard: CALCUATED unidentified leak rate to be 1.356 gpm.

Total leak rate = 2.04 gpm. (acceptable range 2.03 - 2.05 gpm)

Identified leak rate = 0.684 gpm. (acceptable range .68 - .69 gpm)

Unidentified leak rate = 2.04 gpm - 0.684 gpm = 1.356 gpm.

(acceptable range 1.34 - 1.37 gpm)

Comment: SAT UNSAT Perform Step: 13 Unidentified Leak Rate Calculation Independently Verified by:

2.11.2 Standard: MARKED step N/A (from initial conditions)

Comment: SAT UNSAT Page 8 of 10 SONGS NRC 2012 JPM A-3 Rev c.docc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 14 Acceptance Criteria Result:

3.1 MEASUREMENT VALUE ACCEPTANCE RESULT CRITERIA Total Leak Rate 1 gpm YES / NO (TLR) Step 2.9.3 Unidentified Leak 1 gpm YES / NO Rate Step 2.11.1 Identified Leak 10 gpm YES / NO Rate Step 2.10.3 Standard: DETERMINED Total Leak Rate (2.04 gpm) and Unidentified Leak Rate (1.356 gpm) DID NOT satisfy the acceptance criteria. DETERMINED Identified Leak Rate (0.684 gpm) DID satisfy the acceptance criteria.

Comment: SAT UNSAT STOP TIME:

Page 9 of 10 SONGS NRC 2012 JPM A-3 Rev c.docc

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions on Unit 2 at full power:

Initial Data Final Data Time 0200 0400 VCT Level 51.6% 48.1%

PZR Level 53.0% 52.7%

Tavg 577.0ºF 578.0ºF SIT-008 79.1% 79.1%

SIT-007 79.4% 79.4%

SIT-009 79.6% 80.0%

SIT-010 79.8% 79.8%

Quench Tank (QT) 77% 78%

Level

• There is no known in-leakage to the RCS.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Perform a manual leak rate calculation per SO23-3-3.37, Reactor Coolant System Water Inventory Balance, Attachment 2, Manual Leak Rate Calculation.

• Start at step 2.7.

• Stop after step 3.1 is completed.

• Independent verification has been suspended for the performance of this attachment.

• Document results on the Cue Sheet.

Acceptance Criteria Result?

Total Leak Rate: _________________ YES / NO Unidentified Leak Rate: ___________ YES / NO Identified Leak Rate: ______________ YES / NO Page 10 of 10 SONGS NRC 2012 JPM A-3 Rev c.docc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM A-4 Task # 186728 K/A # G 2.4.27 3.4 / 3.9

Title:

Local Area Evacuation Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: x Simulator: x Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions on Unit 2 at full power:

• An at-power Containment Entry is in progress on Unit 2 for emergent repairs.

• One operator and two maintenance workers are inside Containment.

• The operator inside Containment has just radioed the Control Room and informed you that a small fire has started due to welding inside Containment.

• The CRS has entered SO23-13-21, Fire, and SO23-13-1, Local Area Evacuation.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Perform the actions of SO23-13-1, Local Area Evacuation, due to the fire inside the Unit 2 Containment.

Task Standard: MADE the local area evacuation PA announcement (at least two times) AND ACUATED the Containment Emergency Evacuation Siren.

Required Materials: SO23-13-1, Local Area Evacuation.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 5 SONGS NRC 2012 JPM A-4 Rev c.doc c

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP MACHINE OPERATOR:

INITIALIZE to IC- 219 EXAMINER:

PROVIDE the examinee with a copy of SO23-13-1, Local Area Evacuation.

Page 2 of 5 SONGS NRC 2012 JPM A-4 Rev c.doc c

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Make PA Announcement per Attachment 1.

1.a Standard: DIALED 429 on the phone, OR pressed CONTROL ROOM PAGE ALL, OR pressed CONTROL ROOM PAGE PA, and MADE the following announcement at least two times:

Attention all personnel. Due to a fire, a local evacuation of the Unit 2 Containment is required. All unnecessary personnel should evacuate the area immediately. All other personnel should remain clear of Unit 2 Containment until further notice.

Examiner Note: The bolded/italicized words are the fill in the blank portions of the PA Announcement sheet in Attachment 1. Words to this effect that accurately convey that there is a fire in Unit 2 Containment and that personnel should evacuate and remain clear of Unit 2 Containment, satisfy this step.

Comment: SAT UNSAT Perform Step: 2 Verify the Control Room is NOT receiving smoke or other airborne 1.b irritants from the outside.

Standard: RECOGNIZED the Control Room would not be receiving smoke from a fire in the Unit 2 Containment.

Comment: SAT UNSAT Perform Step: 3 Verify a Control Room evacuation is NOT required.

1.c Standard: RECOGNIZED that a Control Room evacuation is NOT required.

Comment: SAT UNSAT Page 3 of 5 SONGS NRC 2012 JPM A-4 Rev c.doc c

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 Verify Containment evacuation is NOT required.

1.d Standard: RECOGNIZED that a Containment evacuation IS required and PROCEEDED to the RNO actions.

Comment: SAT UNSAT Perform Step: 5 Actuate the CNTMT EMER EVAC SIREN (CR-57).

1.d RNO Standard: ACTUATED the Containment Emergency Evacuation Siren on CR-57.

Comment: SAT UNSAT Perform Step: 6 Verify the PA Announcement was heard locally AND onsite sirens are 1.e, 1e RNO NOT necessary based on the severity, location, and urgency of the event.

Examiner Cue: When called to verify PA Announcement was heard locally, No PA Announcement was heard.

Standard: DETERMINED the PA Announcement was NOT heard locally and ACTUATED one or both of the following sirens:

• SIREN LOCAL at the NCOs telephone speed dial sidecar

• EMERGENCY EVAC SIREN on CR-57.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 SONGS NRC 2012 JPM A-4 Rev c.doc c

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions on Unit 2 at full power:

• An at-power Containment Entry is in progress on Unit 2 for emergent repairs.

• One operator and two maintenance workers are inside Containment.

• The operator inside Containment has just radioed the Control Room and informed you that a small fire has started due to welding inside Containment.

• The CRS has entered SO23-13-21, Fire, and SO23-13-1, Local Area Evacuation.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Perform the actions of SO23-13-1, Local Area Evacuation, due to the fire inside the Unit 2 Containment.

Page 5 of 5 SONGS NRC 2012 JPM A-4 Rev c.doc c

ES-301 Administrative Topics Outline Form ES-301-1 Facility: SONGS Units 2 and 3 Date of Examination: 10/12/12 Examination Level SRO Operating Test Number: NRC Administrative Topic Type Code* Describe Activity to be Performed (see Note) 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (4.2)

Conduct of Operations M, R (A5)

JPM: Determine Time to Boil and Containment Closure Requirements (J213A).

2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity Conduct of Operations management (4.6).

M, R (A6)

JPM: Calculate Shutdown Margin (J280A).

2.2.40 Ability to apply Technical Specification for a system (4.7).

Equipment Control N, R (A7)

JPM: Determine Technical Specification Applicability (New).

2.3.4 Knowledge of radiation exposure limits under Radiation Control normal or emergency conditions (3.7).

M, R (A8)

JPM: Determine Stay Times (J219A).

2.4.41 Knowledge of the emergency action level Emergency Plan thresholds and classifications (4.6).

M, R (A9)

JPM: Classify an Emergency Plan Event (J274A).

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

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

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

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

Page 1 of 2 SONGS NRC 2012 ES-301-1 SRO Admin JPM Outline Rev c.doc

Administrative Topics Outline Task Summary A5 The applicant will use data provided to perform a Time to Boil calculation using SO23-5-1.8.1, Shutdown Nuclear Safety. This is a modified bank JPM.

A6 The applicant will use provided data to calculate shutdown margin per SO23 3.29, Determination of Reactor Shutdown Margin. This is a modified bank JPM.

A7 The applicant will determine applicable Technical Specification Conditions and Actions based on a provided timeline of events. This is a new JPM.

A8 The applicant will determine stay times for 5 maintenance workers given year to date doses and radiation levels in the work area per SO123-VII-20, Health Physics Program. This is a modified bank JPM.

A9 The applicant will classify an emergency plan event per SO23-VIII-1, Recognition and Classification of Emergencies, and make protective action recommendations per SO23-VIII-10.3, Protective Action Recommendations. This is a modified bank JPM.

Page 2 of 2 SONGS NRC 2012 ES-301-1 SRO Admin JPM Outline Rev c.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM A-5 Task # 176136 K/A # G 2.1.25 3.9 / 4.2

Title:

Calculation of RCS Time-To-Boil Margin Examinee (Print):

Testing Method:

Simulated Performance: Classroom: x Actual Performance: x Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions during a refueling outage on Unit 3:

• The Reactor was tripped 45 days ago.

• RCS level is 30 above the bottom of the hot leg.

• Core Exit Temperature (Thot) is 95°F.

• Fuel is loaded into the core.

• There are 72 new fuel assemblies.

• No Time to Boil transmittal has been provided by Reactor Engineering.

Initiating Cues: The Shift Manager directs you to PERFORM the following:

• Calculate RCS Time to Boil margin using SO23-5-1.8.1, Shutdown Nuclear Safety, Attachment 7, Calculation of RCS Time-To-Boil Margin/Boil-Off Rate.

• Document the Time to Boil Margin on the Cue Sheet.

Task Standard: Calculated the RCS Time to Boil Margin.

Required Materials: SO23-5-1.8.1, Shutdown Nuclear Safety, Attachment 7, Calculation of RCS Time-To-Boil Margin/Boil-Off Rate.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 5 SONGS NRC 2012 JPM A-5 Rev c.doc

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of SO23-5-1.8.1, Shutdown Nuclear Safety, , Calculation of RCS Time-To-Boil Margin/Boil-Off Rate.

Page 2 of 5 SONGS NRC 2012 JPM A-5 Rev c.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Record the Time-to-Boil Margin (BMref) based on a reference Hot Leg 1.1 level of 26 inches from Table A. (If an outage specific Time-to-Boil Margin Data Transmittal has been prepared by Reactor Engineering (located in the Ops. Physics Summary book), then that Time-to-Boil Margin value should be used.

Standard: RECORDED 48.12 minutes. Interpolation required for 45 days since Reactor trip.

(45.18 + 51.06) / 2 = 48.12 (acceptable range 48.1 - 48.2 minutes)

Comment: SAT UNSAT Perform Step: 2 Record the Level Correction Factor (Lcf) based on the level to which you 1.2 are draining from Table B.

Standard: RECORDED 1.031 from Table B, corresponding to a level of 30 above the bottom of the hot leg.

Comment: SAT UNSAT Perform Step: 3 Record the Temperature Correction Factor (Tcf) based on one of the 1.3, 1.3.1 following temperature correction equations:

For TE levels: Use: Tcf = (212 - THOT) / 92 Standard: RECORDED Tcf as 1.272 (acceptable range 1.270 - 1.272)

Tcf = (212 - 95) / 92 Tcf = 1.2717 Comment: SAT UNSAT Page 3 of 5 SONGS NRC 2012 JPM A-5 Rev c.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 Record the New Fuel Correction Factor (Ncf). Use the following decay 1.4, 1.4.2 heat correction factor which represents the reload Reactor Core status:

For New Fuel Assemblies (Not Irradiated) less than or greater than 108, Use:

Ncf = 217 Irradiated Assemblies 217 Irradiated Assemblies - # of New Assemblies Standard: RECORDED Ncf of 1.50 (acceptable range 1.49 - 1.50)

Ncf = 217 / (217 - 72)

Ncf = 1.4965 Comment: SAT UNSAT Perform Step: 5 Calculate the RCS Actual Time-To-Boil Margin (BMact) as follows:

BMact = (BMref) X (Lcf) X (Tcf) X (Ncf)

1.5 Standard

CALCULATED BMact of 94.51 minutes BMact = (48.12) x (1.031) x (1.2717) x (1.4965)

BMact = 94.416 minutes (acceptable range 93.8 - 94.8 minutes)

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 SONGS NRC 2012 JPM A-5 Rev c.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions during a refueling outage on Unit 3:

• The Reactor was tripped 45 days ago.

• RCS level is 30 above the bottom of the hot leg.

• Core Exit Temperature (Thot) is 95°F.

• Fuel is loaded into the core.

• There are 72 new fuel assemblies.

• No Time to Boil transmittal has been provided by Reactor Engineering.

INITIATING CUES: The Shift Manager directs you to PERFORM the following:

• Calculate RCS Time to Boil margin using SO23-5-1.8.1, Shutdown Nuclear Safety, Attachment 7, Calculation of RCS Time-To-Boil Margin/Boil-Off Rate.

• Document the Time to Boil Margin on the Cue Sheet.

Time to Boil Margin: __________

Page 5 of 5 SONGS NRC 2012 JPM A-5 Rev c.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC A-6 Task # 188318 K/A # G 2.1.37 4.3 / 4.6

Title:

Calculate Shutdown Margin With a Withdrawn CEA Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 2 is in MODE 3 following a Reactor trip from 100% power 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> ago.

• The Unit was at full power for 90 EFPD prior to the trip per Reactor Engineering.

• RCS Boron Concentration is 2600 ppm per Chemistry sample at 0700 today.

• Tave is 545ºF.

• All CEAs are fully inserted except for CEA #52 which is trippable but fully withdrawn.

• No correction factors for B-10 depletion have been provided.

• Use OPS Table 4.4 for CEA Worths.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• CALCULATE Shutdown Margin, Percent Shutdown of the Reactor, and Projected Shutdown Margin (for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> later) using SONGS Unit 2 Cycle 17 BOC Operations Physics Summary Data (Revision 61), and SO23-3-3.29, Determination of Reactor Shutdown Margin and DOCUMENT on the Cue Sheet.

• DETERMINE acceptance criteria and DOCUMENT on the Cue Sheet.

• Start at Step 2.1.

Task Standard: CALCULATE Shutdown Margin with one (1) stuck CEA per SO23-3-3.29, Determination of Reactor Shutdown Margin.

Required Materials: SO23-3-3.29, Determination of Reactor Shutdown Margin, Determination of Reactor Shutdown Margin, AND M38100, Operations Physics Summary, Unit 2, Cycle 17, BOC, Rev. 61.

Page 1 of 10 SONGS NRC 2012 JPM A-6 Rev d

Appendix C JPM WORKSHEET Form ES-C-1 Validation Time: 20 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 10 SONGS NRC 2012 JPM A-6 Rev d

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of Handout:

• SO23-3-3.29, Determination of Reactor Shutdown Margin, Attachment 2, Calculation of Actual Shutdown Margin - MODES 3-6.

• INITIAL Steps 1.1, 1.2, 1.3, & 1.4.

• CHECK Boxes in Steps 1.2 (Actual and 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> projected SDM), & 1.3 (All CEAs are OPERABLE).

• MARK N/A Step 2.6.3.

• M-38100, Operations Physics Summary, Unit 2, Cycle 17, BOC, Rev. 61.

Page 3 of 10 SONGS NRC 2012 JPM A-6 Rev d

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Record present RCS Boron concentration and indicate Source.

2.1.1 Standard

RECORDED present RCS boron concentration of 2600 ppm and CHECKED Chemical Analysis as the source of information.

Comment: SAT UNSAT Perform Step: 2 Record present RCS average temperature.

2.1.2 Standard

RECORDED RCS TAVG of 545ºF.

Comment: SAT UNSAT Perform Step: 3 Record present cycle burnup and indicate source:

2.1.3 Standard

RECORDED present cycle burnup of 90 EFPD and CHECKED Reactor Engineering as the source of information.

Comment: SAT UNSAT Perform Step: 4 Calculate adjusted CBC for potential Reactivity Bias/Boron-10 depletion, 2.2.1 as follows: (Use 150 ppm as the correction factor for Boron-10 depletion or a correction factor provided by Reactor Engineering.)

Standard: CALCULATED the adjusted Critical Boron Concentration from OPS Fig.

2.2-1 and ADDED 150 ppm for B-10 depletion for a total of 2050 ppm.

(acceptable range is 2050 - 2075 ppm)

Comment: SAT UNSAT Perform Step: 5 Calculate the critical Boron margin.

2.3 Standard

CALCULATED the Critical Boron Margin to be 550 ppm.

(acceptable range is 525 - 550 ppm)

Comment: SAT UNSAT Page 4 of 10 SONGS NRC 2012 JPM A-6 Rev d

Appendix C JPM STEPS Form ES-C-1 Perform Step: 6 Determine the inverse Boron worth for the present RCS Tavg and Boron 2.4 concentration using OPS Figure 3.3 Standard: DETERMINE Inverse Boron Worth from OPS Figure 3.3 to be 144.5 ppm/%K/K and CHECKED OPS Figure 3.3 as the data source.

(acceptable range is 144.0 - 145.0 ppm/%K/K)

Comment: SAT UNSAT Perform Step: 7 Calculate the Boron reactivity defect.

2.5 Standard

CALCULATE the Boron Reactivity Defect of + 3.806 %K/K.

(acceptable range is 3.620 - 3.819 %K/K)

Comment: SAT UNSAT Perform Step: 8 Determine Total CEA Worth from OPS Table 4.4.

2.6.1 Standard

DETERMINED Total CEA Worth from OPS Table 4.4 to be 8.289

%K/K and CHECKED OPS Table 4.4 as the data source.

Comment: SAT UNSAT Perform Step: 9 Determine Net CEA Worth from OPS Table 4.4.

2.6.2 Standard

DETERMINED Net CEA Worth from OPS Table 4.4 to be 7.820 %K/K and CHECKED OPS Table 4.4 as the data source.

Comment: SAT UNSAT Page 5 of 10 SONGS NRC 2012 JPM A-6 Rev d

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Step 2.6.3 marked N/A per step 1.3.

Perform Step: 10 Determine withdrawn CEA worth.

2.7 Standard

DETERMINED withdrawn CEA worth to be 0.469 %K/K from OPS Table 4.4 Stuck Worth value (per Guideline # 2) and CHECKED OPS Table 4.4 as the data source.

Comment: SAT UNSAT Perform Step: 11 Determine elapsed time since trip or start of power descension.

2.8.1 Standard

DETERMINED time since trip to be 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> (from initial conditions).

Comment: SAT UNSAT Perform Step: 12 Determine Reactor power level prior to trip.

2.8.2 Standard

DETERMINED Reactor power level prior to trip to be 100% (from initial conditions).

Comment: SAT UNSAT Page 6 of 10 SONGS NRC 2012 JPM A-6 Rev d

Appendix C JPM STEPS Form ES-C-1 Perform Step: 13 Determine present Xenon worth.

2.8.3 Standard

DETERMINED present Xenon worth to be 0.428 %K/K and CHECKED OPS Table 7.1 as the source of information.

Comment: SAT UNSAT Perform Step: 14 Xenon worth 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> later than step 2.8.1.

2.8.4.1 Standard: DETERMINED Xenon worth 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> later than step 2.8.1 to be 0.326

%K/K.

Comment: SAT UNSAT Perform Step: 15 Change in Xenon worth in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

2.8.4.2 Standard: DETERMINED the change in Xenon worth 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> later to be 0.102

%K/K. (0.428 - 0.326 = .0102)

Comment: SAT UNSAT Page 7 of 10 SONGS NRC 2012 JPM A-6 Rev d

Appendix C JPM STEPS Form ES-C-1 Perform Step: 16 Calculate Shutdown Margin.

2.9 Standard

CALCULATED Shutdown Margin of 12.054 %K/K (acceptable range is 11.868 - 12.067 %K/K)

Comment: SAT UNSAT Perform Step: 17 Calculate percent shutdown of the Reactor.

2.10 Standard: CALCULATED percent shutdown of the Reactor to be 12.054 %K/K.

(acceptable range is 11.868 - 12.067 %K/K)

Comment: SAT UNSAT Page 8 of 10 SONGS NRC 2012 JPM A-6 Rev d

Appendix C JPM STEPS Form ES-C-1 Perform Step: 18 IF credit was taken for Xenon in the SDM calculation, THEN calculate 2.11 the projected SDM for the time of the next SDM verification (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> later).

Standard: CALCULATED projected SDM to be 11.952 %K/K.

(acceptable range is 11.766 - 11.965 %K/K)

Comment: SAT UNSAT Perform Step: 19 ACCEPTANCE CRITERIA 3.1 SDM calculation for ACTUAL Shutdown Margin is:

• MODE 3

• SDM >5.15%K/K

• SHUTDOWN MARGIN SATISFIED YES / NO Standard: DETERMINE the Actual Shutdown Margin is greater than 5.15% K/K for MODE 3 and CIRCLE YES.

Comment: SAT UNSAT Perform Step: 20 Mark N/A if SDM is satisfied.

3.1.1 Standard

MARKED N/A on step 3.1.1.

Comment: SAT UNSAT Perform Step: 21 ACCEPTANCE CRITERIA 3.2 SDM calculation for PROJECTED Shutdown Margin is:

• MODE 3

• SDM >5.15%K/K

• SHUTDOWN MARGIN SATISFIED YES / NO Standard: DETERMINE the Projected Shutdown Margin is greater than 5.15%

K/K for MODE 3 and CIRCLE YES.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 9 of 10 SONGS NRC 2012 JPM A-6 Rev d

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Unit 2 is in MODE 3 following a Reactor trip from 100% power 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> ago.

• The Unit was at full power for 90 EFPD prior to the trip per Reactor Engineering.

• RCS Boron Concentration is 2600 ppm per Chemistry sample at 0700 today.

• Tave is 545ºF.

• All CEAs are fully inserted except for CEA #52 which is trippable but fully withdrawn.

• No correction factors for B-10 depletion have been provided.

• Use OPS Table 4.4 for CEA Worths.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• CALCULATE Shutdown Margin, Percent Shutdown of the Reactor, and Projected Shutdown Margin (for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> later) using SONGS Unit 2 Cycle 17 BOC Operations Physics Summary Data (Revision 61),

and SO23-3-3.29, Determination of Reactor Shutdown Margin and DOCUMENT on the Cue Sheet.

• DETERMINE acceptance criteria and DOCUMENT on the Cue Sheet.

• Start at Step 2.1.

Shutdown Margin: _______________

Percent Shutdown of the Reactor: _______________

Projected Shutdown Margin (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> later): _______________

Shutdown Margin Acceptance Criteria Satisfied: Yes / No Projected Shutdown Margin Acceptance Criteria Satisfied: Yes / No Page 10 of 10 SONGS NRC 2012 JPM A-6 Rev d

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM A-7 Task # 189963 K/A # G 2.2.40 3.4 / 4.7

Title:

Technical Specification Determination Examinee (Print):

Testing Method:

Simulated Performance: Classroom: x Actual Performance: x Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Unit 2 is in Mode 1 at 100% power. The following events have occurred over the past 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

• At 0400, Train A EDG 2G002 was declared inoperable.

• At 1100, Train B AFW Pump P-504 was declared inoperable.

• At 1900, Train B EDG 2G003 was declared inoperable.

• At 2000, Train A EDG 2G002 was returned to operable status.

• At 2200, Train B AFW Pump P-504 was returned to operable status.

• At 2300, Train B EDG 2G003 was returned to operable status.

Initiating Cue: Based on the provided information, identify all required Technical Specification LCO Conditions and entry and exit times and document on the Cue Sheet.

Task Standard: IDENTIFIED all required Technical Specification LCO Conditions and entry and exit times and DOCUMENTED on the Cue Sheet.

Required Materials: SONGS Unit 2 Technical Specifications.

Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 5 SONGS NRC 2012 JPM A-7 Rev b.doc

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of SONGS Unit 2 Technical Specifications.

Page 2 of 5 SONGS NRC 2012 JPM A-7 Rev b.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 IDENTIFY LCO entry for Train A EDG 2G002 being declared inoperable at time 0400.

Standard: DOCUMENTED entry into LCO 3.8.1 Condition B, one required EDG inoperable, at time 0400.

Comment: SAT UNSAT Perform Step: 2 IDENTIFY LCO entry for Train B Motor Driven AFW Pump P-504 at time 1100.

Standard: DOCUMENTED entry into LCO 3.7.5 Condition B, one train of AFW inoperable for reasons other than inoperable steam supply to Turbine Driven AFW Pump P-140, at time 1100.

Comment: SAT UNSAT Perform Step: 3 IDENTIFY LCO entry for Train A Motor Driven AFW Pump P-141 at time 1500.

Standard: DOCUMENTED entry into LCO 3.7.5 Condition C, two AFW trains with two motor driven pumps inoperable in MODES 1, 2, or 3, at time 1500.

Examiner Note: Per LCO 3.8.1 Condition B Action B.2, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after an EDG is declared inoperable, any required features supported the inoperable EDG are declared inoperable when its redundant required feature is inoperable. The four hour clock started for AFW Pump P-141 at 1100 when AFW Pump P-504 was declared inoperable.

Comment: SAT UNSAT Perform Step: 4 IDENTIFY LCO entry for Train B EDG 2G003 at time 1900.

Standard: DOCUMENTED entry into LCO 3.8.1 Condition E, two required EDGs inoperable, at time 1900.

Comment: SAT UNSAT Page 3 of 5 SONGS NRC 2012 JPM A-7 Rev b.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 IDENTIFY LCO 3.8.1 Condition E and LCO 3.7.5 Condition C exit conditions met due to Train A EDG 2G002 being declared OPERABLE at time 2000.

Standard: DOCUMENTED exit from LCO 3.8.1 Condition E and LCO 3.7.5 Condition C at time 2000.

Comment: SAT UNSAT Perform Step: 6 IDENTIFY LCO 3.7.5 Condition B exit conditions met due to AFW Pump P-504 being declared OPERABLE at time 2200.

Standard: DOCUMENTED exit from LCO 3.7.5 Condition B at time 2200.

Comment: SAT UNSAT Perform Step: 7 IDENTIFY LCO 3.8.1 Condition B exit conditions met due to Train B EDG 2G003 being declared OPERABLE at time 2300.

Standard: DOCUMENTED exit from LCO 3.8.1 Condition B at time 2300.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 SONGS NRC 2012 JPM A-7 Rev b.doc

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Unit 2 is in Mode 1 at 100% power. The following events have occurred over the past 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

• At 0400, Train A EDG 2G002 was declared inoperable.

• At 1100, Train B AFW Pump P-504 was declared inoperable.

• At 1900, Train B EDG 2G003 was declared inoperable.

• At 2000, Train A EDG 2G002 was returned to operable status.

• At 2200, Train B AFW Pump P-504 was returned to operable status.

• At 2300, Train B EDG 2G003 was returned to operable status.

Initiating Cue: Based on the provided information, identify all required Technical Specification LCO Conditions and entry and exit times in the table below.

Answer Sheet:

LCO Condition Time Entered Time Exited Page 5 of 5 SONGS NRC 2012 JPM A-7 Rev b.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM A-8 Task # 193003 K/A # G 2.3.4 3.2 / 3.7

Title:

Determine Stay Times Examinee (Print):

Testing Method:

Simulated Performance: Classroom: x Actual Performance: x Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Maintenance is required in a high radiation area. The work is expected to take 2 - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Expected dose rate (TEDE) is 300 mrem/hr. The maintenance workers have the following doses (TEDE) year to date:

• Worker #1: Adult contractor with 500 mrem at SONGS, 600 mrem off-site.

• Worker #2: Adult contractor with 200 mrem at SONGS, 1100 mrem off-site.

• Worker #3: 17-year old contractor with no dose year to date.

• Worker #4: Adult SONGS employee with 100 mrem.

• Worker #5: Adult pregnant SONGS employee with no dose year to date.

Initiating Cue: The Shift Manager directs you to:

• Determine stay times for the 5 maintenance workers to prevent exceeding each of their Administrative Dose Control limits per SO123-VII-20, Health Physics Program.

• Document stay times on the Cue Sheet.

Task Standard: DETERMINED stay times of the 5 workers and DOCUMENTED on Cue Sheet.

Required Materials: SO123-VII-20, Health Physics Program.

Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 5 SONGS NRC 2012 JPM A-8 Rev b.doc

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of SO123-VII-20, Health Physics Program.

Page 2 of 5 SONGS NRC 2012 JPM A-8 Rev b.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 DETERMINE Worker #1 stay time.

Standard: DETERMINED Worker #1 stay time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 40 minutes.

SONGS limit = 1 rem, 500 mrem / 300 mrem/hr = 1.67 hrs (100 min).

Comment: SAT UNSAT Perform Step: 2 DETERMINE Worker #2 stay time.

Standard: DETERMINED Worker #2 stay time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 20 minutes.

Combined SONGS and off-site limit = 2 rem, 700 mrem / 300 mrem/hr =

2.33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> (140 min).

Comment: SAT UNSAT Perform Step: 3 DETERMINE Worker #3 stay time.

Standard: DETERMINED Worker #3 stay time of 20 minutes.

SONGS limit for minors = 100 mrem, 100 mrem / 300 mrem/hr = 0.33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> (20 min).

Comment: SAT UNSAT Perform Step: 4 DETERMINE Worker #4 stay time.

Standard: DETERMINED Worker #4 stay time of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

SONGS limit = 1 rem, 900 mrem / 300 mrem/hr = 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (180 min).

Comment: SAT UNSAT Page 3 of 5 SONGS NRC 2012 JPM A-8 Rev b.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 DETERMINE Worker #5 stay time.

Standard: DETERMINED Worker #5 stay time of 10 minutes.

SONGS limit for unborn child = 50 mrem / month, 50 mrem / 300 mrem/hr = 0.17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> (10 min).

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 SONGS NRC 2012 JPM A-8 Rev b.doc

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Maintenance is required in a high radiation area. The work is expected to take 2 - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Expected dose rate (TEDE) is 300 mrem/hr. The maintenance workers have the following doses (TEDE) year to date:

• Worker #1: Adult contractor with 500 mrem at SONGS, 600 mrem off-site.

• Worker #2: Adult contractor with 200 mrem at SONGS, 1100 mrem off-site.

• Worker #3: 17-year old contractor with no dose year to date.

• Worker #4: Adult SONGS employee with 100 mrem.

• Worker #5: Adult pregnant SONGS employee with no dose year to date.

Initiating Cue: The Shift Manager directs you to:

• Determine stay times for the 5 maintenance workers to prevent exceeding each of their Administrative Dose Control limits per SO123-VII-20, Health Physics Program.

• Document stay times on the Cue Sheet.

Stay Times:

Worker #1: ____________________

Worker #2: ____________________

Worker #3: ____________________

Worker #4: ____________________

Worker #5: ____________________

Page 5 of 5 SONGS NRC 2012 JPM A-8 Rev b.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM A-9 Task # 189860 K/A # G 2.4.41 2.9 / 4.6

Title:

Classify an Emergency Plan Event and Determine Protective Actions Examinee (Print):

Testing Method:

Simulated Performance: Classroom: x Actual Performance: x Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions:

• Both Units have tripped from 100% Reactor power due to a loss of the grid stemming from wildfires throughout Southern California.

• Unit 2 Train A EDG 2G002 is disabled for Boundary of the Week activities.

Expected time to restore 2G002 to service is 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

• Unit 2 Train B 1E 4kV bus 2A06 has tripped on overcurrent. Expected time to restore to service is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

• Unit 3 Train A EDG has experienced a mechanical fault and will not start.

Expected time to restore to operation is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• Unit 3 Train B EDG is running, however EDG Output Breaker is mechanically bound and will not close. Expected time to replace breaker is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

• The GOC reports that offsite power will not be available to the switchyard for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

• REPCET on Unit 2 is 705°F and stable.

• REPCET on Unit 3 is 560°F and stable.

• Wind direction obtained from RADDOSE-V is from the West (240°) at 5 mph.

• Interstate 5 and Camp Pendleton are both closed to traffic due to the wildfires.

Initiating Cue: The Shift Manager directs you to:

• Identify the EAL classification for EACH UNIT, per SO123-VIII-1, Recognition and Classification of Emergencies and document on the Cue Sheet.

• Determine the Protective Actions for THE SITE per SO123-VIII-10.3, Protective Action Recommendations and document on the Cue Sheet.

Task Standard: Classified the event per SO123-VIII-1, Recognition and Classification of Emergencies and determined the protective actions per SO123-VIII-10.3, Protective Action Recommendations.

Page 1 of 9 SONGS NRC 2012 JPM A-9 Rev d.docd

Appendix C JPM WORKSHEET Form ES-C-1 Required Materials: SO123-VIII-1, Recognition and Classification of Emergencies and SO123-VIII-10.3, Protective Action Recommendations.

Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 9 SONGS NRC 2012 JPM A-9 Rev d.docd

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

• SO123-VIII-1, Recognition and Classification of Emergencies

• EP(123) 1, Emergency Classification And Event Code Chart

• SONGS EPSD-1, Emergency Action Level Technical Bases

• SO123-VIII-10.3, Protective Action Recommendations Page 3 of 9 SONGS NRC 2012 JPM A-9 Rev d.docd

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from SO123-VIII-1, Recognition and Classification of Emergencies for Unit 2.

Perform Step: 1 CLASSIFY Emergency by Event Code:

2.a.1 IDENTIFY Event Code using Attachment 1, EVENT CODES / MODE APPLICABILITY and Attachment 2, RECOGNITION CATEGORIES.

REVIEW applicable Recognition Categories and subcategories.

Standard: IDENTIFIED Recognition Category S (System Malfunction).

Examiner Note: NOTE: EP(123) 1, EMERGENCY CLASSIFICATION AND EVENT CODE CHART, may also be used for classifying events.

NOTE: SONGS EPSD-1, EMERGENCY ACTION LEVEL TECHNICAL BASES, may be referenced for detailed EAL technical information.

Comment: SAT UNSAT Perform Step: 2 REVIEW applicable Emergency Action Levels.

2.a.2 Standard: IDENTIFIED Emergency Action Level G (General Emergency).

Comment: SAT UNSAT Perform Step: 3 CLASSIFY emergency using highest applicable Event Code based on Emergency Class.

2.a.3 Standard: IDENTIFIED Event Code 1.1 (Event Classification is SG1.1 for Unit 2)

Comment: SAT UNSAT Page 4 of 9 SONGS NRC 2012 JPM A-9 Rev d.docd

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following steps are from SO123-VIII-1, Recognition and Classification of Emergencies for Unit 3.

Perform Step: 4 CLASSIFY Emergency by Event Code:

2.a.1 IDENTIFY Event Code using Attachment 1, EVENT CODES / MODE APPLICABILITY and Attachment 2, RECOGNITION CATEGORIES.

REVIEW applicable Recognition Categories and subcategories.

Standard: IDENTIFIED Recognition Category S (System Malfunction).

Examiner Note: NOTE: EP(123) 1, EMERGENCY CLASSIFICATION AND EVENT CODE CHART, may also be used for classifying events.

NOTE: SONGS EPSD-1, EMERGENCY ACTION LEVEL TECHNICAL BASES, may be referenced for detailed EAL technical information.

Comment: SAT UNSAT Perform Step: 5 REVIEW applicable Emergency Action Levels.

2.a.2 Standard: IDENTIFIED Emergency Action Level S (Site Area Emergency).

Comment: SAT UNSAT Perform Step: 6 CLASSIFY emergency using highest applicable Event Code based on Emergency Class.

2.a.3 Standard: IDENTIFIED Event Code 1.1 (Event Classification is SS1.1 for Unit 3)

Comment: SAT UNSAT Page 5 of 9 SONGS NRC 2012 JPM A-9 Rev d.docd

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following table is from SO123-VIII-10.3, Protective Action Recommendations:

Perform Step: 7 If a GE classification exists, then Determine affected downwind PAZs by referring to the following table:

2.1 Standard

DETERMINED PAZ 1 and 3 to the be the affected downwind PAZs Comment: SAT UNSAT Page 6 of 9 SONGS NRC 2012 JPM A-9 Rev d.docd

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following table is from SO123-VIII-10.3, Protective Action Recommendations:

Perform Step: 8 Identify the Protective Action.

GE PAR Table Standard: IDENTIFIED Evacuate State Beach within PAZ 1 immediately adjacent to SONGS. Shelter PAZ 1 and affected downwind PAZ(s). If wind is toward PAZ 2, then evacuate that zone. Ingest KI for the public in affected PAZs.(Applies to PAZs 1, 2, 3, or 4 only) as the correct Protective Action.

Comment: SAT UNSAT Page 7 of 9 SONGS NRC 2012 JPM A-9 Rev d.docd

Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 Identify the Protective Action.

Standard: IDENTIFIED the correct Protective Action using data from Perform Steps 6 and 7 as follows:

Evacuate State Beach within PAZ 1 immediately adjacent to SONGS. Shelter PAZ 1 and 3. Ingest KI for the public in PAZs 1 and 3.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 8 of 9 SONGS NRC 2012 JPM A-9 Rev d.docd

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions:

• Both Units have tripped from 100% Reactor power due to a loss of the grid stemming from wildfires throughout Southern California.

• Unit 2 Train A EDG 2G002 is disabled for Boundary of the Week activities. Expected time to restore 2G002 to service is 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

• Unit 2 Train B 1E 4kV bus 2A06 has tripped on overcurrent.

Expected time to restore to service is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

• Unit 3 Train A EDG has experienced a mechanical fault and will not start. Expected time to restore to operation is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• Unit 3 Train B EDG is running, however EDG Output Breaker is mechanically bound and will not close. Expected time to replace breaker is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

• The GOC reports that offsite power will not be available to the switchyard for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

• REPCET on Unit 2 is 705°F and stable.

• REPCET on Unit 3 is 560°F and stable.

• Wind direction obtained from RADDOSE-V is from the West (240°) at 5 mph.

• Interstate 5 and Camp Pendleton are both closed to traffic due to the wildfires.

Initiating Cue: The Shift Manager directs you to:

• Identify the EAL classification for EACH UNIT, per SO123-VIII-1, Recognition and Classification of Emergencies and document on the Cue Sheet.

• Determine the Protective Actions for THE SITE per SO123-VIII-10.3, Protective Action Recommendations and document on the Cue Sheet.

Event Classification for Unit 2: ______________

Event Classification for Unit 3: ______________

Protective Actions:

Page 9 of 9 SONGS NRC 2012 JPM A-9 Rev d.docd

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 Facility: SONGS Units 2 and 3 Date of Examination: 10/12/12 Exam Level: 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)

System / JPM Title Type Code* Safety Function S-1 004 - Chemical and Volume Control System (J079S) A, M, S 1 Perform a blended makeup to the VCT S-2 011 - Pressurizer Level Control System (New) N, S 2 Transfer in-service letdown flow controllers S-3 005 - Residual Heat Removal System (New) L, N, S 4P Transfer from parallel to single LPSI Pump operation (Shutdown Cooling)

S-4 045 - Main Turbine Generator System (New) A, N, S 4S Synch the Main Turbine to the grid and apply block load S-5 103 - Containment System (New) A, EN, N, S 5 Verify a Containment Isolation Actuation Signal S-6 062 - AC Electrical Distribution System (J007S) A, M, S 6 Transfer 6.9kV bus 2A01 from UAT to RAT S-7 073 - Process Radiation Monitoring System (J290S) D, S 7 (RO) Change Radiation Monitor setpoints during small S/G tube leak S-8 010 - Pressurizer Pressure Control System (New) A, N, S 3 Respond to a Failed Pressurizer Pressure Transmitter (Manual pressure control required)

In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P-1 039 - Main and Reheat Steam System (J038) D, E 4S Manually open an Atmospheric Dump Valve P-2 064 - Emergency Diesel Generators (J016F1) A, D, E 6 Locally start Emergency Diesel Generator P-3 001 - Control Rod Drive System (J020) D, R, E 1 Place CEA subgroup on the hold bus 1 of 3 SONGS NRC 2012 ES-301-2 RO & SRO JPM Outline Rev e.doce

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 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow Power / Shutdown 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 NRC JPM Examination Summary Description S-1 The applicant will perform a blended makeup to the VCT per SO23-3-2.2, Makeup Operations. When the blend is commenced, the running Boric Acid Makeup Pump will trip on overcurrent requiring the applicant to terminate the blended makeup. This is a modified JPM under the Chemical and Volume Control System - Reactivity Control Safety Function.

S-2 The applicant will place the standby Letdown Flow Control Valve controller in service and remove the in-service Letdown Flow Control Valve from service per SO23-3-2.1, CVCS Operations. This is a new JPM under the Pressurizer Level Control System - Reactor Coolant System Inventory Control Safety Function.

S-3 The applicant will transfer from parallel to single LPSI pump operation while on Shutdown Cooling. This is a new JPM under the Residual Heat Removal System - Primary System Heat Removal From Reactor Core Safety Function.

S-4 The applicant will raise Main Generator load per SO23-5-1.7, Power Operations. The alternate path occurs when high Turbine vibrations require the Reactor to be immediately tripped. This is a new JPM under the Main Turbine Generator System - Secondary System Heat Removal From Reactor Core Safety Function.

S-5 The applicant will verify a Containment Isolation Actuation Signal per SO23-3-2.22, ESFAS Operation. The alternate path occurs when expected valve positions are not obtained due to a failed K-relay. This is a new JPM under the Containment System -

Containment Integrity Safety Function.

2 of 3 SONGS NRC 2012 ES-301-2 RO & SRO JPM Outline Rev e.doce

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 S-6 The applicant will transfer 6.9kV bus 2A01 from the Unit Auxiliary Transformer to the Reserve Auxiliary Transformer per SO23-6-1, Transferring 6.9kv Buses, in preparation for breaker maintenance. The alternate path occurs following the transfer when the supply breaker to bus 2A01 trips on overcurrent. The Reactor will fail to automatically trip on RCS Low Flow and the applicant will have to manually trip the Reactor. This is a modified JPM under the AC Electrical Distribution System - Electrical Safety Function.

S-7 The applicant will reset RE-7870, Condenser Air Ejector Wide Range Gas Monitor, Hi and HI-HI setpoints during a small SGTR per SO23-3-2.36, Radiation Monitoring Data Acquisition System. This is a bank JPM under the Process Radiation Monitoring System

- Instrumentation Safety Function.

S-8 The applicant will respond to a failed Pressurizer pressure transmitter using the Alarm Response Procedure and AOI SO23-13-27, Pressurizer Pressure and Level Malfunctions. The alternate path results from the alternate control transmitter being unresponsive, requiring the applicant to regain control of Pressurizer pressure using manual controls. This is a new JPM under the Pressurizer Pressure Control System -

Reactor Pressure Control Safety Function.

P-1 The applicant will locally open an Atmospheric Dump Valve to establish RCS Heat Removal per SO23-13-2, Shutdown From Outside the Control Room. This is a bank JPM under the Main and Reheat Steam System - Secondary System Heat Removal From Reactor Core Safety Function.

P-2 The applicant will locally start an Emergency Diesel Generator per SO23-13-2, Shutdown from Outside the Control Room. The alternate path occurs when a Hi-Hi Coolant Temperature alarm is received. This is a bank JPM under the Emergency Diesel Generators System - Electrical Safety Function.

P-3 The applicant will place a CEA subgroup on the hold bus per SO23-15-50.A2, Alarm Response Procedure for a CEDMCS Timer Failure alarm. This is a bank JPM under the Control Rod Drive System - Reactivity Control Safety Function.

3 of 3 SONGS NRC 2012 ES-301-2 RO & SRO JPM Outline Rev e.doce

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM S-1 Task # 141244 K/A # 004 A2.06 4.2 / 4.3 SF-1

Title:

Perform a Blended Makeup to the VCT Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: x Simulator: x Alternate Path: x Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 2 is operating at 100% Reactor power.

• VCT Level Transmitter LT-226 has failed to 45% and has been placed in BYPASS.

• VCT Level Transmitter LT-227 is indicating 39% level in the VCT.

• Boric Acid Makeup Pump P-174 is OOS.

• Current Boron Concentration is 892 ppm per Chemistry sample.

• Blend setpoints of 13.2 gpm for Boric Acid and 74.8 gpm for PMW were verified at the beginning of shift.

• PMW tanks are NOT cross-tied.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Perform a manual blended makeup to the VCT to raise VCT level to 50%

per SO23-3-2.2, Makeup Operations, Section 6.7, Manual Blended Makeup Mode.

• A Reactivity Brief has been conducted and the CRS has suspended peer checking for this evolution.

• Start at step 6.7.9.

Task Standard: INITIATED a blended makeup to the VCT, INITIATED action to terminate the blend within one minute of the overcurrent trip of Boric Acid Makeup Pump P-175, and TERMINATED the dilution within five minutes of the Boric Acid Makeup Pump P-175 trip.

Required Materials: SO23-3-2.2, Makeup Operations, Section 6.7, Manual Blended Makeup Mode.

Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Page 1 of 8 SONGS NRC 2012 JPM S-1 Rev d.doc

Appendix C JPM WORKSHEET Form ES-C-1 Examiner (Print / Sign): Date:

Page 2 of 8 SONGS NRC 2012 JPM S-1 Rev d.doc

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP MACHINE OPERATOR:

• INITIALIZE to IC- 221

• ENSURE NRC JPM S-1 event is loaded (event will automatically actuate based on applicant actions).

• ENSURE FIC-0210Y, BAMU Flow Controller, is set to a flowrate of 13.2 gpm.

• ENSURE FIC-0210X, PMW Flow Controller, is set to a flowrate of 74.8 gpm.

• ENSURE an OOS MAGTAG is placed over the BAMU Pump P-174 handswitch.

• ENSURE trend setup on the PCS computer facing the CVCS DCS screen with the following monitoring points:

• Pressurizer Level

• Pressurizer Pressure

• VCT Level

• Reactor Power (CV9739)

EXAMINER:

• PROVIDE the examinee with a copy of SO23-3-2.2, Makeup Operations, Section 6.7, Manual Blended Makeup Mode.

Page 3 of 8 SONGS NRC 2012 JPM S-1 Rev d.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 ENSURE ENTERED required flowrate on FIC-0210Y, BAMU Flow 6.7.9 Controller.

Standard: VERFIED BAMU Flowrate of 13.2 gpm entered on FIC-0210Y.

Comment: SAT UNSAT Perform Step: 2 If flowrate change, then SELECT SET.

6.7.9.1 Standard: MARKED step N/A due to flowrate of 13.2 gpm entered on FIC-0210Y.

Comment: SAT UNSAT Perform Step: 3 ENSURE FIC-0210Y in AUTO.

6.7.9.2 Standard: VERIFIED FIC-0210Y selected to AUTO.

Comment: SAT UNSAT Perform Step: 4 ENSURE ENTERED required flowrate on FIC-0210X, PMW Flow 6.7.10 Controller.

Standard: VERIFIED PMW Flowrate of 74.8 gpm entered on FIC-0210X.

Comment: SAT UNSAT Perform Step: 5 If flowrate change, then SELECT SET.

6.7.10.1 Standard: MARKED step N/A due to flowrate of 74.8 gpm entered on FIC-0210X.

Comment: SAT UNSAT Perform Step: 6 ENSURE FIC-0210X in AUTO.

6.7.10.2 Standard: VERIFIED FIC-0210X selected to AUTO.

Comment: SAT UNSAT Page 4 of 8 SONGS NRC 2012 JPM S-1 Rev d.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 From the MODE SELECTOR, SELECT MODIFY.

6.7.11.1 Standard: SELECTED MODIFY from the MODE SELECTOR.

Examiner Note: The applicant may not select MODIFY since the MODE SELECTOR is already in MANUAL.

Comment: SAT UNSAT Perform Step: 8 From the MODE SELECTOR, SELECT MANUAL.

6.7.11.2 Standard: SELECTED MANUAL from the MODE SELECTOR.

Examiner Note: The applicant may not select MANUAL since the MODE SELECTOR is already in MANUAL.

Comment: SAT UNSAT Perform Step: 9 From the MODE SELECTOR, SELECT EXIT.

6.7.11.3 Standard: SELECTED EXIT from the MODE SELECTOR.

Examiner Note: The applicant may not select EXIT if steps 6.7.11.1 and 6.7.11.2 were not performed due to the MODE SELECTOR already being in MANUAL.

Comment: SAT UNSAT Perform Step: 10 OPEN FV-9253, Blended Makeup to VCT Isolation.

6.7.12 Standard: OPENED FV-9253, Blended Makeup to VCT Isolation by DEPRESSING the OPEN pushbutton.

Examiner Note: Opening FV-9253 causes 58A54, CVCS DCS Trouble, to reset and immediately reflash.

Comment: SAT UNSAT Page 5 of 8 SONGS NRC 2012 JPM S-1 Rev d.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 11 SELECT the BAMU Pump associated with the BAMU Tank used.

6.7.13 Standard: VERIFIED selected BAMU Pump is aligned to a BAMU Tank with sufficient inventory and boron concentration.

Comment: SAT UNSAT Perform Step: 12 START the selected BAMU Pump.

6.7.14 Standard: STARTED the selected BAMU Pump by DEPRESSING the selected BAMU Pump START pushbutton.

Comment: SAT UNSAT Perform Step: 13 VERIFY the PMW Pump selected matches the PMW Pump Discharge 6.7.15 Valve Placard.

Standard: VERIFIED the PMW Pump selected on the DCS screen matched the PMW Pump Discharge Valve indicated open on the DCS screen.

Comment: SAT UNSAT Perform Step: 14 START the selected PMW Pump.

6.7.16 Standard: STARTED the selected PMW Pump on the DCS screen by clicking the PMW Pump Control box, clicking the PMW Pump Control header (to enable pump controls), then clicking the START button.

Comment: SAT UNSAT Perform Step: 15 ENSURE OPEN FV-0210Y, BAMU to VCT Flow Control Valve.

6.7.17 Standard: ENSURED OPEN FV-0210Y, BAMU to VCT Flow Control Valve by OBSERVING FV-0210Y throttling open on the DCS screen.

Comment: SAT UNSAT Page 6 of 8 SONGS NRC 2012 JPM S-1 Rev d.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 16 ENSURE OPEN FV-0210X, PMW to VCT Flow Control Valve.

6.7.18 Standard: ENSURED OPEN FV-0210X, PMW to VCT Flow Control Valve by OBSERVING FV-0210X throttling open on the DCS screen.

Examiner Note: ~ 30 seconds after starting the PMW Pump, the running Boric Acid Makeup Pump will trip, requiring the Manual Blended Makeup to be secured.

Comment: SAT UNSAT Examiner Note: The following step represents the alternate path portion of the JPM.

Perform Step: 17 IDENTIFY the running BAMU Pump has tripped and take action to secure the Manual Blended Makeup.

Standard: IDENTIFIED the running BAMU Pump has tripped and SECURED the blended makeup by any ONE of the following actions:

• Stopping the running PMW Pump from the DCS screen.

• Closing FV-9253, Blended Makeup to VCT Isolation Valve.

• Closing FV-0210X, PMW to VCT Flow Control Valve by placing PMW Flow Controller in MANUAL and lowering output to zero.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 7 of 8 SONGS NRC 2012 JPM S-1 Rev d.doc

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Unit 2 is operating at 100% Reactor power.

• VCT Level Transmitter LT-226 has failed to 45% and has been placed in BYPASS.

• VCT Level Transmitter LT-227 is indicating 39% level in the VCT.

• Boric Acid Makeup Pump P-174 is OOS.

• Current Boron Concentration is 892 ppm per Chemistry sample.

• Blend setpoints of 13.2 gpm for Boric Acid and 74.8 gpm for PMW were verified at the beginning of shift.

• PMW tanks are NOT cross-tied.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Perform a manual blended makeup to the VCT to raise VCT level to 50% per SO23-3-2.2, Makeup Operations, Section 6.7, Manual Blended Makeup Mode.

• A Reactivity Brief has been conducted and the CRS has suspended peer checking for this evolution.

• Start at step 6.7.9.

Page 8 of 8 SONGS NRC 2012 JPM S-1 Rev d.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM S-2 Task #185145 K/A # 011 A4.05 3.2 / 2.9 SF-2

Title:

Shift In-Service Letdown Flow Control Valves Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: x Simulator: x Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 2 is in Mode 1.

• The in-service Letdown Flow Control Valve, 2LV-0110A, is to be taken out of service for maintenance.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Place 2LV-0110B in service in accordance with SO23-3-2.1, CVCS Operation, Attachment 5, Shifting Flow and Backpressure Control Valves, Section 2.1, Shifting the Letdown Flow Control Valves.

• A Reactivity Brief has been conducted and the CRS has suspended peer checking for this evolution.

• The CRS has determined that Accumulator blowdown is NOT required.

• Start at step 2.1.2.

Task Standard: PLACED 2LV-0110B in service while maintaining Pressurizer level > 51.5%

(backup charging pump start) and < 57% (TS limit).

Required Materials: SO23-3-2.1, CVCS Operation, Attachment 5, Shifting Flow and Backpressure Control Valves, Section 2.1, Shifting the Letdown Flow Control Valves Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 6 SONGS NRC 2012 JPM S-2 Rev b.docb

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP MACHINE OPERATOR:

• INITIALIZE to IC- 222

• ENSURE Letdown flow and backpressure are stable prior to starting the JPM.

EXAMINER:

• PROVIDE the examinee with a copy of SO23-3-2.1, CVCS Operation, Attachment 5, Shifting Flow and Backpressure Control Valves, Section 2.1, Shifting the Letdown Flow Control Valves.

Page 2 of 6 SONGS NRC 2012 JPM S-2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 ENSURE HIC-0110B, the out of service (incoming) Letdown Flow 2.1.2 Valve Controller, in MANUAL with zero output.

Standard: ENSURED HIC-0110B in MANUAL with zero output.

Comment: SAT UNSAT Perform Step: 2 OPEN Out of Service Letdown Flow Control Valve Outlet Valve, 2.1.3 S21208MU163 (LV-0110B).

Standard: DIRECTED outside operator to open S21208MU163.

Machine Operator: When called to open S21208MU163, EXECUTED RF CV52B to 100%

open.

Examiner Cue: After outside operator is directed to open S21208MU163, Letdown Flow Control Valve Outlet Valve, S21208MU163, is open and has been independently verified open.

Comment: SAT UNSAT Perform Step: 3 PLACE the controller for the in-service (outgoing) Letdown Flow 2.1.4 Control Valve in MANUAL.

Standard: PLACED HIC-0110A in MANUAL by DEPRESSING the A/M pushbutton on HIC-0110A.

Comment: SAT UNSAT Page 3 of 6 SONGS NRC 2012 JPM S-2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 SLOWLY RAISE the output signal of the incoming Letdown Flow 2.1.5 Control Valve Controller, and SLOWLY LOWER the output signal of the outgoing Letdown Flow Control Valve Controller, while monitoring for proper response of the Letdown Flow Control Valves and Pressurizer level.

Standard: MAINTAINED Pressurizer level > 51.5% (backup charging pump start) and < 57% (TS limit) while transferring Letdown Flow Control Valves in MANUAL.

Comment: SAT UNSAT Perform Step: 5 When the Output signal of the incoming Letdown Flow Control Valve 2.1.6.1 Controller equals the Auto Demand Signal (at or above the controllers floor setting) from its own controller, then perform the following:

PLACE the controller for the incoming Letdown Flow Control Valve in AUTO, and ENSURE proper response.

Standard: PLACED HIC-0110B in AUTO by DEPRESSING the A/M pushbutton on HIC-0110B and ENSURED proper response by observing Letdown Flow Control Valve LV-0110B throttle open/closed in response to current level deviation.

Comment: SAT UNSAT Perform Step: 6 ENSURE CLOSED the outgoing Letdown Flow Control Valve by 2.1.6.2 SLOWLY LOWERING the output signal, to zero while monitoring for proper response of the Letdown Flow Control Valves and Pressurizer level.

Standard: CLOSED LV-0110A by lowering Letdown Flow Controller HIC-0110A output to zero and MONITORED proper response of Letdown Flow Control Valve LV-0110B.

Comment: SAT UNSAT Perform Step: 7 ENSURE that the incoming Letdown Flow Control Valve automatically 2.1.7 throttles to maintain letdown flow, and a stable Pressurizer level.

Standard: ENSURED LV-0110B automatically throttled to maintain Pressurizer level stable.

Comment: SAT UNSAT Page 4 of 6 SONGS NRC 2012 JPM S-2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 CLOSE the Outlet Valve for the Letdown Flow Control Valve which was 2.1.8 taken out of service (S21208MU162)

Standard: DIRECTED outside operator to close S21208MU162.

Examiner Cue: Letdown Flow Control Valve Outlet Valve, S21208MU162, is closed and has been independently verified closed.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 SONGS NRC 2012 JPM S-2 Rev b.docb

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Unit 2 is in Mode 1.

• The in-service Letdown Flow Control Valve, 2LV-0110A, is to be taken out of service for maintenance.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Place 2LV-0110B in service in accordance with SO23-3-2.1, CVCS Operation, Attachment 5, Shifting Flow and Backpressure Control Valves, Section 2.1, Shifting the Letdown Flow Control Valves.

• A Reactivity Brief has been conducted and the CRS has suspended peer checking for this evolution.

• The CRS has determined that Accumulator blowdown is NOT required.

• Start at step 2.1.2.

Page 6 of 6 SONGS NRC 2012 JPM S-2 Rev b.docb

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # S-3 Task #141295 K/A #005 A4.01 3.6 / 3.4 SF-4P

Title:

Transfer From Parallel to Single LPSI Pump Operation (Shutdown Cooling)

Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: x Simulator: x Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 2 is in MODE 5.

• RCS temperature is 75°F.

• Pressurizer level is 15%.

• Two trains of Shutdown Cooling are in service.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Secure Train B LPSI Pump P-016 per SO23-3-2.6, Shutdown Cooling Operation, Section 6.12, Transfer from Parallel to Single LPSI Pump Operation.

• The CRS has set a temperature band of 70 to 80°F for this evolution.

• The CRS has directed SDC flowrates remain within the administrative limits of SO23-3-2.6, Shutdown Cooling Operation.

Task Standard: SECURED Train B LPSI Pump while MAINTAINING the following parameters:

• RCS temperature between 70 and 80°F

• SDC flowrate between 5000 and 8300 gpm with two LPSI pumps in service.

• SDC flowrate between 2500 (or 2400 per CFMS) and 5500 gpm with one LPSI pump in service.

Required Materials: SO23-3-2.6, Shutdown Cooling Operation.

Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 5 SONGS 2012 NRC JPM S-3 Rev b

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP MACHINE OPERATOR:

• INITIALIZE to IC-219

• Bring up PCS Page 314 at the 21 desk and turn the screen to face CR57.

• Leave the simulator in FREEZE until the applicant is ready to begin.

• ENSURE keys are installed in HV-8150 and HV-8151 (will not show up in switchcheck).

• REMOVE Train B CCW Tags from the Control Board.

EXAMINER:

• PROVIDE the examinee with a copy of: SO23-3-2.6, Shutdown Cooling Operation, Sections 6.2, 6.3, 6.12, and the Limits & Specifications.

Page 2 of 5 SONGS 2012 NRC JPM S-3 Rev b

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Ensure RCS and/or SFP alternate cooling procedures SO23-3-2.6.1, 6.12.1 SO23-3-2.6.2, SO23-3-2.6.3, and SO23-3-2.6.4 are not in use.

Standard: VERIFIED no alternate RCS and/or SFP cooling procedures are in use.

Examiner Cue: No alternate cooling procedures are in use.

Comment: SAT UNSAT Perform Step: 2 Notify HP 70' Control Point that radiation levels in the affected areas 6.12.2 may increase.

Standard: INFORMED the 70 Control Point of the potential for increased radiation levels.

Examiner Cue: Control Point has been notified.

Comment: SAT UNSAT Perform Step: 3 Adjust RCS/SDCS temperature and flow per Main Body Section 6.3 6.12.3 during this evolution.

Standard: MAINTAINED the following parameters:

• RCS temperature between 70 and 80°F.

• SDC flowrate between 5000 and 8300 gpm with two LPSI pumps in service.

Examiner Note: Main body Section 6.3 is always in effect while Shutdown Cooling is in service.

Comment: SAT UNSAT Perform Step: 4 SLOWLY CLOSE two LPSI Header Isolation Valves. Valves selected 6.12.4 should be associated with the LPSI Pump being removed from service:

MP-016: 2(3)HV-9322 and 2(3)HV-9331.

Standard: CLOSED LPSI Header Isolation Valves 2HV-9322 and 2HV-9331 while MAINTAINING the following parameters:

• RCS temperature between 70 and 80°F.

• SDC flowrate between 5000 and 8300 gpm with two LPSI pumps in service.

Comment: SAT UNSAT Page 3 of 5 SONGS 2012 NRC JPM S-3 Rev b

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 STOP the LPSI Pump being removed from service:

6.12.5 2(3)MP-016, Train B LPSI Pump.

Standard: STOPPED LPSI Pump P-016 and MAINTAINED the following parameters:

• RCS temperature between 70 and 80°F.

• SDC flowrate between 2500 and 5500 gpm.

Examiner Note: When LPSI Pump P-016 is secured, SDC flowrate will lower ~ 1000 gpm. If the applicant maintains SDC flowrate between 5000 and 8300 gpm before P-016 is secured, and flowrate lowers to between 2500 and 5500 gpm after the pump is secured, he/she has performed the step correctly.

Terminating Cue: When the applicant has secured LPSI Pump P-016 and has control of SDC flowrate and RCS temperature, the JPM can be terminated.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 SONGS 2012 NRC JPM S-3 Rev b

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Unit 2 is in MODE 5.

• RCS temperature is 75°F.

• Pressurizer level is 15%.

• Two trains of Shutdown Cooling are in service.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Secure Train B LPSI Pump P-016 per SO23-3-2.6, Shutdown Cooling Operation, Section 6.12, Transfer from Parallel to Single LPSI Pump Operation.

• The CRS has set a temperature band of 70 to 80°F for this evolution.

• The CRS has directed SDC flowrates remain within the administrative limits of SO23-3-2.6, Shutdown Cooling Operation.

Page 5 of 5 SONGS 2012 NRC JPM S-3 Rev b

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM S-4 Task #192835 K/A # 045 A4.02 2.7 / 2.6 SF-4S

Title:

Synchronize the Main Generator to the Grid and Apply Block Load Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: x Simulator: x Alternate Path: x Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 2 is ready to synchronize the Main Generator to the grid.

• Reactor Power is stable at 18.5%.

• Shift Managers permission has been obtained for this evolution.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Synchronize the Main Generator to the grid and apply block load per SO23-10-1, Turbine Startup and Normal Operation, Attachment 2, Cold Turbine Startup, Section 2.6, Synchronize and Apply Block Load of 55 MW.

• A Reactivity Brief has been conducted and the CRS has suspended peer checking for this evolution.

Task Standard: SYNCHRONIZED the Main Generator to the grid and TRIPPED the Main Turbine within five minutes of the Turbine Vibration Hi alarm (window 99B49).

Required Materials: SO23-10-1, Turbine Startup and Normal Operation, Attachment 2, Cold Turbine Startup, Section 2.6, Synchronize and Apply Block Load, and ARP SO23 99.B, window 99B49, Turbine Vibration Hi.

Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 SONGS NRC 2012 JPM S-4 Rev c.docc

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP MACHINE OPERATOR:

• INITIALIZE to IC-220

• ENSURE the synchroscope keyswitch is in the OFF position.

• ENSURE the Main Turbine Emergency Trip pushbutton key has been removed.

• LEAVE the simulator in FREEZE until the applicant is ready to begin the JPM.

• ENSURE the malfunction auto actuates when the 1st generator output breaker is closed.

EXAMINER:

• PROVIDE the examinee with a copy of SO23-10-1, Turbine Startup and Normal Operation, Attachment 2, Cold Turbine Startup, Section 2.6, Synchronize and Apply Block Load and the Limits & Specifications.

Page 2 of 7 SONGS NRC 2012 JPM S-4 Rev c.docc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 DEPRESS the Generator Output Breakers Trip pushbuttons to ensure 2.6.1 they do not have a trip relay energized.

Standard: DEPRESSED the Generator Output Breakers Trip pushbuttons.

Comment: SAT UNSAT Perform Step: 2 Ensure Reactor Power is 17%.

2.6.2 Standard

VERIFIED Reactor Power is 17%.

Comment: SAT UNSAT Perform Step: 3 Verify Turbine Vibration (XR2110) is not trending up toward alarm 2.6.3 setpoint. (Setpoint is 9 mils.)

Standard: VERIFIED Turbine Vibration (XR2110) is not trending up toward alarm setpoint.

Comment: SAT UNSAT Perform Step: 4 If Turbine Vibration is trending up toward alarm setpoint, then 2.6.3.1 contact Engineering prior to synchronizing to the grid.

Standard: MARKED step N/A due to normal vibration levels identified in step 2.6.3.

Comment: SAT UNSAT Perform Step: 5 Obtain Shift Managers approval to synchronize the Unit and 2.6.4 apply Block Load.

Standard: IDENTIFIED Shift Managers approval has already been obtained from the Initial Conditions.

Comment: SAT UNSAT Page 3 of 7 SONGS NRC 2012 JPM S-4 Rev c.docc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 6 TURN key operated HS-1627A to ON to place the Non-ESF 2.6.5 Synchroscope in service.

Standard: TURNED key operated HS-1627A to ON to place the Non-ESF Synchroscope in service.

Comment: SAT UNSAT Examiner Note: Either Generator Output Breaker 4062 or 6062 may be used first when synching the Generator to the grid.

Perform Step: 7 DEPRESS Generator Output Breaker 4062 or 6062 SYNC pushbutton 2.6.6 to place the synchronizing circuit in service across the respective breaker.

Standard: DEPRESSED Generator Output Breaker 4062 or 6062 SYNC pushbutton to place the synchronizing circuit in service across the respective breaker.

Comment: SAT UNSAT Perform Step: 8 Wait at least 30 seconds for operation of sync check relay.

2.6.7 Standard

WAITED at least 30 seconds for operation of sync check relay.

Comment: SAT UNSAT Perform Step: 9 Adjust the Generator voltage above running voltage (HS-2971).

2.6.8 Standard

ADJUSTED the Generator voltage above running voltage (HS-2971).

Comment: SAT UNSAT Page 4 of 7 SONGS NRC 2012 JPM S-4 Rev c.docc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: L&S 5.6 is above.

Perform Step: 10 Adjust Turbine Speed, so the synchroscope is moving slowly in the 2.6.9 clockwise direction (HS-2210). [LS-5.6]

Standard: ADJUSTED Turbine Speed using Turbine Speed RAISE/LOWER pushbutton HS-2210 as necessary to move the synchroscope slowly in the clockwise direction.

Comment: SAT UNSAT Perform Step: 11 CLOSE the Generator Output Breaker.

2.6.10 Standard: CLOSED the Generator Output Breaker.

Comment: SAT UNSAT Page 5 of 7 SONGS NRC 2012 JPM S-4 Rev c.docc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 12 VERIFY CLOSED Generator Output Breaker, and the synchroscope 2.6.11 stopped in the straight up position.

Standard: VERIFIED closed Generator Output Breaker, and the synchroscope stopped in the straight up position.

Comment: SAT UNSAT Examiner Note: This step may or may not be performed based on applicant speed.

Perform Step: 13 ENSURE Turbine picks up initial Block Load of 55 MWe.

2.6.12 Standard: ENSURED Turbine picked up initial Block Load of 55 MWe.

Comment: SAT UNSAT Examiner Note: The following step is from Alarm Response Procedure 99B49, Turbine Vibration Hi Perform Step: 14 If sustained, and confirmed real, vibration exceeds 12.5 mils, then:

2.1.3

• If < 55% Reactor Power, then Manually Trip the Turbine.

Examiner Cue: If an outside operator is called to confirm the Turbine vibration, There has been a significant rise in the vibration levels of the Main Turbine.

Standard: Manually tripped the Turbine.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 SONGS NRC 2012 JPM S-4 Rev c.docc

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Unit 2 is ready to synchronize the Main Generator to the grid.

• Shift Managers permission has been obtained for this evolution.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Synchronize the Main Generator to the grid and apply block load per SO23-10-1, Turbine Startup and Normal Operation, Attachment 2, Cold Turbine Startup, Section 2.6, Synchronize and Apply Block Load of 55 MW.

Page 7 of 7 SONGS NRC 2012 JPM S-4 Rev c.docc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # S-5 Task # 192833 K/A # 103 A3.01 3.9 / 4.2 SF-5

Title:

Verify Containment Isolation Actuation Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: x Simulator: x Alternate Path: x Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 2 tripped from 100% Reactor power due to an Excess Steam Demand Event.

• Standard Post Trip Actions have been completed and the crew has transitioned to SO23-12-5, Excess Steam Demand Event.

• The Plant Computer System (PCS) is out of service.

• You are the ARO and have been called to the Control Room.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Verify proper actuation of Containment Isolation per SO23-3-2.22, Engineered Safety Features Actuation System Operations, Attachment 7, CIAS Actuation Verification.

Task Standard:

• IDENTIFIED HV-6212, HV-6218, HV-6223, HV-6236, and HV-5388 failed to close on CIAS and CLOSED the valves per SO23-3-2.22.

Required Materials: SO23-3-2.22, Engineered Safety Features Actuation System Operations, Attachment 7, CIAS Actuation Verification.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 SONGS 2012 NRC JPM S-5 Rev c

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP MACHINE OPERATOR:

• INITIALIZE to IC-229

• ENSURE K-Relays K213A, K205A, and K301A are in the fail energized condition.

• ENSURE OOS Tags are placed on the PCS computers and ALL PCS monitors are turned OFF.

• LEAVE the simulator in FREEZE until the applicant is ready to begin.

EXAMINER:

PROVIDE the examinee with a copy of SO23-3-2.22, Engineered Safety Features Actuation System Operations, Attachment 7, CIAS Actuation Verification.

Page 2 of 7 SONGS 2012 NRC JPM S-5 Rev c

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 ENSURE CIAS Train A component actuation at CR-57:

2.2.1 HV-4048, S/G E-088 Main FW Isolation Valve Standard: VERIFIED CLOSED, HV-4048, S/G E-088 Main FW Isolation Valve Comment: SAT UNSAT Perform Step: 2 ENSURE CIAS Train A component actuation at CR-57:

2.2.2 HV-8205, S/G E-088 Main Steam Isolation Valve Standard: VERIFIED CLOSED, HV-8205, S/G E-088 Main Steam Isolation Valve Comment: SAT UNSAT Perform Step: 3 ENSURE CIAS Train A component actuation at CR-57:

2.2.3 HV-6223, CCW NCL Containment Supply Isolation Standard: RECOGNIZED HV-6223, CCW NCL Containment Supply Isolation failed to close and CLOSED HV-6223, CCW NCL Containment Supply Isolation.

Examiner Note: If the applicant mentions writing a notification about the failed component, inform him/her that another operator will write the notification.

Comment: SAT UNSAT Perform Step: 4 ENSURE CIAS Train A component actuation at CR-57:

2.2.4 HV-6236, CCW NCL Containment Return Isolation Standard: RECOGNIZED HV-6236, CCW NCL Containment Return Isolation failed to close and CLOSED HV-6236, CCW NCL Containment Return Isolation.

Comment: SAT UNSAT Perform Step: 5 ENSURE CIAS Train A component actuation at CR-57:

2.2.5 HV-6212, CCW Loop A to NCL Isolation Standard: RECOGNIZED HV-6212, CCW Loop A to NCL Isolation failed to close and CLOSED HV-6212, CCW Loop A to NCL Isolation.

Comment: SAT UNSAT Page 3 of 7 SONGS 2012 NRC JPM S-5 Rev c

Appendix C JPM STEPS Form ES-C-1 Perform Step: 6 ENSURE CIAS Train A component actuation at CR-57:

2.2.6 HV-6218, CCW Loop A from NCL Isolation Standard: RECOGNIZED HV-6218, CCW Loop A from NCL Isolation failed to close and CLOSED HV-6218, CCW Loop A from NCL Isolation.

Comment: SAT UNSAT Perform Step: 7 ENSURE CIAS Train A component actuation at CR-57:

2.2.7 HV-9218, RCP CBO to VCT Isolation Standard: VERIFIED CLOSED, HV-9218, RCP CBO to VCT Isolation Comment: SAT UNSAT Perform Step: 8 ENSURE CIAS Train A component actuation at CR-57:

2.2.8 HV-9205, Letdown Containment Isolation Standard: VERIFIED CLOSED, HV-9205, Letdown Containment Isolation Comment: SAT UNSAT Perform Step: 9 ENSURE CIAS Train A component actuation at CR-57:

2.2.9 HV-0509, Common Hot Leg Sample Isolation Standard: VERIFIED CLOSED, HV-0509, Common Hot Leg Sample Isolation Comment: SAT UNSAT Perform Step: 10 ENSURE CIAS Train A component actuation at CR-57:

2.2.10 HV-0511, PZR STM Space Sample Isolation Standard: VERIFIED CLOSED, HV-0511, PZR STM Space Sample Isolation Comment: SAT UNSAT Perform Step: 11 ENSURE CIAS Train A component actuation at CR-57:

2.2.11 HV-0513, PZR Surge Line Sample Isolation Standard: VERIFIED CLOSED, HV-0513, PZR Surge Line Sample Isolation Comment: SAT UNSAT Page 4 of 7 SONGS 2012 NRC JPM S-5 Rev c

Appendix C JPM STEPS Form ES-C-1 Perform Step: 12 ENSURE CIAS Train A component actuation at CR-57:

2.2.12 HV-0514, Quench Tank Gas Sample Standard: VERIFIED CLOSED, HV-0514, Quench Tank Gas Sample Comment: SAT UNSAT Perform Step: 13 ENSURE CIAS Train A component actuation at CR-57:

2.2.13 HV-0516, RCDT T-012 Gas Sample Isolation Standard: VERIFIED CLOSED, HV-0516, RCDT T-012 Gas Sample Isolation Comment: SAT UNSAT Perform Step: 14 ENSURE CIAS Train A component actuation at CR-57:

2.2.14 HV-7802, Containment Rad Mon Tr A Outlet Isolation Standard: VERIFIED CLOSED, HV-7802, Containment Rad Mon Tr A Outlet Isolation Comment: SAT UNSAT Perform Step: 15 ENSURE CIAS Train A component actuation at CR-57:

2.2.15 HV-7811, Containment Rad Mon Tr B Outlet Isolation Standard: VERIFIED CLOSED, HV-7811, Containment Rad Mon Tr B Outlet Isolation Comment: SAT UNSAT Perform Step: 16 ENSURE CIAS Train A component actuation at CR-57:

2.2.16 HV-9920, Containment Chill Water Inlet Isolation Standard: VERIFIED CLOSED, HV-9920, Containment Chill Water Inlet Isolation Comment: SAT UNSAT Perform Step: 17 ENSURE CIAS Train A component actuation at CR-57:

2.2.17 HV-5388, Inst. Air to Containment Isolation Standard: RECOGNIZED HV-5388, Inst. Air to Containment Isolation, failed to close and CLOSED HV-6218, CCW Loop A from NCL Isolation.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT Page 5 of 7 SONGS 2012 NRC JPM S-5 Rev c

Appendix C JPM STEPS Form ES-C-1 STOP TIME:

Page 6 of 7 SONGS 2012 NRC JPM S-5 Rev c

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Unit 2 tripped from 100% Reactor power due to an Excess Steam Demand Event.

• Standard Post Trip Actions have been completed and the crew has transitioned to SO23-12-5, Excess Steam Demand Event.

• The Plant Computer System (PCS) is out of service.

• You are the ARO and have been called to the Control Room.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Verify proper actuation of Containment Isolation per SO23-3-2.22, Engineered Safety Features Actuation System Operations, Attachment 7, CIAS Actuation Verification.

Page 7 of 7 SONGS 2012 NRC JPM S-5 Rev c

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM S-6 Task #186193 K/A # 062 A4.07 3.1 / 3.1 SF-6

Title:

Manually transfer 6.9kV Bus 2A01 from UAT to RAT Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: x Simulator: x Alternate Path: x Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 2 is operating at 100% Reactor power.

• Maintenance is scheduled for Unit Auxiliary Transformer breaker 2A0104.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Manually transfer 6.9kV bus 2A01 from Unit Auxiliary Transformer 2XU2 to Reserve Auxiliary Transformer 2XR3 in accordance with SO23-6-1, Transferring 6.9kV Buses, Section 6.1, Manual Transfer of 6.9kV Bus from 2XU2 to 2XR3.

• The CRS has suspended Peer Checking for this evolution.

Task Standard: TRANSFERRED 6.9kV bus 2A01 from the Unit Auxiliary Transformer to the Reserve Auxiliary Transformer and TRIPPED the Reactor within one minute of the subsequent loss of 2A01.

Required Materials:

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 SONGS NRC 2012 JPM S-6 Rev c.docc

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP MACHINE OPERATOR:

• INITIALIZE to IC-224.

• OPEN 2012 NRC JPM S-6 event file. The malfunction will automatically actuate based on operator actions.

• VERIFY the event file actuates when 2A01 is transferred from the UAT to the RAT.

• ENSURE running and incoming voltages and frequencies are matched (adjust the meter calibration dials if necessary).

• DO NOT acknowledge any alarms during the performance of this JPM.

EXAMINER:

• PROVIDE the examinee with a copy of SO23-6-1, Transferring 6.9kV Buses, Section 6.1, Manual Transfer of 6.9kV Bus from 2XU2 to 2XR3.

Page 2 of 7 SONGS NRC 2012 JPM S-6 Rev c.docc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 ENSURE the affected Switchgear area is clear of all unnecessary 6.1.1 personnel and maintain it clear until after 6.9 kV bus is energized.

Standard: ENSURED the affected Switchgear area is clear of all unnecessary personnel and maintain it clear until after 6.9 kV bus is energized.

Examiner Cue: The switchgear area is clear of personnel and I will maintain clear of personnel.

Comment: SAT UNSAT Perform Step: 2 VERIFY ENERGIZED 2XR3 Transformer.

6.1.2 Standard

VERIFIED 2XR3 is energized by visually checking the alignment of power to 2XR3.

Comment: SAT UNSAT Perform Step: 3 ENSURE OPEN 3A0105, Res Aux XFMR 2XR3 FDR Breaker. (3HS-6.1.3 1754A)

Standard: VERIFIED OPEN 3A0105, Res Aux XFMR 2XR3 FDR Breaker.

Examiner Note: 3A0105, Res Aux XFMR 2XR3 FDR Breaker is not modeled in the simulator.

Examiner Cue: Breaker 3A0105 is OPEN.

Comment: SAT UNSAT Perform Step: 4 PLACE IN MANUAL 2HS-1613B, Res Aux XFMR 2XR3 FDR Bkr 6.1.4 2A0102 Mode Selector.

Standard: PLACED IN MANUAL 2HS-1613B, Res Aux XFMR 2XR3 FDR Bkr 2A0102 Mode Selector.

Comment: SAT UNSAT Page 3 of 7 SONGS NRC 2012 JPM S-6 Rev c.docc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 PLACE IN SERVICE 2/3HS-1627A, NON-1E Sync Master CNTRL.

6.1.5 Standard

PLACED 2/3HS-1627A, NON ESF SYNC MASTER keyswitch to the ON position.

Comment: SAT UNSAT Perform Step: 6 DEPRESS 2HS-1613A, Res Aux XFMR 2XR3 FDR Breaker 2A0102, 6.1.6 SYNC pushbutton to place the synchronizing circuit in service.

Standard: DEPRESSED 2HS-1613A, Res Aux XFMR 2XR3 FDR Breaker 2A0102, SYNC pushbutton.

Comment: SAT UNSAT Perform Step: 7 VERIFY Breaker SYNC light ILLUMINATED.

6.1.6.1 Standard: OBSERVED Breaker SYNC light ILLUMINATED.

Comment: SAT UNSAT Perform Step: 8 VERIFY SYNC IN MODE light ILLUMINATED.

6.1.6.2 Standard: OBSERVED SYNC IN MODE light ILLUMINATED.

Comment: SAT UNSAT Perform Step: 9 VERIFY SYNC RELAYS TROUBLE light EXTINGUISHED.

6.1.6.3 Standard: OBSERVED SYNC RELAYS TROUBLE light EXTINGUISHED.

Comment: SAT UNSAT Perform Step: 10 VERIFY INCOMING and RUNNING voltage and frequencies matched.

6.1.6.4 Standard: OBSERVED INCOMING and RUNNING voltage and frequencies matched.

Comment: SAT UNSAT Page 4 of 7 SONGS NRC 2012 JPM S-6 Rev c.docc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 11 VERIFY Synchroscope moves to within +/- 5 minutes of the straight up 6.1.6.5 position.

Standard: OBSERVED Synchroscope moved to within +/- 5 minutes of the straight up position.

Comment: SAT UNSAT Examiner Note: ~ 10 seconds after closing Res Aux XFMR 2XR3 FDR Breaker 2A0102, the breaker will trip on overcurrent.

DO NOT allow alarms to be acknowledged by the training staff during this portion of the JPM.

Perform Step: 12 DEPRESS 2HS-1613A, Res Aux XFMR 2XR3 FDR Breaker 2A0102, 6.1.7 CLOSE pushbutton to parallel 2XU2 and 2XR3.

Standard: DEPRESSED 2HS-1613A, Res Aux XFMR 2XR3 FDR Breaker 2A0102, CLOSE pushbutton to parallel 2XU2 and 2XR3 Comment: SAT UNSAT Perform Step: 13 VERIFY OPEN 2A0104, Unit Aux XFMR 2XU2 FDR Breaker. (2HS-1614)

Standard: VERIFIED OPEN 2A0104, Unit Aux XFMR 2XU2 FDR Breaker.

Examiner Note: The following steps represent the alternate path portion of the JPM.

Comment: SAT UNSAT Page 5 of 7 SONGS NRC 2012 JPM S-6 Rev c.docc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 14 RECOGNIZE the failure of the Reactor to automatically trip due to the loss of two RCPs and MANUALLY TRIP the Reactor.

Standard: MANUALLY TRIPPED the Reactor by depressing two manual trip pushbuttons OR by deenergizing 480V loadcenters B15 and B16 within one minute of the loss of 6.9kV bus 2A01.

Termination Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 SONGS NRC 2012 JPM S-6 Rev c.docc

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Unit 2 is operating at 100% Reactor power.

• Maintenance is scheduled for Unit Auxiliary Transformer breaker 2A0104.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Manually transfer 6.9kV bus 2A01 from Unit Auxiliary Transformer 2XU2 to Reserve Auxiliary Transfomer 2XR3 in accordance with SO23-6-1, Transferring 6.9kV Buses, Section 6.1, Manual Transfer of 6.9kV Bus from 2XU2 to 2XR3.

• The CRS has suspended Peer Checking for this evolution.

Page 7 of 7 SONGS NRC 2012 JPM S-6 Rev c.docc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # S-7 Task #191191 K/A #073.A4.02 3.7 / 3.7 SF-7

Title:

Reset HI and HI-HI Alarm Setpoint on DAS Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions on Unit 2:

• A small Steam Generator tube leak has developed in E-088.

• The leak rate is approximately 35 gallons per day (GPD) and stable.

• RE-7870, Condenser Air Ejector Wide Range Gas Monitor HI and HI-HI Alarm setpoints must be raised to 40 GPD and 65 GPD, respectively.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• RESET the HI Alarm setpoint on DAS LEAK RATE page for RE-7870, Condenser Air Ejector Wide Range Gas Monitor, to a value of 40 GPD per SO23-3-2.36, Radiation Monitoring Data Acquisition System, Section 6.14, Using the DAS Primary-to-Secondary Leak Rate Page.

• RESET the HI-HI Alarm setpoint on DAS LEAK RATE page for RE-7870, Condenser Air Ejector Wide Range Gas Monitor, to a value of 65 GPD per SO23-3-2.36, Radiation Monitoring Data Acquisition System, Section 6.14, Using the DAS Primary-to-Secondary Leak Rate Page.

• The CRS has suspended Peer Checking for this evolution.

Task Standard: RESET the HI and HI-HI Alarm setpoints to 40 and 65 GPD (respectively) on the DAS LEAK RATE page for RE-7870, Condenser Air Ejector Wide Range Gas Monitor, per SO23-3-2.36, Radiation Monitor Data Acquisition System.

Required Materials: SO23-3-2.36, Radiation Monitoring Data Acquisition System.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 6 SONGS 2012 NRC JPM S-7 Rev c

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP MACHINE OPERATOR:

• INITIALIZE to IC-225

• EXECUTE malfunction RM04ZD, Condenser Air Ejector WRGM, RE-7870 LEAKRATE at a severity of 35 GPD (7.2x10-7).

• ENSURE RE-7870 HI and HIHI setpoints in DAS are reset to 5 gpd and 30 gpd respectively prior to each performance of this JPM.

• ENSURE the DAS Home Page is being displayed on the Control Operators Desk.

• ENSURE RE-7870 is reading approximately 35 gpd.

• ENSURE 60A46, Secondary Rad Hi, alarm is locked in.

• ACKNOWLEDGE all DAS alarms. RE-7870 Hi and Hi-Hi will remain locked in.

• ENSURE conditions are stable prior to commencing the JPM.

EXAMINER:

• PROVIDE the examinee with a copy of SO23-3-2.36, Radiation Monitoring Data Acquisition System.

Page 2 of 6 SONGS 2012 NRC JPM S-7 Rev c

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: Changes on the Data Acquisition System (DAS) can be performed using the mouse, keyboard, or both.

Perform Step: 1 Confirm that the Setpoint has been changed in the applicable Radiation 6.14.1 & 6.14.1.1 Monitor.

Standard: DETERMINED status of setpoint change in Condenser Air Ejector WRGM, RE-7870.

Examiner Cue: The setpoint has been changed in RE-7870 by I & C and has been peer checked.

Comment: SAT UNSAT Perform Step: 2 Go to the DAS Home Page and select the applicable Unit Leak Rate 6.14.1 & 6.14.1.2 button at the top of the screen. Navigate to the applicable monitor Leak Rate page.

Standard: CLICKED on the U2 LEAK RATE button at top of Home Page.

Comment: SAT UNSAT Perform Step: 3 Go to the DAS Home Page and select the applicable Unit Leak Rate 6.14.1 & 6.14.1.2 button at the top of the screen. Navigate to the applicable monitor Leak Rate page.

Standard: DETERMINED correct Leak Rate Page is displayed by its title, RE-7870.

Comment: SAT UNSAT Perform Step: 4 Double click the parameter to be changed (upper left corner). The only 6.14.1 & 6.14.1.3 parameter normally changed without indication of leakage is the setpoint (not the HI SP or HI-HI SP). A pop-up window with keypad will be displayed.

Standard: DOUBLE CLICKED the HI Alarm Setpoint parameter and CAUSED the keypad pop-up window to appear on screen.

Comment: SAT UNSAT Page 3 of 6 SONGS 2012 NRC JPM S-7 Rev c

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Enter new value in pop-up window (Setpoint Format X.XE+/-X) 6.14.1 & 6.14.1.4 Standard: ENTERED new value for HI Alarm Setpoint in keypad pop-up window and CLICKED on numerals 4" then 0" or TYPED in new setpoint using keyboard.

Examiner Note: The setpoint can be changed either by entering 40 or 4.0E+/-1 Comment: SAT UNSAT Perform Step: 6 SELECT the ENTER button.

6.14.1 & 6.14.1.5 Standard: CLICKED on ENTER button.

Comment: SAT UNSAT Perform Step: 7 SELECT OK to confirm, and the parameter has been changed.

6.14.1 & 6.14.1.6 Standard: CLICKED on OK and CONFIRMED the RE-7870 HI setpoint was changed to 40 GPD.

Comment: SAT UNSAT Perform Step: 8 Repeat Steps 6.14.1.3 to 6.14.1.6 for other parameters to be changed.

6.14.1 & 6.14.1.7 Standard: REINITIATED Steps 6.14.1.3 through 6.14.1.6.

Comment: SAT UNSAT Perform Step: 9 Double click the parameter to be changed (upper left corner). The only 6.14.1 & 6.14.1.3 parameter normally changed without indication of leakage is the setpoint (not the HI SP or HI HI SP). A pop-up window with keypad will be displayed.

Standard: DOUBLE CLICKED the HI-HI Alarm Setpoint parameter and CAUSED the keypad pop-up window to appear on screen.

Comment: SAT UNSAT Page 4 of 6 SONGS 2012 NRC JPM S-7 Rev c

Appendix C JPM STEPS Form ES-C-1 Perform Step: 10 Enter new value in pop-up window (Setpoint Format X.XE+/-X) 6.14.1 & 6.14.1.4 Standard: ENTERED new value for HI-HI Alarm Setpoint in keypad pop-up window and CLICKED on numerals 6" then 5" or TYPED in new setpoint using keyboard.

Examiner Note: The setpoint can be changed either by entering 65 or 6.5E+/-1 Comment: SAT UNSAT Perform Step: 11 SELECT the ENTER button.

6.14.1 & 6.14.1.5 Standard: CLICKED on ENTER button.

Comment: SAT UNSAT Perform Step: 12 SELECT OK to confirm, and the parameter has been changed.

6.14.1 & 6.14.1.6 Standard: CLICKED on OK and CONFIRMED the RE-7870 HI-HI setpoint was changed to 65 GPD.

Comment: SAT UNSAT Perform Step: 13 SELECT the UPDATE SCADA button.

6.14.1 & 6.14.1.8 Standard: CLICKED on UPDATE SCADA button.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 SONGS 2012 NRC JPM S-7 Rev c

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions on Unit 2:

• A small Steam Generator tube leak has developed in E-088.

• The leak rate is approximately 35 gallons per day (GPD) and stable.

• RE-7870, Condenser Air Ejector Wide Range Gas Monitor HI and HI-HI Alarm setpoints must be raised to 40 GPD and 65 GPD, respectively.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• RESET the HI Alarm setpoint on DAS LEAK RATE page for RE-7870, Condenser Air Ejector Wide Range Gas Monitor, to a value of 40 GPD per SO23-3-2.36, Radiation Monitoring Data Acquisition System, Section 6.14, Using the DAS Primary-to-Secondary Leak Rate Page.

• RESET the HI-HI Alarm setpoint on DAS LEAK RATE page for RE-7870, Condenser Air Ejector Wide Range Gas Monitor, to a value of 65 GPD per SO23-3-2.36, Radiation Monitoring Data Acquisition System, Section 6.14, Using the DAS Primary-to-Secondary Leak Rate Page.

• The CRS has suspended Peer Checking for this evolution.

Page 6 of 6 SONGS 2012 NRC JPM S-7 Rev c

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # S-8 Task # 185146 K/A # 010 A4.01 3.7 / 3.5 SF-3

Title:

Respond to a Pressurizer Transmitter Failure Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: x Simulator: x Alternate Path: x Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 2 is operating at 98% Reactor power.

Initiating Cue: You are the 21. Maintain steady state conditions on Unit 2.

Task Standard: CONTROLLED Pressurizer Pressure in MANUAL per SO23-13-27, Pressurizer Pressure and Level Malfunctions.

Required Materials: SO23-15-50.A1, Window 50A14, PZR Press Hi/Lo, Alarm Response Procedure and SO23-13-27, Pressurizer Pressure and Level Malfunction.

Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 5 SONGS 2012 NRC JPM S-8 Rev c

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP MACHINE OPERATOR:

• INITIALIZE to IC-228

• OPEN the 2012 NRC JPM S-8 event file

• When DIRECTED by the Floor Instructor, INITIATE 2012 NRC JPM S-8 Event 1 EXAMINER:

• If referenced, PROVIDE the examinee with a copy of SO23-15-50.A1, Window 50A14, PZR Press Hi/Lo, Alarm Response Procedure.

• If referenced, PROVIDE the examinee with a copy of SO23-13-27, Pressurizer Pressure and Level Malfunction.

EXAMINER NOTE:

• The applicant may use Prompt and Prudent actions to take manual control of Pressurizer Pressure due to both control transmitters failing.

Page 2 of 5 SONGS 2012 NRC JPM S-8 Rev c

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: When ready to start the JPM, signal the Machine Operator to insert the Pressurizer Pressure Transmitter Malfunction.

Examiner Note: The following steps are from SO23-15-50.A1, Window 50A14, PZR Press Hi/Lo. The applicant may go directly to SO23-13-27, Pressurizer Pressure and Level Malfunction.

Perform Step: 1 If a control channel failure has occurred, then perform the following:

1.1.1, 1.1.2

• POSITION HS-0100A, PZR Pressure Channel Select Switch, to the other channel.

• Initiate SO23-13-27, Pressurizer Pressure and Level Malfunction.

Standard: POSITIONED HS-0100A to Channel X (this will have no effect due to the switch being faulted) and INITIATED SO23-13-27, Pressurizer Pressure and Level Malfunction.

Comment: SAT UNSAT Examiner Note: The following steps are from SO23-13-27, Pressurizer Pressure and Level Malfunction.

Perform Step: 2 Verify Pressurizer Spray Valve is NOT stuck OPEN.

3.a Standard: VERIFIED both Pressurizer Spray Valves are CLOSED.

Comment: SAT UNSAT Perform Step: 3 VERIFY the selected Pressurizer Pressure channel is between 2225 3.b and 2275 psia and stable.

Standard: OBSERVED the selected Pressurizer Pressure channel is failed low and PROCEEDED to the RNO actions.

Comment: SAT UNSAT Perform Step: 4 VERIFY the other pressure channel is available by observing PR-0100A 3.b RNO or PR-0100B or CFMS page 325.

Standard: OBSERVED both pressure channels are NOT available and PROCEEDED to step C.

Comment: SAT UNSAT Page 3 of 5 SONGS 2012 NRC JPM S-8 Rev c

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 VERIFY Pressurizer Pressure is stable.

3.c Standard: OBSERVED actual Pressurizer Pressure is rising and PROCEEDED to the RNO actions.

Comment: SAT UNSAT Perform Step: 6 TRANSFER PIC-0100, Pressurizer Pressure Controller to MANUAL.

3.c RNO 1 Standard: TRANSFERRED PIC-0100 to MANUAL by depressing the PIC-0100 A/M pushbutton and observing M displayed on PIC-0100.

Comment: SAT UNSAT Examiner Note: Either perform step 7 OR perform step 8 must be performed. Both are listed as critical steps, however either one being performed satisfies the critical step for performance of the JPM.

Perform Step: 7 ADJUST output as necessary to maintain setpoint.

3.c RNO 2 Standard: RAISED output on PIC-0100 by depressing the SEL pushbutton until the green dot is above the output column (right hand column) and then depressing the up arrow on PIC-0100 to raise output to restore Pressurizer Pressure to 2225 - 2275 psia.

Examiner Note: Raising output on PIC-0100 will lower the output from the Proportional Heaters until 67% output. Above 67% output, the Pressurizer Spray Valves will modulate open.

Comment: SAT UNSAT Perform Step: 8 SECURE heaters, as necessary, to limit pressure increase.

3.c RNO 3 Standard: SECURED heaters, as necessary, to restore Pressurizer Pressure to 2225 - 2275 psia.

Terminating Cue: When the applicant has control of Pressurizer Pressure and is lowering pressure towards the setpoint of 2250 psia, the JPM can be terminated.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 SONGS 2012 NRC JPM S-8 Rev c

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Unit 2 is operating at 98% Reactor power.

Initiating Cue: You are the 21. Maintain steady state conditions on Unit 2.

Page 5 of 5 SONGS 2012 NRC JPM S-8 Rev c

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM P-1 Task # 167206 K/A # 068 AA1.01 4.3 / 4.5 SF-4S

Title:

Manually Open an Atmospheric Dump Valve (HV-8419)

Examinee (Print):

Testing Method:

Simulated Performance: x Classroom:

Actual Performance: Simulator:

Alternate Path: Plant: x Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Both Units have been tripped due to toxic gas in the Control Room area.

• SO23-13-2, Shutdown From Outside the Control Room, has been initiated.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Transfer Atmospheric Dump Valve 2HV-8419 to Local Manual operation per SO23-13-2, Shutdown From Outside the Control Room, Attachment 23, Local Manual Operation of Atmospheric Dump Valves.

• You have retrieved the Safe Shutdown bag from the Safe Shutdown locker.

Task Standard: Locally OPENED the ADV per SO23-13-2, Shutdown From Outside the Control Room, Attachment 23, Local Manual Operation of Atmospheric Dump Valves.

Required Materials: SO23-13-2, Shutdown From Outside the Control Room, Attachment 23, Local Manual Operation of Atmospheric Dump Valves.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 6 SONGS NRC 2012 JPM P-1 Unit 2 Version 2 Rev b.docb

Appendix C JPM WORKSHEET Form ES-C-1 JPM SETUP EXAMINER:

PROVIDE the examinee with a copy of SO23-13-2, Shutdown From Outside the Control Room, Attachment 23, Local Manual Operation of Atmospheric Dump Valves.

Page 2 of 6 SONGS NRC 2012 JPM P-1 Unit 2 Version 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Establish communication with the cognizant CRS.

1.0 Standard

ESTABLISHED communication with the cognizant CRS on the sound powered phone circuit or radio.

Examiner Cue: The CRS directs you to continue with the task.

Comment: SAT UNSAT Perform Step: 2 CLOSE S21301MU1304, 2HV-8419 Instrument Air Isolation Valve.

2.1 Standard

CLOSED S21301MU1304, 2HV-8419 Instrument Air Isolation Valve.

Examiner Cue: S21301MU1304 is in the fully clockwise position.

Comment: SAT UNSAT Perform Step: 3 CLOSE S21301MU1328, 2HV-8419 Nitrogen Isolation Valve.

2.2 Standard

CLOSED S21301MU1328, 2HV-8419 Nitrogen Isolation Valve.

Examiner Cue: S21301MU1328 is in the fully clockwise position.

Comment: SAT UNSAT Perform Step: 4 OPEN S21301MU1264, 2HV-8419 Positioner Equalizing Valve.

2.3 Standard

OPENED S21301MU1264, 2HV-8419 Positioner Equalizing Valve.

Examiner Cue: S21301MU1264 is in the fully counter-clockwise position.

Comment: SAT UNSAT Page 3 of 6 SONGS NRC 2012 JPM P-1 Unit 2 Version 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Unscrew the clevis from the Manual Override Shaft.

3.1 Standard

UNSCREWED the clevis from the Manual Override Shaft.

Examiner Cue: The clevis is removed from the Manual Override Shaft.

Comment: SAT UNSAT Perform Step: 6 Turn the Handwheel to the CLOSE (Clockwise) position until the clevis 3.2 detent on the Actuator Shaft is exposed.

Standard: TURNED the Handwheel to the CLOSE (Clockwise) position until the clevis detent on the Actuator Shaft is exposed.

Examiner Cue: The clevis detent is exposed.

Comment: SAT UNSAT Perform Step: 7 When the clevis detent on the Actuator Shaft is exposed below the 3.3 Manual Override Shaft, then slide the clevis into the detent.

Standard: VERIFIED the clevis detent on the Actuator Shaft is exposed below the Manual Override Shaft, then SLID the clevis into the detent.

Examiner Cue: The clevis is engaged in the detent.

Comment: SAT UNSAT Page 4 of 6 SONGS NRC 2012 JPM P-1 Unit 2 Version 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 Coordinate with the CRS and 21 to manually Throttle 2HV-8419 as necessary to maintain required S/G pressure.

Standard: INFORMED the CRS 2HV-8419 is ready to be operated and OPERATED 2HV-8419 as directed by the CRS.

Examiner Cue: The CRS directs you to slowly open the ADV approximately 10%

open.

Terminating Cue: When the applicant has begun opening the ADV by turning the handwheel in the counterclockwise position, the JPM may be terminated.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 SONGS NRC 2012 JPM P-1 Unit 2 Version 2 Rev b.docb

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Both Units have been tripped due to toxic gas in the Control Room area.

• SO23-13-2, Shutdown From Outside the Control Room, has been initiated.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Transfer Atmospheric Dump Valve 2HV-8419 to Local Manual operation per SO23-13-2, Shutdown From Outside the Control Room, Attachment 23, Local Manual Operation of Atmospheric Dump Valves.

• You have retrieved the Safe Shutdown bag from the Safe Shutdown locker.

Page 6 of 6 SONGS NRC 2012 JPM P-1 Unit 2 Version 2 Rev b.docb

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM P-1 Task # 167206 K/A # 068 AA1.01 4.3 / 4.5 SF-4S

Title:

Manually Open an Atmospheric Dump Valve (HV-8419)

Examinee (Print):

Testing Method:

Simulated Performance: x Classroom:

Actual Performance: Simulator:

Alternate Path: Plant: x Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Both Units have been tripped due to toxic gas in the Control Room area.

• SO23-13-2, Shutdown From Outside the Control Room, has been initiated.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Transfer Atmospheric Dump Valve 3HV-8419 to Local Manual operation per SO23-13-2, Shutdown From Outside the Control Room, Attachment 23, Local Manual Operation of Atmospheric Dump Valves.

• You have retrieved the Safe Shutdown bag from the Safe Shutdown locker.

Task Standard: Locally OPENED the ADV per SO23-13-2, Shutdown From Outside the Control Room, Attachment 23, Local Manual Operation of Atmospheric Dump Valves.

Required Materials: SO23-13-2, Shutdown From Outside the Control Room, Attachment 23, Local Manual Operation of Atmospheric Dump Valves.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 6 SONGS NRC 2012 JPM P-1 Unit 3 Version 2 Rev b.docb

Appendix C JPM WORKSHEET Form ES-C-1 JPM SETUP EXAMINER:

PROVIDE the examinee with a copy of SO23-13-2, Shutdown From Outside the Control Room, Attachment 23, Local Manual Operation of Atmospheric Dump Valves.

Page 2 of 6 SONGS NRC 2012 JPM P-1 Unit 3 Version 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Establish communication with the cognizant CRS.

1.0 Standard

ESTABLISHED communication with the cognizant CRS on the sound powered phone or radio.

Examiner Cue: The CRS directs you to continue with the task.

Comment: SAT UNSAT Perform Step: 2 CLOSE S31301MU1304, 3HV-8419 Instrument Air Isolation Valve.

2.1 Standard

CLOSED S31301MU1304, 3HV-8419 Instrument Air Isolation Valve.

Examiner Cue: S31301MU1304 is in the fully clockwise position.

Comment: SAT UNSAT Perform Step: 3 CLOSE S31301MU1328, 3HV-8419 Nitrogen Isolation Valve.

2.2 Standard

CLOSED S31301MU1328, 3HV-8419 Nitrogen Isolation Valve.

Examiner Cue: S31301MU1328 is in the fully clockwise position.

Comment: SAT UNSAT Perform Step: 4 OPEN S31301MU1264, 3HV-8419 Positioner Equalizing Valve.

2.3 Standard

OPENED S31301MU1264, 3HV-8419 Positioner Equalizing Valve.

Examiner Cue: S31301MU1264 is in the fully counter-clockwise position.

Comment: SAT UNSAT Page 3 of 6 SONGS NRC 2012 JPM P-1 Unit 3 Version 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Unscrew the clevis from the Manual Override Shaft.

3.1 Standard

UNSCREWED the clevis from the Manual Override Shaft.

Examiner Cue: The clevis is removed from the Manual Override Shaft.

Comment: SAT UNSAT Perform Step: 6 Turn the Handwheel to the CLOSE (Clockwise) position until the clevis 3.2 detent on the Actuator Shaft is exposed.

Standard: TURNED the Handwheel to the CLOSE (Clockwise) position until the clevis detent on the Actuator Shaft is exposed.

Examiner Cue: The clevis detent is exposed.

Comment: SAT UNSAT Perform Step: 7 When the clevis detent on the Actuator Shaft is exposed below the 3.3 Manual Override Shaft, then slide the clevis into the detent.

Standard: VERIFIED the clevis detent on the Actuator Shaft is exposed below the Manual Override Shaft, then SLID the clevis into the detent.

Examiner Cue: The clevis is engaged in the detent.

Comment: SAT UNSAT Page 4 of 6 SONGS NRC 2012 JPM P-1 Unit 3 Version 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 Coordinate with the CRS and 31 to manually Throttle 3HV-8419 as 4.0 necessary to maintain required S/G pressure.

Standard: INFORMED the CRS 3HV-8419 is ready to be operated and OPERATED 3HV-8419 as directed by the CRS.

Examiner Cue: The CRS directs you to slowly open the ADV approximately 10%

open.

Terminating Cue: When the applicant has begun opening the ADV by turning the handwheel in the counterclockwise position, the JPM may be terminated.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 SONGS NRC 2012 JPM P-1 Unit 3 Version 2 Rev b.docb

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Both Units have been tripped due to toxic gas in the Control Room area.

• SO23-13-2, Shutdown From Outside the Control Room, has been initiated.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Transfer Atmospheric Dump Valve 3HV-8419 to Local Manual operation per SO23-13-2, Shutdown From Outside the Control Room, Attachment 23, Local Manual Operation of Atmospheric Dump Valves.

• You have retrieved the Safe Shutdown bag from the Safe Shutdown locker.

Page 6 of 6 SONGS NRC 2012 JPM P-1 Unit 3 Version 2 Rev b.docb

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM P-2 Task # 192837 K/A # 068 AA1.31 3.9 / 4.0 SF-6

Title:

Verify Proper Operation of the Emergency Diesel Generator (Unit 2)

Examinee (Print):

Testing Method:

Simulated Performance: x Classroom:

Actual Performance: Simulator:

Alternate Path: x Plant: x Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Both Units have been tripped due to an Operating Basis Earthquake and a Loss of Offsite Power.

• Both Unit 2 Emergency Diesel Generators (EDGs) have started and loaded onto their respective buses.

• A toxic gas leak has forced an evacuation of the Control Room.

• SO23-13-2, Shutdown From Outside the Control Room, has been initiated.

• You have obtained SSD KIT 23.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• ENSURE proper operation of the Unit 2 Train A EDG per SO23-13-2, Shutdown From Outside the Control Room, Attachment 8, 23 Duties..

• Start at step 3.0.

Task Standard: ALIGNED firewater cooling to the Unit 2 Train A EDG per SO23-13-2, Shutdown From Outside the Control Room, Attachment 8, 23 Duties.

Required Materials: SO23-13-2, Shutdown From Outside the Control Room, Attachment 8, 23 Duties.

Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 SONGS NRC 2012 JPM P-2 Unit 2 Rev b.docb

Appendix C JPM WORKSHEET Form ES-C-1 JPM SETUP EXAMINER:

PROVIDE the examinee with a copy of SO23-13-2, Shutdown From Outside the Control Room, Attachment 8, 23 Duties.

Page 2 of 7 SONGS NRC 2012 JPM P-2 Unit 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Connect Headset to CKT No. 1 jack in the west lobby area.

3.1 Standard

CONNECTED Headset to CKT No. 1 jack in the west lobby area.

Comment: SAT UNSAT Perform Step: 2 SELECT all three (3) of the following 2G-002 Equipment Fire Isolation 3.2.1, 3.2.2, 3.2.3 Switches to LOCAL on 2L-160:

• Fire Iso. Switch D/G Control. (2HS-1670A1)

• Fire Iso. Switch Gov. & Exct. Cont. (2HS-1669A1)

• Fire Iso. Switch D/G Bldg. Fans. (2HS-9537E1)

Standard: SELECTED 2HS-1670A1, 2HS-1669A1 and 2HS-9537E1 to LOCAL on 2L-160.

Examiner Cue: Handswitches 2HS-1670A1, 2HS-1669A1 and 2HS-9537E1 are in LOCAL.

Comment: SAT UNSAT Examiner Note: The following steps represent the alternate path portion of the JPM.

Perform Step: 3 Determine whether 2G-002 Cooling Water System has been impaired, 3.2.4.1 as indicated by presence of either of the following alarms:

• "HI-HI COOLANT TEMPERATURE ENGINE #1"

• "HI-HI COOLANT TEMPERATURE ENGINE #2" Standard: IDENTIFIED both annunciators in alarm.

Examiner Cue: You hear an audible alarm and HI-HI COOLANT TEMPERATURE ENGINE #1 and #2 annunciators are fast flashing.

Comment: SAT UNSAT Page 3 of 7 SONGS NRC 2012 JPM P-2 Unit 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 IF either of Step 3.2.4.1 alarms are present, THEN align Firewater 3.2.4.2.1 Makeup to D/G 2G-002 Coolant Expansion Tanks, as follows:

• OPEN S22420MR032, DG G002 ENG #2 (20 CYL) Coolant Expansion Tank T162 Fire Water Emergency Makeup Valve (north side of engine, below grating).

Standard: OPENED S22420MR032, DG G002 ENG #2 (20 CYL) Coolant Expansion Tank T162 Fire Water Emergency Makeup Valve (north side of engine, below grating).

Examiner Cue: S22420MR032 is in its fully counter-clockwise position.

Comment: SAT UNSAT Perform Step: 5 IF either of Step 3.2.4.1 alarms are present, THEN align Firewater 3.2.4.2.2 Makeup to D/G 2G-002 Coolant Expansion Tanks, as follows:

• OPEN S22420MR025, DG G002 ENG #1 (16 CYL) Coolant Expansion Tank T190 Fire Water Emergency Makeup Valve (north side of engine, below grating).

Standard: OPENED S22420MR025, DG G002 ENG #1 (16 CYL) Coolant Expansion Tank T190 Fire Water Emergency Makeup Valve (north side of engine, below grating).

Examiner Cue: S22420MR025 is in its fully counter-clockwise position.

Comment: SAT UNSAT Perform Step: 6 IF either of Step 3.2.4.1 alarms are present, THEN align Firewater 3.2.4.2.3 Makeup to D/G 2G-002 Coolant Expansion Tanks, as follows:

• OPEN S22301MU586, Firewater Makeup to 2G-002 (northwest corner, near Fuel Oil Day Tank).

Standard: OPENED S22301MU586, Firewater Makeup to 2G-002 (northwest corner, near Fuel Oil Day Tank).

Examiner Cue: S22301MU586 is in its fully counter-clockwise position.

Comment: SAT UNSAT Page 4 of 7 SONGS NRC 2012 JPM P-2 Unit 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 SELECT the Diesel Generator Control Panel Ammeter to 1, 2, or 3.

3.2.4.3 Standard: ENSURED the Diesel Generator Control Panel Ammeter selected to 1, 2, or 3 Comment: SAT UNSAT Perform Step: 8 SELECT the Diesel Generator Control Panel voltmeter to 1-2, 2-3, or 3-3.2.4.4 1.

Standard: ENSURED the Diesel Generator Control Panel voltmeter selected to 1-2, 2-3, or 3-1.

Comment: SAT UNSAT Perform Step: 9 ENSURE the Diesel Generator Lockout Relay is reset (2HS-E934; 3.2.4.5 Reset Lamp 2ZL-E906 illuminated).

Standard: IDENTIFIED the Diesel Generator Lockout Relay is reset by observing Reset Lamp 2ZL-E906 illuminated.

Examiner Cue: If the Reset Lamp is extinguished, The Reset Lamp is illuminated.

If the Reset Lamp is illuminated, The Reset Lamp is as you see it.

Comment: SAT UNSAT Perform Step: 10 Establish Communications with, and notify the 22 that 2G-002 is ready 3.2.4.6 to start. (Mark N/A if EDG is already running.)

Standard: MARKED step N/A due to the EDG already running (from the initial conditions)

Comment: SAT UNSAT Perform Step: 11 If the EDG is NOT supplying the Bus and will NOT be supplying the Bus, 3.2.4.7 then DEPRESS Idle Speed on (2HS-1701A). (Mark N/A if EDG is or will be supplying Bus A04.)

Standard: MARKED step N/A due to the EDG already loaded onto the bus (from the initial conditions)

Comment: SAT UNSAT Page 5 of 7 SONGS NRC 2012 JPM P-2 Unit 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 12 WHEN directed by the 22, THEN Start 2G-002 by momentarily placing 3.2.4.8 the Local Engine Control Switch to START (2HS-5995-1). (Mark N/A if EDG is already running.)

Standard: MARKED step N/A due to the EDG already running (from the initial conditions)

Comment: SAT UNSAT Perform Step: 13 IF 2G-002 will not start, THEN notify the 22 and the Unit 2 CRS, 3.2.4.9 terminate this attachment, AND initiate Attachment 25. (Mark N/A if 2G-002 starts or is already running.)

Standard: MARKED step N/A due to the EDG already running (from the initial conditions)

Comment: SAT UNSAT Perform Step: 14 If "HI-HI COOLANT TEMPERATURE ENGINE #1" or "HI-HI COOLANT 3.2.4.10 TEMPERATURE ENGINE #2" is in Alarm, then OPEN S22301MU587, Firewater Makeup to 2G-002. (northwest corner, near Fuel Oil Day Tank). [Mark N/A if "Hi-Hi Coolant Temp." NOT in Alarm]

Standard: OPENED S22301MU587, Firewater Makeup to 2G-002. (northwest corner, near Fuel Oil Day Tank).

Examiner Cue: If applicant checks to see if the listed alarms are still in, Hi-Hi Coolant Temperature Engine #1 and #2 alarms are still locked in.

Terminating Cue: S22301MU587 is in its fully counter-clockwise position. This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 SONGS NRC 2012 JPM P-2 Unit 2 Rev b.docb

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Both Units have been tripped due to an Operating Basis Earthquake and a Loss of Offsite Power.

• Both Unit 2 Emergency Diesel Generators (EDGs) have started and loaded onto their respective buses.

• A toxic gas leak has forced an evacuation of the Control Room.

• SO23-13-2, Shutdown From Outside the Control Room, has been initiated.

• You have obtained SSD KIT 23.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• ENSURE proper operation of the Unit 2 Train A EDG per SO23-13-2, Shutdown From Outside the Control Room, Attachment 8, 23 Duties..

• Start at step 3.0.

Page 7 of 7 SONGS NRC 2012 JPM P-2 Unit 2 Rev b.docb

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM P-2 Task # 192837 K/A # 068 AA1.31 3.9 / 4.0 SF-6

Title:

Locally Start an Emergency Diesel Generator (Unit 3)

Examinee (Print):

Testing Method:

Simulated Performance: x Classroom:

Actual Performance: Simulator:

Alternate Path: x Plant: x Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Both Units have been tripped due to an Operating Basis Earthquake and a Loss of Offsite Power.

• Both Unit 3 Emergency Diesel Generators (EDGs) have started and loaded onto their respective buses.

• A toxic gas leak has forced an evacuation of the Control Room.

• SO23-13-2, Shutdown From Outside the Control Room, has been initiated.

• You have obtained SSD KIT 33.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• ENSURE proper operation of the Unit 3 Train A EDG per SO23-13-2, Shutdown From Outside the Control Room, Attachment 9, 33 Duties..

• Start at step 3.0.

Task Standard: ALIGNED firewater cooling to the Unit 3 Train A EDG per SO23-13-2, Shutdown From Outside the Control Room, Attachment 9, 33 Duties.

Required Materials: SO23-13-2, Shutdown From Outside the Control Room, Attachment 9, 33 Duties.

Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 SONGS NRC 2012 JPM P-2 Unit 3 Rev b.docb

Appendix C JPM WORKSHEET Form ES-C-1 JPM SETUP EXAMINER:

PROVIDE the examinee with a copy of SO23-13-2, Shutdown From Outside the Control Room, Attachment 9, 33 Duties.

Page 2 of 7 SONGS NRC 2012 JPM P-2 Unit 3 Rev b.docb

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Connect Headset to CKT No. 1 jack in the west lobby area.

3.1 Standard

CONNECTED Headset to CKT No. 1 jack in the west lobby area.

Comment: SAT UNSAT Perform Step: 2 SELECT all three (3) of the following 3G-002 Equipment Fire Isolation 3.2.1, 3.2.2, 3.2.3 Switches to LOCAL on 3L-160:

• Fire Iso. Switch D/G Control. (3HS-1670A1)

• Fire Iso. Switch Gov. & Exct. Cont. (3HS-1669A1)

• Fire Iso. Switch D/G Bldg. Fans. (3HS-9537E1)

Standard: SELECTED 3HS-1670A1, 3HS-1669A1 and 3HS-9537E1 to LOCAL on 3L-160.

Examiner Cue: Handswitches 3HS-1670A1, 3HS-1669A1 and 3HS-9537E1 are in LOCAL.

Comment: SAT UNSAT Examiner Note: The following steps represent the alternate path portion of the JPM.

Perform Step: 3 Determine whether 3G-002 Cooling Water System has been impaired, 3.2.4.1 as indicated by presence of either of the following alarms:

• "HI-HI COOLANT TEMPERATURE ENGINE #1"

• "HI-HI COOLANT TEMPERATURE ENGINE #2" Standard: IDENTIFIED both annunciators in alarm.

Examiner Cue: You hear an audible alarm and HI-HI COOLANT TEMPERATURE ENGINE #1 and #2 annunciators are fast flashing.

Comment: SAT UNSAT Page 3 of 7 SONGS NRC 2012 JPM P-2 Unit 3 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 IF either of Step 3.2.4.1 alarms are present, THEN align Firewater 3.2.4.2.1 Makeup to D/G 3G-002 Coolant Expansion Tanks, as follows:

• OPEN S32420MR032, DG G002 ENG #2 (20 CYL) Coolant Expansion Tank T162 Fire Water Emergency Makeup Valve (north side of engine, below grating).

Standard: OPENED S32420MR032, DG G002 ENG #2 (20 CYL) Coolant Expansion Tank T162 Fire Water Emergency Makeup Valve (north side of engine, below grating).

Comment: SAT UNSAT Perform Step: 5 IF either of Step 3.2.4.1 alarms are present, THEN align Firewater 3.2.4.2.2 Makeup to D/G 3G-002 Coolant Expansion Tanks, as follows:

• OPEN S32420MR025, DG G002 ENG #1 (16 CYL) Coolant Expansion Tank T190 Fire Water Emergency Makeup Valve (north side of engine, below grating).

Standard: OPENED S32420MR025, DG G002 ENG #1 (16 CYL) Coolant Expansion Tank T190 Fire Water Emergency Makeup Valve (north side of engine, below grating).

Examiner Cue: S32420MR025 is in its fully counter-clockwise position.

Comment: SAT UNSAT Perform Step: 6 IF either of Step 3.2.4.1 alarms are present, THEN align Firewater 3.2.4.2.3 Makeup to D/G 3G-002 Coolant Expansion Tanks, as follows:

• OPEN S32301MU586, Firewater Makeup to 3G-002 (northwest corner, near Fuel Oil Day Tank).

Standard: OPENED S32301MU586, Firewater Makeup to 2G-002 (northwest corner, near Fuel Oil Day Tank).

Examiner Cue: S32301MU586 is in its fully counter-clockwise position.

Comment: SAT UNSAT Page 4 of 7 SONGS NRC 2012 JPM P-2 Unit 3 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 SELECT the Diesel Generator Control Panel Ammeter to 1, 2, or 3.

3.2.4.3 Standard: ENSURED the Diesel Generator Control Panel Ammeter selected to 1, 2, or 3 Comment: SAT UNSAT Perform Step: 8 SELECT the Diesel Generator Control Panel voltmeter to 1-2, 2-3, or 3-3.2.4.4 1.

Standard: ENSURED the Diesel Generator Control Panel voltmeter selected to 1-2, 2-3, or 3-1.

Comment: SAT UNSAT Perform Step: 9 ENSURE the Diesel Generator Lockout Relay is reset (3HS-E934; 3.2.4.5 Reset Lamp 3ZL-E906 illuminated).

Standard: IDENTIFIED the Diesel Generator Lockout Relay is reset by observing Reset Lamp 3ZL-E906 extinguished.

Examiner Cue: If the Reset Lamp is extinguished, The Reset Lamp is illuminated.

If the Reset Lamp is illuminated, The Reset Lamp is as you see it.

Comment: SAT UNSAT Perform Step: 10 Establish Communications with, and notify the 32 that 3G-002 is ready 3.2.4.6 to start. (Mark N/A if EDG is already running.)

Standard: MARKED step N/A due to the EDG already running (from the initial conditions)

Comment: SAT UNSAT Perform Step: 11 If the EDG is NOT supplying the Bus and will NOT be supplying the Bus, 3.2.4.7 then DEPRESS Idle Speed on (3HS-1701A). (Mark N/A if EDG is or will be supplying Bus A04.)

Standard: MARKED step N/A due to the EDG already loaded onto the bus (from the initial conditions)

Comment: SAT UNSAT Page 5 of 7 SONGS NRC 2012 JPM P-2 Unit 3 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 12 WHEN directed by the 32, THEN Start 3G-002 by momentarily placing 3.2.4.8 the Local Engine Control Switch to START (3HS-5995-1). (Mark N/A if EDG is already running.)

Standard: MARKED step N/A due to the EDG already running (from the initial conditions)

Comment: SAT UNSAT Perform Step: 13 IF 3G-002 will not start, THEN notify the 32 and the Unit 3 CRS, 3.2.4.9 terminate this attachment, AND initiate Attachment 25. (Mark N/A if 3G-002 starts or is already running.)

Standard: MARKED step N/A due to the EDG already running (from the initial conditions)

Comment: SAT UNSAT Perform Step: 14 If "HI-HI COOLANT TEMPERATURE ENGINE #1" or "HI-HI COOLANT 3.2.4.10 TEMPERATURE ENGINE #2" is in Alarm, then OPEN S32301MU587, Firewater Makeup to 3G-002. (northwest corner, near Fuel Oil Day Tank). [Mark N/A if "Hi-Hi Coolant Temp." NOT in Alarm]

Standard: OPENED S32301MU587, Firewater Makeup to 3G-002. (northwest corner, near Fuel Oil Day Tank).

Examiner Cue: If applicant checks to see if the listed alarms are still in, Hi-Hi Coolant Temperature Engine #1 and #2 alarms are still locked in.

Terminating Cue: S32301MU587 is in its fully counter-clockwise position. This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 SONGS NRC 2012 JPM P-2 Unit 3 Rev b.docb

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Both Units have been tripped due to an Operating Basis Earthquake and a Loss of Offsite Power.

• Both Unit 3 Emergency Diesel Generators (EDGs) have started and loaded onto their respective buses.

• A toxic gas leak has forced an evacuation of the Control Room.

• SO23-13-2, Shutdown From Outside the Control Room, has been initiated.

• You have obtained SSD KIT 33.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• ENSURE proper operation of the Unit 3 Train A EDG per SO23-13-2, Shutdown From Outside the Control Room, Attachment 9, 33 Duties..

• Start at step 3.0.

Page 7 of 7 SONGS NRC 2012 JPM P-2 Unit 3 Rev b.docb

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM P-3 Task # 191346 K/A # 005 AA1.01 3.6 / 3.4 SF-1

Title:

Place CEA Subgroup on the Hold Bus Examinee (Print):

Testing Method:

Simulated Performance: x Classroom:

Actual Performance: Simulator:

Alternate Path: Plant: x Time Critical: x READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 2 is operating at full power.

• Annunciator window 50A40, CEDMCS Timer Failure, has just alarmed.

• 50A40, CEDMCS Time Failure, is in solid.

• I&C is NOT on station.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Go to the Unit 2 CEDMCS Room and perform the actions of SO23 50.A2, 50A40, CEDMCS Timer Failure.

• This is a time critical JPM.

Task Standard:

• TRANSFERRED CEA subgroup 11 to the hold bus within 15 minutes per SO23-15-50.A2, 50A40, CEDMCS Timer Failure.

Required Materials: SO23-15-50.A2, 50A40, CEDMCS Timer Failure.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 SONGS NRC 2012 JPM P-3 Unit 2 Rev b.docb

Appendix C JPM WORKSHEET Form ES-C-1 JPM Setup EXAMINER:

When the applicant has arrived in the CEDMCS room and identified the posted laminated copy of ARP 50A40, PROVIDE the examinee with a paper copy of SO23 50.A2, 50A40, CEDMCS Timer Failure.

Page 2 of 7 SONGS NRC 2012 JPM P-3 Unit 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: When the applicant enters the CEDMCS Room and looks at the Timer Failure Alarm Lamps, DISPLAY Picture # 1.

Perform Step: 1 VERIFY alarm is in solid. If alarm resets during performance of the 1.1 following steps, then GO TO Section 3.0 Standard: VERIFIED alarm is in solid (from initial conditions).

Examiner Cue: If the applicant calls the Control Room to verify 50A40 is still in solid, inform them that 50A40, CEDMCS Timer Failure, is in solid.

Comment: SAT UNSAT Perform Step: 2 If while on station for testing, I&C reports that Coil Voltages are normal, 1.1.1 then GO TO Section 4.0 Standard: READ step and proceeded with the procedure.

Comment: SAT UNSAT Perform Step: 3 Dispatch an Operator to the CEDMCS Room 37 foot Radwaste Building 1.2 to check local indications at the CEDMCS Panel.

Standard: RECOGNIZED that they are the Operator who was dispatched to the CEDMCS Room by the Control Room.

Comment: SAT UNSAT Page 3 of 7 SONGS NRC 2012 JPM P-3 Unit 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 If there is more than one subgroup associated with the same hold bus 1.2.1 timer failure or the holding bus is NOT available for the failed subgroup(s), then trip the Reactor and GO TO SO23-12-1, Standard Post Trip Actions Standard: IDENTIFIED only Subgroup 11 is affected and a Reactor trip is NOT required.

Examiner Note: When the applicant looks at Subgroup Maintenance Lights, DISPLAY Picture # 1.

Comment: SAT UNSAT Perform Step: 5 If actions to complete transferring all the affected CEAs to the hold bus 1.2.2 will not be performed within 15 minutes of this alarm being in solid, then trip the Reactor and GO TO SO23-12-1, Standard Post Trip Actions.

Standard: READ the step and continued with the procedure.

Comment: SAT UNSAT Perform Step: 6 If NO lamp is illuminated, then perform a lamp test and replace burnt out 1.2.3 bulbs (use nearby working light bulbs for a quick check).

Standard: IDENTIFIED CEA 47 lamp is illuminated Examiner Note: When the applicant looks at the Timer Failure Alarm Lamps, DISPLAY Picture # 1.

Comment: SAT UNSAT Perform Step: 7 VERIFY the Holding Bus is available as indicated by the following lamps 1.3 extinguished (on appropriate Maintenance Supply Lamp Panel):

• HOLDING BUS FAILURE

• SUBGROUP MAINTENANCE Standard: OBSERVES HOLDING BUS FAILURE and SUBGROUP MAINTENANCE lamps extinguished on Maintenance Supply Lamp Panel.

Examiner Note: When the applicant looks at the Subgroup Maintenance Lights, DISPLAY Picture # 1.

Comment: SAT UNSAT Page 4 of 7 SONGS NRC 2012 JPM P-3 Unit 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 DETERMINE CEA(s) affected by observing the CEA Timer Failure 1.3.1 Alarm lamps.

Standard: OBSERVED CEA 47 lamp is illuminated.

Examiner Note: When the applicant looks at the Timer Failure Alarm Lamps, DISPLAY Picture # 1.

Comment: SAT UNSAT Perform Step: 9 If a HOLDING BUS FAILURE or SUBGROUP MAINTENANCE lamp is 1.3.2 illuminated (bus not available), then notify the Control Room to TRIP the Reactor and GO TO SO23-12-1, Standard Post Trip Actions.

Standard: OBSERVES HOLDING BUS FAILURE and SUBGROUP MAINTENANCE lamps are still extinguished Examiner Note: When applicant looks at the listed lamps, DISPLAY Picture # 1.

Comment: SAT UNSAT Perform Step: 10 NOTIFY the Control Room that the Holding Bus Failure lamp is 1.3.3 EXTINGUISHED and the affected Subgroup is ready to be place on the Holding Bus.

Standard: INFORMED the Control Room that CEA is ready to be placed on the Holding Bus.

Examiner Cue: When the applicant calls the Control Room, acknowledge the information.

Comment: SAT UNSAT Perform Step: 11 SELECT the Subgroup Maintenance switch to the UP position for the 1.3.4 affected subgroup (subgroup 11).

Standard: SELECTED the Subgroup Maintenance switch to the UP position for the affected subgroup (subgroup 11).

Examiner Note: When the applicant simulates placing the Subgroup 11 Subgroup Maintenance switch to the UP position, DISPLAY Picture # 2.

Comment: SAT UNSAT Page 5 of 7 SONGS NRC 2012 JPM P-3 Unit 2 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 12 VERIFY the Subgroup Maintenance lamp ILLUMINATES.

1.3.5 Standard

VERIFIED the Subgroup Maintenance lamp ILLUMINATED.

Comment: SAT UNSAT Examiner Note: When the applicant simulates opening the ACTM Card Panel Door, DISPLAY Picture # 3.

Perform Step: 13 ACTUATE the MAN TRANS switch on the respective ACTM.

1.3.6 Standard

ACTUATED the MAN TRANS switch on the CEA 47 ACTM.

Examiner Cue: When the applicant simulates actuating the MAN TRANS switch for CEA 47, The Manual Transfer switch has spring returned to its original position. The ACTM Card lights are as you see them.

Comment: SAT UNSAT Perform Step: 14 OPEN the circuit breaker(s) to the CEAs that have their CEA Timer 1.3.7 Failure Alarm Lamps illuminated.

Standard: OPENED the CEA 47 individual disconnect circuit breaker.

Terminating Cue: The breaker for CEA 47 is open. This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 SONGS NRC 2012 JPM P-3 Unit 2 Rev b.docb

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Unit 2 is operating at full power.

• Annunciator window 50A40, CEDMCS Timer Failure, has just alarmed.

• 50A40, CEDMCS Time Failure, is in solid.

• I&C is NOT on station.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Go to the Unit 2 CEDMCS Room and perform the actions of SO23 50.A2, 50A40, CEDMCS Timer Failure.

• This is a time critical JPM.

Page 7 of 7 SONGS NRC 2012 JPM P-3 Unit 2 Rev b.docb

Appendix C JPM WORKSHEET Form ES-C-1 Facility: SONGS JPM # NRC JPM P-3 Task # 191346 K/A # 005 AA1.01 3.6 / 3.4 SF-1

Title:

Place CEA Subgroup on the Hold Bus Examinee (Print):

Testing Method:

Simulated Performance: x Classroom:

Actual Performance: Simulator:

Alternate Path: Plant: x Time Critical: x READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 3 is operating at full power.

• Annunciator window 50A40, CEDMCS Timer Failure, has just alarmed.

• 50A40, CEDMCS Time Failure, is in solid.

• I&C is NOT on station.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Go to the Unit 3 CEDMCS Room and perform the actions of SO23 50.A2, 50A40, CEDMCS Timer Failure.

• This is a time critical JPM.

Task Standard:

• TRANSFERRED CEA subgroup 11 to the hold bus within 15 minutes per SO23-15-50.A2, 50A40, CEDMCS Timer Failure.

Required Materials: SO23-15-50.A2, 50A40, CEDMCS Timer Failure.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 SONGS NRC 2012 JPM P-3 Unit 3 Rev b.docb

Appendix C JPM WORKSHEET Form ES-C-1 JPM Setup EXAMINER:

When the applicant has arrived in the CEDMCS room and identified the posted laminated copy of ARP 50A40, PROVIDE the examinee with a paper copy of SO23 50.A2, 50A40, CEDMCS Timer Failure.

Page 2 of 7 SONGS NRC 2012 JPM P-3 Unit 3 Rev b.docb

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: When the applicant enters the CEDMCS Room and looks at the Timer Failure Alarm Lamps, DISPLAY Picture #1.

Perform Step: 1 VERIFY alarm is in solid. If alarm resets during performance of the 1.1 following steps, then GO TO Section 3.0 Standard: VERIFIED alarm is in solid (from initial conditions).

Examiner Cue: If the applicant calls the Control Room to verify 50A40 is still in solid, inform them that 50A40, CEDMCS Timer Failure, is in solid.

Comment: SAT UNSAT Perform Step: 2 If while on station for testing, I&C reports that Coil Voltages are normal, 1.1.1 then GO TO Section 4.0 Standard: READ step and proceeded with the procedure.

Comment: SAT UNSAT Perform Step: 3 Dispatch an Operator to the CEDMCS Room 37 foot Radwaste Building 1.2 to check local indications at the CEDMCS Panel.

Standard: RECOGNIZED that they are the Operator who was dispatched to the CEDMCS Room by the Control Room.

Comment: SAT UNSAT Page 3 of 7 SONGS NRC 2012 JPM P-3 Unit 3 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 If there is more than one subgroup associated with the same hold bus 1.2.1 timer failure or the holding bus is NOT available for the failed subgroup(s), then trip the Reactor and GO TO SO23-12-1, Standard Post Trip Actions Standard: IDENTIFIED only Subgroup 11 is affected and a Reactor trip is NOT required.

Examiner Note: When the applicant looks at Subgroup Maintenance Lights, DISPLAY Picture # 1.

Comment: SAT UNSAT Perform Step: 5 If actions to complete transferring all the affected CEAs to the hold bus 1.2.2 will not be performed within 15 minutes of this alarm being in solid, then trip the Reactor and GO TO SO23-12-1, Standard Post Trip Actions.

Standard: READ the step and continued with the procedure.

Comment: SAT UNSAT Perform Step: 6 If NO lamp is illuminated, then perform a lamp test and replace burnt out 1.2.3 bulbs (use nearby working light bulbs for a quick check).

Standard: IDENTIFIED CEA 47 lamp is illuminated Examiner Note: When the applicant looks at the Timer Failure Alarm Lamps, DISPLAY Picture # 1.

Comment: SAT UNSAT Perform Step: 7 VERIFY the Holding Bus is available as indicated by the following lamps 1.3 extinguished (on appropriate Maintenance Supply Lamp Panel):

• HOLDING BUS FAILURE

• SUBGROUP MAINTENANCE Standard: OBSERVES HOLDING BUS FAILURE and SUBGROUP MAINTENANCE lamps extinguished on Maintenance Supply Lamp Panel.

Examiner Note: When the applicant looks at the Subgroup Maintenance Lights, DISPLAY Picture # 1.

Comment: SAT UNSAT Page 4 of 7 SONGS NRC 2012 JPM P-3 Unit 3 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 DETERMINE CEA(s) affected by observing the CEA Timer Failure 1.3.1 Alarm lamps.

Standard: OBSERVED CEA 47 lamp is illuminated.

Examiner Note: When the applicant looks at the Timer Failure Alarm Lamps, DISPLAY Picture # 1.

Comment: SAT UNSAT Perform Step: 9 If a HOLDING BUS FAILURE or SUBGROUP MAINTENANCE lamp is 1.3.2 illuminated (bus not available), then notify the Control Room to TRIP the Reactor and GO TO SO23-12-1, Standard Post Trip Actions.

Standard: OBSERVES HOLDING BUS FAILURE and SUBGROUP MAINTENANCE lamps are still extinguished Examiner Note: When applicant looks at the listed lamps, DISPLAY Picture # 1.

Comment: SAT UNSAT Perform Step: 10 NOTIFY the Control Room that the Holding Bus Failure lamp is 1.3.3 EXTINGUISHED and the affected Subgroup is ready to be place on the Holding Bus.

Standard: INFORMED the Control Room that CEA is ready to be placed on the Holding Bus.

Examiner Cue: When the applicant calls the Control Room, acknowledge the information.

Comment: SAT UNSAT Perform Step: 11 SELECT the Subgroup Maintenance switch to the UP position for the 1.3.4 affected subgroup (subgroup 11).

Standard: SELECTED the Subgroup Maintenance switch to the UP position for the affected subgroup (subgroup 11).

Examiner Note: When the applicant simulates placing the Subgroup 11 Subgroup Maintenance switch to the UP position, DISPLAY Picture # 2.

Comment: SAT UNSAT Page 5 of 7 SONGS NRC 2012 JPM P-3 Unit 3 Rev b.docb

Appendix C JPM STEPS Form ES-C-1 Perform Step: 12 VERIFY the Subgroup Maintenance lamp ILLUMINATES.

1.3.5 Standard

VERIFIED the Subgroup Maintenance lamp ILLUMINATED.

Comment: SAT UNSAT Examiner Note: When the applicant simulates opening the ACTM Card Panel Door, DISPLAY Picture # 3.

Perform Step: 13 ACTUATE the MAN TRANS switch on the respective ACTM.

1.3.6 Standard

ACTUATED the MAN TRANS switch on the CEA 47 ACTM.

Examiner Cue: When the applicant simulates actuating the MAN TRANS switch for CEA 47, The Manual Transfer switch has spring returned to its original position. The ACTM Card lights are as you see them.

Comment: SAT UNSAT Perform Step: 14 OPEN the circuit breaker(s) to the CEAs that have their CEA Timer 1.3.7 Failure Alarm Lamps illuminated.

Standard: OPENED the CEA 47 individual disconnect circuit breaker.

Terminating Cue: The breaker for CEA 47 is open. This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 SONGS NRC 2012 JPM P-3 Unit 3 Rev b.docb

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

• Unit 3 is operating at full power.

• Annunciator window 50A40, CEDMCS Timer Failure, has just alarmed.

• 50A40, CEDMCS Time Failure, is in solid.

• I&C is NOT on station.

Initiating Cue: The Control Room Supervisor directs you to PERFORM the following:

• Go to the Unit 3 CEDMCS Room and perform the actions of SO23 50.A2, 50A40, CEDMCS Timer Failure.

• This is a time critical JPM.

Page 7 of 7 SONGS NRC 2012 JPM P-3 Unit 3 Rev b.docb

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 & 3 Scenario No.: 1 Op Test No.: October 2012 NRC Examiners: Operators:

Initial Conditions: 100% power MOC. Train B LPSI Pump P-016 is OOS.

Turnover: Maintain steady state conditions.

Critical Tasks:

• Restore Feedwater to both Steam Generators prior to exiting SO23-12-1, Standard Post Trip Actions.

• Restore power to a 1E 4kV bus following a Station Blackout prior to battery depletion and loss of associated 1E 125 DC bus.

• Establish SI flow following the restoration of 1E 4kV power prior to exiting SO23-12-9, Functional Recovery.

Event No. Malf. Event Type* Event Description No.

1 (10 min) RM06 TS (SRO) Containment High Range Area Radiation Monitor RI-7820-1 Fails High 2 (15 min) NSW LP C (BOP, SRO) Nuclear Service Water Pump P-139 O/C Trip, P-138 Fails to Auto Start 3 (25 min) RC03 C (RO, SRO) Reactor Coolant System Leak (30 GPM)

TS (SRO) 4 (45 min) R (RO, BOP, SRO) Rapid Power Reduction due to RCS Leak 5 (50 min) ED04A C (RO) Non-1E 4kV Bus 2A03 O/C Trip 6 (50 min) RC03 M (RO, BOP, SRO) RCS Leak Increases to 300 GPM on Reactor Trip 7 (50 min) PG24 C (RO, BOP, SRO) Loss of Offsite Power upon Reactor Trip (10 second time delay) 8 (50 min) AFW LP C (RO, SRO) AFW Pump P-140 Fails to Start on EFAS 9 (55 min) EG08A C (BOP, SRO) Train A EDG Fails to Start (cannot be started from CR) 10 (55 min) EG16B C (BOP, SRO) Train B EDG Output Breaker Fails to Auto Close 11 (55 min) ED03B M (RO, BOP, SRO) Train B EDG Output Breaker O/C Trip (60 seconds after EDG Output Breaker is manually closed - Station Blackout)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 9 Total malfunctions (5-8) 5 Malfunctions after EOP entry (1-2) 4 Abnormal events (2-4) 2 Major transients (1-2) 2 EOPs entered/requiring substantive actions (1-2) 1 EOP contingencies requiring substantive actions (0-2) 3 Critical tasks (2-3)

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Scenario Event Description NRC Scenario #1 SCENARIO

SUMMARY

NRC #1 The crew will take the watch at 100% power with no scheduled activities per SO23-5-1.7, Power Operations.

Upon taking the watch, Containment High Range Area Radiation Monitor RI-7820-1 will fail high. The crew will respond using the Alarm Response Procedure and validate the high radiation indication using alternate Containment radiation monitors. The crew should determine RI-7820-1 has failed high and the SRO will refer to Technical Specifications.

Following the Technical Specification review, the running Nuclear Service Water Pump will trip on overcurrent and the standby pump will fail to auto start. The crew will either start the standby pump using prompt and prudent actions or refer to the Alarm Response Procedure and start the standby pump per the ARP.

When the standby NSW Pump is started, a 30 GPM RCS leak will occur. The crew will respond per SO23-13-14, RCS Leak. The crew will identify leakage is greater than 25 GPM and commence a rapid down power per SO23-13-28, Rapid Power Reduction. The CRS will refer to Technical Specifications due to excess RCS leakage.

When power has been lowered 3-5%, Non-1E 4kV Bus 2A03 will trip on overcurrent requiring a Reactor trip.

When the Reactor is tripped, the RCS leak will increase to 300 GPM and a Loss of Offsite Power will occur. Both 1E 4kV buses will be deenergized. Train A 1E 4kV bus will remain deenergized due to a mechanical fault on the Train A EDG. The BOP will place the EDG in Maintenance Lockout per SPTA RNO direction. Train B 1E 4kV bus can be reenergized by manually closing the EDG output breaker.

One minute after closing the Train B EDG output breaker, the Train B 1E 4kV bus will trip on overcurrent resulting in a Station Blackout. Additionally, Turbine Driven AFW Pump P-140 will fail to start on EFAS and must be manually started to restore feedwater flow to the Steam Generators.

The crew will perform SO23-12-1, Standard Post Trip Actions and transition to SO23-12-9, Functional Recovery due to the Loss of Coolant Accident and Station Blackout. The scenario is terminated when power is restored to the Train A 1E 4kV bus and HPSI flow is established.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Scenario Event Description NRC Scenario #1 Risk Significance:

• Failure of risk important system prior to trip: Reactor Coolant Leak Loss of 4kV Bus 2A03

• Risk significant core damage sequence: Loss of Coolant Accident Station Blackout Loss of Feedwater

• Risk significant operator actions: Start TDAFW Pump P-140 following EFAS Restore Power to a 1E 4kV Bus Establish HPSI flow SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Scenario Event Description NRC Scenario #1 MACHINE OPERATOR INSTRUCTIONS for SIMULATOR SETUP INITIALIZE to IC-215 NRC Scenario #1 and run associated Setup File.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER SETUP MALF EG08A 2G002 Train A EDG Failure Failure MALF EG16B 2G003 Train B EDG Breaker Fails to Auto Close Fail to Auto Close MALF ED03B Train B 1E 4kV Bus 2A06 OC Fault Fault 2HS-1642 CR63-S03 (+1 minute)

MALF PG24 Loss of Edison Grid Loss Rx Trip MALF RC03 RCS Leak into Containment 7.5 Rx Trip RF PG57 Trip all SDG&E Switchyard Breakers Trip Rx Trip LP N/A AFW Pump P-140 Fails to Auto Start Fail to Auto Start LP N/A LPSI Pump P-016 OOS Bkr Racked out 1 MALF RM06 Containment High Range Radiation Monitor Fails 100 High 2 LP N/A Nuclear Service Water Pump P139 OC Trip / P- Trip / Fail 138 Fails to Auto Start to Auto Start 3 MALF RC03 RCS Leak (30 GPM) .75 4 N/A N/A Rapid Power Reduction due to RCS leak 5 MALF ED04A Non-1E 4kV Bus 2A03 OC Trip Fault 6 Setup Setup RCS Leak Increased to 300 GPM on Rx Trip 7 Setup Setup Loss of Offsite Power Upon Rx Trip 8 Setup Setup AFW Pump P-140 Fails to Start on EFAS SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Scenario Event Description NRC Scenario #1 9 Setup Setup Train A EDG Fails to Start (Cannot be started from CR) 10 Setup Setup Train B EDG Output Breaker Fails to Auto Close 11 Setup Setup Train B EDG Output Breaker OC Trip (60 seconds after EDG Output Breaker is manually closed)

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Scenario Event Description NRC Scenario #1 Machine Operator:

• RESTORE to IC-215

• OPEN 2012 NRC Scenario #1 event file

• RUN Setup Files 1 and 2

• ENSURE OOS Tag on LPSI Pump P-016

• ENSURE Pressurizer Level and Pressure Selector Switches are selected to Channel Y

• ENSURE blend setpoints are 13.2 gpm for BA and 74.8 gpm for PMW

• ENSURE SO23-5-1.7 Attachment 9 MOC placard is posted

• ENSURE OP AID 005-23 on CR63 has BQ aligned to Unit 2, BS aligned to Unit 3

• ENSURE OP AID 005-11 on CR64 has E336 aligned to Unit 2, E335 aligned to Unit 3

• ENSURE OP AID 005-5 for Backpressure Control Valves has PV201B circled

• ENSURE OP AID 005-5 for Letdown Flow Control Valve has LV110A circled

• ENSURE alarms are active Control Room Annunciators in Alarm:

• 57B51 SI/ECW SYS TRAIN B INOPERABLE

• LPSI PP 2P016 (sugar cube)

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 1 Page 7 of 28 Event

Description:

Containment High Range Radiation Monitor Ri-7820-1 Fails High Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 1, Containment High Range Radiation Monitor Fails High Indications Available:

• 57C10 - Containment Rad Hi

• RI-7820-1 Alarm on Data Acquisition System (DAS)

Examiner Note: The following steps are from Alarm Response Procedure 57C10, Containment Rad Hi DETERMINE a high radiation condition DOES NOT exist inside Containment RO by using alternate Containment radiation monitors on DAS computer (Train B Containment RM 7820-2, General Airborne Containment RM, etc.)

DETERMINE the alarm was invalid and notify the Radiation Monitoring RO Department of the instrument failure.

NOTIFY the CRS to review Tech. Specs. LCO 3.3.8, LCS 3.3.112, RO LCO 3.3.11, LCO 3.4.15.

INFORM CRS of compensatory actions (Monitor radiation levels twice every RO shift).

EVALUATE Technical Specifications :

• LCO 3.3.11 SRO

• Condition A - One or more Functions with one required channel inoperable.

• Action A.1 - Restore required channel to OPERABLE status within 30 days.

Examiner Note: When Technical Specifications have been evaluated or at lead evaluators discretion, proceed to Event 2, Nuclear Service Water P-139 Overcurrent Trip.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 2 Page 8 of 28 Event

Description:

Nuclear Service Water Pump P-139 O/C Trip, P-138 Fails to Auto Start Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 2, NSW Pump P-139 O/C Trip, P-138 Fails to Auto Start Indications Available:

• 61A43 - Nuclear Service Water Pump OC

• 61A32 - Nuclear Service Water Press Lo

• 61A33 - Nuclear Service Water Press Lo-Lo Examiner Note: The following steps are from Alarm Response Procedure 61A43, Nuclear Service Water Pump OC, however the standby NSW Pump may be started using Prompt and Prudent Actions per OSM-14, Operations Department Expectations.

BOP Start stand-by Nuclear Service Water Pump.

Dispatch an outside operator to investigate tripped pump breaker and BOP affected pump motor.

DIRECT performance of SO23-6-9, Section for MCC Feeder Circuit Fault BOP Relay/Guidelines for Resetting Tripped Breakers and/or Thermals.

Examiner Note: When NSW Pump P-138 is started or at lead evaluators discretion, proceed to Event 3, Reactor Coolant System Leak.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 3 Page 9 of 28 Event

Description:

Reactor Coolant System Leak (30 GPM)

Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 3, Reactor Coolant System Leak Indications Available:

• Slowly lowering PZR level

• Charging / Letdown mismatch

• Rising Containment Sump level

• 57C43 RCS Leakage Abnormal (+90 sec)

• 57C20 RCS Leakage Detection Activity Hi (+120 sec)

Examiner Note: The following steps are from SO23-13-14, RCS Leak.

VERIFY Pressurizer level - NOT LOWERING.

RO

• (RNO) START Charging Pumps to maintain Pressurizer level.

VERIFY Pressurizer level - NOT LOWERING with all available Charging RO Pumps in operation.

RO VERIFY Pressurizer Level - STABLE or RISING.

VERIFY RCS leak is less than 25 gpm.

RO * (RNO) INITIATE SO23-13-28, Rapid Power Reduction (RPR), at a rate of approximately 15-20% per hour.

Evaluate Technical Specifications:

• LCO 3.4.13 SRO

• Condition A - RCS Operational LEAKAGE not within limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.

• Action A.1 - Reduce LEAKAGE to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 10 of 28 Event

Description:

Rapid Power Reduction Time Position Applicants Actions or Behavior Examiner Note: The following steps are from SO23-13-28, Rapid Power Reduction.

SRO INITIATE notifying the GOC.

If taking the Unit Offline or to target power plateau < 750 MWe ( 65% Rx SRO Power), then INITIATE an immediate MSR Cooldown per SO23-10-2, Attachment for MSR Cooldown for Load Reduction/Turbine Shutdown.

SRO INITIATE monitoring CV-9739, COLSS Raw Delta-T Power.

INITIATE Forcing PZR spray flow using two valves per SO23-3-1.10:

• ENSURE a Reactivity Brief has been conducted for this activity per SO123-0-A1, Section for Reactivity.

• COMMENCE monitoring RCS pressure.

• VERIFY RCS pressure > 1500 psia.

RO

• PLACE both PZR Spray Valve Controllers in AUTO.

• POSITION all Non-1E Backup Heaters to ON.

• LOWER PIC-0100, PZR Pressure Controller, setpoint as required to maintain RCS pressure as directed by the CRS (set setpoint to ~ 2225 psia).

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 11 of 28 Event

Description:

Rapid Power Reduction Time Position Applicants Actions or Behavior BORATE to the Charging Pump Suction or through HV-9247:

• Implement the requirements for a Reactivity Brief and Peer check per OSM-14, Operations Department Expectations, Section for Reactivity Management.

• ENSURE ENTERED required boration flowrate on FIC-0210Y, BAMU Flow Controller.

• If flowrate change, then SELECT SET.

• ENSURE FIC-0210Y in AUTO.

• SET FQIS-0210Y, Boration Counter, to the desired volume as follows:

• SELECT MODIFY.

• ENTER gallons in PRESET.

RO

• SELECT SET PRESET.

• SELECT EXIT.

• SELETE the BAMU Pump associated with the BAMU Tank used.

• VERIFY CLOSED FV-9253, Blended Makeup to VCT Isolation.

• ENSURE HV-9257, BAMU to Charging Pump Suction Block Valve, in AUTO.

• COMMENCE monitoring plant parameters.

• From the MODE SELECTOR:

• SELECT MODIFY.

• SELECT BORATE.

• SELECT GO.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 12 of 28 Event

Description:

Rapid Power Reduction Time Position Applicants Actions or Behavior INSERT CEAs for ASI Control per SO23-3-2.19, to the target level within the following guidance:

• INSERT PLCEAs (Insertion Limit is 112.5. Insertion should be limited to 115 inches or until Power reaches target plateau.)

• INSERT Group 6 to target level. [90" if RCS Boron is < 110 ppm.]

(The maximum recommended is 75 inches.)

RO

• POSITION Group Select switch to the CEA group to be moved.

• POSITION Mode Select Switch to the appropriate mode.

• VERIFY the group indicator lamps are ILLUMINATED for the group selected.

• POSITION CEA(s) as directed by SRO Ops. Supv.

• When CEA positioning has completed, then POSITION the Mode Select Switch to OFF.

INITIATE SO23-5-1.7, Section for Turbine Load Change using Setpoint Adjustment:

• Implement the requirements for a Reactivity Brief and Peer Check per OSM-14, Operations Department Expectations, Section for Reactivity Management.

• INITIATE monitoring TCOLDAVG using PCS.

• PLACE the 1st STAGE PRESSURE feedback loop in service.

• ACTIVATE the Turbine DCS Setpoints Box and SELECT MODIFY.

BOP

• SET the Demand to the target MW value and SELECT ENTER.

• Set the Rate to the target MW/MIN value and SELECT ENTER.

• INITIATE Turbine load change, SELECT P2.

• Control RCS Tcold within the operating band by adjusting the rate setpoint or by canceling and reinitiating the load change as necessary.

• VERIFY Turbine load stabilizes at the target value.

• REMOVE 1st STAGE PRESSURE feedback loop from service.

• RESTORE the Rate to 100 MW/MIN and SELECT ENTER.

SRO INITIATE SO23-5-1.7, Attachment for Power Descension.

If Reactor power changed > 15% in one hour, then NOTIFY Chemistry SRO and LOG the notification.

SRO NOTIFY Reactor Engineering and log the notification.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 13 of 28 Event

Description:

Rapid Power Reduction Time Position Applicants Actions or Behavior Maintain Turbine load, RCS Temperature, and ASI within the expected ALL operating bands per SO23-5-1.7.

Examiner Note: When Reactor power has been lowered 3-5% or at lead evaluators discretion, proceed to Event 5, Non-1E 4kV Bus 2A03 O/C Trip.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5 Page 14 of 28 Event

Description:

Non-1E 4kV Bus 2A03 O/C Trip Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 5, 2A03 O/C Trip Indications Available:

• 63A16 - 2A03 SUPPLY BKR 2A0311 OC Examiner Note: The following steps are from Alarm Response Procedure 63A16, 2A03 Supply Bkr 2A0311 OC.

BOP Notify the CRS/SM of the bus fault on 2A03.

SRO If 2A03 is de-energized, then GO TO SO23-13-26.3, Loss of Power to Non-ESF Bus A03 or Associated L/C or MCC.

Examiner Note: The following steps are from SO23-13-26.3, Loss of Power to A03.

VERIFY a RX AND Turbine trip have occurred.

• (RNO) IF one of the following conditions exist,

• RX power is > 30%

SRO

• Main Feedwater Supply is lost

• SG levels are uncontrolled THEN TRIP the Reactor.

RO/BOP Trip the Reactor by depressing Reactor Trip Pushbuttons 1 and 4 or 2 and 3.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 15 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior Examiner Note: The following steps are from SO23-12-1, Standard Post Trip Actions:

Verify Reactor Trip:

RO VERIFY Reactor Trip Circuit Breakers (8) OPEN.

RO VERIFY Reactor power - LOWERING AND Startup rate NEGATIVE.

RO VERIFY maximum of one full length CEA NOT fully inserted.

Verify Turbine Trip:

BOP ALL HP and LP Stop and Governor valves CLOSED.

BOP VERIFY BOTH Unit Output Breakers OPEN.

BOP VERIFY Main Turbine speed less than 2000 RPM OR lowering.

Critical Task: Manually start TDAFW Pump P-140 following the failure to auto start on EFAS prior to exiting SO23-12-1, Standard Post Trip Actions.

CCT Time:__________

SRO INITIATE Attachment 1, WORKSHEET.

Verify Vital Auxiliaries:

VERIFY BOTH 1E 4kV Buses ENERGIZED.

BOP * (RNO) ENSURE associated EDG OPERATING.

• (RNO) ENSURE associated EDG output breaker CLOSED.

VERIFY all 1E 480V buses ENERGIZED:

• (RNO) IF Train A 1E 480V bus B24 DE-ENERGIZED THEN ENSURE Train A EDG (G002) HS-1767-1, MAINTENANCE LOCKOUT in MAINT. AND INITIATE Attachment 5, DIESEL GENERATOR BOP FAILURE FOLLOW-UP ACTIONS.

• (RNO) IF Train B 1E 480V bus B26 DE-ENERGIZED THEN ENSURE Train B EDG (G003) HS-1770-2, MAINTENANCE LOCKOUT in MAINT. AND INITIATE Attachment 5, DIESEL GENERATOR FAILURE FOLLOW-UP ACTIONS.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 16 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior BOP VERIFY all Class 1E DC Buses ENERGIZED.

VERIFY all Non-1E 4kV Buses ENERGIZED.

BOP * (RNO) RESTORE power to affected bus(es) as time and resources permit.

Verify RCS Inventory Control:

VERIFY PZR level between 10% and 70% AND trending to between 30% and 60%.

RO

• (RNO) ENSURE PZR Level Control System OPERATING in AUTO or MANUAL to restore PZR level.

RO VERIFY Core Exit Saturation Margin greater than or equal to 20°F.

Verify RCS Pressure Control:

VERIFY PZR pressure between 1740 PSIA and 2380 PSIA AND trending to between 2025 PSIA and 2275 PSIA.

• (RNO) ENSURE PZR Pressure Control System OPERATING in AUTO or MANUAL to restore PZR pressure.

• (RNO) IF PZR pressure less than PZR Pressure Control System Setpoint and lowering, THEN ENSURE Normal and Auxiliary Spray valves CLOSED.

• (RNO) IF PZR pressure less than 1740 PSIA, THEN ENSURE the following ACTUATED:

RO

• SIAS

• CCAS

• CRIS.

• (RNO) IF PZR pressure less than or equal to 1430 PSIA, THEN ENSURE one RCP in each loop STOPPED.

• (RNO) IF RCP NPSH requirements of Attachment 3, POST-ACCIDENT PRESSURE / TEMPERATURE LIMITS NOT SATISFIED, THEN ENSURE all RCPs - STOPPED.

Verify Core Heat Removal:

RO VERIFY at least one RCP OPERATING.

• (RNO) GO TO step c.

RO VERIFY Core Exit Saturation Margin greater than or equal to 20°F:

Verify RCS Heat Removal:

VERIFY at least one S/G level between 21% NR and 80% NR AND BOP Feedwater - AVAILABLE.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 17 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior BOP VERIFY RCS TCOLD between 540°F and 550°F.

BOP VERIFY S/G pressures between 960 PSIA and 1050 PSIA.

Verify Containment Isolation:

VERIFY Containment pressure less than 1.5 PSIG.

• (RNO) IF Containment pressure greater than 3.4 PSIG, THEN ENSURE the following have ACTUATED:

• SIAS RO

• CIAS

• CCAS

• CRIS

• ENSURE all RCPs - STOPPED.

VERIFY Containment Area Radiation Monitors NOT alarming or trending to RO alarm. (Although Containment Area Radiation Monitors ARE alarming, there is no RNO action for this step - diagnosis use only).

RO VERIFY Secondary Plant Radiation Monitors NOT alarming or trending to alarm.

Verify Containment Temperature and Pressure Control:

RO VERIFY Containment average temperature less than 120°F.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 18 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior VERIFY Containment pressure less than 1.5 PSIG.

• (RNO) ENSURE proper functioning of Normal Containment Cooling.

• (RNO) ENSURE at least one Containment Dome Air Circulator OPERATING.

• (RNO) IF Containment pressure greater than 3.4 PSIG, THEN:

• ENSURE the following ACTUATED:

• SIAS

• CIAS RO

• CCAS

• CRIS

• ENSURE all RCPs STOPPED.

• ENSURE all available Containment Emergency Cooling Units OPERATING.

• (RNO) IF Containment pressure greater than 14 PSIG, THEN

• ENSURE CSAS - ACTUATED.

• ENSURE all available Containment Spray Header flows greater than 1600 GPM.

VERIFY all safety function criteria per Attachment 1, WORKSHEET RO RECOVERED.

• (RNO) COMPLETE Attachment 2, RECOVERY DIAGNOSTICS.

Examiner Note: The CRS should diagnose two events (Station Blackout and LOCA) and identify SO23-12-9, Functional Recovery, as the optimal EOI.

MO CUE: If the GOC is called about the status of getting offsite power back, inform them that Santiago # 1 is immediately available.

VERIFY REACTOR TRIP RECOVERY DIAGNOSED.

SRO

• (RNO) ENSURE at least one RCP in each loop stopped.

SRO INITIATE steps 12 through 17.

Examiner Note: Steps 12 through 17 of SO23-12-1, Standard Post Trip Actions, are located at the end of the scenario guide.

SRO IMPLEMENT EOI diagnosed.

Examiner Note: The following steps are from SO23-12-9, Functional Recovery:

SRO RECORD time of EOI entry _______.

SRO INITIATE SO23-12-10, SAFETY FUNCTION STATUS CHECKS.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 19 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior INITIATE FOLDOUT PAGE.

• IF SIAS has actuated, THEN INITIATE FS-7, VERIFY SI Throttle/Stop Criteria.

• IF all RCPs are stopped, THEN INITIATE FS-3, MONITOR Natural Circulation Established.

• IF at least one 220kV switchyard section is not energized to the Unit via Reserve Auxiliary or Unit Auxiliary transformers, THEN INITIATE SO23-12-11, Attachment 8, RESTORATION OF OFFSITE POWER.

• IF 4kV bus A04 or A06 becomes de-energized, THEN INITIATE SO23-12-11, Attachment 6, DIESEL GENERATOR FAILURE FOLLOW-UP ACTIONS.

SRO

• IF there is a loss of offsite power, THEN INITIATE SO23-12-11, Attachment 19, NON-1E DC LOAD REDUCTION.

• IF 4kV buses A04 or A06 are de-energized, THEN INITIATE SO23 11, Attachment 9, CONTROL BUILDING VENTILATION EMERGENCY ACTIONS and SO23-12-11, Attachment 20, CLASS 1E BATTERY LOAD REDUCTION.

• IF 4kV bus A04 or A06 remains de-energized, THEN EVALUATE 4kV bus cross tie per SO23-12-11, Attachment 24, SUPPLYING 1E 4KV BUS WITH OPPOSITE UNIT DIESEL.

• If SIAS has initiated, THEN INITIATE SO23-12-11, Attachment 22, NON-QUALIFIED LOAD RESTORATION.

• IF ALL Circulating Water pumps are OFF, THEN INITIATE FS-18, ESTABLISH Secondary Plant Protection.

SRO DIRECT Chemistry to sample both S/Gs for radioactivity and boron.

SRO NOTIFY Shift Manager/Operations Leader of entry into SO23-12-9, FUNCTIONAL RECOVERY.

SRO ENSURE Emergency Plan is initiated.

SRO IMPLEMENT PLACEKEEPER.

SRO IMPLEMENT TIME DEPENDENT STEPS SRO VERIFY SIAS actuation required.

ENSURE the following have actuated:

• SIAS SRO

• CCAS

• CRIS SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 20 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior SRO RECORD time of SIAS _______.

SRO VERIFY CIAS actuated.

RO INITIATE SO23-12-11, Attachment 22, NON-QUALIFIED LOAD RESTORATION.

VERIFY RCP NPSH requirements of SO23-12-11, Attachment 30, POST-ACCIDENT PRESSURE / TEMPERATURE LIMITS satisfied.

RO

• (RNO) STOP all RCPs AND INITIATE FS-3, MONITOR Natural Circulation Established.

ESTABLISH two train SI operation.

SRO * (RNO) REQUEST Shift Manager/Operations Leader to direct plant resources to establish the following support systems for non-operating/unavailable equipment.

VERIFY any safety function recovery attachments (FR-1 through FR-7)

SRO indicated by any optimal EOI.

• (RNO) GO TO step 6c.

IMPLEMENT precautionary actions:

SRO

• INITIATE Boration greater than 40 GPM.

• ENSURE one RCP in each loop stopped.

SRO VERIFY ESDE NOT indicated.

SRO VERIFY SGTR NOT indicated.

SRO VERIFY LOFW NOT indicated.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 21 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior SRO EVALUATE initiation of SO23-3-2.22, ESFAS OPERATION to reset any signals no longer needed.

OBTAIN approval from Shift Manager / Operations Leader to initiate plant SRO cooldown.

SRO INITIATE SO23-12-11, Attachment 3, COOLDOWN / DEPRESSURIZATION, as directed by the Shift Manager/ Operations Leader.

Examiner Note: The following steps are from SO23-12-11, Attachment 8, Restoration of Offsite Power.

BOP VERIFY annunciators for Reserve Auxiliary Transformers reset.

BOP VERIFY any 220kV section bus deenergized.

BOP VERIFY System Separation alarm reset.

ESTABLISH communication with one of the following within 5 minutes:

• SCE Generation Operations Center

• SCE Grid Control Center BOP

• SDG&E Grid Control Center

• CAISO Alhambra Dispatch Office

• CAISO Folsom Dispatch Office

• Orange County Switching Center BOP VERIFY all four 220kV section buses deenergized.

BOP ENSURE all SCE controlled 220kV circuit breakers are open.

Examiner Note: The BOP will open ALL 220kV breakers at this step.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 22 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior VERIFY BOTH 1E 4kV buses energized.

• (RNO) Perform the following for each deenergized 1E 4kV bus:

• ENSURE 1E 4kV Bus Tie breaker AUTO/MANUAL transfer switches selected to MANUAL.

BOP

• DISPATCH an operator to OPEN TS-2 DC knife switches 127F1 through 127F4 at EDG Bus PT Cubicle for each deenergized 1E 4kV bus.

Examiner Note: Since Train B 1E 4kV bus is faulted, only the knife switches on Train A 1E 4kV bus should be operated.

ENSURE 1E 4kV Bus Tie breaker AUTO/MANUAL transfer switches selected BOP to MANUAL.

ENSURE all 6.9kV AUTO/MANUAL and supply breaker switches are aligned:

2A01:

• 2HS-1613B - MANUAL

• 2HS-1754B - MANUAL

• 2HS-1614 - TRIP

• 2HS-1613A - TRIP BOP

• 2HS-1754A - TRIP 2A02:

• 2HS-1610B - MANUAL

• 2HS-1755B - MANUAL

• 2HS-1611 - TRIP

• 2HS-1610A - TRIP

• 2HS-1755A - TRIP SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 23 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior ENSURE all Non-1E 4kV AUTO/MANUAL and supply breaker switches are aligned:

2A08:

• 2HS-1683B - MANUAL

• 2HS-1684 - TRIP

• 2HS-1683 - TRIP 2A09:

• 2HS-1741B - MANUAL

• 2HS-1740 - TRIP

• 2HS-1741A - TRIP BOP 2A07:

• 2HS-1629B - MANUAL

• 2HS-1628 - TRIP

• 2HS-1629A - TRIP 2A03:

• 2HS-1674 - MANUAL

• 2HS-1674A - TRIP Examiner Note: 2HS-1673 trip pushbutton should not be depressed per the CAUTION above.

ENSURE the following loads are aligned:

• Heater Drain Pumps - STOP

• Main Condensate Pumps - STOP/OUT OF AUTO BOP

• Main Condenser Vacuum Pump - STOP/OUT OF AUTO

• Turbine Plant Cooling Water Pumps - STOP/OUT OF AUTO

• Main Circulating Water Pumps - STOP SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 24 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior VERIFY 220kV Bus Section B energized from a SDG&E 220kV line.

• (RNO) If at least one SCE 220kV line energized, then GO TO step 14.

BOP Examiner Note: If the crew has not yet informed the GOC that they are ready to receive the line from the switchyard, they should do so at this point.

BOP ENSURE deenergized 220kV Bus Section A isolated.

ENERGIZE the isolated section bus from a SCE 220kV line - DEPRESS BOP TRIP and then CLOSE energized line CB.

BOP VERFIY System Separation alarm reset.

ENERGIZE Unit 2 Reserve Auxiliary Transformer - DEPRESS TRIP and then BOP CLOSE associated section bus Transformer CB 4042 or 6042.

BOP VERIFY System Separation alarm reset.

ENERGIZE adjacent isolated B section bus associated A section bus -

BOP DEPRESS TRIP and then CLOSE Bus Tie CB 4112 or 6112.

BOP VERIFY System Separation alarm reset.

ENERGIZE Unit 3 Reserve Auxiliary Transformer - DEPRESS TRIP and then BOP CLOSE associated section bus CB 4172 or 6172.

ENSURE (2/3HS-1600) Bus Metering Selector Switch aligned to an energized BOP 220kV bus.

VERIFY BOTH 1E 4kV buses energized.

BOP * (RNO) ENSURE 1E 4kV Bus Tie Breaker AUTO/MANUAL transfer switches selected to MANUAL and GO TO step 20.

ENSURE TS-2 DC knife switches 127F1 through 127F4 at EDG Bus PT Cubicle for each deenergized 1E 4kV bus open.

BOP Examiner Note: Since Train B 1E 4kV bus is faulted, only the knife switches on Train A 1E 4kV bus should be operated.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 25 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior OVERRIDE and STOP not operating 1E 4kV loads:

• Emergency Chillers

• Containment Spray Pumps

• HPSI Pumps BOP

• LPSI Pumps

• Auxiliary Feedwater Pumps

• Component Cooling Water Pumps

• Salt Water Cooling Pumps BOP NOTIFY Control Room Watchstanders before reenergizing the buses.

ENERGIZE the deenergized 1E 4kV buses.

BOP Examiner Note: Only Train A 1E 4kV bus 2A04 should be energized.

Critical Task: Restore power to a 1E 4kV bus following a Station Blackout prior to battery depletion and loss of associated 1E 125 DC bus.

CCT Time:__________

ENSURE TS-2 DC 127F1 through 127F4 knife switches at EDG Bus PT BOP Cubicle closed.

BOP VERIFY 4kV bus low voltage annunciators reset.

BOP ENSURE associated 1E 480V bus energized.

VERIFY SIAS NOT actuated.

• (RNO) Start the following loads for energized bus for desired plant conditions as directed by the Shift Manager:

• HPSI Pump

• LPSI Pump BOP

• Containment Spray Pump

• Component Cooling Water Pump

• Salt Water Cooling Pump

• Auxiliary Feedwater Pump

• Emergency Chillers SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 26 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior Critical Task: Establish SI flow following the restoration of 1E 4kV power prior to exiting SO23-12-9, Functional Recovery.

CCT Time:__________

Scenario Termination: When the crew has established SI flow following the restoration of power to 1E 4kV bus 2A04, or at lead evaluators discretion, the scenario may be terminated.

Examiner Note: The following are steps 12-17 of SO23-12-1, Standard Post Trip Actions.

RO INITIATE Attachment 4, ADMINISTRATIVE ACTIONS.

RO ENSURE a PA System announcement was made regarding the Reactor trip.

OPERATE SBCS to maintain RCS TCOLD between 540°F and 550°F.

RO * (RNO) OPERATE ADVS to maintain RCS TCOLD between 540°F and 550°F.

VERIFY TELECOM 480VAC FDR BKR HS0800S-2 (Q800S) CLOSED:

• (RNO) DEPRESS OVERRIDE pushbutton HS0800S-2 AND VERIFY associated breaker closed.

OR RO * (RNO) ENSURE opposite unit TELECOM 480VAC FDR BKR HS0800S-2 CLOSED.

OR

• (RNO) REQUEST Shift Manager/Operations Leader to direct plant resources to resources to restore Telecom power.

VERIFY TELECOM 480VAC FDR BKR HS0800N-2 (Q800N) CLOSED:

• (RNO) DEPRESS OVERRIDE pushbutton HS0800N-2 AND VERIFY associated breaker closed OR RO * (RNO) ENSURE opposite unit TELECOM 480VAC FDR BKR HS0800N-2 CLOSED OR

• (RNO) REQUEST Shift Manager/Operations Leader to direct plant resources to resources to restore Telecom power.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 27 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior VERIFY all Non-1E 4kV Buses ENERGIZED.

• (RNO) TRANSFER Non-1E 4kV Buses to available Reserve Auxiliary Transformers.

• (RNO) IF ALL Circulating Water pumps OFF, THEN:

RO

• ENSURE MSIVs closed.

AND

• OPERATE ADVs to maintain S/G pressure between 960 PSIA and 1050 PSIA.

VERIFY 480V Load Centers B15 and B16 ENERGIZED:

RO * (RNO) VERIFY 56A20, REACTOR TRIPPED CEDMCS DE-ENERGIZED alarming.

• (RNO) VERIFY CEDM M/G Set Output contactors OPEN.

RO ENSURE 3rd Point Heater Drain Pumps STOPPED.

VERIFY RTO RESET.

RO * (RNO) IF a MFW pump in service THEN RESET RTO per SO23-9-6, Feedwater Control System Operation MAINTAIN one MFW Pump and a maximum of three Condensate Pumps in RO operation.

• (RNO) ENSURE S/G levels - being maintained by AFW Pumps.

ENSURE FIC-3294, Condensate Pump miniflow controller to - set for proper Condensate pump configuration:

RO

• One pump - 4500 GPM

• Two pumps - 6000 GPM

• Three pumps - 9000 GPM RO PLACE Condensate Draw-off valve LV-3245 to - DISABLE.

VERIFY SO23-12-2, REACTOR TRIP RECOVERY being implemented.

• (RNO) ENSURE S/G Blowdown valves HV-4054 and HV-4053 -

RO CLOSED.

• (RNO) GO TO step 16.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, 9, 10, 11 Page 28 of 28 Event

Description:

RCS Leak Increases to 300 GPM, Loss of Offsite Power, Train A EDG Mechanical Failure, Train B EDG Output Breaker Fails to Auto Close, Train B 1E 4kV Bus 2A06 O/C Trip, AFW Pump P-140 Fails to Start on EFAS Time Position Applicants Actions or Behavior ENSURE the following valves closed:

• Extraction Steam Block valves HV-8800, HV-8812, HV-8804, HV-8810, HV-8808, HV-8820, HV-8806, and HV-8816.

• Main Steam to Reheater Block, Bypass, Warmup and Control valves HV-2703 or HV-2704, HV-2721, and HV-2751.

RO

• Bled Steam to Reheaters Block Valve HV-2712A/B.

• (RNO) IF MSR isolation valves CANNOT be verified closed AND RCS TCOLD uncontrolled, THEN:

• CLOSE MSIVs.

• OPERATE ADVs to maintain S/G pressure - between 960 PSIA and 1050 PSIA.

RO VERIFY Main Generator voltage - less than 24kV.

VERIFY annunciators 99A26 TURBINE LUBE OIL TEMP HI and 99A46 RO TURBINE BRG OIL DRAIN TEMP HI - RESET.

• (RNO) CONTROL lube oil temperature locally.

INITIATE SO23-10-2, TURBINE SHUTDOWN, Attachment for Unloading RO the Generator and Removing the Unit from Line.

VERIFY BOTH Start-Up Range channels - OPERABLE.

RO * (RNO) NOTIFY SRO-in-charge of TS 3.3.13 and LCS 3.3.111 entry.

• (RNO) INITIATE SO23-3-2.15, section for Start-Up Range Channel failure.

SONGS 2012 NRC Sim Scenario #1 Rev d.docd

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 & 3 Scenario No.: 2 Op Test No.: October 2012 NRC Examiners: Operators:

Initial Conditions: 100% Power MOC Turnover: Maintain steady state conditions.

Critical Tasks:

• Emergency Borate the RCS following Reactor Trip following the failure of two full-length CEAs to insert on Reactor trip prior to exiting SO23-12-1, Standard Post Trip Actions.

• Trip all 4 RCPs within 30 minutes of the CIAS due to the loss of Component Cooling Water to the RCPs.

Event No. Malf. Event Type* Event Description No.

1 (10 min) SG03G I (BOP, SRO) S/G E-089 Pressure Transmitter PT-1013-3 fails low TS (SRO) 2 (25 min) MFW N (RO, BOP, SRO) MFW Pump K-006 Trip (Rapid Power Reduction to 65% Power)

LP 3 (30 min) FW02A TS (SRO) AFW Pump P-141 O/C Trip 4 (40 min) RC11 I (RO, SRO) Thot instrument TT-0111X1 Fails High 5 (50 min) ED08A C (RO, BOP, SRO) Loss of Non-1E Instrument Bus 2Q065 6 (55 min) RP23B M (RO, BOP, SRO) Inadvertent CIAS - Loss of Forced Circulation 7 (55 min) ED03A C (BOP) 1E 4kV Bus 2A04 O/C Trip on Reactor Trip 8 (60 min) RD1002 C (RO, SRO) Two Full Length CEAs Fail to Fully Insert - Gravity Feed Emergency Boration Required RD4002 9 (65 min) ELEC I (BOP) Non-1E 4kV Bus 2A09 Fails to Auto Transfer on Reactor Trip LP

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 9 Total malfunctions (5-8) 3 Malfunctions after EOP entry (1-2) 4 Abnormal events (2-4) 1 Major transients (1-2) 2 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3)

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Scenario Event Description NRC Scenario #2 SCENARIO

SUMMARY

NRC #2 The crew will take the watch at 100% power with no scheduled activities per SO23-5-1.7, Power Operations.

Upon taking the watch, SG E089 Pressure Transmitter PT-1013-3 will fail low. The crew will identify the failed transmitter and enter SO23-13-18, RPS Malfunctions. The crew will bypass the affected bistables and the BOP will bypass the affected pressure transmitter on the FWCS DCS. The CRS will refer to the Technical Specifications.

Following the Technical Specification review, MFP K006 will trip. The crew will perform a rapid power reduction to lower power 30% in 5 min per SO23-13-28, Rapid Power Reduction. Two minutes after the crew initiates EFAS, Train A AFW Pump P-141 will trip on overcurrent due to a seized shaft. The CRS will address Technical Specifications due to the loss of the motor driven AFW pump.

When power has stabilized at ~ 70%, Loop 1 Thot instrument TT-0111X1 will fail high. The crew will take prompt and prudent action to stabilize Pressurizer level per OSM-14, Operations Department Expectations, and enter AOI SO23-13-27, Pressurizer Pressure and Level Malfunctions. The crew will transfer the Pressurizer level input to Loop 2 and transfer the SBCS Quick Open Block Selector Switch to the unaffected loop.

When automatic level control has been restored, a loss of Non-1E Instrument Bus #1 will occur. The crew will enter SO23-13-19, Loss of a Non-1E Instrument Bus, to address the malfunction. Major actions for the loss of Instrument Bus #1 include placing SBCS in MANUAL, securing charging flow due to letdown automatically isolating, and operating 1E Pressurizer heaters as necessary to control Pressurizer pressure.

When Instrument Bus #1 has been reenergized on its emergency power source, an inadvertent CIAS will occur, requiring a Reactor trip.

Upon the Reactor trip, two full length CEAs will fail to insert requiring an emergency boration to be performed. Train A 1E 4kV Bus will trip on the Reactor trip causing the RO to use gravity feed to emergency borate. The Train A EDG must be placed in maintenance lockout due to the loss of EDG auxiliaries. Non-1E 4kV Bus 2A09 will fail to auto transfer on the Reactor trip and will be manually transferred in SPTA follow up actions. The CIAS will isolate cooling water to the RCPs which the crew will manually secure during the Vital Auxiliaries verification.

The CRS will diagnose a loss of forced circulation and enter SO23-12-7, Loss of Offsite Power/Loss of Forced Circulation. The scenario is terminated when the crew verifies natural ciruculation has been established.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Scenario Event Description NRC Scenario #2 Risk Significance:

• Failure of risk important system prior to trip: MFP K-006 Trip AFW Pump P-141 OC trip

• Risk significant core damage sequence: Failure of two full-length CEAs to insert on Rx trip Loss of 1E 4kV Bus 2A04 Loss of forced circulation

• Risk significant operator actions: Initiate emergency boration following failure of two full length CEAs to insert on Rx trip Trip all RCPs following the loss of cooling water following the inadvertent CIAS SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Scenario Event Description NRC Scenario #2 MACHINE OPERATOR INSTRUCTIONS for SIMULATOR SETUP INITIALIZE to IC-230 NRC Scenario #2 and associated Setup File.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER SETUP MALF ED03A Train A 1E 4kV Bus 2A04 OC Trip Fault Rx Trip MALF RD0502 Stuck CEA # 05 Stuck MALF RD6802 Stuck CEA # 68 Stuck MALF FW02A AFW Pump P-141 Shaft Seizure Seizure EFAS (+2 min)

LP N/A Non-1E 4kV Bus 2A09 Fails to Auto Transfer on Fail to Rx Trip Rx Trip Transfer 1 MALF SG03G SG E089 Pressure Transmitter PT-1013-3 Fails 0 Low RF RP51 PPS Door Open Annunciator Open RF RP54K Lo SG-1 Pressure Channel C Bypass Bypass RF RP54U Hi SG-1 DP EFAS-1 Channel C Bypass Bypass RF RP54V Hi SG-2 DP EFAS-2 Channel C Bypass Bypass RF RP51 PPS Door Open Annunciator Close 2 RF MFP PB MFW Pump 2K006 Trip Trip 3 Setup Setup AFW Pump P-141 OC Trip (Shaft Seizure) Seizure 4 MALF RC11A TT-0111X1 RCS Hot Leg # 1 Temperature 625 Instrument Fails High 5 MALF ED08A Loss of Non-1E Instrument Bus 2Q065 Loss RF ED80 2Q065 Transfer to Emergency Power Source Emer MALF ED08A Loss of Non-1E Instrument Bus 2Q065 Normal (+2 sec) 6 MALF RP23B Inadvertent CIAS (AB Power Matrix Loss) Loss Power 7 Setup Setup Train A 1E 4kV Bus 2A04 OC Trip SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Scenario Event Description NRC Scenario #2 8 Setup Setup Two Full Length CEAs Fail to Insert on Rx Trip 9 Setup Setup Non-1E 4kV Bus 2A08 Fails to Auto Transfer on Rx Trip SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Scenario Event Description NRC Scenario #2 Machine Operator:

• RESTORE to IC-215

• OPEN 2012 NRC Scenario #2 event file

• RUN Setup Files 1 and 2

• ENSURE Pressurizer Level and Pressure Selector Switches are selected to Channel Y

• ENSURE blend setpoints are 13.2 gpm for BA and 74.8 gpm for PMW

• ENSURE SO23-5-1.7 Attachment 9 MOC placard is posted

• ENSURE OP AID 005-23 on CR63 has BQ aligned to Unit 2, BS aligned to Unit 3

• ENSURE OP AID 005-11 on CR64 has E336 aligned to Unit 2, E335 aligned to Unit 3

• ENSURE OP AID 005-5 for Backpressure Control Valves has PV201B circled

• ENSURE OP AID 005-5 for Letdown Flow Control Valve has LV110A circled

• ENSURE alarms are active

• ENSURE Pressurizer level setpoint selected to IN1.

Control Room Annunciators in Alarm:

• None SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 1 Page 7 of 25 Event

Description:

S/G E-089 Pressure Transmitter PT-1013-3 Fails Low Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 1, S/G E-089 Pressure Transmitter PT-1013-3 Fails Low Indications Available:

• 56A52/56A42 SG2 E088 Press > SG1 E089 ESFAS Ch Pretrip/Trip

• 56A53/56A43 SG1 E089 Press Lo Channel Pretrip/Trip

• 52A13 FWCS Trouble Examiner Note: The following steps are from SO23-13-18, RPS Malfunction DETERMINE failure by observing instrumentation for the affected channel RO AND alternate redundant indications monitoring the same plant parameters.

SRO DETERMINE a Single PPS Channel has FAILED and GO TO Step 3.

REFER to Attachment 10 and determine Functional Unit(s) affected.

SRO Examiner Note: Affected bistables are Channel C bistables 11, 21, and 22.

PLACE the affected Functional Unit in BYPASS per SO23-3-2.12, Section for SRO Bypass Operation of Trip Channels.

MO CUE: If requested to place Channel C bistables 11, 21, and 22 in bypass, execute PPS Bypasses event.

CONFIRM failure does NOT affect RPS/ESFAS Matrix Logic, RPS/ESFAS SRO Initiation Logic, RTCBs, RPS/ESFAS Manual Trip, or ESFAS Actuation Logic.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 1 Page 8 of 25 Event

Description:

S/G E-089 Pressure Transmitter PT-1013-3 Fails Low Time Position Applicants Actions or Behavior CONFIRM failure does NOT affect the Feedwater Digital Control System.

• (RNO) BYPASS the affected instrument for E-088 and/or E-089 per SO23-3-2.38, Section for Bypassing Selected Feedwater Control Signals:

• Implement the requirements for a Reactivity Brief as Peer Check per OSM-14, Section for Reactivity Management.

• From the applicable SG FW Control DCS, go to the SELECTED BOP SIGNALS screen.

• Verify the D channel signal is valid.

• SELECT BYPASS for the instrument to be placed in bypass.

• Verify the instrument indicates BYPASS.

• Verify the D channel is not in BYPASS.

• Verify the Selected Signal (SS) output looks valid.

FOLLOW the action requirements of the applicable Tech. Spec./LCS listed in Attachment 10.

• LCO 3.3.1

• Condition A - One or more Functions with one automatic RPS trip channel inoperable.

• Action A.1 - Place Channel in bypass or trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

SRO

• LCO 3.3.5

• Condition B - One automatic trip channel inoperable for RWST Level-Low for the RAS function or SG Pressure-Low or SG Pressure Difference-High for the EFAS function.

• Action B.1 - Place Functional Unit in bypass within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Examiner Note: When bistables have been bypassed and Technical Specifications have been evaluated, or at lead examiners discretion, proceed to Event 2, MFW Pump K-006 trip.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 2, 3 Page 9 of 25 Event

Description:

MFW Pump K-006 Trip, AFW Pump P-141 O/C Trip Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 2, MFW Pump K-006 Trip (Event 3, P-141 O/C Trip will automatically occur 2 min after EFAS is actuated.)

Indications Available:

• MFWP/Turbine P062/K-006 Trip Examiner Note: The following steps are from SO23-13-28, Rapid Power Reduction.

SRO If MFW Pump tripped, then INITIATE EFAS by depressing all (8) EFAS RO/BOP Actuation Pushbuttons once.

BORATE through HV-9247, as established in Rx Brief (Alternate Boration):

• SELECT ALTERNATE BORATION.

• SELECT CONFIRM.

• SELECT GO.

RO

• ENSURE two Charging Pumps are running.

• When the Alternate Boration time has timed out, then verify HV-9247 CLOSED.

• SELECT CANCEL.

• OPERATE Charging Pumps per CRS direction.

BOP ENSURE all available Condensate Pumps - running.

INITIATE Attachment 4 for Turbine Load Change - Manual Runback:

• ENSURE only the FREQUENCY Loop is in service.

• Select INITIATE/CANCEL in the MANUAL RUNBACK box.

• Select INITIATE RUNBACK (P2) in the Confirm Manual Runback window.

BOP

• CANCEL and INITIATE the Manual Runback to maintain Tcoldavg within Operating Band.

• VERIFY Turbine load stabilizes at the target value of 70% Rx Power.

• If Rx Power has NOT reached target value of 70%, then continue load reduction by using 2HS-2210, Main Turbine Speed/Load Control LOWER pushbutton at a rate of 100 MW/MIN to obtain target value of 70% Rx Power while maintaining Tcoldavg within operating band.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 2, 3 Page 10 of 25 Event

Description:

MFW Pump K-006 Trip, AFW Pump P-141 O/C Trip Time Position Applicants Actions or Behavior INSERT Group 6 to 105 inches per SO23-3-2.19:

• POSITION Group Select switch to the CEA group to be moved.

• POSITION Mode Select Switch to Manual Sequential.

• VERIFY the group indicator lamps are ILLUMINATED for the group RO selected.

• POSITION CEA(s) as directed by SRO Ops. Supv. or controlling Procedure

• When CEA positioning has completed, then POSITION the Mode Select Switch to OFF.

RO/BOP INITIATE monitoring CV-9739, COLSS Raw Delta-T Power.

RO/BOP MAINTAIN Tcold AVG within Operating Band per SO23-5-1.7 Attachment for Unit 2 and Unit 3 Tcold vs Reactor Power.

If EFAS initiated, then RESET the EFAS cycling relays, as follows:

• VERIFY Steam Generator level(s) - stable or rising.

• VERIFY Steam Generator Low Level Alarm(s) - reset.

BOP

• VERIFY Feedwater Control Valves - < 100% Open and controlling level.

• When directed by the SRO Ops. Supv., then DEPRESS all (8) EFAS Actuation Pushbuttons a second time to reset the cycling relays.

BOP INITIATE SO23-2-2, Section for On-Line Operation of MP-053.

SRO Notify the GOC and log the notification.

INITIATE forcing PZR spray flow using two valves, per SO23-3-1.10:

• ENSURE a Reactivity Brief has been conducted for this activity per SO123-0-A1, Section for Reactivity.

• COMMENCE monitoring RCS pressure.

• VERIFY RCS pressure > 1500 psia.

RO

• PLACE both PZR Spray Valve Controllers in AUTO.

• POSITION all Non-1E Backup Heaters to ON.

• LOWER PIC-0100, PZR Pressure Contoller, setpoint as required to maintain RCS pressure as directed by the CRS (set setpoint to ~ 2225 psia).

SRO Refer to SO23-5-1.7, Attachment for Recommended Power Plateaus, for operation with one MFW Pump.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 2, 3 Page 11 of 25 Event

Description:

MFW Pump K-006 Trip, AFW Pump P-141 O/C Trip Time Position Applicants Actions or Behavior After stabilizing the Unit at the target power level, then perform the following:

• INITIATE SO23-5-1.7, Attachment for Power Descension.

• INITIATE SO23-3-2.2, Makeup Operations, to ensure CVCS makeup is SRO returned to automatic operation.

• NOTIFY Chemistry and LOG the notification.

• NOTIFY Reactor Engineering and LOG the notification.

Examiner Note: Technical Specification for AFW P-141 O/C Trip:

• LCO 3.7.5

• Condition B - One AFW train inoperable for reasons other than Condition A in Mode 1, 2, or 3.

• Action B.1 - Restore AFW train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 10 days from discovery of failure to meet the LCO.

Examiner Note: When Rx Power has been stabilized at ~ 70% Rx Power and Technical Specifications have been evaluated, or at lead evaluators discretion, proceed to Event 4, Thot instrument TT-111X1 fails high.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 4 Page 12 of 25 Event

Description:

Thot Instrument TT-0111X1 Fails High Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 4, Thot instrument TT-111X1 fails high Indications Available:

• 50A05 Tavg Hi Examiner Note: The crew may respond to this failure using Prompt and Prudent actions prior to referencing ARP 50A05, Tave Hi. The P&P actions to be taken are:

• Place Pressurizer Level Controller LIC-0110 in MANUAL

• Adjust output to maintain Pressurizer level

• Start/Stop Charging pumps as required to maintain Pressurizer level.

• Cycle Heaters as required to maintain Pressurizer pressure.

The following steps are from Alarm Response Procedure 50A05, Tave Hi:

SRO If the Letdown and Charging Systems are not responding as desired, then Initiate SO23-13-27, Pressurizer Pressure and Level Malfunction.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 4 Page 13 of 25 Event

Description:

Thot Instrument TT-0111X1 Fails High Time Position Applicants Actions or Behavior Ensure the following are transferred to the unaffected loop:

2(3)LIC-0110, Pressurizer Level Controller, per SO23-3-1.10, Attachment for Transferring PZR Level and Pressure Controls, Section for Transfer Remote PZR Level Setpoint Inputs (IN1 IN2):

• Ensure a Reactivity Brief has been conducted for this activity per SO123-0-A1, Section for Reactivity.

• Ensure LIC-0110, PZR Level Controller, is in MANUAL with the Output set to ensure Charging and Letdown are matched.

• Go (TAG) to Page 2 on the controller and observe IN1 displayed.

• Note the displayed PZR level.

• Depress SEL pushbutton to display IN2.

• Note the displayed PZR level.

RO

• If both displays IN1 and IN2 appear faulty, then transfer LIC-0110 to Local Setpoint control.

• Depress the SEL pushbutton until the Selected Indicating Light (small dot) is extinguished. This displays the selected setpoint.

• To prevent Charging Pump Auto Start, match actual Pressurizer Level to within 2% of the new selected level setpoint.

• Select the new remote setpoint:

• To select IN1, depress the lower pushbutton once.

• To select IN2, depress the raise pushbutton once.

• To return LIC-0110 to AUTO:

• Go (TAG) to Page 1 on the controller.

• Manually adjust the output (right column) until actual level (middle column) is matches with the generated setpoint (left column).

• Transfer LIC-0110 to AUTO by depressing the A/M button.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 4 Page 14 of 25 Event

Description:

Thot Instrument TT-0111X1 Fails High Time Position Applicants Actions or Behavior Ensure the following are transferred to the unaffected loop:

2(3)HS-8430, SBCS Quick Open Block Tavg Selector Switch per SO23 2.18, Section for Transferring SBCS Tavg Inputs:

BOP

• Implement the requirements for a Reactivity Brief and Peer Check per OSM-14, Section for Reactivity Management.

• VERIFY a Quick Open Signal is not present.

• POSITION 2(3)HS-8430, SBCS Quick Open Block Tavg Selector Switch, to the opposite Loop.

Examiner Note: The following steps are from SO23-13-27, Pressurizer Level and Pressure Malfunction.

PLACE LIC-0110, Pressurizer Level Controller in MANUAL by depressing the RO A/M button.

RO START or STOP Charging Pumps to control Pressurizer Level.

RO SECURE Pressurizer heaters to control Pressurizer pressure.

RO ADJUST the output on LIC-0110 to maintain a steady PZR level.

RO VERIFY normal Charging and Letdown in service.

VERIFY Level Indicators LI-0110A1, LI-0110A2 and LI-103 are reading RO approximately the same.

RO VERIFY Pressurizer level is not lowering due to an RCS leak.

RO GO TO Step 2j.

TRANSFER Remote Pressurizer Level setpoint (IN1-IN2) to the non-faulted RO channel (See steps above, if necessary)

RO Restore Pressurizer Heaters to service to control RCS Pressure.

RO OPERATE Charging Pumps as directed by the CRS.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 4 Page 15 of 25 Event

Description:

Thot Instrument TT-0111X1 Fails High Time Position Applicants Actions or Behavior TRANSFER SBCS Quick Open Block Tavg Selector Switch to the non-BOP affected loop (See steps above, if necessary)

Examiner Note: When LIC-0110 setpoint has been selected to IN2, LIC-0110 has been returned to AUTO, Pressurizer heaters have been restored to normal lineup, and SBCS Quick Open Block Tavg Selector Switch has been transferred to Loop 2, or at lead evaluators discretion, proceed to Event 5, Loss of Non-1E Instrument Bus 2Q065.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5 Page 16 of 25 Event

Description:

Loss of Non-1E Instrument Bus 2Q065 Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 5, Loss of Non-1E Instrument Bus 2Q065 Indications Available:

• 63B24 2Q065 Inst Bus 1 Power Supply Failure Examiner Note: The following steps are fromSO23-13-19, Loss of a Non-1E Instrument Bus VERIFY Instrument Bus #1 (Q065) ENERGIZED.

• (RNO) PLACE SBCS in - MANUAL.

SRO

• (RNO) INITIATE transfer of Instrument Bus #1 to EMERGENCY.

• (RNO) GO TO Step 2.

MO CUE: When directed to place Instrument Bus #1 on its emergency power source, acknowledge but wait for direction/confirmation from the Floor Instructor prior to transferring to emergency.

BOP VERIFY FWCS operating NORMALLY.

BOP VERIFY Steam Generator E-089 level NOT lowering uncontrollably.

BOP VERIFY Steam Generator E-088 level NOT lowering uncontrollably.

VERIFY Pressurizer Pressure Control System maintaining Pressurizer pressure at approximately 2250 psia.

RO

• (RNO) Use 1E Pressurizer Heaters to maintain RCS pressure 2250 psia.

VERIFY Pressurizer Level in Program Band of 41% to 53%.

RO * (RNO) START and STOP Charging Pumps to maintain programmed PZR level.

RO VERIFY Boration NOT in progress from Charging Pump Suction Path.

RO VERIFY Secondary Water Chemistry Computers - ENERGIZED.

RO VERIFY Rad Monitors being used for releases or processing - ENERGIZED.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5 Page 17 of 25 Event

Description:

Loss of Non-1E Instrument Bus 2Q065 Time Position Applicants Actions or Behavior REFER to Attachments 1 through 5 to identify important points to monitor SRO based on the identified loss of the Instrument Bus Power.

SRO GO TO Section 6, Actions After Restoration of NON 1E Power.

BOP VERIFY Power was NOT lost to SBCS.

BOP ENSURE SBCS in Auto.

Examiner Note: When power has been restored to 2Q065 and SBCS has been placed back in AUTO, or at lead evaluators discretion, proceed to Event 6, Inadvertent CIAS.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 6 Page 18 of 25 Event

Description:

Inadvertent CIAS Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 6, Inadvertent CIAS Indications Available:

• 57A02 CIAS Train A Actuation

• 57B02 CIAS Train B Actuation Examiner Note: The following steps are from SO23-13-17, Inadvertent SIAS/CIAS/CSAS SRO ENSURE TRIPPED the Reactor and Turbine.

SRO INITIATE SO23-12-1, Standard Post Trip Actions.

RO AFTER Initial Actions (Step 1 and 2) of SO23-12-1, THEN TRIP all RCPs Examiner Note: If the crew trips the Reactor without referring to SO23-13-17, Inadvertent CIAS, they may not trip the RCPs until the verification of Vital Auxiliaries in SPTAs.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7, 8, 9 Page 19 of 25 Event

Description:

1E 4kV Bus 2A04 OC Trip, Two Full Length CEAs Fail to Insert on Rx Trip, Non-1E 4kV Bus 2A09 Fails to Auto Transfer on Rx Trip Time Position Applicants Actions or Behavior Machine Operator: Events 7, 8, and 9 will automatically initiate on Rx Trip Examiner Note: The following steps are from SO23-12-1, Standard Post Trip Actions Verify Reactor Trip:

RO VERIFY Reactor Trip Circuit Breakers (8) OPEN.

RO VERIFY Reactor power - LOWERING AND Startup rate NEGATIVE.

RO VERIFY maximum of one full length CEA NOT fully inserted.

• (RNO) INITIATE Emergency Boration.

• VERIFY Refueling NOT in progress.

• VERIFY at least one Charging Pump is available.

• DEPRESS OPEN on 2HV-9247, Emergency Boration Block Valve and verify valve is open AND DEPRESS START for either BAMU Pump and verify pump is running.

• (RNO) INITIATE Emergency Boration using Gravity Feed:

• ENSURE CLOSED 2HV-9247, Emergency Boration Block Valve.

• OPEN 2HV-9240, BAMU Tank MT-071 to Charging Pump Gravity Feed Valve.

• OPEN 2HV-9235, BAMU Tank MT-072 to Charging Pump Gravity Feed Valve.

• VERIFY OPEN 2HV-9240, BAMU Tank MT-071 to Charging Pump Gravity Feed Valve.

• VERIFY OPEN 2HV-9235, BAMU Tank MT-072 to Charging Pump Gravity Feed Valve.

• ENSURE IN MANUAL AND CLOSE 2LV-0227B, VCT MT-077 Outlet Valve.

• ENSURE charging flow > 40 gpm.

• START additional Charging Pumps as necessary to increase flow rate.

• VERIFY Boric Acid delivery to RCS by monitoring BAMU Tank level lowering.

• (RNO) Record time of Emergency Boration initiation _______.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7, 8, 9 Page 20 of 25 Event

Description:

1E 4kV Bus 2A04 OC Trip, Two Full Length CEAs Fail to Insert on Rx Trip, Non-1E 4kV Bus 2A09 Fails to Auto Transfer on Rx Trip Time Position Applicants Actions or Behavior Critical Task: Emergency Borate the RCS following Reactor Trip following the failure of two full-length CEAs to insert on Reactor trip prior to exiting SO23-12-1, Standard Post Trip Actions.

CCT Time:__________

Examiner Note: Emergency boration may be stopped when power is <10-4% power and power lowering or stable.

Verify Turbine Trip:

BOP ALL HP and LP Stop and Governor valves CLOSED.

BOP VERIFY BOTH Unit Output Breakers OPEN.

BOP VERIFY Main Turbine speed less than 2000 RPM OR lowering.

SRO INITIATE Attachment 1, WORKSHEET.

Verify Vital Auxiliaries:

VERIFY BOTH 1E 4kV Buses ENERGIZED.

• (RNO) ENSURE associated EDG OPERATING.

• (RNO) ENSURE associated EDG output breaker CLOSED.

BOP Examiner Note: Due to the bus being faulted, the BOP should NOT attempt to close the EDG output breaker.

VERIFY all 1E 480V buses ENERGIZED:

• (RNO) IF Train A 1E 480V bus B24 DE-ENERGIZED THEN ENSURE BOP Train A EDG (G002) HS-1767-1, MAINTENANCE LOCKOUT in MAINT. AND INITIATE Attachment 5, DIESEL GENERATOR FAILURE FOLLOW-UP ACTIONS.

BOP VERIFY all Class 1E DC Buses ENERGIZED.

VERIFY all Non-1E 4kV Buses ENERGIZED.

BOP * (RNO) RESTORE power to affected bus(es) as time and resources permit.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7, 8, 9 Page 21 of 25 Event

Description:

1E 4kV Bus 2A04 OC Trip, Two Full Length CEAs Fail to Insert on Rx Trip, Non-1E 4kV Bus 2A09 Fails to Auto Transfer on Rx Trip Time Position Applicants Actions or Behavior VERIFY one CCW Train OPERATING AND aligned to Non-Critical Loop (NCL) and Letdown Heat Exchanger.

BOP * (RNO) START an available CCW Train.

• (RNO) IF CIAS ACTUATED, THEN ENSURE all RCPs STOPPED AND GO TO step 5.

Critical Task: Trip all 4 RCPs within 30 minutes of the CIAS due to the loss of Component Cooling Water to the RCPs.

CCT Time:__________

Verify RCS Inventory Control:

RO VERIFY PZR level between 10% and 70% AND trending to between 30% and 60%.

RO VERIFY Core Exit Saturation Margin greater than or equal to 20°F.

Verify RCS Pressure Control:

RO VERIFY PZR pressure between 1740 PSIA and 2380 PSIA AND trending to between 2025 PSIA and 2275 PSIA.

Verify Core Heat Removal:

RO VERIFY at least one RCP OPERATING.

• (RNO) GO TO step c.

RO VERIFY Core Exit Saturation Margin greater than or equal to 20°F:

Verify RCS Heat Removal:

VERIFY at least one S/G level between 21% NR and 80% NR AND BOP Feedwater AVAILABLE.

BOP VERIFY RCS TCOLD between 540°F and 550°F.

VERIFY S/G pressures between 960 PSIA and 1050 PSIA.

BOP * (RNO) OPERATE ADVs to maintain S/G pressure between 960 PSIA and 1050 PSIA.

Verify Containment Isolation:

RO VERIFY Containment pressure less than 1.5 PSIG.

RO VERIFY Containment Area Radiation Monitors NOT alarming or trending to alarm.

RO VERIFY Secondary Plant Radiation Monitors NOT alarming or trending to alarm.

Verify Containment and Pressure Control:

RO VERIFY Containment average temperature less than 120°F.

RO VERIFY Containment pressure less than 1.5 PSIG.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7, 8, 9 Page 22 of 25 Event

Description:

1E 4kV Bus 2A04 OC Trip, Two Full Length CEAs Fail to Insert on Rx Trip, Non-1E 4kV Bus 2A09 Fails to Auto Transfer on Rx Trip Time Position Applicants Actions or Behavior VERIFY all safety function criteria per Attachment 1, WORKSHEET RO RECOVERED.

• (RNO) COMPLETE Attachment 2, RECOVERY DIAGNOSTICS.

Examiner Note: The CRS should diagnose a single event, Loss of Forced Circulation, and identify SO23-12-7, Loss of Forced Circulation/Loss of Offsite Power, as the optimal EOI.

VERIFY REACTOR TRIP RECOVERY DIAGNOSED.

SRO

• (RNO) ENSURE at least one RCP in each loop stopped.

SRO INITIATE steps 12 through 17.

Examiner Note: Steps 12 through 17 of SO23-12-1, Standard Post Trip Actions, are located at the end of the scenario guide.

SRO IMPLEMENT EOI diagnosed.

Examiner Note: The following steps are from SO23-12-7, Loss of Forced Circulation/Loss of Offsite Power.

SRO RECORD time of EOI entry _______.

SRO INITIATE SO23-12-10, SAFETY FUNCTION STATUS CHECKS.

INITIATE FOLDOUT PAGE.

• IF all RCPs have stopped, THEN INITIATE FS-3, MONITOR Natural Circulation Established.

SRO

• IF 4kV bus A04 or A06 becomes de-energized, THEN INITIATE SO23-12-11, Attachment 6, DIESEL GENERATOR FAILURE FOLLOW-UP ACTIONS.

• IF 4kV bus A04 or A06 remains de-energized, THEN INITIATE SO23-12-11, Attachment 20, CLASS 1E BATTERY LOAD REDUCTION.

SRO VERIFY at least one train of 1E electrical AC and associated 1E DC Control Power (Train A - D1, Train B - D2) available.

SRO VERIFY at least one Class 1E 120V Vital AC Instrument Bus available.

VERIFY Class 1E 4kV Buses A04 and A06 energized.

SRO

• INITIATE SO23-12-11, Attachment 6, DIESEL GENERATOR FAILURE FOLLOW-UP ACTIONS, for NOT energized bus.

SRO VERIFY all RCPs stopped OR all Non-1E 4kV buses de-energized.

NOTIFY Shift Manager/Operations Leader of SO23-12-7, LOSS OF SRO FORCED CIRCULATION/LOSS OF OFFSITE POWER initiation.

SRO ENSURE Emergency Plan is initiated.

SRO IMPLEMENT PLACEKEEPER.

SRO IMPLEMENT TIME DEPENDENT STEPS SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7, 8, 9 Page 23 of 25 Event

Description:

1E 4kV Bus 2A04 OC Trip, Two Full Length CEAs Fail to Insert on Rx Trip, Non-1E 4kV Bus 2A09 Fails to Auto Transfer on Rx Trip Time Position Applicants Actions or Behavior SRO VERIFY Reserve AUX Transformers to unit energized.

SRO VERIFY all Non-1E 4kV buses energized.

RO/BOP STOP unloaded Diesel Generators.

SRO VERIFY all of the following: At least one CCW critical loop in service AND CCW Pump aligned to Non-Critical Loop (NCL) and Letdown operating.

INITIATE applicable actions of SO23-12-11, Attachment 2, FLOATING SRO STEPS.

RO VERIFY PZR level between 10% and 70% AND trending to between 30% and 60%.

VERIFY PZR pressure (NR and WR) controlled between 1740 PSIA and RO 2380 PSIA AND trending to between 2025 PSIA and 2275 PSIA.

VERIFY SBCS available: MSIVs - open AND Condenser Backpressure BOP less than SBCS Interlock Setpoint.

• (RNO) OVERRIDE (as required) and OPERATE available S/G ADVs.

OPERATE MFW to establish at least one intact S/G level between 40% NR and 80% NR BOP

• (RNO) OVERRIDE and operate AFW to establish at least one intact S/G level between 40% NR and 80% NR.

RO VERIFY operating Loop RCS TCOLD stable or controlled.

VERIFY at least one RCP operating.

SRO

• (RNO) GO TO step 11.

VERIFY Natural Circulation Established in at least one loop:

• VERIFY operating loop T (THOT - TCOLD) less than 58°F.

• VERIFY RCS THOT and TCOLD NOT rising.

RO

• VERIFY Core Exit Saturation Margin greater than or equal to 20°F.

• VERIFY operating loop RCS THOT and REP CET within 16°F.

• VERIFY Reactor Vessel level greater than or equal to 100% (Plenum).

Scenario Termination: When the crew has verified Natural Circulation and Non-1E 4kV bus 2A09 has been manually transferred to the Reserve Auxiliary Transformer, or at Lead Evaluators discretion, the scenario may be terminated.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7, 8, 9 Page 24 of 25 Event

Description:

1E 4kV Bus 2A04 OC Trip, Two Full Length CEAs Fail to Insert on Rx Trip, Non-1E 4kV Bus 2A09 Fails to Auto Transfer on Rx Trip Time Position Applicants Actions or Behavior Examiner Note: The following are steps 12-17 of SO23-12-1, Standard Post Trip Actions.

RO INITIATE Attachment 4, ADMINISTRATIVE ACTIONS.

RO ENSURE a PA System announcement was made regarding the Reactor trip.

OPERATE SBCS to maintain RCS TCOLD between 540°F and 550°F.

RO * (RNO) OPERATE ADVS to maintain RCS TCOLD between 540°F and 550°F.

RO VERIFY TELECOM 480VAC FDR BKR HS0800S-2 (Q800S) CLOSED RO VERIFY TELECOM 480VAC FDR BKR HS0800N-2 (Q800N) CLOSED.

VERIFY all Non-1E 4kV Buses ENERGIZED.

RO * (RNO) TRANSFER Non-1E 4kV Bus 2A09 to available Reserve Auxiliary Transformer.

RO VERIFY 480V Load Centers B15 and B16 ENERGIZED.

RO ENSURE 3rd Point Heater Drain Pumps STOPPED.

VERIFY RTO RESET.

• (RNO) IF a MFW pump in service THEN RESET RTO per SO23-9-6, Feedwater Control System Operation RO Examiner Note: RTO will not be reset until AFW valves are overridden and opened to raise SG levels to 40-80% NR due to the CIAS tripping both MFW pumps.

MAINTAIN one MFW Pump and a maximum of three Condensate Pumps in RO operation.

• (RNO) ENSURE S/G levels being maintained by AFW Pumps.

ENSURE FIC-3294, Condensate Pump miniflow controller set for proper Condensate pump configuration:

RO

• One pump - 4500 GPM

• Two pumps - 6000 GPM

• Three pumps - 9000 GPM RO PLACE Condensate Draw-off valve LV-3245 to DISABLE.

VERIFY SO23-12-2, REACTOR TRIP RECOVERY being implemented.

RO * (RNO) ENSURE S/G Blowdown valves HV-4054 and HV-4053 CLOSED.

• (RNO) GO TO step 16.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7, 8, 9 Page 25 of 25 Event

Description:

1E 4kV Bus 2A04 OC Trip, Two Full Length CEAs Fail to Insert on Rx Trip, Non-1E 4kV Bus 2A09 Fails to Auto Transfer on Rx Trip Time Position Applicants Actions or Behavior ENSURE the following valves closed:

• Extraction Steam Block valves HV-8800, HV-8812, HV-8804, HV-8810, HV-8808, HV-8820, HV-8806, and HV-8816.

RO

• Main Steam to Reheater Block, Bypass, Warmup and Control valves HV-2703 or HV-2704, HV-2721, and HV-2751.

• Bled Steam to Reheaters Block Valve HV-2712A/B.

RO VERIFY Main Generator voltage less than 24kV.

VERIFY annunciators RESET:

RO

• 99A26 TURBINE LUBE OIL TEMP HI

• 99A46 TURBINE BRG OIL DRAIN TEMP HI INITIATE SO23-10-2, TURBINE SHUTDOWN, Attachment for Unloading RO the Generator and Removing the Unit from Line.

RO VERIFY BOTH Start-Up Range channels OPERABLE.

SONGS 2012 NRC Sim Scenario #2 Rev d.docd

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 & 3 Scenario No.: 3 Op Test No.: October 2012 NRC Examiners: Operators:

Initial Conditions: 100% Power MOC Turnover: Perform post-maintenance testing of CEA 21. Maintain steady state conditions.

Critical Tasks:

• Emergency Borate the RCS following a failure of two full-length CEAs to insert on the Reactor trip prior to exiting SO23-12-1, Standard Post Trip Actions.

• Within 10 minutes of loss of heat removal from S/G E088, the crew transfers the primary to secondary heat sink to S/G E089 by steaming S/G E089, maintaining Psat for the lowest RCS Tc, per SO23-12-11, FS-30, Establish Stable RCS Temperature During ESDE.

• Perform SI Throttle Stop prior to the Pressurizer going solid per SO23-12-11, FS-7, Verify SI Throttle Stop Criteria.

• Isolate S/G E-088 prior to exiting SO23-12-5, Excess Steam Demand Event.

Event No. Malf. Event Type* Event Description No.

1 (10 min) SG05A I (BOP, SRO) S/G E-088 Level Transmitter LT-1123-1 fails high TS (SRO) 2 (15 min) N (RO, SRO) Exercise CEA 21 for post-maintenance testing 3 (30 min) RD2103 I (SRO) CEA 21 Drop ~ 75 TS (SRO) 4 (45 min) R (RO, BOP, SRO) Rapid Power Reduction to 90%

5 (50 min) TP02B C (BOP) TPCW Pump P-120 O/C, Standby Pump P-119 Fails to Auto Start TP08A 6 (55 min) FW04A M (RO, BOP, SRO) MFW Rupture in Containment (100% severity, 10 minute ramp) 7 (60 min) RD5902 C (RO) Two Full Length CEAs Fail to Fully Insert on Reactor Trip RD2102 8 (65 min) RP01P C (RO) AFW Pump P-141 Fails to Auto Start on EFAS

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 6 Total malfunctions (5-8) 2 Malfunctions after EOP entry (1-2) 3 Abnormal events (2-4) 1 Major transients (1-2) 2 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 4 Critical tasks (2-3)

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Scenario Event Description NRC Scenario #3 SCENARIO

SUMMARY

NRC #3 The crew will take the watch at 100% Reactor power with a turnover item to exercise CEA #21 for post-maintenance testing.

Prior to exercising the CEA, S/G E-088 level transmitter LT-1123-1 will fail high. The crew will enter SO23-13-18, RPS Malfunctions, and identify the appropriate bistables to bypass for the failed transmitter. The BOP will also bypass the failed indicator in the DCS FWCS as a result of the failure.

When the CRS identifies applicable Technical Specifications, the SM will prompt the CRS to exercise CEA 21.

The ATC will insert CEA 21 2 steps and attempt to withdraw the CEA 2 steps, however when the rod withdrawal switch is placed in the withdraw position, CEA 21 will drop to ~ 75. The crew will enter SO23-13-13, Misaligned CEA to mitigate the rod drop. Major recovery actions include reducing Turbine load to restore Tcold to the pre-drop value and commence a downpower to comply with Technical Specifications.

After the downpower has been commenced, the running TPCW pump will trip on overcurrent and the standby TPCW pump will fail to auto start. The BOP will take prompt and prudent action to start the standby TPCW pump manually.

When the standby TPCW pump has been started, a MFW rupture will occur inside Containment. The crew will identify the MFW rupture and manually trip the Reactor.

Upon the Reactor trip, two full-length CEAs will fail to insert, requiring an emergency boration. The emergency boration will be performed using a Boric Acid Makeup Pump.

EFAS will automatically actuate ~ 30 seconds after the trip and AFW Pump P-141 will fail to auto-start.

A member of the crew will recognize this and manually start P-141.

Following SPTAs, the CRS will diagnose an Excess Steam Demand Event and transition to SO23-12-5, ESDE. The major recovery actions for the ESDE will be the performance of FS-30, Stablization of RCS Temperature during an ESDE. SIAS will actuate due to high Containment pressure, however since there is no inventory loss from the RCS, SI throttle/stop will be performed by the ATC. Once RCS temperature has been stabilized, the CRS will direct the isolation of the affected S/G, at which point the scenario may be terminated.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Scenario Event Description NRC Scenario #3 Risk Significance:

• Failure of risk important system prior to trip: Slipped CEA MFW Rupture

• Risk significant core damage sequence: MFW Rupture Two full length CEAs fail to insert on Rx trip.

• Risk significant operator actions: Emergency boration following two full length CEAs failing to insert on Rx trip.

Stabilization of RCS temperature following loss heat sink on S/G E088.

Perform SI Throttle Stop actions to prevent the Pressurizer from going solid.

Isolate S/G E088 following transfer of primary to secondary heat sink to S/G E089.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Scenario Event Description NRC Scenario #3 MACHINE OPERATOR INSTRUCTIONS for SIMULATOR SETUP INITIALIZE to IC-230 and OPEN NRC Scenario #3 event file.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER SETUP MALF RP01P AFW Pump P-141 Fails to Auto Start on EFAS Fail to Start 1 MALF SG05A SG E088 Level Transmitter LT-1123-1 Fails High 100 RF RP51 PPS Door Open Annunciator Open RF RP52H Lo SG-2 Level Channel A Bypass Bypass RF RP52J Hi SG-2 Level Channel A Bypass Bypass RF RP52V Hi SG-2 DP EFAS-2 Channel A Bypass Bypass RF RP51 PPS Door Open Annunciator Close 2 N/A N/A Post-maintenance Exercise of CEA 21 3 MALF RD2103 CEA 21 Drop Drop Rod withdrawl switch to the withdraw position MALF RD2103 CEA 21 Drop (malfunction delete) Normal CEA 21 less than 100 inches 4 N/A N/A Rapid Downpower to 90%

5 MALF TP02B TPCW Pump P-120 OC Trip Fault MALF TP08A TPCW Pump P-119 Fails to Auto Start Fail to Start 6 MALF FW04A MFW Rupture Inside Containment Fault 7 MALF RD5802 CEA 58 Fails to Insert on Rx Trip Stuck MALF RD2102 CEA 21 Fails to Insert on Rx Trip Stuck 8 Setup Setup AFW Pump P-141 Fails to Auto Start on EFAS Fail to Start SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Scenario Event Description NRC Scenario #3 Machine Operator:

• RESTORE to IC-215

• OPEN 2012 NRC Scenario #3 event file

• RUN Setup File 1

• ENSURE Pressurizer Level and Pressure Selector Switches are selected to Channel Y

• ENSURE blend setpoints are 13.2 gpm for BA and 74.8 gpm for PMW

• ENSURE SO23-5-1.7 Attachment 9 MOC placard is posted

• ENSURE OP AID 005-23 on CR63 has BQ aligned to Unit 2, BS aligned to Unit 3

• ENSURE OP AID 005-11 on CR64 has E336 aligned to Unit 2, E335 aligned to Unit 3

• ENSURE OP AID 005-5 for Backpressure Control Valves has PV201B circled

• ENSURE OP AID 005-5 for Letdown Flow Control Valve has LV110A circled

• ENSURE alarms are active Control Room Annunciators in Alarm:

• None SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 1 Page 6 of 28 Event

Description:

SG E088 Level Transmitter LT-1123-1 Fails High Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 1, S/G E-088 Level Transmitter Fails High Indications Available:

• 56A21 SG2 E088 Level Hi Channel Trip

• 56A31 SG2 E088 Level Hi Pretrip

• 52A13 FWCS Trouble Examiner Note: The following steps are from SO23-13-18, RPS Malfunction DETERMINE failure by observing instrumentation for the affected channel RO AND alternate redundant indications monitoring the same plant parameters.

SRO DETERMINE a Single PPS Channel has FAILED and GO TO Step 3.

SRO REFER to Attachment 10 and determine Functional Unit(s) affected.

Examiner Note: Affected bistables are Channel A bistables 8, 10, and 22 and Channel A DEFAS-2.

PLACE the affected Functional Unit in BYPASS per SO23-3-2.12, Section for SRO Bypass Operation of Trip Channels.

MO CUE: If requested to place Channel A bistables 8, 10, and 22, and Channel A DEFAS-2 in bypass, EXECUTE PPS Bypasses event.

CONFIRM failure does NOT affect RPS/ESFAS Matrix Logic, RPS/ESFAS SRO Initiation Logic, RTCBs, RPS/ESFAS Manual Trip, or ESFAS Actuation Logic.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 1 Page 7 of 28 Event

Description:

SG E088 Level Transmitter LT-1123-1 Fails High Time Position Applicants Actions or Behavior CONFIRM failure does NOT affect the Feedwater Digital Control System.

• (RNO) BYPASS the affected instrument for E-088 and/or E-089 per SO23-3-2.38, Section for Bypassing Selected Feedwater Control Signals:

• Implement the requirements for a Reactivity Brief as Peer Check per OSM-14, Section for Reactivity Management.

• From the applicable SG FW Control DCS, go to the SELECTED BOP SIGNALS screen.

• Verify the D channel signal is valid.

• SELECT BYPASS for the instrument to be placed in bypass.

• Verify the instrument indicates BYPASS.

• Verify the D channel is not in BYPASS.

• Verify the Selected Signal (SS) output looks valid.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 1 Page 8 of 28 Event

Description:

SG E088 Level Transmitter LT-1123-1 Fails High Time Position Applicants Actions or Behavior FOLLOW the action requirements of the applicable Tech. Spec./LCS listed in Attachment 10.

• LCO 3.3.1

• Condition A - One or more Functions with one automatic RPS trip channel inoperable.

• Action A.1 - Place Channel in bypass or trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

• LCO 3.3.5

• Condition A - One or more Functions with one automatic ESFAS trip channel inoperable (other than RWST Level-Low for the RAS function or SG Pressure-Low or SG Pressure Difference-High for the EFAS function).

SRO

• Action A.1 - Place Functional Unit in bypass or trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Examiner Note: When taking the action for LCO 3.3.1, the crew will bypass the SG Pressure Difference - High for the EFAS function which now puts the crew in LCO 3.3.5, Condition B (for which the action is immediately completed). Applicable LCO and Action below:

• LCO 3.3.5

• Condition B - One automatic trip channel inoperable for RWST Level-Low for the RAS function or SG Pressure-Low or SG Pressure Difference-High for the EFAS function.

• Action B.1 - Place Functional Unit in bypass within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Examiner Note: When affected bistables have been bypassed and Technical Specifications have been evaluated, or at Lead Evaluators discretion, proceed to the next event.

FLOOR CUE: If the crew does not perform the CEA exercise following the RPS failure, AND the Lead Evaluator is ready to proceed to the next event, REPORT as the Shift Manger and ask the CRS for the status of the CEA exercise.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2, 3, 4 Page 9 of 28 Event

Description:

Exercise CEA 21 for Post Maintenance Testing, CEA 21 drops ~ 50 into the core, Rapid Power Reduction Time Position Applicants Actions or Behavior Examiner Note: The following steps are from SO23-3-2.19, CEDMCS Operation (for CEA 21 post-maintenance test).

POSITION Group Select Switch to the group containing the CEA to RO be moved.

POSITION the Individual CEA Selection Switch to the CEA to be RO moved.

RO VERIFY the individual CEA light is ILLUMINATED.

RO POSITION Mode Select Switch to MI.

VERIFY the group indicator lamps are ILLUMINATED for the group RO selected.

RO WITHDRAW or INSERT CEA.

Examiner Note: The following steps are from SO23-13-13, Misaligned CEA.

SRO VERIFY Special Test Exception 3.1.12 (Low Power Physics Testing) is NOT invoked.

RO VERIFY NOT more than one CEA is misaligned > 7 inches.

RO ENSURE CEDMCS Mode Select Switch positioned to OFF.

RO VERIFY CEA misaligned.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2, 3, 4 Page 10 of 28 Event

Description:

Exercise CEA 21 for Post Maintenance Testing, CEA 21 drops ~ 50 into the core, Rapid Power Reduction Time Position Applicants Actions or Behavior REDUCE Turbine load to RESTORE RCS Cold Leg temperature to approximately the pre-drop value per SO23-5-1.7, Turbine Load Change Using Speed/Load Adjustment.

• Implement the requirements for a Reactivity Brief and Peer Check per OSM-14, Operations Department Expectations, Section for Reactivity Management.

• INITIATE monitoring TCOLDAVG using PCS.

• ADJUST Turbine load to maintain Tcold per Attachment 15 by one or both of the following methods:

BOP

• Coarse Adjustment - Use HS-2210, Main Turbine Speed/Load Control, RAISE or LOWER pushbuttons.

• Fine Adjustment - ACTIVATE the DCS Speed/Load Pushbuttons Box and ENSURE the Rate is set at an acceptable MW/MIN value.

• SELECT MODIFY.

• Use the UP or DOWN buttons or the +0.5 or -0.5 buttons.

• VERIFY Turbine load stabilizes at the target value.

VERIFY the Reactor is critical and RECORD initial and stabilized Reactor SRO power levels in the NCO Log.

Within 15 minutes, INITIATE monitoring DNBR and LPD per SO23-3-3.6, SRO Attachment for DNBR Margin/Linear Heat Rate Limit Monitoring.

SRO INITIATE Attachment 3, Misaligned CEA Checklist.

SRO VERIFY Reactor power is > 50%.

Within 15 minutes of discovery, INITIATE Reactor power reduction in SRO accordance with region of Acceptable Operation of selected graph from Attachment 4. Use Table below to aid in graph selection.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2, 3, 4 Page 11 of 28 Event

Description:

Exercise CEA 21 for Post Maintenance Testing, CEA 21 drops ~ 50 into the core, Rapid Power Reduction Time Position Applicants Actions or Behavior Examiner Note: CEA 21 is a Group 6 Full Length CEA, which requires a 5% power reduction in the first hour and a total of 10% power reduction within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Examiner Note: Technical Specifications for Slipped CEA:

• LCO 3.1.5

• Condition A - One Regulating CEA trippable and misaligned from its group by > 7 inches.

• Action A.1 - Initiate THERMAL POWER reduction in accordance with COLR requirements within 15 minutes.

• Action A.2 - Restore the misaligned CEA(s) to within 7 inches of its group within two (2) hours.

COMMENCE LOWERING Turbine Generator load while maintaining Tcold per BOP SO23-5-1.7, Guidelines for Changing Turbine Load and Reactor Power.

Examiner Note: The following steps are from SO23-13-28, Rapid Power Reduction.

SRO INITIATE notifying the GOC.

If taking the Unit Offline or to target power plateau < 750 MWe ( 65% Rx SRO Power), then INITIATE an immediate MSR Cooldown per SO23-10-2, Attachment for MSR Cooldown for Load Reduction/Turbine Shutdown.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2, 3, 4 Page 12 of 28 Event

Description:

Exercise CEA 21 for Post Maintenance Testing, CEA 21 drops ~ 50 into the core, Rapid Power Reduction Time Position Applicants Actions or Behavior SRO INITIATE monitoring CV-9739, COLSS Raw Delta-T Power.

INITIATE Forcing PZR spray flow using two valves per SO23-3-1.10:

• ENSURE a Reactivity Brief has been conducted for this activity per SO123-0-A1, Section for Reactivity.

• COMMENCE monitoring RCS pressure.

• VERIFY RCS pressure > 1500 psia.

RO

• PLACE both PZR Spray Valve Controllers in AUTO.

• POSITION all Non-1E Backup Heaters to ON.

• LOWER PIC-0100, PZR Pressure Contoller, setpoint as required to maintain RCS pressure as directed by the CRS (set setpoint to ~ 2225 psia).

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2, 3, 4 Page 13 of 28 Event

Description:

Exercise CEA 21 for Post Maintenance Testing, CEA 21 drops ~ 50 into the core, Rapid Power Reduction Time Position Applicants Actions or Behavior BORATE to the Charging Pump Suction per SO23-3-2.2:

• Implement the requirements for a Reactivity Brief and Peer check per OSM-14, Operations Department Expectations, Section for Reactivity Management.

• ENSURE ENTERED required boration flowrate on FIC-0210Y, BAMU Flow Controller.

• If flowrate change, then SELECT SET.

• ENSURE FIC-0210Y in AUTO.

• SET FQIS-0210Y, Boration Counter, to the desired volume as follows:

• SELECT MODIFY.

• ENTER gallons in PRESET.

RO

• SELECT SET PRESET.

• SELECT EXIT.

• SELETE the BAMU Pump associated with the BAMU Tank used.

• VERIFY CLOSED FV-9253, Blended Makeup to VCT Isolation.

• ENSURE HV-9257, BAMU to Charging Pump Suction Block Valve, in AUTO.

• COMMENCE monitoring plant parameters.

• From the MODE SELECTOR:

• SELECT MODIFY.

• SELECT BORATE.

• SELECT GO.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2, 3, 4 Page 14 of 28 Event

Description:

Exercise CEA 21 for Post Maintenance Testing, CEA 21 drops ~ 50 into the core, Rapid Power Reduction Time Position Applicants Actions or Behavior INSERT CEAs for ASI Control per SO23-3-2.19, to the target level within the following guidance:

• INSERT PLCEAs (Insertion Limit is 112.5. Insertion should be limited to 115 inches or until Power reaches target plateau.)

• INSERT Group 6 to target level. [90" if RCS Boron is < 110 ppm.]

(The maximum recommended is 75 inches.)

RO

• POSITION Group Select switch to the CEA group to be moved.

• POSITION Mode Select Switch to the appropriate mode.

• VERIFY the group indicator lamps are ILLUMINATED for the group selected.

• POSITION CEA(s) as directed by SRO Ops. Supv.

• When CEA positioning has completed, then POSITION the Mode Select Switch to OFF.

INITIATE SO23-5-1.7, Section for Turbine Load Change using Setpoint Adjustment:

• Implement the requirements for a Reactivity Brief and Peer Check per OSM-14, Operations Department Expectations, Section for Reactivity Management.

• INITIATE monitoring TCOLDAVG using PCS.

• PLACE the 1st STAGE PRESSURE feedback loop in service.

• ACTIVATE the Turbine DCS Setpoints Box and SELECT MODIFY.

BOP

• SET the Demand to the target MW value and SELECT ENTER.

• Set the Rate to the target MW/MIN value and SELECT ENTER.

• INITIATE Turbine load change, SELECT P2.

• Control RCS Tcold within the operating band by adjusting the rate setpoint or by canceling and reinitiating the load change as necessary.

• VERIFY Turbine load stabilizes at the target value.

• REMOVE 1st STAGE PRESSURE feedback loop from service.

• RESTORE the Rate to 100 MW/MIN and SELECT ENTER.

SRO INITIATE SO23-5-1.7, Attachment for Power Descension.

If Reactor power changed > 15% in one hour, then NOTIFY Chemistry SRO and LOG the notification.

SRO NOTIFY Reactor Engineering and log the notification.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2, 3, 4 Page 15 of 28 Event

Description:

Exercise CEA 21 for Post Maintenance Testing, CEA 21 drops ~ 50 into the core, Rapid Power Reduction Time Position Applicants Actions or Behavior Maintain Turbine load, RCS Temperature, and ASI within the expected ALL operating bands per SO23-5-1.7.

Examiner Note: When Reactor Power has been lowered 3-5%, or at Lead Evaluators discretion, proceed to Event 5, TPCW Pump OC Trip, Standby TPCW Pump Fails to Auto Start.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5 Page 16 of 28 Event

Description:

TPCW Pump OC Trip, Standby TPCW Fails to Auto Start Time Position Applicants Actions or Behavior Machine Operator: When directed, EXECUTE Event 5, TPCW Pump OC Trip, Standby TPCW Pump Fails to Auto Start.

Indications Available:

• 99A31 TPCW Pump OC

• 99A12 TPCW Press Lo-Lo Examiner Note: The following steps are from Alarm Response Procedure 99A31, TPCW Pump OC.

BOP ENSURE Standby TPCW Pump Has Auto started.

Examiner Note: The standby TPCW Pump may be started prior to referring to the ARP per OSM-14, Operations Department Expectations, Prompt and Prudent Actions.

If a TPCW Pump Supply Breaker has Tripped, then initiate SO23-6-9, Section BOP for 4 kV Feeder Circuit Relay.

Examiner Note: When the standby TPCW Pump has been started, or at Lead Evaluators discretion, proceed to Event 6, MFW Rupture Inside Containment.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 17 of 28 Event

Description:

MFW Rupture Inside Containment, Two Full Length CEAs Fail to Insert on Reactor Trip, AFW Pump P-141 Fails to Auto Start on EFAS Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 6, MFW Rupture Inside Containment.

Indication Available:

• 60A02 Containment Humidity Hi

• 57C43 RCS Leakage Abnormal

• 56A56 Containment Sump Level Hi Examiner Note: The crew should recognize a non-radioactive HELB inside Containment and trip the Reactor. The following steps are from SO23-12-1, Standard Post Trip Actions.

Verify Reactor Trip:

RO VERIFY Reactor Trip Circuit Breakers (8) OPEN.

RO VERIFY Reactor power - LOWERING AND Startup rate NEGATIVE.

RO VERIFY maximum of one full length CEA NOT fully inserted.

• (RNO) INITIATE Emergency Boration.

• VERIFY Refueling NOT in progress.

• VERIFY at least one Charging Pump is available.

• DEPRESS OPEN on 2HV-9247, Emergency Boration Block Valve and verify valve is open AND DEPRESS START for either BAMU Pump and verify pump is running.

• CLOSE 2HV-9236, BAMU Pump 2MP-174 Recirculation Valve.

• CLOSE 2HV-9231, BAMU Pump 2MP-175 Recirculation Valve.

• CLOSE 2FV-9253, Blended Makeup to VCT Isolation, in MANUAL.

• ENSURE charging flow > 40 gpm.

• START additional Charging Pumps as necessary to increase flow rate.

• VERIFY Boric Acid delivery to RCS by monitoring BAMU Tank level lowering.

• (RNO) Record time of Emergency Boration initiation _______.

Critical Task: Emergency Borate the RCS following Reactor Trip following the failure of two full-length CEAs to insert on Reactor trip prior to exiting SO23-12-1, Standard Post Trip Actions.

CCT Time:__________

Examiner Note: Emergency boration may be stopped when power is <10-4% power and power decreasing or stable.

Verify Turbine Trip:

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 18 of 28 Event

Description:

MFW Rupture Inside Containment, Two Full Length CEAs Fail to Insert on Reactor Trip, AFW Pump P-141 Fails to Auto Start on EFAS Time Position Applicants Actions or Behavior BOP ALL HP and LP Stop and Governor valves CLOSED.

BOP VERIFY BOTH Unit Output Breakers OPEN.

BOP VERIFY Main Turbine speed less than 2000 RPM OR lowering.

Examiner Note: The crew should identify AFW Pump P-141 failed to start on EFAS and manually start P-141.

SRO INITIATE Attachment 1, WORKSHEET.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 19 of 28 Event

Description:

MFW Rupture Inside Containment, Two Full Length CEAs Fail to Insert on Reactor Trip, AFW Pump P-141 Fails to Auto Start on EFAS Time Position Applicants Actions or Behavior Examiner Note: The crew will request to pull forward FS-30 during SPTAs. The BOP will perform this procedure and the RO will perform the BOPs SPTA verfications.

The following steps are from SO23-12-11, FS-30, Stabilize RCS Temperature During ESDE:

VERIFY S/G least affected by ESDE NOT isolated for SGTR,

• VERFIY most affected S/G level less than 50% WR.

• On the least affected S/G:

• POSITION ADV controller to match existing S/G pressure.

• ENSURE OVERRIDE pushbutton DEPRESSED.

• ENSURE OPEN/MODULATE pushbutton DEPRESSED.

• MAINTAIN least affected S/G pressure approximately 200 psia above most affected S/G pressure.

• VERIFY S/G dryout on most affected S/G:

• RCS Tcold stable or rising.

OR

• S/G pressure less than 200 psia.

• STABILIZE least affected S/G pressure:

• VERIFY ADV in AUTO/MODULATE.

• MAINTAIN Psat for lowest RCS Tcold.

• STABILIZE AFW flow.

• VERIFY RCS pressure is to the right of the Appensix E curve on Attachment 30, Post-Accident Pressure / Temperature Limits.

• OPERATE feedwater on least affected S/G to maintain level between 40 and 80% NR.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 20 of 28 Event

Description:

MFW Rupture Inside Containment, Two Full Length CEAs Fail to Insert on Reactor Trip, AFW Pump P-141 Fails to Auto Start on EFAS Time Position Applicants Actions or Behavior Critical Task: Within 10 minutes of loss of heat removal from S/G E088, the crew transfers the primary to secondary heat sink to S/G E089 by steaming S/G E089, maintaining Psat for the lowest RCS Tc, per SO23-12-11, FS-30, Establish Stable RCS Temperature During ESDE.

CCT Time:__________

Examiner Note: The following steps are the continuation of SO23-12-1, Standard Post Trip Actions.

Verify Vital Auxiliaries:

BOP VERIFY BOTH 1E 4kV Buses ENERGIZED.

BOP VERIFY all 1E 480V buses ENERGIZED.

BOP VERIFY all Class 1E DC Buses ENERGIZED.

BOP VERIFY all Non-1E 4kV Buses ENERGIZED.

BOP VERIFY one CCW Train OPERATING AND aligned to Non-Critical Loop (NCL) and Letdown Heat Exchanger.

Verify RCS Inventory Control:

RO VERIFY PZR level between 10% and 70% AND trending to between 30% and 60%.

RO VERIFY Core Exit Saturation Margin greater than or equal to 20°F.

Verify RCS Pressure Control:

RO VERIFY PZR pressure between 1740 PSIA and 2380 PSIA AND trending to between 2025 PSIA and 2275 PSIA.

Verify Core Heat Removal:

RO VERIFY at least one RCP OPERATING.

RO VERIFY core loop T (THOT -TCOLD) less than 10°F.

RO VERIFY Core Exit Saturation Margin greater than or equal to 20°F.

Verify RCS Heat Removal:

VERIFY at least one S/G level between 21% NR and 80% NR AND BOP Feedwater - AVAILABLE.

• (RNO) ENSURE EFAS initiated.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 21 of 28 Event

Description:

MFW Rupture Inside Containment, Two Full Length CEAs Fail to Insert on Reactor Trip, AFW Pump P-141 Fails to Auto Start on EFAS Time Position Applicants Actions or Behavior BOP VERIFY RCS TCOLD between 540°F and 550°F.

VERIFY S/G pressures between 960 PSIA and 1050 PSIA.

• (RNO) IF S/G pressure less than 740 PSIA THEN ENSURE MSIS ACTUATED AND GO TO step 9.

• (RNO) IF S/G pressure less than 960 PSIA THEN ENSURE Main Steam to Reheaters valves CLOSED. IF Main Steam to Reheaters CANNOT be verified isolated, AND RCS TCOLD uncontrolled, THEN BOP CLOSE MSIVs AND OPERATE ADVs to maintain S/G pressure between 960 PSIA and 1050 PSIA.

• (RNO) IF S/G pressure greater than 1050 PSIA THEN OPERATE SBCS to maintain S/G pressure between 960 PSIA and 1050 PSIA OR OPERATE ADVs to maintain S/G pressure between 960 PSIA and 1050 PSIA.

Verify Containment Isolation:

VERIFY Containment pressure less than 1.5 PSIG.

• (RNO) IF Containment pressure greater than 3.4 PSIG, THEN:

• ENSURE the following - ACTUATED:

• SIAS RO

• CIAS

• CCAS

• CRIS

• ENSURE all RCPs STOPPED.

RO VERIFY Containment Area Radiation Monitors NOT alarming or trending to alarm.

RO VERIFY Secondary Plant Radiation Monitors NOT alarming or trending to alarm.

Verify Containment Temperature and Pressure Control:

RO VERIFY Containment average temperature less than 120°F.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 22 of 28 Event

Description:

MFW Rupture Inside Containment, Two Full Length CEAs Fail to Insert on Reactor Trip, AFW Pump P-141 Fails to Auto Start on EFAS Time Position Applicants Actions or Behavior VERIFY Containment pressure less than 1.5 PSIG.

• ENSURE proper functioning of Normal Containment Cooling.

• ENSURE at least one Containment Dome Air Circulator OPERATING.

• IF Containment pressure greater than 3.4 PSIG, THEN:

• ENSURE the following ACTUATED:

• SIAS

• CIAS

• CCAS RO

• CRIS

• ENSURE all RCPs - STOPPED.

• ENSURE all available Containment Emergency Cooling Units OPERATING.

• IF Containment pressure greater than 14 PSIG, THEN:

• ENSURE CSAS - ACTUATED.

• ENSURE all available Containment Spray Header flows greater than 1600 GPM.

VERIFY all safety function criteria per Attachment 1, WORKSHEET RO RECOVERED.

• (RNO) COMPLETE Attachment 2, RECOVERY DIAGNOSTICS.

Examiner Note: The CRS should diagnose a single event, Excess Steam Demand Event (MFW Rupture), and identify SO23-12-5, Excess Steam Demand Event, as the optimal EOI.

VERIFY REACTOR TRIP RECOVERY DIAGNOSED.

SRO (RNO) ENSURE at least one RCP in each loop stopped.

INITIATE steps 12 through 17.

Examiner Note: Steps 12 through 17 of SO23-12-1, Standard Post Trip Actions, are located at the end of the scenario guide.

SRO IMPLEMENT EOI diagnosed.

Examiner Note: The following steps are from SO23-12-5, Excess Steam Demand Event.

SRO RECORD time of EOI entry _______.

SRO INITIATE SO23-12-10, SAFETY FUNCTION STATUS CHECKS.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 23 of 28 Event

Description:

MFW Rupture Inside Containment, Two Full Length CEAs Fail to Insert on Reactor Trip, AFW Pump P-141 Fails to Auto Start on EFAS Time Position Applicants Actions or Behavior INITIATE FOLDOUT PAGE:

• IF SIAS has actuated, THEN INITIATE FS-7, VERIFY SI Throttle/Stop Criteria.

• IF all RCPs are stopped, THEN INITIATE FS-3, MONITOR Natural SRO Circulation Established.

• IF SIAS has initiated, THEN INITIATE SO23-12-11, Attachment 22, NON-QUALIFIED LOAD RESTORATION.

• IF any S/G steaming rate - NOT operator controlled, THEN INITIATE FS-30, ESTABLISH Stable RCS Temperature during ESDE.

Examiner Note: The following steps are from FS-7, Verify SI Throttle/Stop Criteria.

• VERIFY at least one S/G operating:

• SBCS or ADV available AND feedwater available.

• VERIFY PZR level greater than 30% and NOT lowering.

• VERIFY Core Exit Saturation Margin greater than or equal to 20ºF.

• VERIFY Reactor Vessel level greater than or equal to 100% in the plenum.

• RCS Cooldown NOT in progress.

• VERIFY SI Pumps NOT operating to meet Reactivity Control RC-3 Success Path.

RO

• THROTTLE OR STOP SI Pumps as required, one train at a time.

• VERIFY Charging Pumps NOT operating to meet Reactivity Control RC-2 Success Path.

• VERIFY PZR Level less than 80%.

• STOP Charging Pumps as required one at a time.

Examiner Note: OSM-9, Standard EOI Good Practices and Strategies, provides direction for SI Throttle/Stop during an ESDE as follows, If a SINGLE event ESDE with two trains HPSI running, then stop HPSI Pump on one train, and close the valves on the other train.

Critical Task: Perform SI Throttle Stop prior to the Pressurizer going solid per SO23-12-11, FS-7, Verify SI Throttle Stop Criteria.

CCT Time:__________

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 24 of 28 Event

Description:

MFW Rupture Inside Containment, Two Full Length CEAs Fail to Insert on Reactor Trip, AFW Pump P-141 Fails to Auto Start on EFAS Time Position Applicants Actions or Behavior Examiner Note: The following steps are from FS-3, Monitor Natural Circulation Established.

• VERIFY at least one S/G is operating:

• SBCS or ADV available AND feedwater available.

• VERIFY all RCPs are stopped.

o VERIFY operating loop T less than 58ºF.

o VERIFY Thot and Tcold NOT rising.

o VERIFY Core Exit Saturation Margin greater than or equal to 20ºF.

o VERIFY operating loop Thot and REP CET within 16ºF.

RO o VERIFY Reactor Vessel level greater than or equal to 100% in the plenum.

o Examiner Note: If any steps marked with a are not satisfied:

• MAXIMIZE available S/G level less than 80% NR.

• RAISE available S/G steaming rate.

• RAISE Core Exit Saturation Margin greater than or equal to 20ºF.

Examiner Note: The following steps are the Control Room actions from SO23-12-11, Attachment 22, Restoration of Non-Qualified Loads.

• OBTAIN approval of Shift Manager to restore non-qualified loads required for plant operations.

• VERIFY TELECOM 480VAC FDR BKR HS-0800S-2 closed.

RO

• VERIFY TELECOM 480VAC FDR BKR HS-0800N-2 closed.

• ENSURE HS-1738-1, Non-1E UPS Normal Feeder, is placed in OVERRIDE/CLOSED on panel CR63.

Examiner Note: The following steps are the continuation of SO23-12-5, Excess Steam Demand Event.

SRO VERIFY ESDE diagnosis using Figure 1, BREAK IDENTIFICATION CHART.

SRO INITIATE sampling of both Steam Generators for radioactivity and boron.

NOTIFY Shift Manager/Operations Leader of SO23-12-5, EXCESS STEAM SRO DEMAND EVENT, initiation.

SRO ENSURE Emergency Plan is initiated.

SRO IMPLEMENT PLACEKEEPER.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 25 of 28 Event

Description:

MFW Rupture Inside Containment, Two Full Length CEAs Fail to Insert on Reactor Trip, AFW Pump P-141 Fails to Auto Start on EFAS Time Position Applicants Actions or Behavior SRO IMPLEMENT TIME DEPENDENT STEPS.

VERIFY SIAS actuation required:

• PZR pressure less than SIAS setpoint.

SRO OR

• Containment pressure greater than 3.4 PSIG.

ENSURE the following actuated:

• SIAS SRO

• CCAS

• CRIS SRO RECORD time of SIAS ______.

RO STOP unloaded Diesel Generators.

INITIATE SO23-12-11, Attachment 22, RO NON-QUALIFIED LOAD RESTORATION.

VERIFY MSIS actuation required:

SRO

• S/G pressure less than 740 PSIA.

SRO ENSURE MSIS actuated.

VERIFY CIAS actuation required:

SRO

• Containment pressure greater than 3.4 PSIG.

SRO ENSURE CIAS actuated.

SRO VERIFY SIAS actuated.

ESTABLISH two train operation:

• All available Charging Pumps operating.

• One HPSI and one LPSI per train operating.

• All Cold Leg flow paths aligned.

• VERIFY SI flow required:

SRO

• SI flow indicated OR

• RCS pressure greater than 1250 PSIA.

OR

• VERIFY FS-7, VERIFY SI Throttle/Stop Criteria satisfied.

ENSURE MSIVs closed:

SRO

• E-088 - HV-8205

• E-089 - HV-8204 SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 26 of 28 Event

Description:

MFW Rupture Inside Containment, Two Full Length CEAs Fail to Insert on Reactor Trip, AFW Pump P-141 Fails to Auto Start on EFAS Time Position Applicants Actions or Behavior ENSURE MSIV bypasses closed:

SRO

• E-088 - HV-8203

• E-089 - HV-8202 SRO INITIATE FS-30, ESTABLISH Stable RCS Temperature during ESDE.

SRO IF SIAS actuated THEN INITIATE FS-7, VERIFY SI Throttle/Stop Criteria.

VERIFY RCP NPSH requirements of SO23-12-11, Attachment 30, POST-SRO ACCIDENT PRESSURE / TEMPERATURE LIMITS satisfied.

VERIFY excess steam demand isolated:

• VERIFY BOTH S/Gs levels greater than 10% WR.

• Both S/G pressures stable or rising SRO AND

• RCS TCOLD in each loop stable or rising.

• (RNO) GO TO Step c.

SRO IDENTIFY most affected S/G.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 27 of 28 Event

Description:

MFW Rupture Inside Containment, Two Full Length CEAs Fail to Insert on Reactor Trip, AFW Pump P-141 Fails to Auto Start on EFAS Time Position Applicants Actions or Behavior ISOLATE affected S/G:

• CLOSE/STOP the following components for most affected S/G (E-089):

• MSIV HV-8204

• MSIV Bypass HV-8202

• ADV HV-8421 BOP

• MFIV HV-4052

• AFW valves HV-4731 and HV-4715

• Steam to AFW P-140 HV-8200

• S/G Blowdown Isolation HV-4053

• S/G Water Sample Isolation HV-4057

• Electric AFW Pump P-141

• ENSURE ADV on most affected S/G selected to MANUAL.

Critical Task: Isolate S/G E-089 prior to exiting SO23-12-5, Excess Steam Demand Event.

CCT Time:__________

Scenario Termination: When RCS Temperature has been stabilized, SI Throttle Stop has been performed, and S/G E-089 has been isolated, or at Lead Evaluators discretion, the scenario may be terminated.

Examiner Note: The following are steps 12-17 of SO23-12-1, Standard Post Trip Actions.

RO INITIATE Attachment 4, ADMINISTRATIVE ACTIONS.

RO ENSURE a PA System announcement was made regarding the Reactor trip.

OPERATE SBCS to maintain RCS TCOLD between 540°F and 550°F.

RO * (RNO) OPERATE ADVS to maintain RCS TCOLD between 540°F and 550°F.

RO VERIFY TELECOM 480VAC FDR BKR HS0800S-2 (Q800S) CLOSED RO VERIFY TELECOM 480VAC FDR BKR HS0800N-2 (Q800N) CLOSED.

RO VERIFY all Non-1E 4kV Buses ENERGIZED.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 28 of 28 Event

Description:

MFW Rupture Inside Containment, Two Full Length CEAs Fail to Insert on Reactor Trip, AFW Pump P-141 Fails to Auto Start on EFAS Time Position Applicants Actions or Behavior RO VERIFY 480V Load Centers B15 and B16 ENERGIZED.

RO ENSURE 3rd Point Heater Drain Pumps STOPPED.

VERIFY RTO RESET.

• (RNO) IF a MFW pump in service THEN RESET RTO per SO23-9-6, RO Feedwater Control System Operation Examiner Note: RTO will not be reset due to the loss of all feedwater.

MAINTAIN one MFW Pump and a maximum of three Condensate Pumps in RO operation.

• (RNO) ENSURE S/G levels being maintained by AFW Pumps.

ENSURE FIC-3294, Condensate Pump miniflow controller set for proper Condensate pump configuration:

RO

• One pump - 4500 GPM

• Two pumps - 6000 GPM

• Three pumps - 9000 GPM RO PLACE Condensate Draw-off valve LV-3245 to DISABLE.

VERIFY SO23-12-2, REACTOR TRIP RECOVERY being implemented.

RO * (RNO) ENSURE S/G Blowdown valves HV-4054 and HV-4053 CLOSED.

• (RNO) GO TO step 16.

ENSURE the following valves closed:

• Extraction Steam Block valves HV-8800, HV-8812, HV-8804, HV-8810, HV-8808, HV-8820, HV-8806, and HV-8816.

RO

• Main Steam to Reheater Block, Bypass, Warmup and Control valves HV-2703 or HV-2704, HV-2721, and HV-2751.

• Bled Steam to Reheaters Block Valve HV-2712A/B.

RO VERIFY Main Generator voltage less than 24kV.

VERIFY annunciators RESET:

RO

• 99A26 TURBINE LUBE OIL TEMP HI

• 99A46 TURBINE BRG OIL DRAIN TEMP HI INITIATE SO23-10-2, TURBINE SHUTDOWN, Attachment for Unloading RO the Generator and Removing the Unit from Line.

RO VERIFY BOTH Start-Up Range channels OPERABLE.

SONGS 2012 NRC Sim Scenario #3 Rev d.docd

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 & 3 Scenario No.: 4 Op Test No.: October 2012 NRC Examiners: Operators:

Initial Conditions: 100% Power MOC, AFW Pump P-141 OOS.

Turnover: Maintain steady state conditions.

Critical Tasks:

• Transfer the CCW Non-Critical Loop prior to exceeding an RCP thrust bearing temperature exceeding 225°F following a loss of Train A SWC Pump P-112.

• Restore Feedwater to at least one S/G prior to a complete loss of secondary inventory per SO23-12-6, Loss of Feedwater.

Event No. Malf. Event Type* Event Description No.

1 (5 min) SC01A C (BOP, SRO) Train A Saltwater Cooling Pump P-112 Shaft Seizure TS (SRO) 2 (15 min) RC15B I (RO, SRO) Pressurizer Pressure Transmitter PT-0100Y Fails High 3 (25 min) ED07B C (RO, BOP, SRO) Loss of Vital Bus Y02 TS (SRO) 4 (45 min) SWC LP C (BOP, SRO) Stator Water Cooling Pump P-291 OC Trip, P-290 Fails to Auto Start 5 (50 min) SEIS LP C (RO, BOP, SRO) Earthquake / MFBV HV-4051 Closes 6 (55 min) FW23 C (BOP) Loss of Condenser Vacuum on Rx Trip 7 (58 min) FW02B C (SRO) AFW Pump P-504 Shaft Seizure (+ 3 min) 8 (61 min) FW25 M (RO, BOP, SRO) AFW Pump P-140 Overspeed Trip (+ 6 min) 9 (70 min) ELEC C (RO) RCP P-003 Breaker Fails to Open LP

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 9 Total malfunctions (5-8) 3 Malfunctions after EOP entry (1-2) 3 Abnormal events (2-4) 1 Major transients (1-2) 2 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3)

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Scenario Event Description NRC Scenario #4 SCENARIO

SUMMARY

NRC #4 The crew will take the watch with the Reactor operating at 100% power and AFW Pump P-141 OOS.

The running Saltwater Cooling Pump, P-112, will experience a shaft seizure. Approximately 1 minute later, the pump will trip on overcurrent. The crew will enter SO23-13-7, Loss of CCW/SWC, and transfer CCW and SWC to Train B. The crew will also transfer the Letdown Heat Exchanger and Non-Critical Loop from Train A to Train B. The CRS will evaluate Technical Specifications for the loss of Train A SWC.

Following the trip of P-112, the in-service Pressurizer pressure control transmitter will fail high. The crew will take prompt and prudent actions per OSM-14, Operations Department Expectations, to verify the alternate channel is functioning properly and select the opposite channel. The crew will then enter SO23-13-27, Pressurizer Pressure and Level Malfunctions to restore the Pressurizer Pressure Control System to a normal operating lineup.

When pressure control has been restored, Vital Bus Y02 will lose the normal power source. The crew will enter SO23-13-18, Loss of a Vital Bus. The crew will transfer Pressurizer level control to the opposite channel due to the loss of the Vital Bus and direct an operator to transfer Y02 to its alternate source of power.

When the crew has reenergized Y02, restored affected systems, and the CRS has evaluated Technical Specifications, the running Stator Water Cooling Pump will trip. The standby Stator Water Cooling Pump will trip and the BOP will start the standby pump manually with CRS concurrence.

An earthquake will occur and 30 seconds after the earthquake hits, Main Feedwater Isolation Valve HV-4052 will trip closed. This will cause a trip of both Main Feedwater Pumps approximately 30 seconds later. The crew will recognize the loss of both MFW Pumps and trip the Reactor.

Upon the Reactor trip, an air leak in the Main Condenser will require the crew to place Atmospheric Dump Valves in service to control RCS temperature.

3 minutes after the Reactor trip, AFW Pump P-504 will trip and 6 minutes after the Reactor trip, AFW Pump P-140 will trip on overspeed, placing the crew in a complete Loss of Feedwater condition. The crew will complete SPTAs and transition to SO23-12-6, Loss of Feedwater.

When directed by SO23-12-6 to trip all RCPs, RCP P-003 breaker will fail to open, requiring the crew to deenergize 6.9 kV Bus 2A02 to secure the RCP. The crew will identify low pressure condensate as their feedwater restoration success path and depressurize the S/Gs to less than Condensate Pump discharge pressure to restore feedwater flow to the S/Gs. When feedwater flow has been reestablished, the scenario may be terminated.

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Scenario Event Description NRC Scenario #4 Risk Significance:

• Failure of risk important system prior to trip: SWC Pump P-112 Shaft Seizure Loss of MFW due to the closure of HV-4052

• Risk significant core damage sequence: Complete loss of Main and Aux feedwater

• Risk significant operator actions: Transfer RCP cooling to standby loop Restore feedwater to at least one S/G SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Scenario Event Description NRC Scenario #4 MACHINE OPERATOR INSTRUCTIONS for SIMULATOR SETUP INITIALIZE to IC-230 NRC Scenario #4 and associated Setup File.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER SETUP MALF FW25 Turbine Driven AFW Pump P-140 OS Trip Trip Rx Trip

(+ 6 min)

MALF FW23 Condenser Air Leakage 100 Rx Trip MALF FW02B AFW Pump P-504 Shaft Seizure Seizure Rx Trip

(+ 3 min)

LP N/A AFW Pump P-141 OOS OOS LP N/A RCP P-003 Breaker Fails As Is Fail As Is 1 MALF SC01A SWC Pump P-112 Seized Shaft Seizure 2 MALF RC15B Pressurizer Pressure Transmitter PT-0100Y Fails 2500 High 3 MALF ED07B Vital Bus Y02 Inverter Failure Loss RF ED51B Vital Bus Y02 Transfer to Emergency Power Alternate 4 LP N/A Stator Water Cooling Pump P-291 OC Trip, P-290 Trip / Fail Fails to Auto Start to Start 5 LP N/A Earthquake OBE LP N/A SG E089 Feedwater Block Valve 2HV-4051 Close Earthquake Closes

(+ 10 sec) 6 Setup Setup Loss of Condenser Vacuum Rx Trip 7 Setup Setup AFW Pump P-504 Shaft Seizure Rx Trip

(+ 3 min)

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Scenario Event Description NRC Scenario #4 8 Setup Setup Turbine Driven AFW Pump P-140 OS Trip Rx Trip

(+ 6 min) 9 Setup Setup RCP P-003 Breaker Fails As Is SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Scenario Event Description NRC Scenario #4 Machine Operator:

• RESTORE to IC-215

• OPEN 2012 NRC Scenario #4 event file

• RUN Setup Files 1, 2, and 3

• INSTALL AFW P-141 OOS MAGTAG installed

• ENSURE Pressurizer Level and Pressure Selector Switches are selected to Channel Y

• ENSURE blend setpoints are 13.2 gpm for BA and 74.8 gpm for PMW

• ENSURE SO23-5-1.7 Attachment 9 MOC placard is posted

• ENSURE OP AID 005-23 on CR63 has BQ aligned to Unit 2, BS aligned to Unit 3

• ENSURE OP AID 005-11 on CR64 has E336 aligned to Unit 2, E335 aligned to Unit 3

• ENSURE OP AID 005-5 for Backpressure Control Valves has PV201B circled

• ENSURE OP AID 005-5 for Letdown Flow Control Valve has LV110A circled

• ENSURE alarms are active Control Room Annunciators in Alarm:

• 57A58 EMERGENCY FEEDWATER SYS TRAIN A INOPERABLE

• TR A EMER FW SYS INOPERABLE (sugar cube)

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 1 Page 7 of 19 Event

Description:

Train A Salt Water Cooling Pump P-112 Shaft Seizure Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 1, Salt Water Cooling Pump P-112 Shaft Seizure.

Indications Available:

• 64A24 SWC Pump Motor Brg Temp Hi

• SWC Pump P-112 Amps Off-Scale High

• 64A41 SWC Pump Train A OC (+40 sec)

The following steps are from SO23-13-7, Loss of CCW/SWC.

BOP ENSURE CCW/SWC on the unaffected loop - IN SERVICE.

BOP TRANSFER Noncritical loop to the unaffected loop.

BOP TRANSFER the Letdown HX to the unaffected loop.

Critical Task: Transfer the CCW Non-Critical Loop prior to exceeding an RCP thrust bearing temperature exceeding 225°F following a loss of Train A SWC Pump P-112.

CCT Time:__________

INITIATE placing the standby SWC Pump for the affected loop - IN SRO SERVICE.

VERIFY normal parameters on the in-service SWC Train:

• SWC flow is in acceptable range per PCS min Saltwater Flow VS BOP Saltwater injection Temperature Calculation.

• CCW HX Delta Pressure > 3pisd and < 12psid.

• CCW HX outlet Temperature < 90°F.

VERIFY reset:

SRO

• UA64A47, CCW HX TRAIN A OUTLET TEMP HI

• UA64A48, CCW HX TRAIN B OUTLET TEMP HI SRO VERIFY affected Train SWC flow - RESTORED.

EVALUATE Technical Specifications:

• LCO 3.7.8 SRO

• Condition A - One SWC train inoperable.

• Action A.1 - Restore SWC train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Examiner Note: When Train B CCW and SWC has been placed in service, the Non-Critical Loop and Letdown Heat Exchanger have been aligned to Train B, and Technical Specifications have been evaluated, or at Lead Evaluators discretion, proceed to Event 2, Pressurizer Pressure Transmitter PT-0100Y Fails High.

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 2 Page 8 of 19 Event

Description:

Pressurizer Pressure Transmitter PT-0100Y Fails High Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 2, Pressurizer Pressure Transmitter PT-0100Y Fails High.

Indications Available:

• 50A04 PZR Press Deviation Hi/Lo

• 50A14 PZR Press Hi/Lo Examiner Note: The following steps are from 50A14 Alarm Response Procedure.

If a control channel failure has occurred, then perform the following:

• POSITION HS-0100A, PZR Pressure Channel Select Switch, to the RO other channel.

• Initiate SO23-13-27, Pressurizer Pressure and Level Malfunction.

Examiner Note: Placing PZR Pressure Channel Select Switch to Channel X in this situation is an approved Prompt and Prudent action per OSM-14, Operations Department Expectations. In this case, the operator may take this action prior to referencing the ARP.

Examiner Note: The following steps are from SO23-13-27, Pressurizer Pressure and Level Malfunction.

RO VERIFY Pressurizer Spray Valve is NOT stuck OPEN.

VERIFY the selected Pressurizer Pressure channel is between 2225 and 2275 psia and stable.

• (RNO) VERIFY the other pressure channel is available by observing RO PR-0100A or PR-0100 B or CFMS page 325.

• (RNO) POSITION HS-0100A, PZR Pressure Channel Select Switch, to the other channel (this may have already been done using Prompt and Prudent actions).

RO VERIFY Pressurizer Pressure is stable.

SRO VERIFY normal Charging and Letdown in service.

SRO GO TO Step 3i.

VERIFY the Pressurizer Pressure signal had not failed high.

RO

• OPERATE PZR Non-1E Backup and Proportional Heaters per SRO Ops Supv. Direction.

VERIFY Pressurizer Pressure Control System is operating properly in RO automatic.

SRO VERIFY Pressurizer Spray was not initiated with delta temperature > 180ºF.

INITIATE a Notification for I&C to reprogram the affected pressure SRO controller(s) or to restore the pressure input.

Examiner Note: When Pressurizer Pressure Control Channel has been selected to Channel X and Non-1E Pressurizer Heaters have been restored, or at Lead Evaluators discretion, proceed to Event 3, Loss of Vital Bus Y02.

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 3 Page 9 of 19 Event

Description:

Loss of Vital Bus Y02 Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 3, Loss of Vital Bus Y02.

Indications Available for the Loss of Y02:

• 57C13 Vital Bus 2 Inverter Failure Examiner Note: The following steps are from SO23-13-18, Loss of a Vital Bus.

CONFIRM that a single Vital Bus is lost by checking:

• Alarms on CR57 associated with a single Vital Bus Inverter trouble or SRO failure ANNUNCIATED.

• Lumigraphs for associated single channel FAILED on CR56.

VERIFY 125V DC Bus indication for the associated Inverter has voltage RO indicated (not blank) and indication is 101 Volts.

Examiner Note: The RO may take Prompt and Prudent actions per OSM-14, Operations Department Expectations, to stabilize Pressurizer level following the loss of Y02. P&P actions for this event include

• Placing LIC-0110 in MANUAL

• Stopping Charging Pumps which auto started

• Adjusting the output of LIC-0110 to stabilize Pressurizer level.

CONFIRM Loss of Vital Bus Y01 or Y02 has NOT occurred.

• (RNO) If the Pressurizer Level Controls are selected to the affected channel, then perform the following:

• PLACE LIC-0110, Pressurizer Level Controller, in MANUAL by depressing the A/M button.

• START or STOP Charging Pumps as necessary to control Pressurizer level and match Letdown flow as close as possible.

• ADJUST the output on LIC-0110 as necessary to match RO Letdown flow as closely as possible and maintain a steady PZR level.

• SELECT HS-0110, PZR Level Channel Select Switch, to the unaffected channel.

• (RNO) If Pressurizer Heaters have de-energized as a result of a failed Low PZR Level signal, then perform the following:

• DEPRESS HS-0100C, PZR Lo-Lo Level Heater Cutout Channel Selector, selecting the unaffected level transmitter.

• RESET PZR Heaters by DEPRESSING OFF, then AUTO/ON.

CONFIRM failure does NOT affect RPS/ESFAS Matrix Logic, RPS/ESFAS SRO Initiation Logic, RTCBs, RPS/ESFAS Manual Trip, or ESFAS Actuation Logic.

INITIATE re-energizing the affected Vital Bus from the Alternate source per SRO SO23-6-17 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. (Tech. Spec. LCO 3.8.7 and LCO 3.8.9).

SRO GO TO Attachment for affected loss of Vital Bus.

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 3 Page 10 of 19 Event

Description:

Loss of Vital Bus Y02 Time Position Applicants Actions or Behavior Examiner Note: Technical Specifications for loss of Y02:

• LCO 3.8.7

• Condition A - One required inverter inoperable.

• Action A.1 - Power AC vital bus from its Class 1E constant voltage source transformer within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

AND

• Action A.2 - Restore inverter to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• LCO 3.8.9

• Condition B - One or more AC vital bus inoperable.

• Action B.1 - Restore AC vital bus subsystem to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from discovery of failure to meet LCO.

Examiner Note: The following steps list the affected equipment in BOLD and the associated actions / information unbolded.

PPS B Status Lights extinguished - VERIFY protection system bistables RO NOT TRIPPED on PPS Channels A and C ROMs.

Channels 1-4 Red ESFAS Functions lights along the bottom of the ROM RO extinguished - VERIFY all ESFAS function lights EXTINGUISHED on PPS Channels A, B, C and D ROMs.

Channel B Lumigraphs on CR56 extinguished - VERIFY Safety Channel RO indications providing input to PPS Channels A, C, and D DO NOT indicate that a Plant Protection Trip Setpoint has been exceeded.

Charging Pumps P-190, P-191, and P-192 - Operate Charging Pumps as RO necessary to control PZR level.

PZR Pressure and Level Control - ENSURE PZR Level Channel X is SELECTED.

• If LIC-0110 is selected to setpoint LS2, then transfer Pressurizer level RO setpoint to LS1 per SO23-3-1.10, Attachment for Transferring Pressurizer Level and Pressure Controls.

• If an ACTUAL Pressurizer Lo-Lo level exists, then ENSURE all heaters are de-energized.

Vital Bus Inverter Y002 de-energized - ENSURE SO23-6-17, Attachment for RO Re-energizing Vital Bus Y02 from the Alternate Source, in progress.

Atmospheric Dump Valve/Controller HV-8421/PIC-8421 HV-8421, RO Atmospheric Dump Valve, FAILS CLOSED. HV-8421, Atmospheric Dump Valve, may be operated locally.

Atmospheric Dump Valve/Controller HV-8419/PIC-8419 HV-8419, RO Atmospheric Dump Valve, will lose its Pressure input but can be operated from the Controller in MANUAL using PIC-8419-1.

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 3 Page 11 of 19 Event

Description:

Loss of Vital Bus Y02 Time Position Applicants Actions or Behavior EFAS Trip Paths 2 & 4 Valves:

• HV-4712, AFWP 2(3)MP-504 to SG E-088 Disch Valve

• HV-4705, AFWP 2(3)MP-140 to SG E-088 Disch. Valve

• HV-4715, AFW to SG E-089 Iso. Valve

• HV-4731, AFW to SG E-089 Iso. Valve

• HV-4716, AFWPT 2(3)K-007 Steam Inlet Valve RO

• Valves Open.

• If an Auxiliary Feed Pump is in service in Mode 2 or 3, then ensure closed HV4730 and HV4714 to prevent S/G E088 Overfill.

• If Required to feed S/G E088, then throttle open HV4730 and batch feed S/G to high end of control band (70% NR).

• If AFW Pump P140 not required for feeding S/Gs, then override and close HV4716.

• The affected Unit is in a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Action Statement (Tech. Spec. LCO 3.7.5) since these valves will not close on a MSIS signal.

Machine Operator: When the crew secures AFW Pump P-140, or when directed, place Vital Bus

1. 2 Y02 on its alternate source of power.

Examiner Note: The following steps will be performed after Y02 has been placed on its alternate source of power.

ENSURE AFW Valves CLOSED:

• HV-4712, AFWP 2(3)MP-504 to SG E-088 Disch Valve

• HV-4705, AFWP 2(3)MP-140 to SG E-088 Disch. Valve BOP

• HV-4731, AFW to SG E-089 Iso. Valve

• HV-4715, AFW to SG E-089 Iso. Valve

• HV-4716, AFWPT 2(3)K-007 Steam Inlet Valve Examiner Note: When Y02 has been placed on its alternate source, AFW Valves have been closed, and Technical Specifications have been evaluated, or at Lead Evaluators discretion, proceed to Event 4, Stator Water Cooling Pump OC Trip (Standby pump fails to auto start).

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 4 Page 12 of 19 Event

Description:

Stator Water Cooling Pump P-291 OC Trip, P-290 Fails to Auto Start Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 4, Stator Water Cooling Pump P-291 OC Trip, P-290 Fails to Auto Start.

Indications Available:

• 99C35 Stator Water Pump OC

• 99C16 Stator Water Flow Lo Pretrip Examiner Note: The following steps are from Alarm Response Procedure 99C35.

BOP Ensure standby Stator Water Pump running.

Examiner Note: Starting the standby Stator Water Cooling Pump is an approved Prompt and Prudent Action per OSM-14, Operations Department Expectations. This action may be taken prior to referencing the ARP.

BOP Dispatch an Operator to the field to check for SPECIFIC CAUSES.

Examiner Note: After Stator Water Cooling Pump P-290 has been started, or at Lead Evaluators discretion, proceed to Event 5, Earthquake / Main Feedwater Block Valve HV-4051.

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 5, 6, 7, 8, 9 Page 13 of 19 Event

Description:

Earthquake / S/G E-089 Main Feedwater Block Valve HV-4051 Closes, Loss of Vacuum on Reactor Trip, AFW Pump P-504 Shaft Seizure (+ 3 min), AFW Pump P-140 Overspeed Trip (+ 6 min), RCP P-003 Breaker Fails to Open Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 5, Earthquake / S/G E-089 Main Feedwater Block Valve HV-4051 Closes. Events 6, 7, 8, and 9 will automatically activate on Reactor Trip.

Indications Available:

• 61C22 Operating Basis Earthquake Detected

• 52A60 FWBV HV-4051 Trouble

• 52A07 FWCS SG1 E089 Level Deviation Examiner Note: The crew may enter the Earthquake AOI momentarily, however the closure of the Main Feedwater Block Valve will cause two Main Feedwater Pumps to trip in ~ 30 seconds, requiring a Reactor Trip.

BOP RECOGNIZE both Main Feedwater Pumps have tripped and trip the Reactor.

Examiner Note: The following steps are from SO23-12-1, Standard Post Trip Actions.

Verify Reactor Trip:

RO VERIFY Reactor Trip Circuit Breakers (8) OPEN.

RO VERIFY Reactor power - LOWERING AND Startup rate NEGATIVE.

RO VERIFY maximum of one full length CEA NOT fully inserted.

Verify Turbine Trip:

BOP ALL HP and LP Stop and Governor valves CLOSED.

BOP VERIFY BOTH Unit Output Breakers OPEN.

BOP VERIFY Main Turbine speed less than 2000 RPM OR lowering.

SRO INITIATE Attachment 1, WORKSHEET.

Verify Vital Auxiliaries:

BOP VERIFY BOTH 1E 4kV Buses ENERGIZED.

BOP VERIFY all 1E 480V buses ENERGIZED.

BOP VERIFY all Class 1E DC Buses ENERGIZED.

BOP VERIFY all Non-1E 4kV Buses ENERGIZED.

BOP VERIFY one CCW Train OPERATING AND aligned to Non-Critical Loop (NCL) and Letdown Heat Exchanger.

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 5, 6, 7, 8, 9 Page 14 of 19 Event

Description:

Earthquake / S/G E-089 Main Feedwater Block Valve HV-4051 Closes, Loss of Vacuum on Reactor Trip, AFW Pump P-504 Shaft Seizure (+ 3 min), AFW Pump P-140 Overspeed Trip (+ 6 min), RCP P-003 Breaker Fails to Open Time Position Applicants Actions or Behavior Verify RCS Inventory Control:

RO VERIFY PZR level between 10% and 70% AND trending to between 30% and 60%.

RO VERIFY Core Exit Saturation Margin greater than or equal to 20°F.

Verify RCS Pressure Control:

RO VERIFY PZR pressure between 1740 PSIA and 2380 PSIA AND trending to between 2025 PSIA and 2275 PSIA.

Verify Core Heat Removal:

RO VERIFY at least one RCP OPERATING.

RO VERIFY core loop T (THOT -TCOLD) less than 10°F.

RO VERIFY Core Exit Saturation Margin greater than or equal to 20°F.

Verify RCS Heat Removal:

VERIFY at least one S/G level between 21% NR and 80% NR AND BOP Feedwater - AVAILABLE.

• (RNO) ENSURE EFAS - ACTUATED.

BOP VERIFY RCS TCOLD between 540°F and 550°F.

BOP VERIFY S/G pressures between 960 PSIA and 1050 PSIA.

Verify Containment Isolation:

RO VERIFY Containment pressure less than 1.5 PSIG.

RO VERIFY Containment Area Radiation Monitors NOT alarming or trending to alarm.

RO VERIFY Secondary Plant Radiation Monitors NOT alarming or trending to alarm.

Verify Containment Temperature and Pressure Control:

RO VERIFY Containment average temperature less than 120°F.

RO VERIFY Containment pressure less than 1.5 PSIG.

VERIFY all safety function criteria per Attachment 1, WORKSHEET RO RECOVERED.

• (RNO) COMPLETE Attachment 2, RECOVERY DIAGNOSTICS.

Examiner Note: The CRS should diagnose a single event, Loss of Feedwater, and identify SO23-12-6, Loss of Feedwater, as the optimal EOI.

VERIFY REACTOR TRIP RECOVERY DIAGNOSED.

SRO

• (RNO) ENSURE at least one RCP in each loop stopped.

Examiner Note: If the CRS directs securing RCPs 2 and 3, the RO will have to stop RCP P-003 by de-energizing 6.9kV Bus 2A02 (RCP P-003 breaker fails to open).

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 5, 6, 7, 8, 9 Page 15 of 19 Event

Description:

Earthquake / S/G E-089 Main Feedwater Block Valve HV-4051 Closes, Loss of Vacuum on Reactor Trip, AFW Pump P-504 Shaft Seizure (+ 3 min), AFW Pump P-140 Overspeed Trip (+ 6 min), RCP P-003 Breaker Fails to Open Time Position Applicants Actions or Behavior SRO INITIATE steps 12 through 17.

Examiner Note: Steps 12 through 17 of SO23-12-1, Standard Post Trip Actions, are located at the end of the scenario guide.

SRO IMPLEMENT EOI diagnosed.

Examiner Note: The following steps are from SO23-12-6, Loss of Feedwater.

SRO RECORD time of EOI entry _______.

SRO INITIATE SO23-12-10, SAFETY FUNCTION STATUS CHECKS.

INITIATE FOLDOUT PAGE. (No steps of the Foldout Page are applicable SRO at this time)

SRO ENSURE EFAS 1 and EFAS 2 actuated.

VERIFY LOFW diagnosis:

• Both S/Gs level less than 40% NR.

AND

• TOTAL AFW less than 400 GPM.

AND SRO

• Both MFW Pumps NOT operating.

• PZR level - stable or rising.

• PZR pressure - stable or rising.

• S/G E-088 pressure greater than 740 PSIA AND stable or rising.

• S/G E-089 pressure greater than 740 PSIA AND stable or rising.

NOTIFY Shift Manager/Operations Leader of SO23-12-6, LOSS OF SRO FEEDWATER, initiation.

SRO ENSURE Emergency Plan is initiated.

SRO IMPLEMENT PLACEKEEPER.

SRO IMPLEMENT TIME DEPENDENT STEPS.

SRO ENSURE all RCPs stopped.

Examiner Note: If the CRS has not previously directed securing RCPs 2 and 3, the RO will have to stop RCP P-003 by de-energizing 6.9kV Bus 2A02 (RCP P-003 breaker fails to open).

ENSURE S/G blowdown and sample valves - closed:

BOP

• E-088: HV-4054 and HV-4058

• E-089: HV-4053 and HV-4057 SRO IF AFW Pump available, THEN GO TO step 7.

SRO IF MFW Pump and 2 Condensate Pumps available, THEN GO TO step 8.

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 5, 6, 7, 8, 9 Page 16 of 19 Event

Description:

Earthquake / S/G E-089 Main Feedwater Block Valve HV-4051 Closes, Loss of Vacuum on Reactor Trip, AFW Pump P-504 Shaft Seizure (+ 3 min), AFW Pump P-140 Overspeed Trip (+ 6 min), RCP P-003 Breaker Fails to Open Time Position Applicants Actions or Behavior IF at least one Condensate Pump from either unit available, THEN GO TO SRO step 10.

Examiner Note: The success path is low pressure Condensate, the CRS should go to step 10.

SRO VERIFY at least one Condensate Pump from either Unit available.

ENSURE Full Flow Condensate Polishing Demineralizers - bypassed:

• FV-4902A - open BOP

• HV-4900A - closed

• HV-4900B - closed DISPATCH an operator to UNLOCK and INITIATE OPENING 1305MU024, BOP MFW Pump Bypass.

ENSURE FIC-3294, Condensate Pump miniflow controller set for proper Condensate pump configuration:

BOP

• One pump - 3000 GPM

• Two pumps - 6000 GPM

• Three pumps - 9000 GPM TRANSFER Individual MFW Regulator Bypass valve controllers to LOCAL:

BOP

• E-088: HIC-1106

• E-089: HIC-1105 ENSURE MFW Block valves closed:

BOP

• E-088: HV-4047

• E-089: HV-4051 ENSURE MFW Regulator Bypass valves closed:

BOP

• E-088: HV-1106

• E-089: HV-1105 INITIATE the following:

RO

• SIAS

• CCAS INITIATE raising PZR level. OVERRIDE and operate Charging Pumps as RO necessary to a establish PZR level between 45% and 55%.

SRO VERIFY Boration in progress at greater than or equal to 40 GPM.

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 5, 6, 7, 8, 9 Page 17 of 19 Event

Description:

Earthquake / S/G E-089 Main Feedwater Block Valve HV-4051 Closes, Loss of Vacuum on Reactor Trip, AFW Pump P-504 Shaft Seizure (+ 3 min), AFW Pump P-140 Overspeed Trip (+ 6 min), RCP P-003 Breaker Fails to Open Time Position Applicants Actions or Behavior ADJUST available S/G steaming rate to initiate lowering S/G pressure less than 500 PSIA:

• RESET MSIS setpoint as controlled cooldown proceeds.

BOP

• MAINTAIN available S/G steaming rates to control RCS temperature within the following limits:

• Core Exit Saturation Margin between 20°F and 160°F.

BOP ENSURE MFW Pump tripped AND MFW Pump miniflow valves closed.

SRO VERIFY intact feedwater flowpath available.

SRO VERIFY CIAS NOT actuated.

VERIFY MFIV to available S/G - OPEN:

BOP

• E-088: HV-4048

• E-089: HV-4052 BOP START at least one Condensate Pump on affected unit.

THROTTLE MFW Regulator Bypass valve to available S/G - 20% open:

• E-088: HV-1106 BOP

• E-089: HV-1105 AND ENSURE Condensate Pump discharge pressure - greater than S/G pressure.

BOP MAINTAIN reduced feedwater flow for 5 minutes.

Critical Task: Restore Feedwater to at least one S/G prior to a complete loss of secondary inventory per SO23-12-6, Loss of Feedwater.

CCT Time:__________

Scenario Termination: When Feedwater has been restored to at least one S/G, or at Lead Evaluators discretion, the scenario may be terminated.

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 5, 6, 7, 8, 9 Page 18 of 19 Event

Description:

Earthquake / S/G E-089 Main Feedwater Block Valve HV-4051 Closes, Loss of Vacuum on Reactor Trip, AFW Pump P-504 Shaft Seizure (+ 3 min), AFW Pump P-140 Overspeed Trip (+ 6 min), RCP P-003 Breaker Fails to Open Time Position Applicants Actions or Behavior Examiner Note: The following are steps 12-17 of SO23-12-1, Standard Post Trip Actions.

RO INITIATE Attachment 4, ADMINISTRATIVE ACTIONS.

RO ENSURE a PA System announcement was made regarding the Reactor trip.

OPERATE SBCS to maintain RCS TCOLD between 540°F and 550°F.

RO * (RNO) OPERATE ADVS to maintain RCS TCOLD between 540°F and 550°F.

RO VERIFY TELECOM 480VAC FDR BKR HS0800S-2 (Q800S) CLOSED RO VERIFY TELECOM 480VAC FDR BKR HS0800N-2 (Q800N) CLOSED.

RO VERIFY all Non-1E 4kV Buses ENERGIZED.

RO VERIFY 480V Load Centers B15 and B16 ENERGIZED.

RO ENSURE 3rd Point Heater Drain Pumps STOPPED.

VERIFY RTO RESET.

• (RNO) IF a MFW pump in service THEN RESET RTO per SO23-9-6, RO Feedwater Control System Operation Examiner Note: RTO will not be reset due to the loss of all feedwater.

MAINTAIN one MFW Pump and a maximum of three Condensate Pumps in RO operation.

• (RNO) ENSURE S/G levels being maintained by AFW Pumps.

ENSURE FIC-3294, Condensate Pump miniflow controller set for proper Condensate pump configuration:

RO

• One pump - 4500 GPM

• Two pumps - 6000 GPM

• Three pumps - 9000 GPM RO PLACE Condensate Draw-off valve LV-3245 to DISABLE.

VERIFY SO23-12-2, REACTOR TRIP RECOVERY being implemented.

• (RNO) ENSURE S/G Blowdown valves HV-4054 and HV-4053 RO CLOSED.

• (RNO) GO TO step 16.

ENSURE the following valves closed:

• Extraction Steam Block valves HV-8800, HV-8812, HV-8804, HV-8810, HV-8808, HV-8820, HV-8806, and HV-8816.

RO

• Main Steam to Reheater Block, Bypass, Warmup and Control valves HV-2703 or HV-2704, HV-2721, and HV-2751.

• Bled Steam to Reheaters Block Valve HV-2712A/B.

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 5, 6, 7, 8, 9 Page 19 of 19 Event

Description:

Earthquake / S/G E-089 Main Feedwater Block Valve HV-4051 Closes, Loss of Vacuum on Reactor Trip, AFW Pump P-504 Shaft Seizure (+ 3 min), AFW Pump P-140 Overspeed Trip (+ 6 min), RCP P-003 Breaker Fails to Open Time Position Applicants Actions or Behavior RO VERIFY Main Generator voltage less than 24kV.

VERIFY annunciators RESET:

RO

• 99A26 TURBINE LUBE OIL TEMP HI

• 99A46 TURBINE BRG OIL DRAIN TEMP HI INITIATE SO23-10-2, TURBINE SHUTDOWN, Attachment for Unloading RO the Generator and Removing the Unit from Line.

RO VERIFY BOTH Start-Up Range channels OPERABLE.

SONGS 2012 NRC Sim Scenario #4 Rev d.docd

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 & 3 Scenario No.: 5 Op Test No.: October 2012 NRC Examiners: Operators:

Initial Conditions: 100% Power MOC Turnover: Maintain steady state conditions.

Critical Tasks:

• Restore CCW flow to the RCPs within 10 minutes and prior to RCP thrust bearing temperature exceeding 225°F.

• Within 10 minutes of loss of heat removal from S/G E088, the crew transfers the primary to secondary heat sink to S/G E089 by steaming S/G E089, maintaining Psat for the lowest RCS Tc, per SO23-12-11, FS-30, Establish Stable RCS Temperature During ESDE.

• Manually initiate Containment Spray prior to exceeding Containment temperature and pressure limits following a failure of Containment Spray to automatically actuate.

• Isolate S/G E-088 prior to exiting SO23-12-9, Functional Recovery.

Event No. Malf. Event Type* Event Description No.

1 (10 min) RC16B I (RO, SRO) Pressurizer Level Control Channel Transmitter LT-0110-2 fails low TS (SRO) 2 (20 min) CC06B C (BOP, SRO) CCW Pump P-025 O/C TS (SRO) 3 (30 min) CV03C C (RO, SRO) RCP P-003 Upper and Middle Seal Failures CV04C 4 (50 min) N (RO, BOP, SRO) Rapid Power Reduction 5 (55 min) OBE LP C (RO) Earthquake (OBE w/o MFW Pump Trip)

SG01A M (BOP, SRO) 400 GPM SGTR on S/G E-088 TS (SRO) 6 (55 min) MS03A M (RO, BOP, SRO) ESDE inside containment from S/G E-088 on Reactor Trip 7 (55 min) TU07 I (BOP) Main Turbine Fails to Trip on Reactor Trip 8 (60 min) PPS LP I (RO) CSAS Fails to Auto Actuate

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 7 Total malfunctions (5-8) 3 Malfunctions after EOP entry (1-2) 4 Abnormal events (2-4) 2 Major transients (1-2) 2 EOPs entered/requiring substantive actions (1-2) 1 EOP contingencies requiring substantive actions (0-2) 4 Critical tasks (2-3)

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Scenario Event Description NRC Scenario #5 SCENARIO

SUMMARY

NRC #5 The crew will take the watch operating at 100% Reactor power and no equipment out of service.

The in-service Pressurizer level control transmitter will fail low. The crew will take manual control of the letdown flow controller to stabilize Pressurizer level per OSM-14, Operations Department Expectations and enter SO23-13-27, Pressurizer Pressure and Level Malfunctions. The CRS will evaluate Technical Specifications due to one Train of 1E backup heaters being inoperable with a failed low level transmitter.

When the crew has established Pressurizer level control on the opposite channel, CCW Pump P-025 will trip on overcurrent. The crew will start the standby CCW pump on the same train and will not transfer the Letdown Heat Exchanger and Non-Critical Loop. Although there is still two trains of CCW available, the CRS will declare Train A CCW inoperable until P-025 is racked out as it would still be aligned to receive the auto start signal on a SIAS however it would not start.

Following the Technical Specification evaluation, RCP P-003 will have a failure of the upper seal and 2 minutes later the middle seal will fail. The two failed seals will require a down power and the crew will enter SO23-13-28, Rapid Power Reduction, to commence taking the unit offline.

An operating basis earthquake will occur and cause a 400 GPM SGTR on S/G E-088. When the crew recognizes the leak, they will enter SO23-13-14, Reactor Coolant Leak, and attempt to mitigate the leak. When it is recognized that the leak exceeds makeup capacity, they crew will trip the Reactor.

Upon the Reactor trip, the Main Turbine will fail to auto trip and will be manually tripped by the BOP.

Additionally, an ESDE will occur inside Containment on E-088 when the Reactor is tripped. The crew will pull forward FS-30, Stabilization of RCS Temperature During an ESDE, during SPTAs and then transition to SO23-12-9, Functional Recovery, due to the SGTR and EDSE. The crew will identify that CSAS failed to auto actuate when Containment pressure exceeded 14 psig and will manually actuate CSAS.

When RCS heat removal is transferred to the intact S/G and the faulted S/G has reached dryout, the crew will isolate S/G E-088 and the scenario can be terminated.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Scenario Event Description NRC Scenario #5 Risk Significance:

• Failure of risk important system prior to trip: Loss of CCW Pump P-025 Two RCP Seal Failures Operating Basis Earthquake

• Risk significant core damage sequence: SGTR and ESDE on S/G E-088 Failure of the Main Turbine to trip Failure of CSAS to actuate

• Risk significant operator actions: Transfer RCS cooling to the intact S/G Manually initiate CSAS Isolate S/G E-088 SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Scenario Event Description NRC Scenario #5 MACHINE OPERATOR INSTRUCTIONS for SIMULATOR SETUP INITIALIZE to IC-215 NRC Scenario #5 and run associated Setup Files.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER SETUP MALF MS03A Main Steam Line Break Inside Containment 1.5 Rx Trip

(+ 30 sec)

MALF TU07 Main Turbine Fails to Trip on Rx Trip Failure LP N/A Containment Spray Fails to Auto Actuate Fail to Actuate 1 MALF RC16B Pressurizer Level Transmitter LT-0110-2 Fails 0 Low 2 MALF CC06B CCW Pump P-025 OC Trip Fault 3 MALF CV04C RCP P-003 Upper Seal Failure 100 MALF CV03C RCP P-003 Middle Seal Failure 100 (+ 2 min) 4 N/A N/A Rapid Power Reduction due to Failed RCP Seals 5 LP N/A Earthquake OBE MALF SG01A SGTR From SG E088 .6 (5 min ramp) 6 Setup Setup ESDE From SG E088 1.5 Rx Trip

(+ 30 sec) 7 Setup Setup Main Turbine Fails to Trip on Rx Trip Failure 8 Setup Setup Containment Spray Fails to Auto Actuate Fail to Actuate SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Scenario Event Description NRC Scenario #5 Machine Operator:

• RESTORE to IC-215

• OPEN 2012 NRC Scenario #5 event file

• RUN Setup Files 1 and 2

• ENSURE Pressurizer Level and Pressure Selector Switches are selected to Channel Y

• ENSURE blend setpoints are 13.2 gpm for BA and 74.8 gpm for PMW

• ENSURE SO23-5-1.7 Attachment 9 MOC placard is posted

• ENSURE OP AID 005-23 on CR63 has BQ aligned to Unit 2, BS aligned to Unit 3

• ENSURE OP AID 005-11 on CR64 has E336 aligned to Unit 2, E335 aligned to Unit 3

• ENSURE OP AID 005-5 for Backpressure Control Valves has PV201B circled

• ENSURE OP AID 005-5 for Letdown Flow Control Valve has LV110A circled

• ENSURE alarms are active Control Room Annunciators in Alarm:

• None SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 1 Page 6 of 26 Event

Description:

Pressurizer Level Control Channel Transmitter LT-0110-2 fails low Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 1, Pressurizer level Control channel Transmitter LT-0110-2 Fails Low.

Indications Available:

• 50A03 - PZR Level LO-LO

• 50A23 - PZR Level Error LO Examiner Note: The following steps are from OSM-14 Operations Department Expectations Prompt and Prudent Actions.

RO Place LIC 0110 in Manual.

RO Stop Charging Pumps that auto-started.

RO Adjust LIC 0110 to stabilize level.

Examiner Note: The following steps are from SO23-13-27, Pressurizer Pressure and Level Malfunction RO VERIFY normal Charging and Letdown in Service.

VERIFY Level Indicators LI-0110A1, LI-0110A2 and LI-103 are reading RO approximately the same.

• (RNO) Go to step 2h.

Transfer to the operable level channel as follows:

• VERIFY the channel not selected is reading within the program band.

• TRANSFER HS-0110, Pressurizer Level Channel Selector, to the operable Channel.

• ADJUST LIC-0110 to match the actual level with Pressurize Level Setpoint by adjusting the output.

• WHEN the level is within 2% of the setpoint, THEN TRANSFER LIC-0110 to AUTO by depressing the A/M pushbutton.

• SELECT the operable level transmitter by depressing HS-0100C, Non-RO 1E PZR Lo-Lo Level Heater Cutout Channel Selector.

• Verify Non-1E Pressurizer Heaters have not tripped.

• (RNO) RESET ALL PZR Non-1E Backup and Proportional Heaters, by going to Manual/Off THEN Back to Auto.

• OPERATE PZR Non-1E Backup, unaffected 1E Heaters and Proportion Heaters as directed by CRS.

• OPERATE Charging Pumps as directed by CRS.

• VERIFY PZR Level Control System is operating satisfactory in AUTO within the level band.

RO ENSURE LIC-0110 is in AUTO.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 1 Page 7 of 26 Event

Description:

Pressurizer Level Control Channel Transmitter LT-0110-2 fails low Time Position Applicants Actions or Behavior Examiner Note: Technical Specification for failed Pressurizer level transmitter:

• LCO 3.4.9

• Condition B - One required group of pressurizer heaters inoperable.

• Action B.1 - Restore required group of pressurizer heaters to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Examiner Note: When Technical Specifications have been evaluated or at Lead Evaluators discretion, proceed to Event 2.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 2 Page 8 of 26 Event

Description:

CCW Pump P-025 OC Trip Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 2, CCW Pump P-025 OC Trip.

Indications Available:

• 64A21 - CCW Pump Train A OC Examiner Note: The following steps are from Alarm Response Procedure 64A21, CCW Pump Train A OC BOP Start stand-by CCW Pump aligned to Train A.

Critical Task: Restore CCW flow to the RCPs within 10 minutes and prior to RCP thrust bearing temperature exceeding 225°F.

CCT Time:__________

EVALUTE Technical Specifications:

• LCO 3.7.7 SRO

• Condition A - One CCW Train inoperable.

• Action A.1 - Restore CCW Train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Examiner Note: When Technical Specifications have been evaluated or at lead evaluators discretion, proceed to Event 3, RCP P-003 Upper and Middle Seal Failure.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 3 Page 9 of 26 Event

Description:

RCP P-003 Upper and Middle Seal Failure Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 3, RCP P-003 Upper and Middle Seal Failure.

Indications Available:

• 56C26 - RCP P003 SEAL PRESSURE HI/LO Examiner Note: The following steps are from SO23-13-6 RCP Seal Failure RO DETERMINE if RCP seal failure has occurred by observing PCS screen for RCP Seal Status, or by using Attachment 1 if PCS page NOT available.

RO DETERMINE if any RCP operating parameters are out of normal range per Attachment 2.

SRO INFORM Maintenance Engineering of the situation.

RO TREND abnormal parameters on Plant Computer System per Attachment 3.

IDENTIFY that 2 Seals stages have failed:

• INTIATE a plant shutdown per SO23-5-1.7 Power Operations.

SRO

• After the Reactor is tripped then trip the affected RCP after Steps 1 and 2 of SO23-12-1 Standard Post Trip Actions.

Examiner Note: The crew will commence a downpower using SO23-13-28 Rapid Power Reduction at a rate of 15%/hour. Proceed to Event 4, Rapid Power Reduction.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 4 Page 10 of 26 Event

Description:

Rapid Power Reduction Time Position Applicants Actions or Behavior Examiner Note: The following steps are from SO23-13-28, Rapid Power Reduction.

SRO INITIATE notifying the GOC.

If taking the Unit Offline or to target power plateau < 750 MWe ( 65% Rx SRO Power), then INITIATE an immediate MSR Cooldown per SO23-10-2, Attachment for MSR Cooldown for Load Reduction/Turbine Shutdown.

GUIDELINES

1. If RCS Boron is < 110 ppm, then the optimal approach is to use CEAs and MTC with little or no boration. A 5% power reduction credit can be taken for MTC, because the temperature increase adds considerable negative reactivity due to the large negative MTC at the EOC along with Xenon building in. Expect average Tcold to be initially high outside the control band. (LS-1.1, LS-1.4)

2. At EOC, existing conditions may necessitate slowing power change rate when between 80%

and 70% power.

SRO INITIATE monitoring CV-9739, COLSS Raw Delta-T Power.

INITIATE Forcing PZR spray flow using two valves per SO23-3-1.10:

• ENSURE a Reactivity Brief has been conducted for this activity per SO123-0-A1, Section for Reactivity.

• COMMENCE monitoring RCS pressure.

• VERIFY RCS pressure > 1500 psia.

RO

• PLACE both PZR Spray Valve Controllers in AUTO.

• POSITION all Non-1E Backup Heaters to ON.

• LOWER PIC-0100, PZR Pressure Controller, setpoint as required to maintain RCS pressure as directed by the CRS (set setpoint to ~ 2225 psia).

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 4 Page 11 of 26 Event

Description:

Rapid Power Reduction Time Position Applicants Actions or Behavior BORATE to the Charging Pump Suction per SO23-3-2.2:

• Implement the requirements for a Reactivity Brief and Peer check per OSM-14, Operations Department Expectations, Section for Reactivity Management.

• ENSURE ENTERED required boration flowrate on FIC-0210Y, BAMU Flow Controller.

• If flowrate change, then SELECT SET.

• ENSURE FIC-0210Y in AUTO.

• SET FQIS-0210Y, Boration Counter, to the desired volume as follows:

• SELECT MODIFY.

• ENTER gallons in PRESET.

RO

• SELECT SET PRESET.

• SELECT EXIT.

• SELETE the BAMU Pump associated with the BAMU Tank used.

• VERIFY CLOSED FV-9253, Blended Makeup to VCT Isolation.

• ENSURE HV-9257, BAMU to Charging Pump Suction Block Valve, in AUTO.

• COMMENCE monitoring plant parameters.

• From the MODE SELECTOR:

• SELECT MODIFY.

• SELECT BORATE.

• SELECT GO SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 4 Page 12 of 26 Event

Description:

Rapid Power Reduction Time Position Applicants Actions or Behavior INSERT CEAs for ASI Control per SO23-3-2.19, to the target level within the following guidance:

• INSERT PLCEAs (Insertion Limit is 112.5. Insertion should be limited to 115 inches or until Power reaches target plateau.)

• INSERT Group 6 to target level. [90" if RCS Boron is < 110 ppm.]

(The maximum recommended is 75 inches.)

RO

• POSITION Group Select switch to the CEA group to be moved.

• POSITION Mode Select Switch to the appropriate mode.

• VERIFY the group indicator lamps are ILLUMINATED for the group selected.

• POSITION CEA(s) as directed by SRO Ops. Supv.

• When CEA positioning has completed, then POSITION the Mode Select Switch to OFF.

INITIATE SO23-5-1.7, Section for Turbine Load Change using Setpoint Adjustment:

• Implement the requirements for a Reactivity Brief and Peer Check per OSM-14, Operations Department Expectations, Section for Reactivity Management.

• INITIATE monitoring TCOLDAVG using PCS.

• PLACE the 1st STAGE PRESSURE feedback loop in service.

• ACTIVATE the Turbine DCS Setpoints Box and SELECT MODIFY.

BOP

• SET the Demand to the target MW value and SELECT ENTER.

• Set the Rate to the target MW/MIN value and SELECT ENTER.

• INITIATE Turbine load change, SELECT P2.

• Control RCS Tcold within the operating band by adjusting the rate setpoint or by canceling and reinitiating the load change as necessary.

• VERIFY Turbine load stabilizes at the target value.

• REMOVE 1st STAGE PRESSURE feedback loop from service.

• RESTORE the Rate to 100 MW/MIN and SELECT ENTER.

SRO INITIATE SO23-5-1.7, Attachment for Power Descension.

If Reactor power changed > 15% in one hour, then NOTIFY Chemistry SRO and LOG the notification.

SRO NOTIFY Reactor Engineering and log the notification.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 4 Page 13 of 26 Event

Description:

Rapid Power Reduction Time Position Applicants Actions or Behavior Maintain Turbine load, RCS Temperature, and ASI within the expected ALL operating bands per SO23-5-1.7.

Examiner Note: When Reactor power has been lowered 3-5% or at lead evaluators discretion, proceed to Event 5, Earthquake (OBE w/o MFW Pump Trip) and 400 GPM SGTR on S/G E-088.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 5 Page 14 of 26 Event

Description:

Earthquake (OBE w/o MFW Pump Trip) and 400 GPM SGTR on S/G E-088 Time Position Applicants Actions or Behavior Machine Operator: When directed, INITIATE Event 5, Earthquake (OBE w/o MFW Pump Trip) 400 GPM SGTR on S/G E-088 Indications Available:

• 61C21 - Seismic Recording System Activated

• 61C22 - OP Basis EQ Detected

• 60A46 - Secondary Radiation High (+ 60 sec)

• DAS Leak Rate Examiner Note: The following steps are from SO23-13-3 Earthquake.

NOTES

1. If an aftershock occurs, then this AOI must be re-initiated for the aftershock along with the completion of the current usage of this AOI.

2. Seismic Panels of Units 2/3 alarm at g rating 0.019.

VERIFY the following occurred:

Valid activation of any of the following Alarms or Seismic Instrument Panel indications:

• 2UA61C21, Seismic Recording System Activated alarm - illuminated (SO123-VIII-1, EAL HU1.1)

SRO

• Strong Motion Acceleration System Activation (light indication on 2UA-8020, actuates at 0.019g)

• Event 2ZLH-8020G (light indication on 2XY-8020)

AND Ground motion that is readily felt by a consensus of Control Room personnel.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 5 Page 15 of 26 Event

Description:

Earthquake (OBE w/o MFW Pump Trip) and 400 GPM SGTR on S/G E-088 Time Position Applicants Actions or Behavior VERIFY Operating Basis Earthquake occurred(SO123-VIII-1, EAL HA1.1):

• 2UA61C22, Operating Basis Earthquake Acceleration alarm -

illuminated (actuates at 0.33g)

AND SRO

• OBE alarms (both white lamps: Containment Base OBE AND Containment Operating Level OBE) on Seismic Instrumentation Panel

- illuminated.

OR

• Confirmation of earthquake ground acceleration by offsite agency 0.33g SRO INITIATE Attachment 1.

Examiner Note: The crew may enter SO23-13-14 RCS Leak momentarily before tripping the reactor due to the 400 GPM SGTR on S/G E-088. The applicable steps of SO23-13-14, RCS Leak are listed below.

VERIFY Pressurizer level NOT LOWERING

• (RNO) ENSURE all available Charging Pumps in AUTO to maintain Pressurizer Level VERIFY Pressurizer level NOT LOWERING with all available Charging Pumps in Operation.

• (RNO) ISOLATE Letdown by closing one of the following valves:

• TV-0221, LTDN Temperature Control Valve

• HV-9204, LTDN Isolation Valve

• TV-9267, LTDN Containment Isolation Valve VERIFY in Mode 1 or 2.

VERIFY SDC NOT in service.

VERIFY Pressurizer Level - STABLE or RISING.

• (RNO) If in Mode 1 or 2, then TRIP the Reactor and GO TO SO23 1, Standard Post Trip Actions.

Technical Specification for SGTR:

• 3.4.13 RCS Operational Leakage

• Condition B - Primary to secondary leakage not within limit.

• Action B.1 and B.2 - Be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Examiner Note: When the crew trips the Reactor, proceed to Event 6, ESDE from S/G E-088. All remaining events will auto actuate upon the Reactor trip.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 6, 7, 8 Page 16 of 26 Event

Description:

ESDE from S/G E-088 on Reactor Trip, Main Turbine Fails to Trip on Reactor Trip, CSAS Fails to Auto Actuate.

Time Position Applicants Actions or Behavior Examiner Note: The following steps are from SO23-12-1, Standard Post Trip Actions:

Verify Reactor Trip:

RO VERIFY Reactor Trip Circuit Breakers (8) OPEN.

RO VERIFY Reactor power - LOWERING AND Startup rate NEGATIVE.

RO VERIFY maximum of one full length CEA NOT fully inserted.

Verify Turbine Trip:

BOP ALL HP and LP Stop and Governor valves CLOSED.

• (RNO) Manually trip turbine.

BOP VERIFY BOTH Unit Output Breakers OPEN.

BOP VERIFY Main Turbine speed less than 2000 RPM OR lowering.

Examiner Note: RCP P-003 should be tripped at this time per SO23-13-6, RCP Seal Failure.

RO Trip RCP P-003 due to the failed seals.

SRO INITIATE Attachment 1, WORKSHEET.

Verify Vital Auxiliaries:

BOP VERIFY BOTH 1E 4kV Buses ENERGIZED.

BOP VERIFY all 1E 480V buses ENERGIZED.

BOP VERIFY all Class 1E DC Buses ENERGIZED.

BOP VERIFY all Non-1E 4kV Buses ENERGIZED.

VERIFY one CCW Train OPERATING AND aligned to Non-Critical Loop (NCL) and Letdown Heat Exchanger.

BOP * (RNO) START an available CCW Train.

• (RNO) IF CIAS - ACTUATED, THEN ENSURE all RCPs STOPPED AND GO TO step 5.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 6, 7, 8 Page 17 of 26 Event

Description:

ESDE from S/G E-088 on Reactor Trip, Main Turbine Fails to Trip on Reactor Trip, CSAS Fails to Auto Actuate.

Time Position Applicants Actions or Behavior Examiner Note: The crew will request to pull forward FS-30 during SPTAs. The BOP will perform this procedure and the RO will perform the BOPs SPTA verifications. The following steps are from SO23-12-11, FS-30, Stabilize RCS Temperature During ESDE:

VERIFY S/G least affected by ESDE NOT isolated for SGTR,

• VERFIY most affected S/G level less than 50% WR.

• On the least affected S/G:

• POSITION ADV controller to match existing S/G pressure.

• ENSURE OVERRIDE pushbutton DEPRESSED.

• ENSURE OPEN/MODULATE pushbutton DEPRESSED.

• MAINTAIN least affected S/G pressure approximately 200 psia above most affected S/G pressure.

• VERIFY S/G dryout on most affected S/G:

• RCS Tcold stable or rising.

OR

• S/G pressure less than 200 psia.

• STABILIZE least affected S/G pressure:

• VERIFY ADV in AUTO/MODULATE.

• MAINTAIN Psat for lowest RCS Tcold.

• STABILIZE AFW flow.

• VERIFY RCS pressure is to the right of the Appendix E curve on Attachment 30, Post-Accident Pressure / Temperature Limits.

• OPERATE feedwater on least affected S/G to maintain level between 40% and 80% NR.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 6, 7, 8 Page 18 of 26 Event

Description:

ESDE from S/G E-088 on Reactor Trip, Main Turbine Fails to Trip on Reactor Trip, CSAS Fails to Auto Actuate.

Time Position Applicants Actions or Behavior Critical Task: Within 10 minutes of loss of heat removal from S/G E088, the crew transfers the primary to secondary heat sink to S/G E089 by steaming S/G E089, maintaining Psat for the lowest RCS Tc, per SO23-12-11, FS-30, Establish Stable RCS Temperature During ESDE.

CCT Time:__________

Verify RCS Inventory Control:

VERIFY PZR level between 10% and 70% AND trending to between 30% and 60%.

RO

• (RNO) ENSURE PZR Level Control System - OPERATING in AUTO or MANUAL to restore PZR level.

RO VERIFY Core Exit Saturation Margin greater than or equal to 20°F.

Verify RCS Pressure Control:

VERIFY PZR pressure between 1740 PSIA and 2380 PSIA AND trending to between 2025 PSIA and 2275 PSIA.

• (RNO) ENSURE PZR Pressure Control System OPERATING in AUTO or MANUAL to restore PZR pressure.

• (RNO) IF PZR pressure less than PZR Pressure Control System Setpoint and lowering, THEN ENSURE Normal and Auxiliary Spray valves CLOSED.

• (RNO) IF PZR pressure less than 1740 PSIA, THEN ENSURE the RO following ACTUATED:

• SIAS

• CCAS

• CRIS.

• (RNO) IF PZR pressure less than or equal to 1430 PSIA, THEN ENSURE one RCP in each loop STOPPED.

• (RNO) IF RCP NPSH requirements of Attachment 3, POST-ACCIDENT PRESSURE / TEMPERATURE LIMITS NOT SATISFIED, THEN ENSURE all RCPs STOPPED.

Verify Core Heat Removal:

VERIFY at least one RCP OPERATING.

RO

• (RNO) GO TO Step c.

RO VERIFY Core Exit Saturation Margin greater than or equal to 20°F.

Verify RCS Heat Removal:

RO VERIFY at least one S/G level between 21% NR and 80% NR AND Feedwater AVAILABLE.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 6, 7, 8 Page 19 of 26 Event

Description:

ESDE from S/G E-088 on Reactor Trip, Main Turbine Fails to Trip on Reactor Trip, CSAS Fails to Auto Actuate.

Time Position Applicants Actions or Behavior VERIFY RCS TCOLD between 540°F and 550°F.

• (RNO) IF RCS TCOLD less than 540°F THEN:

• ENSURE feed water flow is NOT excessive.

RO

• ENSURE SBCS valves CLOSED.

• ENSURE ADVs CLOSED.

• IF MSIS ACTUATED AND cooldown terminates THEN STABILIZE RCS temperature for lowest RCS TCOLD.

VERIFY S/G pressures between 960 PSIA and 1050 PSIA.

RO * (RNO) IF S/G pressure less than 740 PSIA THEN ENSURE MSIS ACTUATED AND GO TO step 9.

Verify Containment Isolation:

VERIFY Containment pressure less than 1.5 PSIG.

• (RNO) IF Containment pressure greater than 3.4 PSIG, THEN ENSURE the following ACTUATED:

• SIAS RO

• CIAS

• CCAS

• CRIS

• (RNO) ENSURE all RCPs STOPPED.

RO VERIFY Containment Area Radiation Monitors NOT alarming or trending to alarm.

RO VERIFY Secondary Plant Radiation Monitors NOT alarming or trending to alarm.

Examiner Note: Secondary Plant Radiation Monitors are alarming or were trending to alarm before the MSIS and CIAS, however there are no RNO actions for this step.

This information will be used during event diagnosis.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 6, 7, 8 Page 20 of 26 Event

Description:

ESDE from S/G E-088 on Reactor Trip, Main Turbine Fails to Trip on Reactor Trip, CSAS Fails to Auto Actuate.

Time Position Applicants Actions or Behavior Verify Containment Temperature and Pressure Control:

VERIFY Containment average temperature less than 120°F.

• (RNO) ENSURE proper functioning of Normal Containment Cooling.

• (RNO) ENSURE at least one Containment Dome Air Circulator OPERATING.

• (RNO) IF Containment pressure greater than 3.4 PSIG, THEN:

• ENSURE the following ACTUATED:

• SIAS

• CIAS ROR

• CCAS

• CRIS

• ENSURE all RCPs STOPPED.

• ENSURE all available Containment Emergency Cooling Units OPERATING.

• (RNO) IF Containment pressure greater than 14 PSIG, THEN:

• ENSURE CSAS ACTUATED.

• ENSURE all available Containment Spray Header flows greater than 1600 GPM.

Critical Task: Manually initiate Containment Spray prior to exceeding Containment temperature and pressure limits following a failure of Containment Spray to automatically actuate.

CCT Time:__________

RO VERIFY Containment pressure less than 1.5 PSIG.

Examiner Note: Containment pressure is not less than 1.5 psig, however the RNO actions for high Containment pressure and high Containment temperature are the same, therefore the RNO actions are not addressed twice.

VERIFY all safety function criteria per Attachment 1, WORKSHEET SRO RECOVERED.

• (RNO) COMPLETE Attachment 2, RECOVERY DIAGNOSTICS.

Examiner Note: The CRS should diagnose two events (Excess Steam Demand and Steam Generator Tube Rupture) and identify SO23-12-9, Functional Recovery, as the optimal EOI.

VERIFY REACTOR TRIP RECOVERY DIAGNOSED.

SRO

• (RNO) ENSURE at least one RCP in each loop stopped.

SRO INITIATE steps 12 through 17.

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Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 6, 7, 8 Page 21 of 26 Event

Description:

ESDE from S/G E-088 on Reactor Trip, Main Turbine Fails to Trip on Reactor Trip, CSAS Fails to Auto Actuate.

Time Position Applicants Actions or Behavior SRO IMPLEMENT EOI diagnosed.

Examiner Note: The following steps are from SO23-12-9, Functional Recovery:

SRO RECORD time of EOI entry _______.

SRO INITIATE SO23-12-10, SAFETY FUNCTION STATUS CHECKS.

INITIATE FOLDOUT PAGE.

• IF SIAS has actuated, THEN INITIATE FS-7, VERIFY SI Throttle/Stop Criteria.

SRO

• IF all RCPs are stopped, THEN INITIATE FS-3, MONITOR Natural Circulation Established.

• If SIAS has initiated, THEN INITIATE SO23-12-11, Attachment 22, NON-QUALIFIED LOAD RESTORATION.

SRO DIRECT Chemistry to sample both S/Gs for radioactivity and boron.

SRO NOTIFY Shift Manager/Operations Leader of entry into SO23-12-9, FUNCTIONAL RECOVERY.

SRO ENSURE Emergency Plan is initiated.

SRO IMPLEMENT PLACEKEEPER.

SRO IMPLEMENT TIME DEPENDENT STEPS SRO VERIFY SIAS actuation required.

ENSURE the following have actuated:

• SIAS SRO

• CCAS

• CRIS SRO RECORD time of SIAS _______.

SRO VERIFY CIAS actuated.

RO STOP unloaded Diesel Generators.

RO INITIATE SO23-12-11, Attachment 22, NON-QUALIFIED LOAD RESTORATION.

VERIFY RCP NPSH requirements of SO23-12-11, Attachment 30, POST-ACCIDENT PRESSURE / TEMPERATURE LIMITS satisfied.

RO

• (RNO) STOP all RCPs AND INITIATE FS-3, MONITOR Natural Circulation Established.

ESTABLISH two train SI operation.

SRO * (RNO) REQUEST Shift Manager/Operations Leader to direct plant resources to establish the following support systems for non-operating/unavailable equipment.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 6, 7, 8 Page 22 of 26 Event

Description:

ESDE from S/G E-088 on Reactor Trip, Main Turbine Fails to Trip on Reactor Trip, CSAS Fails to Auto Actuate.

Time Position Applicants Actions or Behavior VERIFY any safety function recovery attachments (FR-1 through FR-7)

SRO indicated by any optimal EOI.

• (RNO) GO TO step 6c.

IMPLEMENT precautionary actions:

SRO

• INITIATE Boration greater than 40 GPM.

• ENSURE one RCP in each loop stopped.

VERIFY ESDE NOT indicated.

• (RNO) INITIATE SO23-12-11, Attachment 29 ISOLATION OF STEAM SRO GENERATOR WITH ESDE.

• (RNO) INITIATE FS-30, ESTABLISH Stable RCS Temperature during ESDE.

VERIFY SGTR NOT indicated.

SRO * (RNO) INITIATE Attachment FR-6, RECOVERY - CONTAINMENT ISOLATION Success Path CI-2, S/G ISOLATION.

Examiner Note: The following steps are from SO23-12-9, Functional Recovery, FR-6, Recovery -

Containment Isolation.

VERIFY Containment Isolation Success Path IDENTIFIED by SO23-12-10, SRO SAFETY FUNCTION STATUS CHECKS, Attachment for Functional Recovery OR implementation directed by another EOI.

Examiner Note: The CRS will determine Success Path CI-2 will not work due to high containment pressure and proceed to Success Path CI-3. The following steps are from Success Path CI-3.

SRO VERIFY Containment pressure greater than 3.4 PSIG OR Containment Area Radiation Monitors alarming or trending to alarm.

SRO VERIFY MFW NOT required for RCS Heat Removal Success Paths.

SRO ENSURE SIAS actuated.

SRO VERIFY CIAS actuated.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 6, 7, 8 Page 23 of 26 Event

Description:

ESDE from S/G E-088 on Reactor Trip, Main Turbine Fails to Trip on Reactor Trip, CSAS Fails to Auto Actuate.

Time Position Applicants Actions or Behavior VERIFY at least one valve in each Containment penetration not required to be open closed unless penetration open to support:

• ECCS SRO

• RCP operation

• Instrument Air

• S/G heat sink.

SRO VERIFY SGTR indicated.

BOP PERFORM SO23-12-11, Attachment 28, SGTR ACTIONS.

Examiner Note: The following steps are from SO23-12-11, Attachment 28, SGTR Actions.

BOP ENSURE one RCP in each loop is stopped.

ENSURE the following actuated:

• SIAS BOP

• CCAS

• CRIS BOP VERIFY Containment pressure less than Instrument Air pressure.

OVERRIDE and OPEN HV-5388, Instrument Air to Containment Isolation BOP valve and ENSURE HV-5343, Excess Flow Check valve open.

BOP IDENTIFY S/G most affected by SGTR (E088).

OPERATE MFW or AFW to maintain affected S/G level greater than 40% NR and RCS cooldown less than 100ºF in one hour.

BOP Examiner Note: This step will not be met due to the concurrent ESDE, however there is no RNO action for this step.

SRO NOTIFY Shift Manager of S/G most affected by SGTR.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 6, 7, 8 Page 24 of 26 Event

Description:

ESDE from S/G E-088 on Reactor Trip, Main Turbine Fails to Trip on Reactor Trip, CSAS Fails to Auto Actuate.

Time Position Applicants Actions or Behavior BOP VERIFY at least one electric AFW Pump operating.

BOP VERIFY electric AFW Pump to least affected S/G operating.

BOP VERIFY least affected S/G available for continued heat removal.

BOP ENSURE RCS Thot less than 530ºF.

ISOLATE affected S/G:

• CLOSE/STOP the following components for most affected S/G (E088):

• MSIV HV-8205

• MSIV Bypass HV-8203

• ADV HV-8419 BOP

• MFIV HV-4048

• AFW valves HV-4714 and HV-4730

• Steam to AFW P-140 HV-8201

• S/G Blowdown Isolation HV-4054

• S/G Water Sample Isolation HV-4058

• Electric AFW Pump P-504 BOP RECORD time of S/G isolation ____.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 6, 7, 8 Page 25 of 26 Event

Description:

ESDE from S/G E-088 on Reactor Trip, Main Turbine Fails to Trip on Reactor Trip, CSAS Fails to Auto Actuate.

Time Position Applicants Actions or Behavior Critical Task: Isolate S/G E-088 prior to exiting SO23-12-9, Functional Recovery.

CCT Time:__________

Scenario Termination: When the crew has stabilized RCS temperature and isolated SG E088, or at Lead Evaluators discretion, the scenario may be terminated.

Examiner Note: The following are steps 12-17 of SO23-12-1, Standard Post Trip Actions.

RO INITIATE Attachment 4, ADMINISTRATIVE ACTIONS.

RO ENSURE a PA System announcement was made regarding the Reactor trip.

OPERATE SBCS to maintain RCS TCOLD between 540°F and 550°F.

RO * (RNO) OPERATE ADVS to maintain RCS TCOLD between 540°F and 550°F.

RO VERIFY TELECOM 480VAC FDR BKR HS0800S-2 (Q800S) CLOSED RO VERIFY TELECOM 480VAC FDR BKR HS0800N-2 (Q800N) CLOSED.

RO VERIFY all Non-1E 4kV Buses ENERGIZED.

RO VERIFY 480V Load Centers B15 and B16 ENERGIZED.

RO ENSURE 3rd Point Heater Drain Pumps STOPPED.

VERIFY RTO RESET.

• (RNO) IF a MFW pump in service THEN RESET RTO per SO23-9-6, RO Feedwater Control System Operation Examiner Note: RTO will not be reset due to the loss of all feedwater.

Examiner Note: RTO will not be reset due to the loss of all feedwater.

MAINTAIN one MFW Pump and a maximum of three Condensate Pumps in RO operation.

• (RNO) ENSURE S/G levels being maintained by AFW Pumps.

ENSURE FIC-3294, Condensate Pump miniflow controller set for proper Condensate pump configuration:

RO

• One pump - 4500 GPM

• Two pumps - 6000 GPM

• Three pumps - 9000 GPM RO PLACE Condensate Draw-off valve LV-3245 to DISABLE.

VERIFY SO23-12-2, REACTOR TRIP RECOVERY being implemented.

RO * (RNO) ENSURE S/G Blowdown valves HV-4054 and HV-4053 CLOSED.

• (RNO) GO TO step 16.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 5 Event # 6, 7, 8 Page 26 of 26 Event

Description:

ESDE from S/G E-088 on Reactor Trip, Main Turbine Fails to Trip on Reactor Trip, CSAS Fails to Auto Actuate.

Time Position Applicants Actions or Behavior ENSURE the following valves closed:

• Extraction Steam Block valves HV-8800, HV-8812, HV-8804, HV-8810, HV-8808, HV-8820, HV-8806, and HV-8816.

RO

• Main Steam to Reheater Block, Bypass, Warmup and Control valves HV-2703 or HV-2704, HV-2721, and HV-2751.

• Bled Steam to Reheaters Block Valve HV-2712A/B.

RO VERIFY Main Generator voltage less than 24kV.

VERIFY annunciators RESET:

RO

• 99A26 TURBINE LUBE OIL TEMP HI

• 99A46 TURBINE BRG OIL DRAIN TEMP HI INITIATE SO23-10-2, TURBINE SHUTDOWN, Attachment for Unloading RO the Generator and Removing the Unit from Line.

RO VERIFY BOTH Start-Up Range channels OPERABLE.

SONGS 2012 NRC Sim Scenario #5 Rev d.docd