ML14251A041

08 Final Operating Test

ML14251A041
Person / Time
Site:	Diablo Canyon
Issue date:	08/11/2014
From:	Vincent Gaddy Operations Branch IV
To:	Pacific Gas & Electric Co
laura hurley
References
50-275/14-OL, 50-323/14-OL
Download: ML14251A041 (246)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Diablo Canyon Date of Examination: 08/11/2014 Examination Level: RO SRO Operating Test Number: L121 Administrative Topic Type Describe activity to be performed (See Note) Code*

Determine Ultimate Heat Sink Temperature Conduct of Operations 2.1.23 Ability to perform specific system and integrated plant M, R procedures during all modes of operation (NRCL121-A1) (4.3)

(modified from bank LJACO-02R)

Determine Boration/Dilution Req for Power Rise Conduct of Operations 2.1.25 Ability to interpret reference materials, such as graphs, M, R curves, tables, etc.

(NRCL121-A2) (3.9)

(modified from L081 NRC ADMRO1)

Perform Outage Safety Checklist Equipment Control 2.2.37 Ability to determine operability and/or availability of D, R safety related equipment.

(NRCL121-A3) (3.6)

(bank: LJAEC-01R ; previously used in L061C NRC ADM02)

Review Liquid Radwaste Discharge Checklist Radiation Control 2.3.11 Ability to control radiation releases.

M, R (3.8)

(NRCL121-A4) (modified from L061C NRC ADM04)

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

• Type Codes & Criteria: (C)ontrol room, (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)

ES 301, Page 22 of 27 Rev 0 Rev 0: Initial Submittal

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Diablo Canyon Date of Examination: 08/11/2014 Examination Level: RO SRO Operating Test Number: L121 Administrative Topic Type Describe activity to be performed (See Note) Code*

Verify Determination of Ultimate Heat Sink Temp Conduct of Operations 2.1.23 Ability to perform specific system and integrated plant M, R procedures during all modes of operation (NRCL121-A5) (4.4)

(modified from LJACO-02S)

Determine Boration/Dilution Req for Power Rise Conduct of Operations 2.1.25 Ability to interpret reference materials, such as graphs, M, R curves, tables, etc.

(NRCL121-A6) (4.2)

(modified from L081 NRC ADMRO1)

Verify Outage Safety Checklist Equipment Control 2.2.37 Ability to determine operability and/or availability of M, R safety related equipment.

(NRCL121-A7) (4.6)

(modified from bank LJAEC-01R ; previously used in L061C NRC ADM02)

Review Liquid Radwaste Discharge Checklist Radiation Control 2.3.11 Ability to control radiation releases.

M, R (4.3)

(NRCL121-A8) (modified from L061C NRC ADM04)

Classification of a FH Accident in Containment Emergency Procedures/Plan 2.4.41 Knowledge of the emergency action level thresholds D, R and classifications.

(NRCL121-A9) (4.6)

(direct from bank - LJE-017)

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

• Type Codes & Criteria: (C)ontrol room, (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)

ES 301, Page 22 of 27 Rev 0 Rev 0: Initial Submittal

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A1

Title:

DETERMINE ULTIMATE HEAT SINK TEMPERATURE Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, Rev.

127 Technical Specifications, DCPP Units 1 & 2 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2.3, 2.7, 3.4 Job Designation: RO Rev Comments: modified from bank LJACO02R Gen KA / Rating: G2.1.23 - Ability to perform specific system and integrated 4.3 plant procedures during all modes of plant operation.

Note: This is an admin JPM (RO), intended for the classroom setting.

AUTHOR: LISA TORIBIO/ DATE: 06/20/2014 OPERATIONS ABDUL KADIR/ DATE: 06/20/2014 REPRESENTATIVE:

REV. 0

JPM TITLE: DETERMINE ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: NRCL121-A1 EVALUATOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: Unit 1 STP I1A, MODE 1 Shift Checks, Step 37 (SR 3.7.9.2)

Initial Conditions GIVEN:

• Unit 1 is at 50% power

• CWP 1-2 out of service for replacement of damaged screens

• Unit 2 is in day 14 of a refueling outage.

Current plant conditions for the Circ Water and ASW systems are as follows:

Component Status Current Ocean Temperature CWP 1-1 In-service TI-311 Out of Calibration CWP 1-2 Cleared TI-328 60.1°F ASW Pp 1-1 In-service to CCW HX 1-1 TI-1484 61.4°F ASW Pp 1-2 In-STBY TI-1485 60.2°F CWP 2-1 Cleared TI-311 60.3°F CWP 2-2 Cleared TI-328 60.4°F ASW Pp 2-1 In-service to CCW HX 2-1 TI-1484 61.5°F ASW Pp 2-2 Cleared TI-1485 60.4°F Initiating Cue: Shift Forman directs you to determine the Ultimate Heat Sink Temperature, using STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, Step 37.

DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: Using step 37, determined ocean temperature is 62.1°F and needs to be recorded every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

NRCL121-A1 PAGE 2 OF 5 REV. 0

JPM TITLE: DETERMINE ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: NRCL121-A1 EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 Obtains STP I1A, Attachment 12.1.

Sat: ______ Unsat _______

Comment:

2.**

0B Determine ocean temperature 2.1 Reads NOTE prior to step 37.a.

N/A checked for step 37.a (Method 1) 2.2 (TI-311 is Out of Service and CWP 1-2 is not running)

Performed step 37.b (Method 2), and 1B 2.3 recorded Pacific Ocean water temperature, 61.4°F (TI-1484).**

N/A checked for TI-1485, (ASW Pp 1-2 2.4 2B not running).

Determined 61.4°F is the highest available 2.5 3B indication.

2.6 Adds 0.7°F 4B Recorded 62.1°F as the corrected ocean 2.7 5B temperature. **

2.8 Checks N/A for step 37.c (Method 3)

Sat: ______ Unsat _______

Comment:

NRCL121-A1 PAGE 3 OF 5 REV. 0

JPM TITLE: DETERMINE ULTIMATE HEAT SINK TEMPERATURE JPM NUMBER: NRCL121-A1 EVALUATOR W ORKSHEET

3. Document monitoring requirements 3.1 Read NOTE prior to step 37.d.

3.2 Checked N/A for step 37.d 3.3 Checked step 37.e.1) to inform SFM to review SR 3.7.9.2 Checked step 37.d.2) due to ocean temperature determined to be greater than 3.4 62°F but less than 64°F, and that temperatures need to be recorded every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.**

3.5 N/A step 37.f Sat: ______ Unsat _______

Comment:

Stop Time:

Total Time: (Enter total time on the cover page)

Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL121-A1 PAGE 4 OF 5 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A1 Initial Conditions: GIVEN:

• Unit 1 is at 50% power

• CWP 1-2 out of service for replacement of damaged screens

• Unit 2 is in day 14 of a refueling outage.

• Current plant conditions for the Circ Water and ASW systems are as follows:

Component Status Current Ocean Temperature CWP 1-1 In-service TI-311 Out of Calibration CWP 1-2 Cleared TI-328 60.1°F ASW Pp 1-1 In-service to CCW HX 1-1 TI-1484 61.4°F ASW Pp 1-2 In-STBY TI-1485 60.2°F CWP 2-1 Cleared TI-311 60.3°F CWP 2-2 Cleared TI-328 60.4°F ASW Pp 2-1 In-service to CCW HX 2-1 TI-1484 61.5°F ASW Pp 2-2 Cleared TI-1485 60.4°F Initiating Cue: Shift Forman directs you to determine the Ultimate Heat Sink Temperature, using STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, Step 37.

NRCL121-A1 PAGE 5 OF 5 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A2

Title:

DETERMINE DILUTION REQUIREMENTS TO RAISE POWER Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

DCPP Unit 2 Cycle 18 Reactivity Briefing Sheet (263 to 310 EFPD)

Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2.2, 3.3, 4.1, 5.1 Job Designation: RO or SRO Rev Comments: modified from L081 NRC ADMRO1 Gen KA / Rating: G2.1.25 - Conduct of Operations 3.9 Note: This is an admin JPM (RO), intended for the classroom setting.

AUTHOR: LISA TORIBIO/ DATE:

OPERATIONS ABDUL KADIR/ DATE:

REPRESENTATIVE:

REV. 0

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE JPM NUMBER: NRCL121-A2 POWER EVALUATOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: Calculator, Reactivity Briefing Sheet from the Reactivity Handbook Initial Conditions Given:

• Unit 2 was ramped down due to high vibration on the main turbine.

• Unit 2 has been at 80% power for 3 days.

• Control Bank D is at 200 steps Initiating Cue: The Shift Foreman directs you to determine the dilution or boration requirements, in gallons, to raise power to 90% assuming final rod position of 210 steps using the data from the Reactivity Briefing Sheet (from Reactivity Handbook)

DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: Determined that 928 (+/- 5 ) gallons of primary water is required for the 10% power increase.

NRCL121-A2 PAGE 2 OF 5 REV. 0

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE JPM NUMBER: NRCL121-A2 POWER EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 Cue: Provide examinee with reactivity briefing sheet, if not already done.

Sat: ______ Unsat _______

Comment:

Calculate reactivity change for 10% 2.1 From graph power coefficient is -15.47 2.** change in power pcm/% power.

0B 2.2 Recorded (-)154.7 pcm for 10% increase in power. **

Sat: ______ Unsat _______

Comment:

Recorded 45.9 pcm for Control Bank D at Calculate reactivity change due to change 3.1 210 steps.

3.** 1B in rod position (From graph, A. Control Bank D Integral Rod Worth)

Recorded 98.1 pcm for Control Bank D at 3.2 200 steps.

(From graph, A. Control Bank D Integral Rod Worth)

Recorded (+)52.2 pcm for change in rod 3.3 position. **

(98.1 - 45.9 )

Sat: ______ Unsat _______

Comment:

NRCL121-A2 PAGE 3 OF 5 REV. 0

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE JPM NUMBER: NRCL121-A2 POWER EVALUATOR W ORKSHEET Recorded (-)102.5 pcm)reactivity from change Calculate reactivity left after accounting in rods position on total reactivity from change 4.** 4.1 in power. **

change in rod position.

2B

(-154.7 + 52.2)

Sat: ______ Unsat _______

Comment:

Note: The examinee may set up a ratio to get the primary water needed, Determines amount of primary water to or may do two steps (determine 5.**

add power change needing dilution, 3B and then dilution for that power change).

Determined 928 (+/- 5 ) gallons of primary water is required.

5.1 (102.5 pcm/15.47 pcm/% = 6.63 % pwr)

(6.63% x 140 gal/% =

928 gallons (+/- 5 gallons) **

Note: The critical part of the above step is the dilution gallons, as the data can be manipulated several different ways in one or more steps to arrive at the right answer.

Sat: ______ Unsat _______

Comment:

Stop Time:

Total Time: (Enter total time on the cover page)

Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ___________________________________________________________________

NRCL121-A2 PAGE 4 OF 5 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A2 Initial Conditions: Given:

• Unit 2 was ramped down due to high vibration on the main turbine.

• Unit 2 has been at 80% power for 3 days.

• Control Bank D is at 200 steps Initiating Cue: The Shift Foreman directs you to determine the dilution or boration requirements, in gallons, to raise power to 90% assuming final rod position of 210 steps using the data from the Reactivity Briefing Sheet (from Reactivity Handbook)

Answer (show work):

NRCL121-A2 PAGE 5 OF 5 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A3

Title:

PERFORM OUTAGE SAFETY CHECKLIST Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

AD8.DC55, Outage Safety Scheduling, Attachment 4, pg. 6, Rev. 38 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2.1, 2.2, (3 or 4 & 5) 6, 7, 8 Job Designation: RO Rev Comments: Bank: LJAEC-01R ; previously used in L061C NRC ADM02 Gen KA / Rating: G2.2.37 - Ability to determine operability and/or availability of 3.6 safety related equipment Note: This is an admin JPM (RO), intended for the classroom setting.

AUTHOR: LISA TORIBIO/ DATE:

OPERATIONS ABDUL KADIR/ DATE:

REPRESENTATIVE:

REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A3 Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: AD8.DC55, Outage Safety Scheduling, Attachment 4, pg. 6, Rev. 38 Technical Specifications (available)

NRCL121-A3 PAGE 2 OF 9 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A3 Initial Conditions Unit 1 is currently in MODE 6 with Core reload in progress.

Current plant parameters are as follows:

Operable Cleared Offsite power sources Startup power X Aux power X Onsite power sources Diesel Generator 1 X Diesel Generator 2 X Diesel Generator 3 X Vital bus crosstie 4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Onsite distribution sys. 4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Instrument AC Panels PY-11 X PY-11A X PY-12 X PY-13 X PY-13A X PY-14 X Vital DC Power DC Bus 1-1 X DC Bus 1-2 X DC Bus 1-3 X Refueling cavity level 23.4 Feet Initiating Cue: The Shift Foreman directs you to perform the AD8.DC55, "Outage Safety Scheduling," Att 4, page 6, Mode 6 Outage Safety Checklist for the current plant conditions DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: Correctly completes AD8.DC55, Att 4, page 6, Mode 6 Outage Safety Checklist for VITAL AC POWER.

NRCL121-A3 PAGE 3 OF 9 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A3 Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. Note: Provide exam copy of AD8.DC55, Att 4, page 6 (page 9 of this JPM).

Sat: ______ Unsat _______

Comment:

Determines status of power to operable Determines S/U Power is operable and 2.** 2.1 marks the appropriate "boxes" on Att 4, vital buses.

0B page 6. **

Determines that a D/G is operable for 4kV 2.2 vital bus F (D/G 1-3) and G (D/G 1-2) and marks the appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment:

Determines onsite power supply Note: Examinee may complete either 3.** 1B operability. step 3 (page 7) or both steps 4 and 5 (page 8 of this JPM).

Determines that D/G 1-2 and 1-3 are 3.1 operable and marks the appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment:

NRCL121-A3 PAGE 4 OF 9 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A3 Step Expected Operator Actions Determines that refueling cavity level is 23.4 feet ( 23 feet above the vessel 4.**

2B Determines status of refueling cavity. 4.1 flange) and the upper internals are removed (i.e., core onload is in progress) and marks the appropriate "boxes" on Att 4, page 6.

Determines that S/U power is operable and 4.2 marks the appropriate "boxes" on Att 4, page 6.

Sat: ______ Unsat _______

Comment:

Determines that one D/G is operable Determines Diesel Generator (D/G) 5.1 5.** 3B Operability (either D/G 1-2 or 1-3) and marks appropriate "boxes" on Att 4, page 6.**

Determines that a different D/G (either 5.2 D/G 1-3 or 1-2) is either operable or available and marks appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment:

Determines that 4 kV buses F and G, as Determines TS required 4kV and 480V 6.1 well as 480V buses F and G, are operable 6.** 4B bus operability and marks appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment:

NRCL121-A3 PAGE 5 OF 9 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A3 Step Expected Operator Actions Determines status of Instrument AC Determines that all vital instrument AC 7.** 7.1 power panels are operable and marks Power Panels.

5B appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment:

Determines that all vital DC buses are 8.** 6B Determines status of Vital DC Power 8.1 operable and marks appropriate "boxes" on Att 4, page 6. **

Sat: ______ Unsat _______

Comment:

Stop Time:

Total Time: (Enter total time on the cover page)

Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL121-A3 PAGE 6 OF 9 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A3 NRCL121-A3 PAGE 7 OF 9 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A3 NRCL121-A3 PAGE 8 OF 9 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A3 Initial Conditions: Unit 1 is currently in MODE 6 with Core reload in progress.

Current plant parameters are as follows:

Operable Cleared Offsite power sources Startup power X Aux power X Onsite power sources Diesel Generator 1 X Diesel Generator 2 X Diesel Generator 3 X Vital bus crosstie 4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Onsite distribution sys. 4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Instrument AC Panels PY-11 X PY-11A X PY-12 X PY-13 X PY-13A X PY-14 X Vital DC Power DC Bus 1-1 X DC Bus 1-2 X DC Bus 1-3 X Refueling cavity level 23.4 Feet Initiating Cue: The Shift Foreman directs you to perform the AD8.DC55, "Outage Safety Scheduling," Att 4, page 6, Mode 6 Outage Safety Checklist for the current plant conditions NRCL121-A3 PAGE 9 OF 9 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A4

Title:

REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, Rev. 37A CAP A-5, Liquid Radwaste Discharge Management, Rev. 48 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Step(s): 6.1, 7.1 Job Designation: RO Rev Comments: modified from L061C NRC ADM04 Gen KA / Rating: 2.3.11 Ability to control radiation releases 3.8 Note: This is an admin JPM (RO), intended for the classroom setting.

AUTHOR: LISA TORIBIO/ DATE:

OPERATIONS ABDUL KADIR/ DATE:

REPRESENTATIVE:

REV. 1

JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCL121-A4 EVALUATOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, Rev.37A Partially completed Section 12 CAP A-5 Completed Attachment 11.1 Parts 1 & 2 Initial Conditions Chemistry has issued a discharge permit for PWR 0-2 using CAP A-5 Att. 11.1 parts 1 & 2. OP G-1:II Section 12 has been partially completed. CCW HX 1-1 is in service, and both Units are at 100%

power Initiating Cue: Review OP G-1:II Section 12 Discharge Checklists for accuracy and completeness thru step 12.10. Document any discrepancies noted DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: 2 Technical errors identified:

Section 12 page 1 (of 8), PWR 0-2 is designated as the discharge source, but alignment has been performed for PWR 0-1 (LWS-0-934 is open when LWS-0-937 should be open)

Section 12 page 2 (of 8), CCW HX 1-1 is designated to be used for the release (initial condition), but alignment has been performed for CCW HX 1-2 (SW-1-68 is open when SW-1-67 should be open)

NRCL121-A4 PAGE 2 OF 5 REV. 1

JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCL121-A4 EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions Review step 12.1 - Parts 1 and 2 of Reviewed Parts 1 and 2 of CAP A-5,

1. discharge permit complete and signed by 1.1 Attachment 11.1 and determined parts 1 & 2 Chemistry are complete and signed by Chemistry Sat: ______ Unsat _______

Comment:

Review step 12.2 - Appropriate tank Identified that PWR 0-2 has been correctly

2. identified 2.1 circled for discharge Sat: ______ Unsat _______

Comment:

Review steps 12.3 (RE-18 adjustment) & Identified that RE-18 setpoint doesnt require

3. 3.1 12.4 (FIT-243 not operable actions) adjustment 3.2 Identified FIT-243 is OPERABLE Sat: ______ Unsat _______

Comment:

Review step 12.5 - Discharge flowpath Identified that LWS-0-436 to U1 CCW,

4. aligned to inservice U1 CCW heat 4.1 marked as OPEN exchanger identified Identified that LWS-0-439 to U2 CCW, 4.2 marked as CLOSED Sat: ______ Unsat _______

Comment:

NRCL121-A4 PAGE 3 OF 5 REV. 1

JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCL121-A4 EVALUATOR W ORKSHEET Step Expected Operator Actions Review steps 12.6 thru 12.9 - valves Identified that steps 12.6 through 12.8 signed

5. 5.1 closed as completed Sat: ______ Unsat _______

Comment:

Review step 12.9 - Check OPEN PWR Identified that PWR 0-1 was aligned for 6.** Pp Discharge (second off) 6.1 discharge instead of PWR 0-2.**

Sat: ______ Unsat _______

Comment:

Identified CCW HX 11 should be circled to be 7.** Review step 12.10 - ASW checklist 7.1 used, but that valve alignment was incorrectly done for CCW HX 12. **

Sat: ______ Unsat _______

Comment:

Stop Time:

Total Time: (Enter total time on the cover page)

Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL121-A4 PAGE 4 OF 5 REV. 1

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A4 Initial Conditions: Chemistry has issued a discharge permit for PWR 0-2 using CAP A-5 Att. 11.1 parts 1 & 2. OP G-1:II Section 12 has been partially completed. CCW HX 1-1 is in service, and both Units are at 100%

power Initiating Cue: Review OP G-1:II Section 12 Discharge Checklists for accuracy and completeness thru step 12.10. Document any discrepancies noted NRCL121-A4 PAGE 5 OF 5 REV. 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A5

Title:

VERIFY A DETERMINATION OF ULTIMATE HEAT SINK TEMPERATURE Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, Rev. 126

References:

Technical Specifications, DCPP Units 1 & 2 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 1.2, 3.1, 4.1 Job Designation: SRO Rev Comments: modified from LJACO-02S Gen KA / Rating: G2.1.25 - Conduct of Operations 3.9 Note: This is an admin JPM (SRO), intended for the classroom setting.

AUTHOR: LISA TORIBIO/ DATE:

OPERATIONS ABDUL KADIR/ DATE:

REPRESENTATIVE:

REV. 1

JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT JPM NUMBER: NRCL121-A5 SINK TEMPERATURE EVALUATOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: Completed copy of STP I-1A, Attachment 12.1, MODE 1 Shift Checklist, Step 37 (SR 3.7.9.2). LCO 3.7.9 Initial Conditions GIVEN:

• Unit 1 is at 50% power

• CWP 1-2 out of service for replacement of damaged screens

• Unit 2 is in day 14 of a refueling outage.

Current plant conditions for the Circ Water and ASW systems are as follows:

Component Status Current Ocean Temperature CWP 1-1 In-service TI-311 Out of Calibration CWP 1-2 Cleared TI-328 61.1°F ASW Pp 1-1 In-service to CCW HX 1-1 TI-1484 59.5°F ASW Pp 1-2 In-STBY TI-1485 61.4°F CWP 2-1 Cleared TI-311 60.3°F CWP 2-2 Cleared TI-328 60.4°F ASW Pp 2-1 In-service to CCW HX 2-1 TI-1484 59.5°F ASW Pp 2-2 Cleared TI-1485 60.4°F Initiating Cue: Unit 1 BOPCO has just completed STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, Step 37.

BOPCO has just informed you that the Ultimate Heat Sink Temperature requires 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> recordings for the given conditions.

Review the completed STP data sheet and determine if the unit is in a LCO ACTION statement for Ultimate Heat Sink and what frequency of ocean temperature monitoring is required.

DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, is reviewed and it is determined the calculation of Ultimate Heat Sink temperature was incorrect. The correct temperature is above the limit for increased monitoring (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />), but the LCO is satisfied, (temperature is less than 64°F)

NRCL121-A5 PAGE 2 OF 5 REV. 1

JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT JPM NUMBER: NRCL121-A5 SINK TEMPERATURE EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions 1.** Review Step 37, Method 1 Data. 1.1 Read NOTE prior to step 37.a Method 1 incorrectly used. CWP 1-2 is not 1.2 running (Per note, temperature indicator not available) and TI-311 is out of calibration.**

Sat: ______ Unsat _______

Comment:

NOTE: The sheet may not be completed as the key is however, some manner must be used to determine the correct ocean temperature

2. Perform Step 37, Method 2 2.1 Used method 2 to determine ocean temperature:

TI-1484 = 59.5°F TI-1485. = N/A 2.2 Added 0.7°F for instrument error correction 2.3 Determined ocean temperature to be between 60 and 62°F (60.2°F)

Sat: ______ Unsat _______

Comment:

Determine ocean temperature monitoring 3.1 Required ocean temperature monitoring is 37.d 3.** required (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) **

Sat: ______ Unsat _______

Comment:

4.1 LCO is met, UHS is OPERABLE (less than 4.** Evaluates LCO 3.7.9 (UHS) **

64°F)**

Sat: ______ Unsat _______

Comment:

NRCL121-A5 PAGE 3 OF 5 REV. 1

JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT JPM NUMBER: NRCL121-A5 SINK TEMPERATURE EVALUATOR WORKSHEET Stop Time:

Total Time: (Enter total time on the cover page)

Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

Key:

Is the unit in an ACTION statement for Ultimate Heat Sink? Yes / No.

What is the frequency of ocean temperature monitoring required?

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 12 hours 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Explanation:

(From 3.7.9 bases: The UHS is required to be OPERABLE and is considered OPERABLE if it is at or below the maximum temperature that would allow the ASW to operate for at least 30 days following the DBA without exceeding the maximum design temperature of the CCW system. To meet this condition, the UHS temperature should not exceed 64°F unless two CCW heat exchangers are in service during normal unit operation. With two heat exchangers in service, operation with elevated UHS temperatures as high as 70°F is acceptable.)

NRCL121-A5 PAGE 4 OF 5 REV. 1

69-20232 01/27/14 Page 15 of 26 STP I-1A (UNIT 1)

ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.7.9.2 37. Determine the Ultimate Heat Sink (UHS) temperature using one of the following methods:

NOTE: Temperature indicators are only available when their associated pumps are running.

a. Method 1 - Record Pacific Ocean water temp as read on the following indicators: GLH N/A [ ] ______

TI-311 (T2400A)

TI-328 (T2401A)

EY (CWP 1-1)

(CWP 1-2)

_______F 61.1

_______F Record the highest of the available indicators. 61.1 F N/A [X]

N/A [ ]

K Instrument Error Correction Add the highest available indicator reading and the Instrument Error 1.9 F SW Correction. 63.0 F

b. Method 2 - Record Pacific Ocean water temp on the following indicators: N/A [ X] ______

ER TI-1484 (ASWP 1-1) _59.5__F N/A [ ]

TI-1485 (ASWP 1-2) _______F N/A [ ]

Record the highest of the available indicators. 59.5°F Instrument Error Correction 0.7 F N Add the highest available indicator reading and the Instrument Error Correction. 60.2°F A

STP_I-1Au1r27.DOC 06 0515.1508

69-20232 01/27/14 Page 16 of 26 STP I-1A (UNIT 1)

ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.7.9.2 c. Method 3 - If Method 1 and Method 2 are not available, M&TE may be used. GLH N/A [X] ______

(Continued)

Instrument Used: ____________________

Cal Due Date: ____________________

Reading using M&TE F Uncertainty of M&TE F Add M&TE ocean temp and uncertainty F NOTE: Tech Spec Bases B3.7.9 specifies that the UHS is common to both units. Therefore any required action due to elevated ocean water temp would apply to both units depending on mode requirements. Notify the Unit 2 SFM as required.

d. IF corrected ocean temp is > [60F] AND [62F],

THEN perform the following: N/A [ X]

1) Notify SFM to review Tech Spec SR 3.7.9.2. ______

2) Record ocean temp every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ______

X

e. IF corrected ocean temp is > [62F] AND [64F],

THEN perform the following: N/A [ ]

1) Notify SFM to review Tech Spec SR 3.7.9.2. GLH

2) Record ocean temp every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. GLH

f. IF corrected ocean temp is > [64F],

THEN place both CCW HXs in service: GLH N/A [X] ______

STP_I-1Au1r27.DOC 06 0515.1508

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A5 Initial Conditions: GIVEN:

• Unit 1 is at 50% power

• CWP 1-2 out of service for replacement of damaged screens

• Unit 2 is in day 14 of a refueling outage.

• Current plant conditions for the Circ Water and ASW systems are as follows:

Component Status Current Ocean Temperature CWP 1-1 In-service TI-311 Out of Calibration CWP 1-2 Cleared TI-328 61.1°F ASW Pp 1-1 In-service to CCW HX 1-1 TI-1484 59.5°F ASW Pp 1-2 In-STBY TI-1485 61.4°F CWP 2-1 Cleared TI-311 60.3°F CWP 2-2 Cleared TI-328 60.4°F ASW Pp 2-1 In-service to CCW HX 2-1 TI-1484 59.5°F ASW Pp 2-2 Cleared TI-1485 60.4°F Initiating Cue: Unit 1 BOPCO has just completed STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, Step 37.

BOPCO has just informed you that the Ultimate Heat Sink Temperature requires 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> recordings for the given conditions.

Review the completed STP data sheet and determine if the unit is in a LCO ACTION statement for Ultimate Heat Sink and what frequency of ocean temperature monitoring is required.

Is the unit in an ACTION statement for Ultimate Heat Sink? Yes / No.

What is the frequency of ocean temperature monitoring required?

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 12 hours 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> NRCL121-A5 PAGE 5 OF 5 REV. 1

69-20232 01/27/14 Page 15 of 26 STP I-1A (UNIT 1)

ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.7.9.2 37. Determine the Ultimate Heat Sink (UHS) temperature using one of the following methods:

NOTE: Temperature indicators are only available when their associated pumps are running.

a. Method 1 - Record Pacific Ocean water temp as read on the following indicators: GLH N/A [ ] ______

TI-311 (T2400A) (CWP 1-1) _______F N/A [X]

TI-328 (T2401A) (CWP 1-2) 61.1

_______F N/A [ ]

Record the highest of the available indicators. 61.1 F Instrument Error Correction 1.9 F Add the highest available indicator reading and the Instrument Error Correction. 63.0 F

b. Method 2 - Record Pacific Ocean water temp on the following indicators: N/A [ X] ______

TI-1484 (ASWP 1-1) _______F N/A [ ]

TI-1485 (ASWP 1-2) _______F N/A [ ]

Record the highest of the available indicators. F Instrument Error Correction 0.7 F Add the highest available indicator reading and the Instrument Error Correction. °F STP_I-1Au1r27.DOC 06 0515.1508

69-20232 01/27/14 Page 16 of 26 STP I-1A (UNIT 1)

ATTACHMENT 12.1 TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.7.9.2 c. Method 3 - If Method 1 and Method 2 are not available, M&TE may be used. GLH N/A [X] ______

(Continued)

Instrument Used: ____________________

Cal Due Date: ____________________

Reading using M&TE F Uncertainty of M&TE F Add M&TE ocean temp and uncertainty F NOTE: Tech Spec Bases B3.7.9 specifies that the UHS is common to both units. Therefore any required action due to elevated ocean water temp would apply to both units depending on mode requirements. Notify the Unit 2 SFM as required.

d. IF corrected ocean temp is > [60F] AND [62F],

THEN perform the following: N/A [ X]

1) Notify SFM to review Tech Spec SR 3.7.9.2. ______

2) Record ocean temp every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ______

e. IF corrected ocean temp is > [62F] AND [64F],

THEN perform the following: N/A [ ]

1) Notify SFM to review Tech Spec SR 3.7.9.2. GLH

2) Record ocean temp every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. GLH

f. IF corrected ocean temp is > [64F],

THEN place both CCW HXs in service: GLH N/A [X] ______

STP_I-1Au1r27.DOC 06 0515.1508

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: LJACO-02S

Title:

VERIFY A DETERMINATION OF ULTIMATE HEAT SINK TEMPERATURE Examinee:

Evaluator:

Results: Sat Print Unsat on Signature Total Time:

Date minutes Comments:

Ve This JPM requires that STP I-1A, Attachment 12.1, Step 37 be filled out ahead of time. The required data is included in an attachment to this JPM. Rev 4A changes to current rev of I-1A approved by ILT supervisor

References:

12.1, Rev. 121 rs i STP I-1A, Routine Shift Checks Required by Licenses, Attachment Technical Specifications, DCPP Units 1 & 2 Alternate Path: Yes X No Time Critical:

Time Allotment:

al Yes 10 Minutes No X in Critical Steps:

Job Designation:

2, 4 SRO rig Task Number:

Rating:

G2.1.23

4.4 OAUTHOR

REVIEWED BY:

DAVID RICHARDS / CHARLES HIBBARD JOHN P. LYLE DATE:

DATE:

05/04/11 05/04/11 TRAINING SUPERVISOR APPROVED BY: KEN JOHNSTON DATE: 05/05/11 MANAGER - OPERATIONS REV. 4A

JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK JPM NUMBER: LJACO-02S TEMPERATURE INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to Required Materials:

Initial Conditions:

begin.

Checklist, Step 37 (SR 3.7.9.2) on Completed copy of STP I-1A, Attachment 12.1, MODE 1 Shift Unit 1 is at 50% power with CWP 1-2 out of service for replacement of Ve damaged screens. Unit 2 is in day 14 of a refueling outage.

Current plant conditions for the Circ Water and ASW systems are as follows:

Component CWP 1-1 CWP 1-2 rs i Status In-service Cleared ASW Pp 1-1 In-service to CCW HX 1-1 Current Ocean Water Temperature TI-311 TI-328 TI-1484 61°F 61°F 61.5°F ASW Pp 1-2 In-STBY TI-1485 60°F al CWP 2-1 CWP 2-2 Cleared Cleared ASW Pp 2-1 In-service to CCW HX 2-1 TI-311 TI-328 TI-1484 61°F 61°F 62°F in Initiating Cue:

ASW Pp 2-2 Cleared TI-1485 Required by Licenses, Attachment 12.1, Step 37.

61°F Unit 1 BOPCO has just completed STP I-1A, Routine Shift Checks rig BOPCO has determined that the Ultimate Heat Sink Temperature is satisfactory for the given conditions. Review the completed STP data sheet and determine if his assessment is correct and implement any actions needed based on your review.

O Task Standard:

DO NOT READ TASK STANDARD TO EXAMINEE STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, Step 33 reviewed for completeness and any actions implemented based on your review.

DOCCONTENT.dll PAGE 2 OF 6 REV. 4A

JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK JPM NUMBER: LJACO-02S TEMPERATURE INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtains correct procedure 1.1 Obtains completed STP I-1A, Attachment 12.1, Step 37.

on Note: Provide completed exam copy of STP I-1A, Attachment 12.1, Step 37.

Step was: Sat: _______ Unsat _______*

2.

Ve

• • Verifies UHS temperature method 1. 2.1 Reads NOTE prior to step 37.a.

rs i 2.2 2.3 Verifies that the Pacific Ocean water temperature of 61°F is entered for TI-311.**

Verifies that the TI-328 entry (CWP 1-2) is checked N/A, because the pump is not running (per Note).

2.4 Verifies that 61°F is entered as the al 2.5 highest temperature.**

Notes that the instrument error was added incorrectly.**

in Note: The value entered on the completed STP I-1A was 61.9°F. The correct value is 62.9°F.

rig Step was: Sat: _______ Unsat _______*

O

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DOCCONTENT.dll PAGE 3 OF 6 REV. 4A

JPM TITLE: VERIFY A DETERMINATION OF ULTIMATE HEAT SINK JPM NUMBER: LJACO-02S TEMPERATURE INSTRUCTOR WORKSHEET Step Expected Operator Actions

3. Verifies UHS temperature using 3.1 Verifies that N/A is checked for methods 2 & 3. Method 2.

3.2 Verifies that N/A is checked for Method 3.

4. **Verifies appropriate Tech Spec actions are taken.

4.1 on Step was: Sat: _______ Unsat _______*

Determines that step 37.d was completed incorrectly.**

Ve Note: The step on the completed STP I-1A was marked N/A. Step d should rs i have been initialed and the Unit 1 SFM informed of the actions in the step.

4.2 Notes that Unit 1 needs to record UHS temperatures every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in the Operations Shift Log.**

Note: Unit 2 SFM does not need to be informed since Unit 2 is in a al 4.3 refueling outage (not in Modes 1-4).

Verifies step 37.e is checked N/A.

in Step was: Sat: _______ Unsat _______*

rig Stop Time:

Total Time: (Enter total time on the cover page)

O

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DOCCONTENT.dll PAGE 4 OF 6 REV. 4A

EXAMINEE CUE SHEET JPM NUMBER: LJACO-02S Initial Conditions: Unit 1 is at 50% power with CWP 1-2 out of service for replacement of damaged screens. Unit 2 is in day 14 of a refueling outage.

Current plant conditions for the Circ Water and ASW systems are as follows:

Component CWP 1-1 CWP 1-2 Status In-service Cleared ASW Pp 1-1 In-service to CCW HX 1-1 on Current Ocean Water Temperature TI-311 TI-328 TI-1484 61°F 61°F 61.5°F ASW Pp 1-2 CWP 2-1 CWP 2-2 Ve In-STBY Cleared Cleared TI-1485 TI-311 TI-328 60°F 61°F 61°F Initiating Cue:

ASW Pp 2-2 rs ASW Pp 2-1 In-service to CCW HX 2-1 i

Cleared TI-1484 TI-1485 62°F 61°F Unit 1 BOPCO has just completed STP I-1A, Routine Shift Checks Required by Licenses, Attachment 12.1, Step 37.

BOPCO has determined that the Ultimate Heat Sink Temperature is satisfactory for the given conditions. Review the completed STP data al sheet and determine if his assessment is correct and implement any actions needed based on your review.

in rig O

DOCCONTENT.dll PAGE 5 OF 6 REV. 4A

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A6

Title:

DETERMINE DILUTION REQUIREMENTS TO RAISE POWER Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

DCPP Unit 2 Cycle 18 Reactivity Briefing Sheet (263 to 310 EFPD)

Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2.2, 3.3, 4.1, 5.1 Job Designation: RO or SRO Rev Comments: modified from L081 NRC ADMRO1 Gen KA / Rating: G2.1.25 - Conduct of Operations 3.9 Note: This is an admin JPM (SRO), intended for the classroom setting.

AUTHOR: LISA TORIBIO/ DATE:

OPERATIONS ABDUL KADIR/ DATE:

REPRESENTATIVE:

REV. 0

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE JPM NUMBER: NRCL121-A6 POWER EVALUATOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: Calculator, Reactivity Briefing Sheet from the Reactivity Handbook Initial Conditions Given:

• Unit 2 was ramped down due to high vibration on the main turbine.

• Unit 2 has been at 80% power for 3 days.

• Control Bank D is at 200 steps Initiating Cue: The Shift Foreman directs you to determine the dilution or boration requirements in gallons to raise power to 90% assuming final rod position of 210 steps using the data from the Reactivity Briefing Sheet (from Reactivity Handbook)

DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: Determined that 928 (+/- 5 ) gallons of primary water is required for the 10% power increase.

NRCL121-A6 PAGE 2 OF 5 REV. 0

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE JPM NUMBER: NRCL121-A6 POWER EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 Cue: Provide examinee with reactivity briefing sheet, if not already done.

Sat: ______ Unsat _______

Comment:

Calculate reactivity change for 10% 2.1 From graph power coefficient is -15.47 2.** change in power pcm/% power.

0B 2.2 Recorded (-)154.7 pcm for 10% increase in power. **

Sat: ______ Unsat _______

Comment:

Recorded 45.9 pcm for Control Bank D at Calculate reactivity change due to change 3.1 210 steps.

3.** 1B in rod position (From graph, A. Control Bank D Integral Rod Worth)

Recorded 98.1 pcm for Control Bank D at 3.2 200 steps.

(From graph, A. Control Bank D Integral Rod Worth)

Recorded (+)52.2 pcm for change in rod 3.3 position. **

(98.1 - 45.9 )

Sat: ______ Unsat _______

Comment:

NRCL121-A6 PAGE 3 OF 5 REV. 0

JPM TITLE: DETERMINE DILUTION REQUIREMENTS TO RAISE JPM NUMBER: NRCL121-A6 POWER EVALUATOR W ORKSHEET Recorded (-)102.5 pcm)reactivity from change Calculate reactivity left after accounting in rods position on total reactivity from change 4.** 4.1 in power. **

change in rod position.

2B

(-154.7 + 52.2)

Sat: ______ Unsat _______

Comment:

Note: The examinee may set up a ratio to get the primary water needed, Determines amount of primary water to or may do two steps (determine 5.**

add power change needing dilution, 3B and then dilution for that power change).

Determined 928 (+/- 5 ) gallons of primary water is required.

5.1 (102.5 pcm/15.47 pcm/% = 6.63 % pwr)

(6.63% x 140 gal/% =

928 gallons (+/- 5 gallons) **

Note: The critical part of the above step is the dilution gallons, as the data can be manipulated several different ways in one or more steps to arrive at the right answer.

Sat: ______ Unsat _______

Comment:

Stop Time:

Total Time: (Enter total time on the cover page)

Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ___________________________________________________________________

NRCL121-A6 PAGE 4 OF 5 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A6 Initial Conditions: Given:

• Unit 2 was ramped down due to high vibration on the main turbine.

• Unit 2 has been at 80% power for 3 days.

• Control Bank D is at 200 steps Initiating Cue: The Shift Foreman directs you to determine the dilution or boration requirements in gallons to raise power to 90% assuming final rod position of 210 steps using the data from the Reactivity Briefing Sheet (from Reactivity Handbook)

Answer (show work):

NRCL121-A6 PAGE 5 OF 5 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A7

Title:

VERIFY OUTAGE SAFETY CHECKLIST Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

AD8.DC55, Outage Safety Scheduling, Att 4, page 6, Rev. 38 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 3 Job Designation: SRO Rev Comments: Modified from LJAEC-01S G2.2.37 - Ability to determine operability and/or availability of Gen KA / Rating: 4.6 safety related equipment Note: This is an admin JPM (SRO), intended for the classroom setting.

AUTHOR: LISA TORIBIO DATE:

OPERATIONS ABDUL KADIR DATE:

REPRESENTATIVE:

REV. 0

JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A7 EVALUATOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: Calculator, Reactivity Briefing Sheet from the Reactivity Handbook Initial Conditions Unit 1 is currently in MODE 6 with a Core Load planned to start on the next shift (upper internals are installed).

Current plant parameters are as follows:

Operable Cleared Offsite power sources Startup power X Aux power X Onsite power sources Diesel Generator 1 X Diesel Generator 2 X Diesel Generator 3 X Vital bus crosstie 4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Onsite distribution sys. 4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Instrument AC Panels PY-11 X PY-11A X PY-12 X PY-13 X PY-13A X PY-14 X Vital DC Power DC Bus 1-1 X DC Bus 1-2 X DC Bus 1-3 X Refueling cavity level 135 Feet NRCL121-A7 PAGE 2 OF 8 REV. 0

JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A7 EVALUATOR W ORKSHEET Initiating Cue: The Unit 1 Control Operator has just completed AD8.DC55, Outage Safety Scheduling, Att 4, page 6, Unit 1 Outage Safety Checklist -

Mode 6 RCS Level Greater Than or Equal to 111', for the current plant conditions.

The Control Operator has determined that the checklist is satisfactory.

Perform a review of the completed checklist and determine if it is acceptable. If not, document any discrepancies found DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: Review completed of the completed portion of AD8.DC55, Outage Safety Scheduling, Att 4, page 6, Unit 1 Outage Safety Checklist -

Mode 6 RCS Level Greater Than or Equal to 111'.

• Determined the checklist is NOT acceptable.

• Identified and documented that the status of refueling cavity is incorrect.

• Identified and documented that D/G 1-2 has been incorrectly credited as both the operable and available diesel when a different D/G is required to be available or operable.

NRCL121-A7 PAGE 3 OF 8 REV. 0

JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A7 EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions Obtained completed copy of AD8.DC55, Att 4,

1. Obtain the correct procedure. 1.1 page 6, Unit 1 Outage Safety Checklist - Mode 6 RCS Level Greater Than or Equal to 111'.

Sat: ______ Unsat _______

Comment:

Determined status is satisfactory (requires aux or startup power AND cross-tie capability or operable diesels to operable vital buses)

• Aux Power is operable and the

2. Status of On-site power 2.1 appropriate "box" on Att 4, page 6 marked.

• Cross tie capability is available for the Operable Vital Buses F and G and the appropriate "boxes" on Att 4, page 6 marked.

Sat: ______ Unsat _______

Comment:

NRCL121-A7 PAGE 4 OF 8 REV. 0

JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A7 EVALUATOR W ORKSHEET Determined status incorrectly marked as satisfactory (requires 1condition met) -

• 2 diesels (not met - only D/G 1-2 correctly marked)

OR

• either cavity level w/ internals removed (not met - both marked incorrectly, cavity level is less than 23 above the flange)**

3.** Status of On-site Power supply 3.1

• or both Aux and Startup power and (not met - correctly marked only Aux available)

AND

• One diesel operable (met - D/G 1-2 correctly marked)

AND

• Different diesel (from 1-2) operable**

(not met - D/G 1-2 incorrectly marked. No other D/G available or operable)

Sat: ______ Unsat _______

Comment:

4 kV buses F and G, as well as 480V buses F

4. Status of 480 VAC 4.1 and G, are operable and the appropriate "boxes" on Att 4, page 6 are marked.

Sat: ______ Unsat _______

Comment:

NRCL121-A7 PAGE 5 OF 8 REV. 0

JPM TITLE: VERIFY OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCL121-A7 EVALUATOR W ORKSHEET Note: The boxes at the bottom of the right hand column of Att 4, page 6

5. Status of Instrument AC Power Panels are a continuation of the boxes at the bottom of the left hand column.

Note: Tech Spec 3.8.2 states only one vital buses required to be operable in Mode 6.

Determined that all vital instrument AC 5.1 power panels are operable and marks appropriate "boxes" on Att 4, page 6.

Comment:

Determined that all vital DC buses are

6. Status of Vital DC Power 6.1 operable and marks appropriate "boxes" on Att 4, page 6.

Comment:

Stop Time:

Total Time: (Enter total time on the cover page)

Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL121-A7 PAGE 6 OF 8 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A7 Initial Conditions: Unit 1 is currently in MODE 6 with a Core Load planned to start on the next shift (upper internals are installed).

Current plant parameters are as follows:

Operable Cleared Offsite power sources Startup power X Aux power X Onsite power sources Diesel Generator 1 X Diesel Generator 2 X Diesel Generator 3 X Vital bus crosstie 4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Onsite distribution sys. 4kV & 480v Bus F X 4kV & 480v Bus G X 4kV & 480v Bus H X Instrument AC Panels PY-11 X PY-11A X PY-12 X PY-13 X PY-13A X PY-14 X Vital DC Power DC Bus 1-1 X DC Bus 1-2 X DC Bus 1-3 X Refueling cavity level 135 Feet Initiating Cue: The Unit 1 Control Operator has just completed AD8.DC55, Outage Safety Scheduling, Att 4, page 6, Unit 1 Outage Safety Checklist -

Mode 6 RCS Level Greater Than or Equal to 111', for the current plant conditions.

The Control Operator has determined that the checklist is satisfactory.

Perform a review of the completed checklist and determine if it is acceptable. If not, document any discrepancies found NRCL121-A7 PAGE 7 OF 8 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A7 Document Answer Here VITAL AC Power is:

Acceptable / Not Acceptable*

• Not acceptable due to:

NRCL121-A7 PAGE 8 OF 8 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A8

Title:

REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, Rev.

37A CAP A-5, Liquid Radwaste Discharge Management, Rev. 48 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 1.2, 1.3 Job Designation: SRO Rev Comments: modified from L061C NRC ADM04 Gen KA / Rating: G2.3.11 - Ability to control radiation releases. 4.3 Note: This is an admin JPM (SRO), intended for the classroom setting.

AUTHOR: LISA TORIBIO/ DATE: 06/20/2014 OPERATIONS ABDUL KADIR/ DATE: 06/20/2014 REPRESENTATIVE:

REV. 1

JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCL121-A8 EVALUATOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, Rev.37A, completed Section 12 Initial Conditions GIVEN:

• Unit 1 is in MODE 5

• Unit 2 is at 45%

• CCW HX 2-1 is in service

• CWP 2-1 is in service

• CWP 2-2 is secured

• No Unit 1 CWPs are running

• RR-102, Radiation Monitoring System Recorder is currently out of service for calibration Chemistry has issued a discharge permit for PWR 0-2 using CAP A-5 Att. 11.1 parts 1 & 2. OP G-1:II Section 12 has been completed and ready for signature.

Initiating Cue: Review OP G-1:II Section 12 Discharge Checklists for accuracy and completeness.

Make a recommendation to the Shift Foreman to approve or not approve the discharge permit. Justify your answer DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: Recommends not approving the discharge permit due to inadequate dilution flow.

NRCL121-A8 PAGE 2 OF 5 REV. 1

JPM TITLE: REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCL121-A8 EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions Review section 12 (steps 12.1 through 1.1 Steps 12.1 through 12.12 reviewed as 1.** 12.18) completed correctly.

0B Identified errors in step 12.13 for determination of recorder RR-102 operability (initial conditions identify RR-102 out-of-service) 1.2

• Step 12.13.2, last bullet (checks RE-18 being recorded on RR-102)

• Step 12.13.3 (requires comp measures for RR-102 being inoperable) **

1.3 Step 12.14 reviewed as completed correctly.

Determined that actual current dilution flow 1.4 was incorrectly calculated by the operator (actual flowrate is 0.455 x 106 gpm (0.433

+ 0.011 + 0.011 x 106 gpm)) **

NOTE: assumed flow may be determined by noting which pumps were credited (checkmarks next to pumps at step 12.15) and/or the use of N/A of 12.16 (contact chemistry if flowrate is inadequate)

Recommends not approving the discharge 1.5 permit because the actual flowrate is less than the required flowrate (8.77 x 105 gpm)

Sat: ______ Unsat _______

Comment:

Stop Time:

Total Time: (Enter total time on the cover page)

KEY:

The Shift Foreman SHOULD / SHOULD NOT approve the discharge permit because:

• Comp measures have not been implemented for inoperable R-102, Radiation Monitoring

• System Recorder actual flowrate is less than required flowrate. (actual of 0.455 x 106 gpm vs.

required 8.77 x 105 gpm)

NRCL121-A8 PAGE 3 OF 5 REV. 1

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A8 Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL121-A8 PAGE 4 OF 5 REV. 1

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A8 Initial Conditions: GIVEN:

• Unit 1 is in MODE 5

• Unit 2 is at 45%

• CCW HX 2-1 is in service

• CWP 2-1 is in service

• CWP 2-2 is secured

• No Unit 1 CWPs are running

• RR-102, Radiation Monitoring System Recorder is currently out of service for calibration Chemistry has issued a discharge permit for PWR 0-2 using CAP A-5 Att. 11.1 parts 1 & 2. OP G-1:II Section 12 has been completed and ready for signature.

Initiating Cue: Review OP G-1:II Section 12 Discharge Checklists for accuracy and completeness.

Make a recommendation to the Shift Foreman to approve or not approve the discharge permit. Justify your answer The Shift Foreman SHOULD / SHOULD NOT approve the discharge permit because:

NRCL121-A8 PAGE 5 OF 5 REV. 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-A9

Title:

CLASSIFICATION OF A FUEL HANDLING ACCIDENT IN CONTAINMENT Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

EP G-1, Accident Classification and Emer Plan Activation, Rev.43 Forms 69-21608, 69-21609, 69-21610 (06/19/12, 07/24/13, 12/5/11)

Alternate Path: Yes No X Time Critical: Yes X No Time Allotment: 15 minutes Critical Steps: 2, 3 Job Designation: SRO Rev Comments: Bank LJE-017 Gen KA / Rating: G2.4.38 - Ability to take actions called for in the facility 4.4 emergency plan, including supporting or acting as emergency coordinator if required.

Note: This is an admin JPM (SRO), intended for the classroom setting.

AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS ABDUL KADIR DATE: 06/20/2014 REPRESENTATIVE:

REV. 0

JPM TITLE: CLASSIFICATION OF A FUEL HANDLING ACCIDENT JPM NUMBER: NRCL121-A9 IN CONTAINMENT EVALUATOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials:

• EP G-1, and EAL Wall Charts.

• Vol 11, Emergency Plan, App D (classification bases), should be available to the examinee.

Initial Conditions GIVEN:

• Unit 1 is REFUELING

• Core off-loading is in progress

• Containment closure has been established

• The fuel handling crew in containment has just reported seeing bubbles in the transfer canal area from an assembly that has just been placed into the upender. Visual inspection showed the appearance of some structural damage to the assembly

• Radiation Monitor RE-2 has also just alarmed, and reads 25 mR/hour at this time

• There are no other Radiation Monitors in alarm Initiating Cue: The Shift Manager directs you to classify the event DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: In less than 15 minutes, classifies the event as Alert, RA2.1

• Damage to irradiated fuel resulting in a valid high alarm on RM-2

(>21 mr/hr)

NRCL121-A9 PAGE 2 OF 4 REV. 0

JPM TITLE: CLASSIFICATION OF A FUEL HANDLING ACCIDENT JPM NUMBER: NRCL121-A9 IN CONTAINMENT EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions 1.1 References EP G all pages of wall

1. Obtain the correct procedure.

chart provided Sat: ______ Unsat _______

Comment:

2.1 Classified the event as Alert,

2. ** Accurately classify the event.

RA2.1 **

0B Sat: ______ Unsat _______

Comment:

Classified the event < 15 min. of the Event Initiation Time. **

Classification Time: _____________

3.**

1B Classification time less than 15 minutes 3.1 Event Initiation Time: _____________

(Event initiation time is JPM Start Time)

Difference: ____________ min**

3.2 Sat: ______ Unsat _______

Comment:

Stop Time:

Total Time: (Enter total time on the cover page)

Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL121-A9 PAGE 3 OF 4 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-A9 Initial Conditions: GIVEN:

• Unit 1 is REFUELING

• Core off-loading is in progress

• Containment closure has been established

• The fuel handling crew in containment has just reported seeing bubbles in the transfer canal area from an assembly that has just been placed into the upender. Visual inspection showed the appearance of some structural damage to the assembly

• Radiation Monitor RE-2 has also just alarmed, and reads 25 mR/hour at this time

• There are no other Radiation Monitors in alarm Initiating Cue: The Shift Manager directs you to classify the event NRCL121-A9 PAGE 4 OF 4 REV. 0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Diablo Canyon Date of Examination: 08/11/2014 Exam Level: RO SRO-I SRO-U Operating Test Number: L121 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. (S1) (001.A2.03) Verify Misaligned Rod Is Not Stuck (LJC-066) D,S 1

b. (S2) (013.A4.01) Manually Isolate Phase A Components (LJC-026) A,D,EN,L,S 2

c. (S3) (055.EA1.07) Energize Vital Busses From 230 KV System A,L,N,S 6

d. (S4) (022.A4.01) Respond to High CFCU Vibration A,N,S 5

e. (S5) (073.A4.01) Respond to High Radiation on RE-17A/B N,S 7

f. (S6) (002.A4.02) Initiate a Nat Cir Cooldown (LJC-046) M,L,S 4P

g. (S7) (059.A2.07) Perform Immediate Actions for MFW Pump Trip A,M,S 4S (NRCLJC051051)

h. (S8) (006.A4.05) Align RHR for Hot Leg Recirc (NRCL081LJC-S3) A,L,D,S 3 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) (067.AA1.08) Manually Operate the Cardox System (LJP-138A) A,D,E 8

j. (P2) (068.AA1.21) Align 480V Bus G for Control from HSDP (LJP-007) D,E,L 6

k. (P3) (061.A2.04) Align Alternate AFW from the FWST (LJP-104A) D,E,L,R 4S

@ 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 ES-301, Page 23 of 27 Rev 2 Rev 2: Revs follow initial submittal

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Diablo Canyon Date of Examination: 08/11/2014 Exam Level: RO SRO-I SRO-U Operating Test Number: L121 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. (S1) (001.A2.03) Verify Misaligned Rod Is Not Stuck (LJC-006) D,S 1

b. (S2) (013.A4.01) Manually Isolate Phase A Components (LJC-026) A,D,EN,L,S 2

c. (S3) (055.EA1.07) Energize Vital Busses From 230 KV System A,L,N,S 6

d. (S4) (022.A4.01) Respond to High CFCU Vibration A,N,S 5

e. (S5) (073.A4.01) Respond to High Radiation on RE-17A/B N,S 7 f.

g. (S7) (059.A2.07) Perform Immediate Actions for MFW Pump Trip A,M,S 4S (NRCLJC051051)

h. (S8) (006.A4.05) Align RHR for Hot Leg Recirc (NRCL081LJC-S3) A,L,D,S 3 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) (067.AA1.08) Manually Operate the Cardox System (LJP-138A) A,D,E 8

j. (P2) (068.AA1.21) Align 480V Bus G for Control from HSDP (LJP-007) D,E,L 6

k. (P3) (061.A2.04) Align Alternate AFW from the FWST (LJP-104A) D,E,L,R 4S

@ 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 ES-301, Page 23 of 27 Rev 1 Rev 1: Revs follow initial submittal

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Diablo Canyon Date of Examination: 08/11/2014 Exam Level: RO SRO-I SRO-U Operating Test Number: L121 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function a.

b. (S2) (013.A4.01) Manually Isolate Phase A Components (LJC-026) A,D,EN,L,S 2

c. (S3) (055.EA1.07) Energize Vital Busses From 230 KV System A,L,N,S 6 d.

e. (S5) (073.A4.01) Respond to High Radiation on RE-17A/B N,S 7 f.

g.

h.

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

i. (P1) (067.AA1.08) Manually Operate the Cardox System (LJP-138A) A,D,E 8 j.

k. (P3) (061.A2.04) Align Alternate AFW from the FWST (LJP-104A) D,E,L,R 4S

@ 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 ES-301, Page 23 of 27 Rev 1 Rev 1: Rev follows initial submittal

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-P1

Title:

MANUALLY OPERATE THE CARDOX SYSTEM Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: This is a UNIT 2 JPM

References:

U1 & 2 OP K-2B:II, Manual Use of the Cardox System, Rev. 10 Alternate Path: Yes __X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 2.4, 3.2, 3.3 Job Designation: RO or SRO Rev Comments: Bank LJP-138A Gen KA / Rating: 067.AA1.08 - Ability to operate and / or monitor the following 3.4/3.7 as they apply to the Plant Fire on Site: Fire fighting equipment used on each class of fire AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS ABDUL KADIR DATE: 06/20/2014 REPRESENTATIVE:

REV. 0

JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: U1&2 OP K-2B:II, Section 6.3.

Initial Conditions Given:

• A fire has been detected in the Unit 2 Cable Spreading Room.

• DC power has been lost to the cardox control circuitry.

• There are NO personnel in either Cable Spreading Room Initiating Cue: The Shift Foreman directs you to locally actuate cardox discharge to the Unit 2 Cable Spreading Room, per OP K-2B:II, step 6.3 DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: Cardox initiated to the U2 Cable Spreading Room for the proper duration, in accordance with OP K-2B:II.

NRCL121-P1 PAGE 2 OF 7 REV. 0

JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions Step 6.3.1 - Attempt LOCAL discharge to 1.1 Read NOTE prior to step 6.3.1.

1. U-2 Cable Spreading Room (CSR) 1.2 For 2-FCV-102, pulled cover and depressed button.

Note: Knowledge of the systems and IC may lead examinee to move to step 6.3.2. In that case, step 1 is N/A.

Cue: NO audible flow noise heard in the CO2 piping.

1.3 Determined that CO2 discharge did not occur, and moved on to next step.

Sat: ______ Unsat _______

Comment:

NRCL121-P1 PAGE 3 OF 7 REV. 0

JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR W ORKSHEET Step 6.3.2 - Manually actuate CARDOX 2.1 Read CAUTION prior to step 6.3.2.a.

2. ** at local station 0B0B Step 6.3.2.a - Personnel clear of CSR 2.2 Ensured personnel are clear of the Unit 2 Cable Spreading Room.

Cue: There are no personnel in the Cable Spreading Room.

Note: The valve handle is in line/parallel to the pipe when the valve is open.

2.3 Ensured abort valve for Unit 2 Cable Step 6.3.2.b - Ensure 2-HCV-2074 open Spreading Room was open (2-HCV-2074).

Cue: The valve operator for 2-HCV-2074 is in line/parallel with the piping.

Step 6.3.2.c - Open 2-FCV-102 pilot 2.4 Broke glass and opened pilot for valve 2-FCV-102. **

Cue: NO audible flow noise is heard in the CO2 piping.

Sat: ______ Unsat _______

Comment:

NRCL121-P1 PAGE 4 OF 7 REV. 0

JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR W ORKSHEET 6.3.2.d - At the storage tank, manually 3.1

3. ** Read note prior to step 6.3.2.d open the Selector Pilot Control Valve 1B1B 3.2 Broke glass and opened the Pilot Valve for Master Valve 0-FCV-104. **

Cue: Audible flow noise is heard in the CO2 piping.

Note: Give following Cue only after examinee verbalizes that valve will be kept open for 2 minutes and 40 seconds.

Cue: Two minutes and 40 seconds have elapsed.

Step 6.3.2.e - Close 2-FCV-102 pilot 3.3 Closed the Pilot Valve for 2-FCV-102. **

valve Note: This is the valve opened in step 6.3.2.c. The valve is closed to ensure any subsequent actuation does not result in Cardox going to the CSR again.

Cue: There is no more audible flow noise in the CO2 piping.

Sat: ______ Unsat _______

Comment:

NRCL121-P1 PAGE 5 OF 7 REV. 0

JPM TITLE: MANUALLY OPERATE THE CARDOX SYSTEM JPM NUMBER: NRCL121-P1 EVALUATOR W ORKSHEET Stop Time:

Total Time: (Enter total time on the cover page)

Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL121-P1 PAGE 6 OF 7 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-P1 Initial Conditions: Given:

• A fire has been detected in the Unit 2 Cable Spreading Room.

• DC power has been lost to the cardox control circuitry.

• There are NO personnel in either Cable Spreading Room Initiating Cue: The Shift Foreman directs you to locally actuate cardox discharge to the Unit 2 Cable Spreading Room, per OP K-2B:II, step 6.3 NRCL121-P1 PAGE 7 OF 7 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-P2

Title:

ALIGN 480V BUS G FOR CONTROL FROM THE HOT SHUTDOWN PANEL Examinee:

Evaluator:

Print Signature Date Testing Method: Perform Simulate X Results: Sat Unsat Total Time: minutes Comments:

References:

OP AP-8A, Control Room Inaccessibility - Establishing Hot Stby, Rev.

36 Alternate Path: Yes _______ No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 1.2, 1.3, 2.1 Job Designation: RO or SRO Rev Comments: Bank LJP-007 Gen KA / Rating: 068.AA1.21 - Ability to operate and / or monitor the following as 3.9/4.1 they apply to the Control Room Evacuation: Transfer of controls from control room to shutdown panel or local control AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS ABDUL KADIR DATE: 06/20/2014 REPRESENTATIVE:

REV. 0

JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT JPM NUMBER: NRCL121-P2 SHUTDOWN PANEL EVALUATOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: Provide a copy of the reference procedure (partial procedure allowed), if the task is being done in the plant or lab; U1 OP AP-8A, App F Initial Conditions GIVEN:

• A fire in the control boards has caused a Unit 1 Control Room evacuation.

• OP AP-8A is being performed and the operating crew is ready to align bus 1G 480 VAC loads for control from the Hot Shutdown Panel Initiating Cue: The Shift Foreman directs you to align bus 1G 480 vac loads for control at the Hot Shutdown Panel, per OP AP-8A, App F, step 2 DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: Breakers and switches aligned for 480 vac bus 1G per App F, step 2 of OP AP-8A.

NRCL121-P2 PAGE 2 OF 5 REV. 0

JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT JPM NUMBER: NRCL121-P2 SHUTDOWN PANEL EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions Step 2.a. - Place the control transfer Located 480V vital bus 1G aux relay panel 1.** cutout switches for 480V vital bus 1G to 1.1 in the vital switchgear room.

the CUT-IN position.

Note: CUT IN / CUT OUT switches are located inside the aux relay panel.

The aux relay panel may be opened.

Placed the following switches to the CUT-1.2 IN position:

• FCV-95, switch 43X-1230.**

Cue: (may be given after each switch operation)

The switch is in the CUTIN (up) position.

• CFCU 15, switch 43X-1G-02.**

• Emergency Borate valve 8104, switch 1.3 43X-1G-57.**

• BATP 1-2, switch 43X-1G-04.**

• LCV-106, switch 43X-1G-44.**

• LCV-107, switch 43X-1G-68.**

Sat: ______ Unsat _______

Comment:

NRCL121-P2 PAGE 3 OF 5 REV. 0

JPM TITLE: ALIGN 480V BUS G FOR CONTROL FROM THE HOT JPM NUMBER: NRCL121-P2 SHUTDOWN PANEL EVALUATOR W ORKSHEET Step 2.b - Open 480V vital bus 1G 2.1 Opened the following breakers:

2. breakers to prevent spurious operation.

Cue: (may be given after each breaker operation)

The breaker is in the OFF position.

• FCV-356 bkr 52-1G-36. **

• 9003A, bkr 52-1G-48. **

• 8982A, bkr 52-1G-58. **

• LCV-112C, bkr 52-1G-11.**

• 8805B, bkr 52-1G-14. **

• FCV-363, bkr 52-1G-23. **

• 8100, bkr 52-1G-26. **

• FCV-431, bkr 52-1G-28 **

Comment:

3.1 Informed the HSDP Operator that the 480V Bus

3. Report alignment complete 1G Alignment is complete.

Sat: ______ Unsat _______

Comment:

Stop Time:

Total Time: (Enter total time on the cover page)

Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL121-P2 PAGE 4 OF 5 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-P2 Initial Conditions: GIVEN:

• A fire in the control boards has caused a Unit 1 Control Room evacuation.

• OP AP-8A is being performed and the operating crew is ready to align bus 1G 480 VAC loads for control from the Hot Shutdown Panel Initiating Cue: The Shift Foreman directs you to align bus 1G 480 vac loads for control at the Hot Shutdown Panel, per OP AP-8A, App F, step 2 NRCL121-P2 PAGE 5 OF 5 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-P3

Title:

ALIGN ALTERNATE AFW FROM THE FIRE WATER STORAGE TANK Examinee:

Evaluator:

Print Signature Date Testing Method: Perform Simulate X Results: Sat Unsat Total Time: minutes Comments: This is a UNIT 2 JPM

References:

Unit 2 OP D-1:V, Aux Feedwater System - Alternate AFW Supplies, Rev. 18 OP1.ID2, TCOAs, Rev 5 (& TCOA database); TCOA item 35 Alternate Path: Yes _______ No X Time Critical: Yes X No Time Allotment: 20 minutes Critical Steps: 4.4, 6.3, 6.5, 7.2, 8.1, 8.2 Job Designation: RO or SRO Rev Comments: Bank LJP-104A Gen KA / Rating: 061 A2.04 - Ability to (a) predict the impacts of the following 3.4/3.8 malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: pump failure or improper operation AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS ABDUL KADIR DATE: 06/20/2014 REPRESENTATIVE:

REV. 0

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: NRCL121-P3 STORAGE TANK EVALUATOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Note: This JPM is started within the RCA at Aux Board Required Materials: Copy of the reference procedure (partial procedure allowed):

• Unit 2 OP D-1:V, Section 6.1 and Attachment 1.

• PG&E 909 key.

Initial Conditions Following a reactor trip from 100% power, the Unit 2 CST level has just lowered to less than 10%

Initiating Cue: The Shift Foreman gives you a PG&E 909 key and directs you to transfer U-2 AFW pump suction supply to Fire Water Storage Tank in accordance with OP D-1:V, Section 6.1 DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: U-2 AFW pump suction aligned to the Fire Water Storage Tank, in accordance with OP D-1:V.

Time Critical This JPM was evaluated against TCOA # 35 (Realign the AFW pumps Operator Action to a new suction source within 20 minutes).

(TCOA): This TCOA:

• is applicable to this JPM, so the steps in this task related to the TCOA will be critical. This task is also time critical with a start time of the beginning of the task, and ending when the alignment is completed (venting not required). The time limit is 19 minutes (20 minutes minus one minute to read the procedure step and give the direction to the field operator).

NRCL121-P3 PAGE 2 OF 8 REV. 1

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: NRCL121-P3 STORAGE TANK EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions Step 6.1.1 - Check OPEN FP 0 4 1.1 Read NOTEs 1 and 2 prior to step

1. (115' Elev., in FWST vault).

1.2 Located FP-0-4.

1.3 Checked the position of FP-0-4 (large, rising stem valve).

Cue: Valve stem extends 12-14" from valve handwheel (open).

1.4 Determined FP-0-4 is open Sat: ______ Unsat _______

Comment:

Step 6.1.2 - Check AFW suction being 2.1 Read Step 6.1.2 and determined that step does

2. realigned from the CST not need to be performed.

Sat: ______ Unsat _______

Comment:

Step 6.1.3 - Check MU-0-1557 closed 3.1 Located MU-0-1557.

3. (100' Elev., chain operated, in hallway 3.1 near RWST vault) 3.2 3.2 Checked MU-0-1557 closed.

Cue: (if tugs on chainfall in CW direction) Valve will not move 3.3 (closed). (if examinee climbs up ladder; flashlight needed) Pointer is on "C" (closed).

3.4 Determined MU-0-1557 is closed.

Sat: ______ Unsat _______

Comment:

NRCL121-P3 PAGE 3 OF 8 REV. 1

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: NRCL121-P3 STORAGE TANK EVALUATOR W ORKSHEET Step 6.1.4 - First Bullet - Verify MU 0 Note: Steps 4 and 5 may be performed 284 closed (100' Elev., north end of in any order (steps are bullets in hallway).

OP D-1:V). Both valves are rising stem handwheel operated Note: MU-0-284 and 286 are the valves ( 10" rise when open);

4. downstream isolations for the in-line 4.1 MU-0-284 is normally OPEN.

strainers. One will be in service, and the other OOS. This JPM is written for current plant conditions, but if the "lower" strainer is in service [MU 286], then make step 4 non-critical, and step 5 critical [ie, both strainers OOS].

4.2 Located MU-0-284 4.3 Checked MU-0-284 position.

Cue: Valve stem is 10" out from valve handwheel.

4.4 Closed MU-0-284. **

Cue: Valve stem is now only about an inch from the handwheel, and the handwheel won't move in CW direction (closed).

Sat: ______ Unsat _______

Comment:

Step 6.1.4 - Second Bullet - Verify 5.1 Located MU-0-286

5. closed MU-0-286 (100' Elev., north end of hallway).

5.2 Checked MU-0-286 position.

Cue: Valve stem is 1" out from valve handwheel, and won't move in CW direction.

5.3 Determined MU-0-286 is closed Sat: ______ Unsat _______

Comment:

NRCL121-P3 PAGE 4 OF 8 REV. 1

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: NRCL121-P3 STORAGE TANK EVALUATOR W ORKSHEET Step 6.1.5 - Open FP-0-306 and FP 6.1 Read Step 6.1.5 and determined that step 6.

307 (chain operated, normally locked needs to be performed.

closed 100' Elev., above MU Water pps, near north wall).

Note: FP-0-306 and -307 are normally chained and locked closed. These valves may be operated in any order (steps are bullets ).

Cue: The SFM has assigned another operator to complete the sealed component change forms.

6.2 Located FP-0-306.

6.3 Unlocked and opened FP-0-306. **

Cue: (if chainfall operated to turn valve operator CCW to open) The valve moved several turns CCW and stopped (open seat).

6.4 Located FP-0-307.

6.5 Unlocked and opened FP-0-307. **

Cue: (if chainfall operated to turn valve operator CCW to open) The valve moved several turns CCW and stopped (open seat).

Sat: ______ Unsat _______

Comment:

NRCL121-P3 PAGE 5 OF 8 REV. 1

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: NRCL121-P3 STORAGE TANK EVALUATOR W ORKSHEET Step 6.1.6 - Open FCV 436 and 437 Note: These valves in the next several

7. (100' Elev., AFW Pp 2-1 room) steps may be operated in any order (steps are bullets).

7.1 Located FCV-436 and FCV-437.

7.2 Opened FCV- 436 and FCV-437**.

Cue: (for each valve) Pointer is at "O" (open).

Sat: ______ Unsat _______

Comment:

Step 6.1.7 - Close AFW pump 8.1 Located and Closed FW-2-121**

8.

suctions from CST Cue: (for FW-2-121, HW operated valve)

Pointer is at "CLOSED".

8.2 Located and Closed FW-2-159 & 180**

Cue: (for FW-2-159 and FW-2-180, handle operated butterfly valves)

Handle is down to the "perpendicular to pipe" position.

Note the time the examinee closed the final normal suction valve (TCOA stop time):

Sat: ______ Unsat _______

Comment:

NRCL121-P3 PAGE 6 OF 8 REV. 1

JPM TITLE: ALIGN ALTERNATE AFW FROM THE FIRE WATER JPM NUMBER: NRCL121-P3 STORAGE TANK EVALUATOR W ORKSHEET Step 6.1.8 - If necessary, vent AFW **********************************

pump casings Cue: Suction to the AFW pumps was

9. NOT lost.

9.1 Determined venting is not required.

Sat: ______ Unsat _______

Comment:

Step 6.1.9 - Notify Control Room 10.1 Notified the Control Room AFW pumps 10.

now available from the FWST Sat: ______ Unsat _______

Comment:

Stop Time:

Total Time: (Enter total time on the cover page)

Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL121-P3 PAGE 7 OF 8 REV. 1

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-P3 Initial Conditions: Following a reactor trip from 100% power, the Unit 2 CST level has just lowered to less than 10%

Initiating Cue: The Shift Foreman gives you a PG&E 909 key and directs you to transfer U-2 AFW pump suction supply to Fire Water Storage Tank in accordance with OP D-1:V, Section 6.1 NRCL121-P3 PAGE 8 OF 8 REV. 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-S1

Title:

VERIFY MISALIGNED ROD IS NOT STUCK Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

OP AP-12B, Control Rod Misalignment, Rev. 14B Alternate Path: Yes _______ No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 4.1, 5.1, 7.1, 8.1 Job Designation: RO or SRO Rev Comments: Bank LJC-066 Gen KA / Rating: 001 A2.03 - Ability to (a) predict the impacts of the following 3.5/4.2 malfunction or operations on the CRDS- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect of stuck rod or Misaligned rod AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS ABDUL KADIR DATE: 06/20/2014 REPRESENTATIVE:

REV. 1

JPM TITLE: VERIFY MISALIGNED ROD IS NOT STUCK JPM NUMBER: NRCL121-S1 EVALUATOR W ORKSHEET Directions: All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: None Initial Conditions GIVEN:

• Unit 1 is at approximately 75% power and was in the process of being returned to 100% following curtailment for condenser cleaning.

• The power increase was stopped 5 minutes ago when control rod K2 was observed to be 12 steps below the other Control Bank D rods based on DRPI.

• Procedure OP AP-12B, Control Rod Misalignment has been implemented Initiating Cue: The Shift Foreman directs you to verify that the misaligned rod is not stuck in accordance with OP AP-12B, Step 14 DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: All actions of OP AP-12B, step 14, completed, the status of control rod K2 verified (not stuck), the bank restored to its original position.

NRCL121-S1 PAGE 2 OF 7 REV. 1

JPM TITLE: VERIFY MISALIGNED ROD IS NOT STUCK JPM NUMBER: NRCL121-S1 EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 Obtained copy of OP AP-12B Sat: ______ Unsat _______

Comment:

2. Step 14.a - Verify Misaligned Rod 2.1 Read three CAUTIONS prior to step 14.a NOT STUCK - check group1 and group2 control bank counters at same step 2.2 Checked both groups of bank D at the same step as the demand counter Sat: ______ Unsat _______

Comment:

3. Step 14.b - Record bank step 3.1 Recorded ALL bank demand positions counters (all banks)

Sat: ______ Unsat _______

Comment:

4.** Step 14.c - Rotate Rod Bank Selector 4.1 Rotated Rod Bank Selector switch to Switch to AFFECTED Bank Control Bank D (CBD) **

Sat: ______ Unsat _______

Comment:

NRCL121-S1 PAGE 3 OF 7 REV. 1

JPM TITLE: VERIFY MISALIGNED ROD IS NOT STUCK JPM NUMBER: NRCL121-S1 EVALUATOR W ORKSHEET Step Expected Operator Actions

5. Step 14.d - Record PPC position for Note: Operator may call up the CBD the Bank address listed in App. B of AP-12B (U0052), or record the value from an existing PPC group display (CDB is at 193 steps) 5.1 Displayed the Control Bank D position from the plant computer and records the value.

Sat: ______ Unsat _______

Comment:

6.** Step 14.e - Drive the affected bank in 6.1 Inserted rods for Control Bank D until a several steps (enough to see a DRPI DRPI change is observed **

change)

Sat: ______ Unsat _______

Comment:

7.** Step 14.f - Check misaligned rod DRPI 7.1 Checked that rod K2 moves and diagnosed position changes with bank position. that rod K2 is not stuck. **

Sat: ______ Unsat _______

Comment:

8.** Step 14. G - g. Return the rods in the 8.1 Withdrew Control Bank D until the bank affected bank to the step counter was restored to its previously recorded position recorded in Step 14.b position **

Sat: ______ Unsat _______

Comment:

Stop Time:

Total Time: (Enter total time on the cover page)

NRCL121-S1 PAGE 4 OF 7 REV. 1

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-S1 Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL121-S1 PAGE 5 OF 7 REV. 1

JPM

Title:

VERIFY MISALIGNED ROD IS NOT STUCK JPM Number: NRCL121-S1 Attachment 1, Simulator Setup Restore the simulator to IC-11 (75%, MOL).

Verify step counters and RBU are updated to current CBD rod position.

Run Lesson NRCL121-LJCS1.lsn Place Rod Control Switch to Manual after simulator goes to freeze.

Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet.

NRCL121-S1 PAGE 6 OF 7 REV. 1

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-S1 Initial Conditions: GIVEN:

• Unit 1 is at approximately 75% power and was in the process of being returned to 100% following curtailment for condenser cleaning.

• The power increase was stopped 5 minutes ago when control rod K2 was observed to be 12 steps below the other Control Bank D rods based on DRPI.

• Procedure OP AP-12B, Control Rod Misalignment has been implemented Initiating Cue: The Shift Foreman directs you to verify that the misaligned rod is not stuck in accordance with OP AP-12B, Step 14 NRCL121-S1 PAGE 7 OF 7 REV. 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-S2

Title:

MANUALLY ISOLATE PHASE A COMPONENTS - TRAIN A & B FAILURES Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

EOP E-0, Reactor Trip or Safety Injection, Rev 43 Alternate Path: Yes __X No Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 4.1, 5.1, 6.1, 7.1 Job Designation: RO or SRO Rev Comments: Bank LJC-026 Gen KA / Rating: 013.A4.01 - Ability to manually operate and/or monitor 4.5/4.8 in the control room: ESFAS-initiated equipment which fails to actuate AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS REPRESENTATIVE: ABDUL KADIR DATE: 06/20/2014 REV. 1

JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS - JPM NUMBER: NRCL121-S2 TRAIN A & B FAILURES EVALUATOR W ORKSHEET Directions: All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: E-0, Reactor Trip or Safety Injection, Appendix E Initial Conditions A Unit 1 reactor trip and safety injection have occurred Initiating Cue: You are directed by the Shift Foreman to verify Containment Isolation Phase A in accordance with Appendix E, step 3, of EOP E-0 DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: Containment Isolation Phase A completed in accordance with EOP E-0 App E, step 3, and no non-Phase A valves or equipment manipulated/operated.

NRCL121-S2 PAGE 2 OF 9 REV. 1

JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS - JPM NUMBER: NRCL121-S2 TRAIN A & B FAILURES EVALUATOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References EOP E-0, Appendix E, Step 3.

Sat: ______ Unsat _______

Comment:

Note: Alternate Path begins here Observed the following on the CONTAINMENT ISOLATION PHASE A

2. Step 3 - Ensure Phase A actuated 2.1 portion of Monitor Light Box B:

• Train A red activate light - OFF

• Train B red activate light - OFF 2.2 Determined Phase A actuated but has not fully isolated containment Sat: ______ Unsat _______

Comment:

NRCL121-S2 PAGE 3 OF 9 REV. 1

JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS - JPM NUMBER: NRCL121-S2 TRAIN A & B FAILURES EVALUATOR W ORKSHEET Step Expected Operator Actions Note: Operator may manually actuate PHASE A Isolation, but this will not Step 3 RNO - Manually close Phase A work. Alignment steps (as well as 3.

valves with White Status lights ON the valves themselves) that follow may be performed in any order.

3.1 Turned the Phase A actuation switch to ACTUATE. (optional) 3.2 Positioned the MONITOR LIGHT TEST switch to TEST.

Identified open Phase A Isol valves using:

• CONTAINMENT ISOLATION PHASE A portion of Monitor Light Box 3.3 (MLB) B (white status lights ON for mispositioned valves)

• Control Board indications (RED position light ON and/or control switch in OPEN position).

Sat: ______ Unsat _______

Comment:

NRCL121-S2 PAGE 4 OF 9 REV. 1

JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS - JPM NUMBER: NRCL121-S2 TRAIN A & B FAILURES EVALUATOR W ORKSHEET Step Expected Operator Actions Closed each open Containment Isolation Phase A valve on VB-1. **

Step 3 RNO (continued) - Close valves 4.1

• 9355A/B 4.**

on VB1

• 9356A/B

• 8880 Verified that each Containment Isolation 4.2 Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB).

Sat: ______ Unsat _______

Comment:

Closed each open Containment Isolation Phase A valve on VB-2. **

• 8149C

• RW isolations IC and OC Step 3 RNO (continued) - Close valves 5.1

• 8152 5.**

on VB2

• 8045

• 8029

• 8100

• 8112 Verified that each Containment Isolation 5.2 Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB).

Sat: ______ Unsat _______

Comment:

NRCL121-S2 PAGE 5 OF 9 REV. 1

JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS - JPM NUMBER: NRCL121-S2 TRAIN A & B FAILURES EVALUATOR W ORKSHEET Step Expected Operator Actions Closed open Containment Isolation Phase Step 3 RNO (continued) - Close valves 6.1 A valve on VB-3. **

6.**

on VB3

• FCV-633 Verified that each Containment Isolation 6.2 Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB).

Sat: ______ Unsat _______

Comment:

Closed open Containment Isolation Phase Step 3 RNO (continued) - Close valves 7.1 7.** A valve on VB-3. **

on VB4

• FCV-584 Verified that each Containment Isolation 7.2 Phase A valve has closed (Red light OFF, Green light ON, and/or white light OFF on MLB).

Sat: ______ Unsat _______

Comment:

Stop Time:

Total Time: (Enter total time on the cover page)

Follow up Question Documentation:

Question: ____________________________________________________________________

NRCL121-S2 PAGE 6 OF 9 REV. 1

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-S2 Response: ____________________________________________________________________

NRCL121-S2 PAGE 7 OF 9 REV. 1

JPM TITLE: MANUALLY ISOLATE PHASE A COMPONENTS - JPM NUMBER: NRCL121LJC-S2 TRAIN A & B FAILURES ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-10 (100%, MOL).

Enter lesson file NRCL121-LJCS2.lsn:

Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet.

NRCL121-S2 PAGE 8 OF 9 REV. 1

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-S2 Initial Conditions: A Unit 1 reactor trip and safety injection have occurred Initiating Cue: You are directed by the Shift Foreman to verify Containment Isolation Phase A in accordance with Appendix E, step 3, of EOP E-0 NRCL121-S2 PAGE 9 OF 9 REV. 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121-S3

Title:

ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

References:

EOP ECA-0.3, Restore Vital 4KV Busses, Rev 17 Alternate Path: Yes ______X No Time Critical: Yes No X Time Allotment: 25 minutes Critical Steps: 2.a.2, 2.b.1, 5.b.2, 5.f.1, 5.f.2, 5.f.3 Job Designation: RO or SRO Rev Comments:

Gen KA / Rating: 055 EA1.07 - Ability to operate and monitor the 4.3/4.5 following as they apply to a Station Blackout: Restoration of power from offsite AUTHOR: LISA TORIBIO DATE: 06/20/2014 OPERATIONS REPRESENTATIVE: ABDUL KADIR DATE: 06/20/2014 REV. 1

JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S3 EVALUATOR WORKSHEET Directions: All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: EOP ECA-0.3, Restore Vital 4KV Busses, Rev 17 Initial Conditions GIVEN:

• U-1 was at 100% power, when a loss of ALL OFFSITE power resulted in a reactor trip

• ALL DGs failed to start, and could not be started from the control room, or locally

• EOP ECA-0.3 has been implemented as directed by step 10 of ECA-0.0

• Attempts to start Diesel Generators are in progress Initiating Cue: The Shift Foreman directs you to implement EOP ECA-0.3 starting at step 2, to attempt to restore power to any vital 4KV bus.

DO NOT READ TASK STANDARD TO EXAMINEE Task Standard: ALL vital 4KV busses are energized from U-2 startup power, crosstied to U-1 per EOP ECA-0.3.

NRCL121-S3 PAGE 2 OF 12 REV. 1

JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S3 EVALUATOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References ECA-0.3, step 2 Sat: ______ Unsat _______

Comment:

Note: Step 2 - Prepare buses for return of offsite power, consists of multiple substeps 2.a** Step 2.a - Place AUTO TRANSFER to 2.a.1 Read NOTE prior to step 2.

START-UP CUTOUT switch in CUTOUT position for all 4kV and 12 kV buses 2.a.2 Placed vital 4kV (bus F, G, and H) auto-transfer relay cutout switches in CUTOUT.

2.a.3 Placed non-vital (bus D and E) 4kV and 12KV auto-transfer relay cutout switches in CUTOUT.

Sat: ______ Unsat _______

Comment:

2.b** Step 2.b - Depress the AUTO BUS 2.b.1 Pressed vital 4kV (bus F, G, and H) auto-TRANSFER Reset pushbuttons on all 4 transfer relay reset PBs to reset auto kV and 12 kV buses transfer relays. **

2.b.2 Pressed non-vital (bus D and E) auto-transfer relay reset PBs to reset auto transfer relays.

2.b.3 Verified all (7) auto transfer relay blue lights OUT.

Sat: ______ Unsat _______

Comment:

NRCL121-S3 PAGE 3 OF 12 REV. 1

JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S3 EVALUATOR WORKSHEET Step Expected Operator Actions 2.c Place all condensate and booster 2.c.1 Placed all Condensate/Booster Pump pump selector switches in MANUAL Selector Switches in MANUAL.

(VB-3)

Sat: ______ Unsat _______

Comment:

2.d Open all Aux and Startup Feeders to 2.d.1 Read Caution prior to verifying 4 and 12 Deenergized 4 kV Vital Buses F, G, & kV breakers open H

2.d.2 Verified that ALL vital 4kV Aux and S/U Fdr Bkrs are OPEN:

• 52-HH-13

• 52-HH-14

• 52-HG-13

• 52-HG-14

• 52-HF-13

• 52-HF-14 Sat: ______ Unsat _______

Comment:

2.e Open all Aux and Startup Feeders to 2.e.1 Verified that ALL Nonvital 4kV Aux and Deenergized 4 kV Nonvital Buses D & S/U Fdr Bkrs are OPEN .

E

• 52-HE-2

• 52-HE-3

• 52-HD-15

• 52-HD-14 Sat: ______ Unsat _______

Comment:

NRCL121-S3 PAGE 4 OF 12 REV. 1

JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S3 EVALUATOR WORKSHEET Step Expected Operator Actions 2.f Open all Aux and Startup Feeders to 2.f.1 Verified that ALL Nonvital 12 kV Aux and Deenergized 12 kV Nonvital Buses D S/U Fdr Bkrs are OPEN .

&E

• 52-VD-8

• 52-VD-4

• 52-VE-2

• 52-VE-6 Sat: ______ Unsat _______

Comment:

3.1 Observed that SI signal is not present -

3. Step 3 - Verify SI Reset may reset SI again Sat: ______ Unsat _______

Comment:

4.1 Checked the status of 500KV power (may

4. Step 4 - Check 500 kV available use sync key on CC3 and/or phone call).

Cue: 500KV power is NOT available; it is expected back in 2 to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

4.2 Continued to next step per step 4 RNO.

Sat: ______ Unsat _______

Comment:

NRCL121-S3 PAGE 5 OF 12 REV. 1

JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S3 EVALUATOR WORKSHEET Step Expected Operator Actions 5.1 Checked status of CB-212 (visual check at 5 Step 5 - Check 230 kV available VB-5, and/or phone call).

Cue: (from SM) 230KV power is stable, and CB-212 is closed.

Note: Alternate Path begins here 5.2 Observed that S/U transformer power available light is NOT ON, and goes to step 5b RNO actions.

Cue: (from SM) S/U transformer 1-1 is faulted, and has been isolated.

Sat: ______ Unsat _______

Comment:

NRCL121-S3 PAGE 6 OF 12 REV. 1

JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S3 EVALUATOR WORKSHEET Step Expected Operator Actions 5.b** Step 5.b RNO - close VU-11 5.b.1 Observed that U-2 S/U crosstie is energized (white light on VB-5 above VU-11 is ON)

Cue: (if asked) U-2 SFM reports that VU-24 is closed, and U-2 S/U bus voltage is stable.

Note: If, during the following step, VU-12 is closed in error, it is critiquable, but not a critical miss-step.

5.b.2 Inserted sync key in VU-11, turned to ON, and closed VU-11 (may remove key when done). **

5.b.3 Continued on to step 5.d Sat: ______ Unsat _______

Comment:

5.d Step 5.d - Verify the feeder breaker 5.d.1 Observed that S/U Transformer 1-2 feeder to Startup transformer 1-2 CLOSED VU-14 is CLOSED.

5.e Step 5.e - Verify common 4 kV 5.e.1 Observed that S/U feeder to vital 4KV startup feeder CLOSED buses 52-HG-15 is CLOSED.

Sat: ______ Unsat _______

Comment:

NRCL121-S3 PAGE 7 OF 12 REV. 1

JPM TITLE: ENERGIZE VITAL BUSES FROM THE 230KV SYSTEM JPM NUMBER: NRCL121-S3 EVALUATOR WORKSHEET Step Expected Operator Actions Cue: The SFM reports that all ESF pump 5.f** Step 5.f - Energize 4 kV Vital buses interlock devices have been installed.

Inserted Sync Key, turned ON, and CLOSED 5.f.1 S/U breaker for Bus F. **

Note: Busses may be energized in any order.

Inserted Sync Key, turned ON, and CLOSED 5.f.2 S/U breaker for Bus G. **

Inserted Sync Key, turned ON, and CLOSED 5.f.3 S/U breaker for Bus H. **

5.f.4 Removed sync key (optional)

Sat: ______ Unsat _______

Comment:

Stop Time:

Total Time: (Enter total time on the cover page)

NRCL121-S3 PAGE 8 OF 12 REV. 1

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-S3 Follow up Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL121-S3 PAGE 9 OF 12 REV. 1

JPM

Title:

ENERGIZE VITAL BUSES FROM THE 230KV JPM Number: NRCL121-S3 SYSTEM Attachment 1, Simulator Setup Initialize the simulator to IC-10 (100%, MOL).

Enter lesson file NRCL121-LJCS3.lsn:

A (Continued on Next Page)

NRCL121-S3 PAGE 10 OF 12 REV. 1

JPM

Title:

ENERGIZE VITAL BUSES FROM THE 230KV JPM Number: NRCL121-S3 SYSTEM , Simulator Setup (Continued from Previous Page)

A NRCL121-S3 PAGE 11 OF 12 REV. 1

EXAMINEE CUE SHEET JPM NUMBER: NRCL121-S3 Initial Conditions: GIVEN:

• U-1 was at 100% power, when a loss of ALL OFFSITE power resulted in a reactor trip

• ALL DGs failed to start, and could not be started from the control room, or locally

• EOP ECA-0.3 has been implemented as directed by step 10 of ECA-0.0

• Attempts to start Diesel Generators are in progress Initiating Cue: The Shift Foreman directs you to implement EOP ECA-0.3 starting at step 2, to attempt to restore power to any vital 4KV bus.

NRCL121-S3 PAGE 12 OF 12 REV. 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121LJC-S4

Title:

RESPOND TO CFCU HIGH VIBRATION Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

AR PK01-21, CONTMT FAN CLRS, Rev. 14

References:

OP H-2:I, Containment Fan Cooler Units - Make Available and System Operation, Rev. 34.

Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 2.3, 3.5 Job Designation: RO/SRO Rev Comments:

Gen KA / Rating: G2.4.31 - Knowledge of annunciator alarms, indications, 4.2 / 4.1 or response procedures.

AUTHOR: DATE:

OPERATIONS REPRESENTATIVE: DATE:

REV. 1

JPM

Title:

Respond to CFCU High Vibration JPM Number: NRCL121LJC-S4 INSTRUCTOR WORKSHEET Directions: All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed.

After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step at which to begin.

Required Materials: None.

Initial Conditions: Given:

• Unit 1 is at 100% power

• Maintenance has requested shutdown of CFCU 1-2 for a routine inspection.

Initiating Cue: The Shift Foreman directs you to start CFCU 1-1 and shutdown CFCU 1-2 in accordance with OP H-2:I, Containment Fan Cooler Units -

Make Available and System Operation, starting at step 6.4. All precautions and limitations are complete.

NOTE: Do NOT provide the student with the Task Standard.

Task Standard: PK01-21, CONTMT FAN CLRS alarm for high vibration is cleared and CFCU 1-1 is shutdown in accordance with AR PK01-21 and OP H-2:I.

NRCL121LJC-S4 PAGE 2 OF 7 REV. 1

JPM

Title:

Respond to CFCU High Vibration JPM Number: NRCL121LJC-S4 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References OP H-2:I, Section 6.4, Swapping Running CFCUs.

Step was: Sat: ______ Unsat _______

Comments:

2. Step 6.4.1 - Start CFCU 1-1. 2.1 Reads notes prior to step 6.4.1 2.2 Verified SPEED SELECT switch for CFCU is selected to LOW.

• • 2.3 Depressed switch to start fan.**

2.4 Checked that fan current stabilizes.

2.5 Attempted reset of PK01-21 caused by high vibration Note: Alternate Path begins here 2.6 Implemented AR PK01-21.

Step was: Sat: ______ Unsat _______

Comments:

• • Denotes a Critical Step.

NRCL121LJC-S4 PAGE 3 OF 7 REV. 1

JPM

Title:

Respond to CFCU High Vibration JPM Number: NRCL121LJC-S4 INSTRUCTOR WORKSHEET Step Expected Operator Actions

3. Implements Section 2.3, Fan Cooler 3.1 Confirmed high vibration condition on High Vibration. CFCU 1-1.

3.2 Read note prior to step 2.3.2.

3.3 Presses VIB ALARM RESET pushbutton on VB-1 to reset alarm

• • Step 2.3.3 - Shuts down CFCU 1-1. 3.4 Notes reflash of PK01-21.

3.5 Presses STOP button for CFCU 1-1 on VB-1** (step 2.3.3.a).

3.6 Reports unable to perform the CFCU swap.

Cue: The SFM will contact maintenance to investigate.

Step was: Sat: ______ Unsat _______

Comments:

Stop Time:

Total (Enter total time on the cover page)

Time:

• • Denotes a Critical Step.

NRCL121LJC-S4 PAGE 4 OF 7 REV. 1

JPM

Title:

Respond to CFCU High Vibration JPM Number: NRCL121LJC-S4 INSTRUCTOR WORKSHEET Followup Question Documentation:

Question: ___________________________________________________________________

Response: ___________________________________________________________________

• • Denotes a Critical Step.

NRCL121LJC-S4 PAGE 5 OF 7 REV. 1

JPM TITLE: Respond to CFCU High Vibration JPM NUMBER: NRCL121LJC-S4 ATTACHMENT 1, SIMULATOR SETUP INIT to IC 10.

Shutdown CFCU 1-1 and clear all alarms Verify CFCU 2, 4, and 5 running in LOW speed; CFCU 1-3 running in HIGH Note: Entering drill file prior to shutting down CFCU 1-1 will corrupt drill logic.

Enter drill file NRCL121-LJCS4 or manually insert the following:

Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet.

NRCL121-S4 R1 PAGE 6 OF 7 REV. 1

EXAMINEE CUE SHEET JPM NUMBER: NRCL121LJC-S4 Initial Conditions: Given:

• Unit 1 is at 100% power

• Maintenance has requested shutdown of CFCU 1-2 for a routine inspection Initiating Cue: The Shift Foreman directs you to start CFCU 1-1 and shutdown CFCU 1-2 in accordance with OP H-2:I, Containment Fan Cooler Units -

Make Available and System Operation, starting at step 6.4. All precautions and limitations are complete.

NRCL121-S4 R1 PAGE 7 OF 7 REV. 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121LJC-S5

Title:

RESPOND TO HIGH RADIATION ON RE-17A/B Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

AR PK11-21, High Radiation, Rev. 31

References:

OP AP-11, Malfunction of Component Cooling Water System, Rev 31.

Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 20 minutes (average validation time __ min)

Critical Steps: 3.2, 13.4, 13.5, 13.6 Job Designation: RO/SRO Rev Comments:

Gen KA / Rating: 073.A4.01 - Ability to manually operate and/or monitor in 3.9 / 3.9 the control room: effluent release AUTHOR: LISA TORIBIO DATE: 07/14/14 OPERATIONS REPRESENTATIVE: ABDUL KADIR DATE: 07/14/14 REV. 1

JPM TITLE: RESPOND TO HIGH RADIATION ON RE-17A/B JPM NUMBER: NRCL121LJC-S5 INSTRUCTOR WORKSHEET Directions: All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed.

After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step at which to begin.

Required Materials: None.

Initial Conditions: Given:

• Unit 1 is at 100% power.

• PK11-21 has just alarmed Initiating Cue: The Shift Foreman directs you to respond to the alarm per AR PK11-21, High Radiation, beginning with step 2.4.

NOTE: Do NOT provide the student with the Task Standard.

Task Standard: RCV-16 is closed and Letdown Heat Exchanger is isolated in accordance with AR PK11-21 and OP AP-11.

NRCL121-S5 R1 PAGE 2 OF 11 REV. 1

JPM TITLE: RESPOND TO HIGH RADIATION ON RE-17A/B JPM Number: NRCL121LJC-S5 INSTRUCTOR WORKSHEET Start Time:

Step Standards

1. AR PK11-21, Step 2.4.1 - Identify 1.1 Read NOTE prior to step 2.4.1.

process monitors in alarm.

1.2 Observed both 17A and 17B in alarm.

Step was: Sat: ______ Unsat _______

Comments:

2. AR PK11-21, Step 2.4.2 - Check ***********************************

process monitor high rad was Cue: No other process monitors were in already in alarm state. alarm prior to this event.

2.1 Determined no other process monitors in alarm.

Step was: Sat: ______ Unsat _______

Comments:

3. ** AR PK11-21, Step 2.4.3 - Ensure 0B Note: May have already completed this appropriate automatic action has action based on RE-17A/B alarm occurred. condition.

Note: Action to close RCV-16 is single action alternate path.

3.1 Noted automatic closure of RCV-16 did NOT occur.

3.2 Closed RCV-16 **

Step was: Sat: ______ Unsat _______

Comments:

• • Denotes a Critical Step.

NRCL121-S5 R1 PAGE 3 OF 11 REV.1

JPM TITLE: RESPOND TO HIGH RADIATION ON RE-17A/B JPM Number: NRCL121LJC-S5 INSTRUCTOR WORKSHEET Step Standards

4. AR PK11-21, Step 2.4.4 - Check if 4.1 Noted RE-3 is NOT in alarm.

RE-3 is in alarm OR the Oily Water Separator influent is suspected to be radioactive.

Step was: Sat: ______ Unsat _______

Comments:

5. AR PK11-21, Step 2.4.5 - Check if 5.1 Determined RM-12 is in service and no RM-12 is out-of-service OR a Containment Ventilation Isolation has Containment Ventilation Isolation occurred.

occurs.

Step was: Sat: ______ Unsat _______

Comments:

6. AR PK11-21, Step 2.4.6 - Check if 6.1 Determined RM-11 and RM-12 are NOT in RM-11 or RM-12 is in alarm. alarm.

Step was: Sat: ______ Unsat _______

Comments:

• • Denotes a Critical Step.

NRCL121-S5 R1 PAGE 4 OF 11 REV.1

JPM TITLE: RESPOND TO HIGH RADIATION ON RE-17A/B JPM Number: NRCL121LJC-S5 INSTRUCTOR WORKSHEET Step Standards

7. AR PK11-21, Step 2.4.7 - Check if 7.1 Determined RE-17A and RE-17B are both RE-17A or RE-17B is in alarm. in alarm.

7.2 Noted corroborating upscale reading on both 17A/B and determined alarm is NOT spurious (step 2.4.7.a) 7.3 Noted upscale reading on CCW Surge Tank Level Indicators LI-139 and LI-140 (step 2.4.7.b)

Note: Alternate Path begins here.

7.4 Transitioned to OP AP-11, Section B, CCW System In-Leakage (step 2.4.7.c)

Step was: Sat: ______ Unsat _______

Comments:

8. OP AP-11, Section B, Step 1 - Check 8.1 Determined PK11-21 IS in alarm and if PK11-21 is NOT in alarm. followed RESPONSE NOT OBTAINED column.

8.2 Checked CCW Surge Tank Vent RCV-16 is CLOSED.

Step was: Sat: ______ Unsat _______

Comments:

• • Denotes a Critical Step.

NRCL121-S5 R1 PAGE 5 OF 11 REV.1

JPM TITLE: RESPOND TO HIGH RADIATION ON RE-17A/B JPM Number: NRCL121LJC-S5 INSTRUCTOR WORKSHEET Step Standards

9. 1B0 OP AP-11, Section B, Step 2 - 9.1 Read both CAUTIONS prior to step 2.

Ensure RCP Operability.

9.2 Checked thermal barrier CCW outlet valve FCV-357 was in OPEN position.

9.3 Checked RCP Radial Bearing Temperature LESS THAN 225oF for all RCPs.

9.4 Checks RCP No.1 seal outlet temperature LESS THAN 235oF for all RCPs.

Step was: Sat: ______ Unsat _______

Comments:

10. 2B0 OP AP-11, Section B, Step 3 - Note: May determine CCW makeup Ensure CCW Surge Tank Makeup supply position from either of the NOT the source of inleakage. following:

10.1 Determined LCV-69 and LCV-70 are both closed by one of the following:

• Checks RONAN for PK01-07, CCW Surge Tk Lvl/Mk-Up, input 88 or 203 (makeup valve open)

• Dispatches Aux Watch to locally verify valves are closed If Local Valve Position Check Requested:

Cue: Using Time Compression, Operator reports both LCV-69 and LCV-70 are in the closed position.

Step was: Sat: ______ Unsat _______

Comments:

• • Denotes a Critical Step.

NRCL121-S5 R1 PAGE 6 OF 11 REV.1

JPM TITLE: RESPOND TO HIGH RADIATION ON RE-17A/B JPM Number: NRCL121LJC-S5 INSTRUCTOR WORKSHEET Step Standards

11. 3B0 OP AP-11, Section B, Step 4 - 11.1 Contacts Shift CARP to request sampling of Request Sample Analysis. CCW.

Cue: Using Time Compression, Chemistry reports the Letdown Heat Exchanger appears to be the source of RCS In-Leakage.

Step was: Sat: ______ Unsat _______

Comments:

12. 4B0 OP AP-11, Section B, Step 5 - 12.1 Read NOTE prior to step 5.

Determine Leak Location.

12.2 May have checked Letdown Heat Exchanger for corroborating indications:

• Letdown Flow Low (FI-134A)

• Letdown Pressure High (PI-135)

• VCT Level Low

• CCW Surge Tank Level High (LI-139 and LI-140) 12.3 Determined Letdown Heat Exchanger is probable source of in-leakage and followed RESPONSE NOT OBTAINED column.

12.4 Transitioned to OP AP-11, Appendix B, step 1 to isolate the Letdown Heat Exchanger.

Step was: Sat: ______ Unsat _______

Comments:

• • Denotes a Critical Step.

NRCL121-S5 R1 PAGE 7 OF 11 REV.1

JPM TITLE: RESPOND TO HIGH RADIATION ON RE-17A/B JPM Number: NRCL121LJC-S5 INSTRUCTOR WORKSHEET Step Standards

13. ** OP AP-11, Appendix B, Step 1.a -

5B0 13.1 Read three NOTES prior to step 1.

Isolate Letdown.

Note: CVCS-8149A/B are already in the CLOSED position.

13.2 Checked CVCS-8149A CLOSED (step 1.a.1) 13.3 Checked CVCS-8149B CLOSED (step 1.a.2) 13.4 CLOSED CVCS-8149C (step 1.a.3)**

13.5 CLOSED LCV-459 (step 1.a.4)**

13.6 CLOSED LCV-460 (step 1.a.5)**

Step was: Sat: ______ Unsat _______

Comments:

14. 6B0 OP AP-11, Appendix B, Step 1.b-g 14.1 ***********************************

(remaining Control Room actions of Cue: Other operators will continue with Appendix B). performance of OP AP-11 and PK11-21.

Step was: Sat: ______ Unsat _______

Comments:

Stop Time:

Total Time: (Enter total time on the cover page)

• • Denotes a Critical Step.

NRCL121-S5 R1 PAGE 8 OF 11 REV.1

JPM TITLE: RESPOND TO HIGH RADIATION ON RE-17A/B JPM Number: NRCL121LJC-S5 INSTRUCTOR WORKSHEET Followup Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL121-S5 R1 PAGE 9 OF 11 REV.1

JPM TITLE: RESPOND TO HIGH RADIATION ON RE-17A/B JPM Number: NRCL121LJC-S5 ATTACHMENT 1, SIMULATOR SETUP INIT to IC 10.

Run lesson NRCL121-LJCS5 or manually insert the following:

Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet.

NRCL121-S5 R1 PAGE 10 OF 11 REV.1

EXAMINEE CUE SHEET JPM Number: NRCL121LJC-S5 Initial Conditions: Given:

• Unit 1 is at 100% power.

• PK11-21 has just alarmed Initiating Cue: The Shift Foreman directs you to respond to the alarm per AR PK11-21, High Radiation, beginning with step 2.4.

NRCL121-S5 R1 PAGE 11 OF 11 REV.1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121LJC-S6

Title:

INITIATE A NATURAL CIRCULATION COOLDOWN Examinee:

Evaluator:

Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: RO Only

References:

EOP E-0.2, Natural Circulation Cooldown, Rev. 26 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes (average validation time ___ min)

Critical Steps: 6.1, 6.3 Job Designation: RO Rev Comments/TIPs: LJC-046 Gen KA # / Rating: 002.A4.02 - Ability to manually operate and/or monitor in the 4.3 control room: Indications necessary to verify natural circulation from appropriate level, flow, and temperature indications and valve positions upon loss of forced circulation AUTHOR: DATE:

OPERATIONS REPRESENTATIVE: DATE:

REV. 1

JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: NRCL121LJC-S6 INSTRUCTOR WORKSHEET Directions: All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed.

After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step at which to begin.

Required Materials: EOP E-0.2, Natural Circulation Cooldown, Rev. 26 Initial Conditions: GIVEN:

• Unit 1 has tripped from 100% power.

• EOP E-0.1, Reactor Trip Response, is complete; RCPs are not available.

• EOP E-0.2 has been performed up to and including Step 9.

• Boration to Cold Shutdown is complete.

Initiating Cue: The Shift Foreman directs you to initiate a natural circulation cooldown in accordance with EOP E-0.2, Step 10 (page 6) .

NOTE: Do NOT provide the student with the Task Standard.

Task Standard: A natural circulation cooldown using the 10% steam dumps initiated in accordance with EOP E-0.2 (see examiner note on step 4).

NRCL121-S6 r1 PAGE 2 OF 8 REV. 1

JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: NRCL121LJC-S6 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. References EOP E-0.2. Read CAUTION Read NOTE.

Step was: Sat: ______ Unsat _______

Comments:

2. Step 10.a - Check status of all S/Gs. Checked steam release capabilities of all S/Gs available.

Checked feed flow available to all S/Gs.

Step was: Sat: ______ Unsat _______

Comments:

3. Step 10.b.1 Establish LESS THAN a Noted that C/D rate is limited to 25°F/hr.

25°F/hr COOLDOWN RATE by dumping steam to the condenser Observed that the MSIVs are open and condenser is available.

Step was: Sat: ______ Unsat _______

Comments:

• • Denotes Critical Step and Sub Steps.

nrcl121-s6 r1 PAGE 3 OF 8 REV. 1 1

JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: NRCL121LJC-S6 INSTRUCTOR WORKSHEET Step Expected Operator Actions

4. Step 10.b.3 - Initiate cooldown, using Note: Examinee may raise steam flow HC-507 by manual control of demand or by adjusting Auto setupoint 4.1 Placed HC-507 in Manual and reduced demand to 0%.

OR Raised setpoint on HC-507 to achieve 0%

demand 4.2 Placed Steam Dump Control Switch in Pressure Mode Note: It will only take a few percent increase in demand to start a slow cooldown. Monitor the examinee to see that they throttle the cooldown rate to attain the desired rate. It is expected that the rate may initially overshoot the limit, but should be throttled back 4.3 Manually raises steam demand on HC-507 Steam Pressure Controller OR Ensured HC-507 was in auto and adjusted HC-507 controller setpoint to raise demand Step was: Sat: ______ Unsat _______

Comments:

• • Denotes Critical Step and Sub Steps.

nrcl121-s6 r1 PAGE 4 OF 8 REV. 1 1

JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: NRCL121LJC-S6 INSTRUCTOR WORKSHEET Step Expected Operator Actions 5 Step 10.c - Maintain S/G narrow rangle 5.1 Checked S/G narrow range level between level 20%-65% 20%-65%

Step was: Sat: ______ Unsat _______

Comments:

6** Step 10.d - At P-12 activiation 6.1 Placed Train A and B Steam Dump Control in Bypass InterlocK**

6.2 Verified PK07-05 STM DUMP CONTROL BYPASS came on.

Note: Once the examinee has demonstrated that the rate can be controlled within limits, the ending cue may be given.

6.3 Reestablised cooldown rate LESS THAN 25°F/hr **

Step was: Sat: ______ Unsat _______

Comments:

• • Denotes Critical Step and Sub Steps.

nrcl121-s6 r1 PAGE 5 OF 8 REV. 1 1

JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: NRCL121LJC-S6 INSTRUCTOR WORKSHEET Step Expected Operator Actions 7 Step 11 - Monitor for stagnant loops **********************************

Cue: (if step 11 referenced)

Another operator will monitor for inactive loops / stagnation, and act accordingly.

Cue: (once cooldown rate is properly established)

Another operator will continue with E-0.2 performance.

Step was: Sat: ______ Unsat _______

Comments:

Stop Time:

Total Time: (Enter total time on the cover page)

• • Denotes Critical Step and Sub Steps.

nrcl121-s6 r1 PAGE 6 OF 8 REV. 1 1

JPM TITLE: INITIATE A NATURAL CIRCULATION COOLDOWN JPM NUMBER: NRCL121LJC-S6 ATTACHMENT 1, SIMULATOR SETUP Load IC 261 from L121 Setup Files (approx: 540-555oF)

Select E-0.2 display on SPDS.

Select grpdis "cooldown on a CC2 PPC computer Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet (or the sim can remain in RUN, since the plant is stable) nrcl121-s6 r1 PAGE 7 OF 8 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121LJC-S6 Initial Conditions: GIVEN:

• Unit 1 has tripped from 100% power.

• EOP E-0.1, Reactor Trip Response, is complete; RCPs are not available.

• EOP E-0.2 has been performed up to and including Step 9.

• Boration to Cold Shutdown is complete.

Initiating Cue: The Shift Foreman directs you to initiate a natural circulation cooldown in accordance with EOP E-0.2, Step 10 (page 6).

nrcl121-s6 r1 PAGE 8 OF 8 REV. 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121LJC-S7

Title:

PERFORM OP AP-15 IMMEDIATE ACTIONS FOR MAIN FEED PUMP TRIP Examinee:

Evaluator:

Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:

OP AP-15, Loss of Feedwater Flow, Rev 24.

References:

Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 5 minutes Critical Steps: 1.2, 4.4 Job Designation: RO/SRO Rev Comments: Modified - NRCLCJ051-501 Gen KA / Rating: 059.A2.07 3.0 / 3.3 AUTHOR:

DATE:

OPERATIONS REPRESENTATIVE: DATE:

REV. 1

JPM TITLE: PERFORM OP AP-15 IMMEDIATE ACTIONS FOR MAIN JPM NUMBER: NRCL121LJC-S7 FEED PUMP TRIP INSTRUCTOR WORKSHEET Directions: All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed.

After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step at which to begin.

Required Materials: None.

Initial Conditions: Given:

• Unit 1 is at 100% power.

• PK09-12, Main Feedwater Pump Trip, and PK09-13, Main Feedwater Pump No. 11, have just alarmed

• The Shift Foreman has announced he is entering OP AP-15, Loss of Feedwater Flow Initiating Cue: The Shift Foreman directs you to immediate actions to respond to plant conditions.

NOTE: Do NOT provide the student with the Task Standard.

Task Standard: The Immediate Actions for a Loss of Feedwater were performed in accordance OP AP-15, Loss of Feedwater Flow, from memory, with follow up using the procedure.

NRCL121-S7 R1 PAGE 2 OF 7 REV. 1

JPM TITLE: PERFORM OP AP-15 IMMEDIATE ACTIONS FOR MAIN JPM Number: NRCL121LJC-S7 FEED PUMP TRIP INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. ** Step 1 - Check Reactor power Less 0B 1.1 Determined power is greater than 80%.

Than 80%.

1.2 Perform step 1 RNO Started AFW Pp 1-2.**

Started AFW Pp 1-3.**

Step was: Sat: ______ Unsat _______

Comments:

2. Step 2 - Reduce Turbine Load. 2.1 Determined turbine load is greater than 650 MW 2.2 Determined programmed ramp executing appropriately:

• DEH MW feedback in service

• TARGET set for 550 MW

• RAMP RATE at 225 MW/min.

Step was: Sat: ______ Unsat _______

Comments:

NRCL121-S7 R1 PAGE 3 OF 7 REV. 1

JPM TITLE: PERFORM OP AP-15 IMMEDIATE ACTIONS FOR MAIN JPM Number: NRCL121LJC-S7 FEED PUMP TRIP INSTRUCTOR WORKSHEET Step Expected Operator Actions

3. Step 3 - MFW Pp Suction Pressure 3.1 Determined MFW Pp Suction Pressure is GREATER THAN 260 PSIG greater than 260 PSIG Step was: Sat: ______ Unsat _______

Comments:

4. ** Step 4 - Rods Controlling Properly in 4.1 Checked Tave / Tref mismatch greater than 1.5 oF.

1B AUTO.

4.2 Determined rods are NOT controlling properly in Auto.

Note: Alternate Path begins here 4.3 Placed Rod Control in MANUAL.** (step 4 RNO) 4.4 Inserted rods at maximum available rate of 48 steps/min. **

Cue: Another Operator will continue with performance of OP AP-15.

Step was: Sat: ______ Unsat _______

Comments:

Stop Time:

Total Time: (Enter total time on the cover page)

NRCL121-S7 R1 PAGE 4 OF 7 REV. 1

JPM TITLE: PERFORM OP AP-15 IMMEDIATE ACTIONS FOR MAIN JPM Number: NRCL121LJC-S7 FEED PUMP TRIP INSTRUCTOR WORKSHEET Followup Question Documentation:

Question: ____________________________________________________________________

Response: ____________________________________________________________________

NRCL121-S7 R1 PAGE 5 OF 7 REV. 1

JPM TITLE: PERFORM OP AP-15 IMMEDIATE ACTIONS FOR JPM NUMBER: NRCL121LJC-S7 MAIN FEED PUMP TRIP ATTACHMENT 1, SIMULATOR SETUP INIT to IC 10.

Run lesson NRCL121-LJCS7 or manually insert the following:

Inform the examiner that the simulator setup is complete.

Go to RUN when instructed by examiner.

NRCL121-S7 R1 PAGE 6 OF 7 REV. 1

EXAMINEE CUE SHEET JPM NUMBER: NRCL121LJC-S7 Initial Conditions: Given:

• Unit 1 is at 100% power.

• PK09-12, Main Feedwater Pump Trip, and PK09-13, Main Feedwater Pump No. 11, have just alarmed

• The Shift Foreman has announced he is entering OP AP-15, Loss of Feedwater Flow Initiating Cue: The Shift Foreman directs you to immediate actions to respond to plant conditions.

NRCL121-S7 R1 PAGE 7 OF 7 REV. 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL121LJC-S8

Title:

ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments:

References:

EOP E-1.4, Transfer to Hot Leg Recirculation, Rev. 19 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 4.1, 4.2 Job Designation: RO/SRO Rev Comments/TIPs: NRCL081LJC-S3 Gen KA # / Rating: 006.A4.05 - Ability to manually operate and/or monitor in 3.9 / 3.8 the control room: Transfer of ECCS flowpaths prior to recirculation AUTHOR: DATE:

OPERATIONS REPRESENTATIVE: DATE:

REV. 0

JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER: NRCL121LJC-S8 INSTRUCTOR WORKSHEET Directions: All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed.

After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step at which to begin.

Required Materials: EOP E-1.4 GIVEN:

Initial Conditions:

• A Unit 1 reactor trip and safety injection has occurred

• Cold leg recirculation was initiated just over 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago

• Both RHR pumps are running

• Both SI pumps are aligned for hot leg recirculation.

Initiating Cue: The Shift Foreman directs you to align RHR pump 12 for hot leg recirculation, per EOP E-1.4, steps 6 - 7.

Task Standard: RHR pump 12 aligned for cold leg recirculation in accordance with EOP E-1.4.

NRCL121-S8 r0 PAGE 2 OF 6 REV. 0

JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER: NRCL121LJC-S8 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References EOP E-1.4.

Step was: Sat: ______ Unsat _______

Comments:

2. Step 6 - Check RHR pump 12 running. Observed that RHR pump 12 running.

Step was: Sat: ______ Unsat _______

Comments:

3. Step 7 - Align RHR pump 12 for Hot 3.1 Opened valve 8716B.

Leg RecircOpen 8716B, RHR Verifies valve open.

pump 12 discharge crosstie valve.

4. Note: Alternate Path begins here 4.1 Attempted to open valve 8703, when valve did not open, went to step 7.b RNO Step was: Sat: ______ Unsat _______

Comments:

• • Denotes Critical Step and Sub Steps.

nrcl121-s8 r0 PAGE 3 OF 6 REV. 0

JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER: NRCL121LJC-S8 INSTRUCTOR WORKSHEET Step Expected Operator Actions

5. Step 7.b RNO 5.1 Opened 8809A AND B **

5.2 Closed 8716B, RHR Pp 2 Disch Crosstie Vlv **

5.3 Throttled RHR HX Outlet valve as needed to maintain motor current LESS THAN 57 amps (if needed) 5.4 Went to step 9 Step was: Sat: ______ Unsat _______

Comments:

6. Step 9 - Contact Plant Engineering in 6.1 Contacted TSC to evaluate CCW System TSC to evaluate CCW System train train separation.

separation.

Cue: Another Operator will continue with performance of EOP E-1.4.

Step was: Sat: ______ Unsat _______

Stop Time:

Total Time: (Enter total time on the cover page)

• • Denotes Critical Step and Sub Steps.

nrcl121-s8 r0 PAGE 4 OF 6 REV. 0

JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER: NRCL121LJC-S8 ATTACHMENT 1, SIMULATOR SETUP Restore IC 207 This SNAP allows entry into EOP E-1.4 at Step 6. Both SI and RHR pumps are running.

Manually insert the following:

Command Description vlv rhr7 1,0,0,0,d,0 Fails 8703 closed Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet.

nrcl121-s8 r0 PAGE 5 OF 6 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: NRCL121LJC-S8 Initial Conditions: GIVEN:

A Unit 1 reactor trip and safety injection has occurred

• Cold leg recirculation was initiated just over 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago

• Both RHR pumps are running

• Both SI pumps are aligned for hot leg recirculation.

Initiating Cue: The Shift Foreman directs you to align RHR pump 12 for hot leg recirculation, per EOP E-1.4, steps 6 - 7.

nrcl121-s8 r0 PAGE 6 OF 6 REV. 0

Appendix D (rev 9) Required Operator Actions Form ESD1 Facility: Diablo Canyon (PWR) Scenario No.: 3 OpTest No.: L121NRC Examiners: Operators:

Initial Conditions: 75%, MOL, 1014 ppm boron Turnover: Bus H Work Week: AFW 12 OOS, D/G 11 OOS Maintenance in progress on PCV20.

CCP 11 In Service.

Event Malf Event Event No No. Type* Description 1 MAL_NIS6D 200 (ramp I (ALL) NI44, Power Range Nuclear Instrument, slowly fails high causing in slowly) unwarranted rod motion (TS 3.3.1.D, E,S,T; ECGs 37.2, 37.3) (AP 5) 2 PMP_CND2 C (SRO, Condensate Booster Pump 13 Trips on overcurrent. Standby fails BLOCK_AUTO_STRT BOP) to autostart (AP15).

PMP_CND3_MTRF 15.0 3 MAL_RCS4F 35 delay=0 C (ALL) 35 gpm tube leak ramps in over 2 minutes on S/G 12, requiring ramp=120 R (ATC) power reduction. (TS 3.4.15.A) (AP3) 4 MAL_CWS2C 1.3 C (SRO, Condenser inleakage in SW quadrant requiring 25 MW/min ramp delay=0 ramp=2 BOP) (AP20) 5 MAL_RCS4F 400 M (ALL) S/G 12 ruptures (400 gpm) requiring Safety Injection.

delay=0 ramp=120 6 VLV_SIS3_1 1 C (BOP) Charging Injection Outlet Valves 8801A/B fail to open on SI, VLV_SIS4_1 1 requiring manual opening to establish high head ECCS injection (CT) 7 insert MAL_MSS1B M (ALL) Main Steam Line Break on S/G 12 inside containment 3500000.0 cd='fnispr lt downstream of flow restrictor on Rx Trip resulting in 5.0' delay=0 ramp=60 faulted/ruptured S/G (CT) 8 insert VLV_MSS7_2 1.0 C (BOP) Main Steam Isolation Valves s on leads 1 & 2 fail to close in auto, insert VLV_MSS8_2 1.0 but can be closed manually delIA VLV_MSS7_2 2 delIA VLV_MSS8_2 2

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L121 NRC ESD103 r2.doc Page 1 of 3 Rev 2

Appendix D (rev 9) Required Operator Actions Form ESD1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES3014) Actual Attributes

1. Total malfunctions (5-8) (Events 1,2,3,4,5,6,7,8) 8

2. Malfunctions after EOP entry (1-2) (Events 6,8) 2

3. Abnormal events (2-4) (AP5, AP15, AP3, AP20) 4

4. Major transients (1-2) (Event 5,7) 2

5. EOPs entered/requiring substantive actions (1-2) (E2, E3) 2

6. EOP contingencies requiring substantive actions (0-2) (terminate @ ECA3.1 entry) 0

7. Critical tasks (2-3) (See Scenario Summary) 2 L121 NRC ESD103 r2.doc Page 2 of 3 Rev 2

SCENARIO

SUMMARY

- NRC #3

1. Power Range Nuclear Instrument NI44 slowly fails high causing inward rod motion. Crew diagnoses failure, and once motion is deemed unwarranted, takes rods to manual. Failure is addressed per OP AP5, Malfunction of Eagle 21 Protection or Control Channel, which removes the failed channel from service and directs the Shift Foreman to address Tech Specs 3.3.1.D,E,S,T Reactor Trip System Instrumentation; ECG 37.2 Axial Flux Difference (AFD) monitoring, and ECG 3.73 (Quadrant Power Tilt Ratio Alarms).

2. Condensate Booster Pump 13 trips and standby pump fails to autostart. Crew responds by manually starting standby pump and following guidance of OP AP15, Loss of Feedwater Flow.

3. S/G 12 develops a 35 gpm tube leak over a two minute period. Crew determines leak rate and enters OP AP3, Steam Generator Tube Failure. Leak is also evaluated per OP O4, Primary to Secondary Steam Generator Tube Leak Detection, which directs crew to reduce power by 50% in the next hour and be in Mode 3 within two hours. Shift Foreman determines TS 3.4.13.A, RCS Operations Leakage applies.

4. A saltwater leak develops in the SW quadrant of the condenser, requiring the crew to raise the ramp rate to 25 MW/min per OP AP20, Condenser Tube Leak.

5. S/G 12 ruptures during ramp, requiring crew to initiate a Safety Injection and enter EOP E0, Reactor Trip or Safety Injection.

6. On the SI, two of the charging injection isolation valves fail to open, but are opened manually in order to supply highhead ECCS injection. (Critical Task E0D: Establish high head ECCS flow prior to exiting EOP E0) **

7. On the Reactor Trip, a Main Steam Line Break occurs on S/G 12 inside containment, downstream of the flow restrictor, resulting in a faulted/ruptured condition. The S/G will be isolated per EOP E2, Faulted S/G Isolation (Critical Task E2A: Isolation of Faulted S/G initiated before transition out of EOP E2) **

8. Main Steam Isolation Valves on steam leads 1 and 2 fail to isolate and are closed manually by the crew. The crew will continue to mitigate the casualty following the guidance of EOP E3, Steam Generator Tube Rupture, and transition to EOP ECA3.1, SGTR with Loss of Reactor Coolant -

Subcooled Recovery Desired.

The scenario is terminated once crew transitions to ECA 3.1, SGTR with Loss of Reactor Coolant - Subcooled Recovery.

L121 NRC ESD103 r2.doc Page 3 of 3 Rev 2

Appendix D (rev 9) Scenario Event Description Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 1 Page 1 of 20 Event

Description:

Power Range Nuclear Instrument NI44 Slow Failure High Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.

ALL Diagnoses power range NI44 failure from the following:

NI44 meter failing high (CC1, VB2 lower chart)

Several PK alarms, all associated with power range NIs, have alarmed Turbine power (PPC, CC3 turbine control) has not changed, Tave is close to Tref, but controls rods are moving in (CC1)

ATC Takes control rods to manual (due to inward rod motion caused by NI44 failing high) (CC1)

SRO Enters OP AP5, "Malfunction of Eagle21 Protection or Control Channel" (OP AP5, Malfunction of Eagle21 Protection or Control Channel)

Note: Depending on how quickly this failure is diagnosed, and how quickly control rods are placed in manual (fairly high worth area for rods), there may be an immediate need to control temperature. If needed, the Shift Foreman may chose to use the turbine load to raise Tave, or may "move up" a substep in OP AP5 to bypass the C2 rod stop (that prevents outward rod motion), so that rods are again available. If failure identified fairly quickly, these responses may be delayed until rod control is restored (below).

SRO/ATC (1) Determines Primary and Secondary Control Systems are NOT controlling properly in AUTO (specifically Rod Control has a failure)

(1.a RNO) Verifies Rod Control has been taken to manual. Restores Tave to Tref (if needed; see note above). This may be done by ramping the turbine down, or by moving rods out (see below for bypassing rod stop C2)

(1.b RNO) Notes failure is due to single instrument and not an entire Process Control Rack SRO Reads NOTES regarding Channel Set Failure Alarm and failure of LCP prior to step 2 and determines they are not applicable for this failure (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 4 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 1 Page 2 of 20 Event

Description:

Power Range Nuclear Instrument NI44 Slow Failure High, continued Time Position Applicants Actions or Behavior (OP AP5, Malfunction of Eagle21 Protection or Control Channel, continued)

SRO/BOP (2) Determines not an Eagle21 failure based on PK0601 and PK0603 OFF SRO (3) Notes no Delta T channel failure (step is N/A) (VB2)

SRO/BOP (4) Checks steam dumps not actuated (no armed, open, or tripped open signals) (VB3)

SRO (5) Notifies I&C SRO Reads CAUTION before step 6 regarding Eagle 21 design feature associated with rack issues and notes as N/A for this failure (6) Reminds crew of necessity to ensure affected channels are removed from service prior to maintenance SRO/BOP (7) Reviews Attachments 4.1 (Rx Trip and ESF Bistable Channel positioning per TS) and 4.2 (Process Control System Racks) to determine affected controls and indicators (a) Places OOS tags on NI44 (CC1, VB2) and OTT (VB2)

(b) Determines NI-44 provides control inputs and can be defeated/bypassed (these actions may be done at several steps in OP AP-5; pg 19 of Att 4.1) (all of these switches are "in back" on the NI panels, all on the right hand cabinet, four switches on the top drawer, and the last switch on the middle drawer) o Places rod stop bypass switch to N44 position (this one cause defeat alarm, PK07-07, and allows rod movement) o Places power mismatch switch to the N44 position o Places quadrant power tilt upper section to the N44 position o Places quadrant power tilt lower section to the N44 position o Places comparator defeat switch to the N44 position (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 5 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 1 Page 3 of 20 Event

Description:

Power Range Nuclear Instrument NI44 Slow Failure High, continued Time Position Applicants Actions or Behavior (OP AP5, Malfunction of Eagle21 Protection or Control Channel, continued)

SRO (8) Evaluates Tech Specs and ECGs:

o TS 3.3.1.E One channel inoperable for OTDeltaT trip (place in trip within 72 hrs);

o TS 3.3.1.D - One power range neutron fluxhigh channel inoperable (Hi flux trip)

(72 hrs) (also 12 hrs on QPTR surveillance) o TS 3.3.1.S - One or more channels or trains inoperable (P10 permissive check)

(verify status within 1 hr) o TS 3.3.1.T - One or more channels or trains inoperable (P7, P8, P9 permissive checks) (verify status within 1 hr) o Equip Control Guideline (ECG) 37.2 Axial Flux Difference Monitor Alarm inoperable (verify AFD within limits for each operable channel within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per hour thereafter) o Equip Control Guideline (ECG) 37.3 Quadrant Power Tilet Ratio Alarm inoperable (verify QPTR within limits of TS 3.2.4 once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)

SRO/ATC If not completed earlier, checks Tave restored to Tref (CC1 or CC3)

Returns rods to AUTO (CC1)

Proceed to the next event once Tech Specs are addressed, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 6 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 2 Page 4 of 20 Event

Description:

Condensate Booster Pump (CBP) 13 Overcurrent Trip Time Position Applicants Actions or Behavior ALL Diagnoses CBP 13 trip from the following:

PK1006, "CNDS & CNDS BSTR PPS", in alarm Low Feedpump Suction Pressure (VB3, upper right center)

Overcurrent (blue) light on for CBP 13 (VB3, lower center skirt)

SRO May enter PK1006, which directs crew to OP AP15 (section D, for Cond/booster Pp trip)

BOP May start standby CBP 12 (failed to autostart) (VB3, lower center skirt)

SRO Enters OP AP15: Section D "Loss of Feedwater Flow - Condensate/Booster Pump Set Trip" (OP AP15: Section D, "Loss of Feedwater Flow - Condensate/Booster Pump Set Trip")

SRO/BOP (1) Determines all available CBPs are NOT running (CBP 12 did NOT autostart as expected)

(1 RNO) o Takes CBP 12 Standby Select Switch to MAN (VB3, lower center skirt) o Starts CBP 12 (checks amps stable) (VB3, lower center skirt)

SRO/BOP (2) Checks Main Feed Pump suction pressure greater than 260 psig (VB3, upper center)

SRO May direct Turbine Watch to walkdown pump and breaker; may contact maintenance to investigate issue (3) Exits AP15 Proceed to the next event when AP15 exited, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 7 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 3 Page 5 of 20 Event

Description:

S/G 12 Tube Leak (35 gpm)

Time Position Applicants Actions or Behavior ALL Diagnoses Steam Generator Tube Leak from the following:

Increased charging flow (PPC, CC2)

Air ejector offgas hirad in alarm (PPC, RM15/15R) (PK1106)

Steam generator blowdown hirad and/or isolation (PPC, RM19,23) (PK1117)

Main steam line hirad (RM72) (PPC, PK1118)

ATC Observes PK1106 (SJAE HIRAD) alarming and informs the Shift Foreman.

ATC/BOP May check PPC and/or VB2 Recorders (lower left) for upscale readings/ trends on rad monitors If AR PK1106 is entered; otherwise this section is N/A SRO/ATC (1) Identifies input 423 (SJAE HiRad) and goes to section 2.1, General Actions.

SRO/BOP (2.1.1) Checks for upscale readings on both 15 and 15R (PPC, RCDR3 VB2 lower left)

(both are in alarm; may be over ranged) o (2.1.1.a) Implements OP O4, "Primary to Secondary Steam Generator Tube Leak Detection" o (2.1.1.b) Notifies Chemistry of abnormal condition o (2.1.1.c) Transitions to OP AP3 (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 8 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 3 Page 6 of 20 Event

Description:

S/G 12 Tube Leak (35 gpm), continued Time Position Applicants Actions or Behavior Note: Review of OP O4 shutdown criteria is also covered as part of OP AP3, "Steam Generator Tube Failure" (if not addressed during AR PK1106 response)

OP O4, "Primary to Secondary Steam Generator Tube Leak Detection" Implementation BOP Reviews OP O4 for action levels and shutdown criteria Evaluates OP O4 action level using PPC Group Display Determines current OP O4 action level as 3b (leak >= 150 gpd) and updates Shift Foreman SRO Enters OP AP3 "Steam Generator Tube Failure" (OP AP3 "Steam Generator Tube Failure")

SRO Reads NOTE prior to step 1 regarding requirement to complete procedure actions unless superseded by EOP E3 ("Steam Generator Tube Rupture")

Note: Maintaining Pressurizer level stable is a Continuous Action. Associated RNO steps are performed when crew reports applicable conditions exist (i.e unable to maintain pressurizer level).

SRO/ATC (1) Checks pressurizer level and charging flow o May take manual control and attempt to adjust charging and seal flow to maintain pressurizer level (CC2) o (1.a) Determines charging flow is NOT maintaining pressurizer level stable (CC2, PPC)

SRO/BOP (1.a RNO) Starts additional charging pump when requested by ATC (VB2, center skirt)

SRO/ATC (1.b) Checks for continuing decrease in pressurizer level o Readjusts charging and seal flow (CC2) o Determines pressurizer level is stable (CC2, PPC) (Continuous Action to Monitor)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 9 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 3 Page 7 of 20 Event

Description:

S/G 12 Tube Leak (35 gpm), continued Time Position Applicants Actions or Behavior (OP AP3, "Steam Generator Tube Failure", continued)

SRO/BOP (2) Takes actions to identify affected steam generator o (2.a) Determines that no S/G levels are rising unexpectedly (VB3 meters, PPC) o (2.b) Identifies main steamline rad monitors RM71 and 72 rising (corresponds to S/G 12; RM71 reading is elevated as result of shine and is reading considerably lower than RM72 ) (VB2 recorders, upper left; PPC) o (2.c) Verifies S/G blowdown isolation/sample valves open (VB3 lower left)

(Depending on pace of crew, blowdown may have isolated due to high rad on RM23; RNO step is performed to allow sampling by chemistry)

(2.c RNO) Checks blowdown isolation due to RM12 in alarm (PPC, RCDR3 VB2 lower left); Places RE19, 23 Hi Rad S/G Blowdown and Sample Valve iso defeat cutout switch to "cutin" and opens blowdown sample valves (FCV244, 24, 248, 250) (VB3, lower left skirt) o (2.d) Contacts Chemistry to perform S/G sampling SRO/ATC (3) Determines VCT level can be maintained by RCS makeup (CC2,VB2, PPC)

(Continuous Action to Monitor)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 10 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 3 Page 8 of 20 Event

Description:

S/G 12 Tube Leak (35 gpm), continued Time Position Applicants Actions or Behavior (OP AP3, "Steam Generator Tube Failure", continued)

Note 1: OP O4, action level 3b corresponds to T.S. 3.4.13.d (150 gpd primary to secondary leakage), Action B, which requires the unit to be in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Note 2: Once the shutdown commences, however, continuous radiation monitoring via RM15 and 15R is no longer valid (power reduction invalidates the rad monitor's cpmgpd conversion factor). OP O4 guidance for Action Level 3b (section 6.6) is as follows for Rx power 50%:

The shutdown should begin promptly, but may be delayed for up to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Once power reduction begins, Rx power shall be less than 50% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and shutdown to MODE 3 within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

SRO (4) Determines plant shutdown is required based on OP O4 shutdown criteria o (4.a) Reviews OP O4 criteria and PPC GRPDIP OP O4 data and concurs with action level 3b assessment o (4.b) Implements OP AP25 to take unit offline May perform reactivity brief prior to entry (5) May perform additional actions to minimize secondary contamination o (5.a) Contacts polisher wash to reduce number of vessels in service o (5.b) Checks Aux Steam aligned to Unit 2 SRO/BOP o (5.c,e) Directs Turbine Watch to align gland sealing steam supply to Aux Steam and close VAC733 o (5.d) Contacts Aux Senior regarding discharge of condensate (current permit likely invalidated by leak)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 11 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 3 Page 9 of 20 Event

Description:

S/G 12 Tube Leak (35 gpm), continued Time Position Applicants Actions or Behavior (OP AP25, "Rapid Load Reduction or Shutdown")

SRO (1.a) Determines runback/programmed ramp is not in progress (may not vocalize, since this ramp is initiated by the crew)

SRO/BOP Starts load reduction (guidance is also on lamicoid pegboard on CC3):

o (1.b) Places MW and IMP feedbacks in service (all on Triconex turbine HMI, CC3) o (1.c,d) Sets load target and ramp rate (expected ~ 10MW/min to 150 MW, but at discretion of Shift Foreman) o (1.e) Pushes GO o (1.f) Contacts Chemistry to advise 15%/hr shutdown rate will be exceeded SRO/ATC (2) Ensures control rods are inserting in AUTO (3) Turns Pressurizer heaters on (CC1)

(4) Checks charging adequate to prevent flashing in the letdown system; may take manual control to ensure adequate flow (CC2)

SRO/BOP (5) Ensures DFWCS is controlling S/G levels in AUTO (MFW control/bypass valves; MFPs all in AUTO) (CC2)(VB3)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 12 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 3 Page 10 of 20 Event

Description:

S/G 12 Tube Leak (35 gpm), continued Time Position Applicants Actions or Behavior (OP AP25, "Rapid Load Reduction or Shutdown")

Note: Boration values described below are representative of the conditions given, but will vary based on the actual ramp rate and target specified by SRO. Total gallons boron required for shutdown is determined from Reactivity Handbook.

SRO/ATC (6) Performs boration (the following guidance is on the boration checklist in the reactivity handbook) o Presses STOP on M/U Ctrl HMI (CC2) o Presses BORATE on HMI o Sets target gallons for boration (expected approx. 2050 gallons for first batch);

verifies batch is reset o Sets boric acid flowrate (expected value 20 gpm) o Presses START, and monitors boration o Once stopped, either returns to AUTO (presses AUTO, then START), or performs additional boration per the Shift Foreman(CC2)

SRO/BOP (7) Checks MFP suction pressure greater than 260 psig (VB3)

SRO/ATC (8) Checks Tave trending to Tref (PPC, CC1)

(9) Checks Pressurizer pressure and level trending to programmed band (PPC, CC2)

SRO If not already completed, reviews T.S. 3.4.13.d, Action B - greater than 150 gpd primary to secondary leakage. Required actions: be in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 in 36 hrs.

Proceed to the next event once ramp commenced, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 13 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 4 Page 11 of 20 Event

Description:

Condenser InLeakage Time Position Applicants Actions or Behavior Observes PK1205 (COND PPS DISCH HRD CATION CONDT'Y HI) alarming and informs the ATC Shift Foreman.

(1) Identifies input 1104 (Cond Pps Disch Header Cation Conductivity Hi) and goes to SRO/ATC section 2.1, General Actions.

SRO/BOP (2.1.1) Contacts Polisher Watch to investigate cause of alarm SRO (2.1.2) Enters OP AP20 "Condenser Tube Leak" (OP AP20 "Condenser Tube Leak")

SRO/BOP Reads NOTE regarding delay time between Control Room readout and realtime values for Secondary Chemistry (1) Determines condensate cation conductivity is greater than 1.0 S/cm (may report units as mhos/cm, which is equivalent) (DDR10, VB3 far right, middle, points 17,18,19) o Directs Polisher Watch to monitor chemistry data and alert control room for adverse trend o Compares DDR values and trend with those reported by Polisher Watch; may contact Chemistry to perform additional sampling o May direct Chemistry to sample Condensate Storage Tank (CST) as possible source of sodium contamination (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 14 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 4 Page 12 of 20 Event

Description:

Condenser InLeakage, continued Time Position Applicants Actions or Behavior (OP AP20 "Condenser Tube Leak", continued)

SRO/BOP Reads NOTE regarding identification of leak location and implementation of compensatory actions.

(2) Determines area of leak (condenser quadrant) (DDR10, VB3 far right, middle) o Identifies point 7 is elevated, indicating leak in condenser outlet, SW quadrant o Requests confirmation of location from Polisher Watch o May direct Chemistry to sample locally SRO/BOP Reads CAUTION regarding requirement to trip Rx if FCV230 (condensate polisher demineralizer bypass valve) goes open for any reason.

(3) Performs actions to prevent bypass of condensate demineralizers o (3.a) Verifies FCV230 closed (VB3, lower right skirt) o (3.b) Directs Turbine Watch to open supply breaker for FCV230 SRO/BOP (4) Monitors Feedwater Cation Conductivity for indications of condensate demin breakthrough; (DDR10, point 32 greater than 0.25 S/cm indicates breakthrough, requiring Rx Trip) (DDR10, VB3 far right, middle)

Note: Ramp adjustment is required if current rate is less than 25 MW/min and power is still greater than 50%

SRO/BOP (5) Evaluates Attachment 4.1,"Condenser Tube Leak Corrective Action Limits" Determines minimum ramp is 25MW/min down to 50% power Changes rate to min of 25 MW/min (CC3, Turbine Control HMI)

SRO/BOP (611) May perform additional actions to minimize secondary contamination (not previously performed as part of AP3) o Takes manual control and closes Condenser Hotwell Reject Valve, LCV12 (VB3, lower right skirt) o Directs field realignment of CWP 11 Auto Reclose and SCW Hx Proceed to the next event once minimum ramp rate establish, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 15 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 5 Page 13 of 20 Event

Description:

S/G 12 Tube Rupture (400 gpm)

Time Position Applicants Actions or Behavior ALL Diagnoses Steam Generator Tube Rupture from the following:

Pressurizer level and pressure lowering (PPC, CC2, VB2)

S/G 12 level rising (PPC, VB3)

Main steam line hirad rising, loops 1 & 2 (RM71 and 72) (PPC, VB2)

SRO/BOP May attempt to isolate letdown (VB2, upper center skirt)

SRO/ATC Initiates manual SI (CC2, far right)

ALL Crew enters EOP E0 on trip/SI actuation and silently performs immediate actions:

Verifies reactor trip (trip bkrs open, rods on bottom, NIs decreasing)

Verifies turbine trip (stop valves closed (CC3 HMI or VB2 RPS indicator lamps)

Checks vital 4kv busses (VB4, vital busses F/G/H have white lights on mimic busses)

Checks if SI actuated (PK0821 ON, also checks VB1 red train lights and/or train equipment to verify both trains actuated)

(EOP E0, Reactor Trip or Safety Injection")

Note: Immediate action steps are reverified by Shift Foreman after first being performed independently by each member of crew SRO/ATC (1) Verifies reactor trip (trip bkrs open, rods on bottom, NIs decreasing) (VB2, CC1)

SRO/ATC (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 16 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 5,6 Page 14 of 20 Event

Description:

S/G 12 Tube Rupture (400 gpm), continued Charging Injection Outlet Valves 8801A/B fail to open on SI (CT)

Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection", continued)

SRO/BOP (3) Checks vital 4kv bus status (VB4, vital busses F/G/H have white lights on mimic busses)

SRO/ATC (4) Checks SI actuated (PK0821 ON, also checks VB1 red train light ON and/or train equipment to verify both trains actuated) o Both trains of SI actuated as indicated by PK0821, SI red light above Monitor Light Box C (VB1), and both trains of SI/RHR pumps running (VB1 skirt)

SRO (5) Directs implementation of App E (usually given to BOP)

Note: Critical task to establish high head ECCS flow prior to exiting EOP E0 requires manually opening of 8801A/B. Action is addressed as part of App E, step 5 alignment verification, but may be addressed as soon as failure is identified. Manual realignment should be communicated to Shift Foreman as part of step 11 status report.

BOP Implements App E (ESF Auto Actions, Secondary and Auxiliaries Status):

(1a) Checks no personnel in Containment (part of turnover; may not voice)

(1b) Announces trip/SI on PA system (2) Checks main generator - tripped (PK1401 ON, output bkrs open, and exciter field bkr open, CC3 right side)

(3 & 4) Verifies Phase A and Containment Vent Isolation complete (VB1, Monitor Light Box B: red lights ON, white lights OFF)

(5) Verifies ESF (SI) actuation complete (SI Portion of Monitor Light Box C: red light ON, white lights some ON);

o Identifies white lights associated with 8801A/B injection valves (failed closed)

• • Manually opens 8801A and/or 8801B and verifies injection flow (VB2, upper left, next to DRPI)

(Critical Task E0D, Establish high head ECCS flow prior to exiting EOP E0) **

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 17 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 5,7,8 Page 15 of 20 Event

Description:

S/G 12 Tube Rupture (400 gpm), continued Main Steam Line Break on S/G 12 inside containment Main Steam Isolation Valves on leads 1 & 2 fail to close in auto, but can be closed manually Time Position Applicants Actions or Behavior (EOP E0, Appendix E, continued)

BOP (6) Verifies Feedwater isolation complete (F.W. Isolation and S.G. Level Portions of Monitor Light Box C: red lights ON, white lights OFF)

(7) Checks containment spray, Phase B - NOT required (Contmt Isol, Phase B portion of Monitor Light Box D: red lights are OFF); may also note containment pressure, while elevated, is well below actuation setpoint)

Note: Based on operator pace through App E., MSLI may not have actuated by time operator reaches procedural step to verify isolation (isolation actuates approximately 2 minutes after the trip). Main Steam Isolation Valves FCV41 and FCV42 (leads 1 & 2) fail to close, but can be manually actuated from VB3. Numerous related indicators and subsequent alarms occur over the course of the scenario, providing the crew ample opportunity to identify and correct the failure.

BOP (8) Checks Main Steamline Isolate complete (Main Steam Isolation portion of Monitor Light Box D: red light ON, white light, some ON) o Identifies white lights associated with FCV41 and FCV42 (failed open) o Manually closes FCV41 and FCV42 (VB3, center left)

Note: Step to control AFW to limit cooldown may have already been completed (E0, step 6 RNO) by other crew members; actions taken in Appendix E should reflect overall mitigation strategy (maintain secondary heat sink while limiting cooldown)

BOP (9) Checks AFW status (AFW Pp 13 is running, TDAFP will start once 2 out of 4 S/G levels falls below 15% (with time delay))

o Determines if TD AFW Pp 11 is needed (if not already running) (VB3, middle center skirt) o Verifies either min of 435 gpm flow (VB3 center) or S/G level > 15% (VB3 center)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 18 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 5 Page 16 of 20 Event

Description:

S/G 12 Tube Rupture (400 gpm), continued Time Position Applicants Actions or Behavior (EOP E0, Appendix E, continued)

BOP (10) Verifies ECCS flows (charging injection (VB2 upper panel left), SI, RHR (both on VB1 upper panel); shuts down CCP 13 (VB2, middle center skirt)

(11) Reports ESF and AFW status to the Shift Foreman (Shift Foreman may direct operator to continue with Appendix E, or redirect to higher priority tasks)

BOP (12 & 13) Checks excess letdown - not in service (8166/8167 closed); turns on aux bldg vent charcoal filter preheater (VB4 lower panel, left side)

(14) Checks secondary systems (MFPs tripped (VB2, green lights ON), stops all but one CB Pp set, takes LCV12 control switch to CONT ONLY. Determines Condenser is NOT available (MSIVs are closed) and directs field operators to break vacuum when turbine is less than 200 rpm (15) Verifies proper operation of Aux Bldg and Control Rm vent systems (VB4 vent status light panel white lights); verifies containment iodine fans secured (VB4, lower panel)

(16 21) Verifies available DGs running normally (VB4, freq (60), volts (120), speed (900)); verifies vital batteries supplied by chargers (charger and bus volts on VB5, upper panel middle/lower area); verifies MSRs reset (CC3 Triconex HMI); throttles RCP seal injection flows to normal (FCV128, to 813 gpm each, CC2); checks PK1104 NOT IN (SFP alarm); notifies Shift Foreman of completion (EOP E0, Reactor Trip or Safety Injection", continued)

SRO/ATC (6) Checks RCS temperature - stable (temps will initially be dropping due to faulted S/G (VB2, upper panel lower area); Throttles AFW as required to control temperature (VB3, lower left skirt)

SRO/ATC (7) Checks Pzr PORVs and Pzr safeties (closed) / PORV block valves (all open); notes elevated tailpipe temps due to containment environment; no sonic flows on safeties/PORVs (VB2 - upper panel, far right); checks Pzr sprays closed (CC2)

SRO/ATC (8) Checks RCP trip criteria (RCS pressure [VB2, PPC] < 1300 psig and SI or ECCS CCPs running, criteria could be met depending on timing of events) (VB1 and VB2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 19 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 7 Page 17 of 20 Event

Description:

MSLB on S/G 12 inside containment (CT)

Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection", continued)

SRO/ATC (9) Checks for faulted S/Gs o Faulted - notes 12 S/G pressure is dropping uncontrollably and/or completely depressurized (PPC, VB3) o Transitions to EOP E2, "Faulted Steam Generator Isolation" (EOP E2, "Faulted Steam Generator Isolation)

SRO Reads three CAUTIONS prior to step 1 SRO/ATC (1) Verifies ALL MSIVs and bypasses are closed (VB3, upper panel, left side)

SRO/ATC (2) Checks for any intact S/G (11, 13, and 14 S/Gs have stable pressures, consistent with the RCS cooldown from the 12 S/G); continues in E2 SRO/ATC (3) Identifies 12 S/G as faulted (VB3, pressure is still dropping in uncontrolled manner, or completely depressurized at this point)

SRO/BOP (4) Implements Appendix HH, "Isolate Faulted Steam Generator" (see page 17) (CT)

SRO/ATC (5) Checks CST level > 10% (VB3, upper panel, center area meter and recorders)

SRO/ATC (6) Checks for ruptured S/Gs o Ruptured - notes valid alarm on PK1106, PK1117, or PK1118 (RM23 is failed high) and upward trend on RM19, 15/15R, and RM72 (recorders on VB2 (and PPC))

o Transitions to EOP E3, "Stem Generator Tube Rupture" (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 20 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 7 Page 18 of 20 Event

Description:

MSLB on S/G 12 inside containment (CT)

Time Position Applicants Actions or Behavior (EOP E2, "Appendix HH, "Isolate Faulted Steam Generator")

BOLD substeps below must be assigned prior to exit from EOP E2 (Critical Task E2A: Isolation of Faulted S/G initiated before transition out of EOP E2) **

BOP Reads CAUTION regarding TDAFW as only source of feedflow prior to step 1 (1) Isolates faulted S/G 12

a. Verifies MFIV FCV439 closed (all of these controls on VB3, lower left) (already closed)

b. Verifies SGBD valves FCV761, 154, and 248 closed (IC, OC, and sample) (already closed)

c. Verifies S/G 12 10% steam dump closed (PCV20) (isolated as part of setup)

• • d. Closes TDAFP AFW LCV107 Closes MDAFP AFW LCV111 for 12 S/G to isolate AFW

• • e. Closes FCV37 to isolate steam from 12 S/G to TDAFP

f. Verifies AFW flow to at least one intact S/G (VB3, upper panel, center area meters)

g. Informs Shift Foreman S/G 12 isolation is complete BOP (2) Removes WR Thot input to SCMM for loop 2 (behind boards, PAMS panel behind VB3)

(a) Goes to PAM4 panel (b) Presses Configuration Summary (c) Presses Failed S/G (d) Presses the PB for the Thot to be disabled (2)

(e) Presses Disable Loop 2 (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 21 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 5 Page 19 of 20 Event

Description:

S/G 12 Tube Rupture (400 gpm), continued Time Position Applicants Actions or Behavior (EOP E3, "Steam Generator Tube Rupture)

SRO/ATC (1) Checks if RCPs should be stopped (probably already stopped in E0) (VB2)

SRO/ATC (2) Identifies S/G 12 as ruptured (RM72 in alarm, previous indications of rising level without feed during E0)

SRO/BOP (3) Implements Appendix FF to isolate ruptured S/G 12 (EOP E3, "Appendix FF, "Isolate Faulted Steam Generator")

Note: Majority of actions will have already been completed as part of (EOP E2, "Appendix HH, "Isolate Faulted Steam Generator")

BOP Reads CAUTION regarding TDAFW as only source of feedflow prior to step 1 (1) Reads step to insure 10% steam dump controller in AUTO and set to 86.7%; notes valves is OOS and isolated from initial conditions.

(2) Checks S/G 12 10% steam dump valve closed (PCV20) (VB3)

(3) Verifies S/G 12 MSIV and bypass () valves closed (VB3)

(4) Verifies S/G 12 supply to TD AFW Pp (FCV37) closed (VB3, skirt)

(5) Verifies S/G 12 SGBD valves (FCV154 and FCV248) closed (VB3, lower left skirt)

(6) Verifies S/G 12 is isolated from intact S/G (S/G 12 MSIV and MSIV Bypass are both closed as are all intact S/G MSIV and MSIV Bypasses)

(7) Informs Shift Foreman S/G 12 isolation is complete BOP (8) Verifies removal of WR Thot input to SCMM for loop 2 (behind boards, PAMS panel behind VB3) o Goes to PAM4 panel o Checks Loop 2 Thot Disabled (continued on next page)

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 22 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 3 Event No.: 5 Page 20 of 20 Event

Description:

S/G 12 Tube Rupture (400 gpm), continued Time Position Applicants Actions or Behavior (EOP E3, "Appendix FF, "Isolate Faulted Steam Generator")

BOP (9) Prepares for S/G sampling (a) Notifies Chemistry to sample S/G using CAP AP1 (b) Verifies SI and Phase A Isolation are reset (VB1, center)

(c) Verifies instrument air to containment (FCV584) is open (VB4, lower left skirt)

(d) Opens S/G blowdown isolation valves inside containment if contacted by Chemistry for sampling (EOP E3, "Steam Generator Tube Rupture, continued)

SRO/ATC Reads CAUTION regarding maintaining isolation of Faulted/Ruptured S/G (do not feed)

(4.a) Notes ruptured S/G level is less than 15% [25% if still in adverse containment conditions]

(4.a RNO) Applies CAUTION and does NOT apply RNO action to feed ruptured S/G SRO/ATC (5) Observes ruptured S/G is LESS THAN 225 psig; transitions to EOP ECA3.1, "SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED" per RNO Terminate the scenario once transition is made to ECA 3.1 , per the Lead Examiner.

• • Critical Task L121 NRC Sim Exam 03 r1.doc Page 23 of 32 Rev 1

Appendix D (rev 9) Required Operator Actions Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No: 1 Op-Test No: L121 NRC Examiners: Operators:

Initial Conditions: 10E-8 with AFW in service, MOL, 1660 ppm boron Turnover: At OP L-2, step 6.1.25, ready to raise power to 2%. Continue to raise power, and stabilize at 2%.

Event Malf Event Event No No. Type* Description 1 N/A R(ATC) Raise reactor power from 10E-8 to 2% per OP L-2, sec 6.1 2 XMT_RCS6_3 SRO PT-403, RCS Wide Range Pressure Transmitter, fails low (TS 3.3.3.A, ECG 7.8) (Used for SRO TS/ECG Only) 3 PMP_CCW2_MTRF C (BOP, Component Cooling Water Pump 1-2 (CCW Pp 1-2) overcurrent trip.

SRO) (AP-11; TS 3.7.7.A) 4 PMP_TUR2 C (BOP, Thermal overload of AC Bearing Oil Pump (AP-29).

OVERLOAD_DEV_FAIL SRO) 5 XMT_MSS1_3 I (SRO, PT-507, Steam Generator Header Pressure Transmitter, slow failure low ATC) causing Group I dumps to close. (AP-5) 6 MAL_RCS3A 0.06 C (ALL) RCS leak ramps in over 1 minute. Leak is within the capacity of charging (60 gpm), but requires second pump to be started. (AP-1, TS 3.4.13.A) 7 MAL_RCS3A 0.75 M (ALL) 700 gpm SBLOCA requiring Safety Injection (SI) - (Auto SI failed; manual SI is required CT).

8 MAL_PPL5A/B M (ALL) ATWS, Both manual trip and 13D/E fail.

9 PMP_CVC1 C (BOP) On SI, running CCPs trip on OC, standby pump fail to autostart - CT )

PMP_CVC2

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L121 NRC ES-D-1-01 r2.doc Page 1 of 3 Rev 2

Appendix D (rev 9) Required Operator Actions Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301-4) Actual Attributes

1. Total malfunctions (5-8) (Events 2,3,4,5,6,7,8,9) 8

2. Malfunctions after EOP entry (1-2) (Events 8&9) 2

3. Abnormal events (2-4) (AP-11,29,5,1) 4

4. Major transients (1-2) (Events 7&8) 2

5. EOPs entered/requiring substantive actions (1-2) (E-1) 1

6. EOP contingencies requiring substantive actions (0-2) (FR-S.1) 1

7. Critical tasks (2-3)(See Scenario Summary) 2 L121 NRC ES-D-1-01 r2.doc Page 2 of 3 Rev 2

SCENARIO

SUMMARY

- NRC #1

1. Control rods are used to raise power from 10E-8 Amps (IR) to 2% per OP L-2, Hot Standby to Startup Mode, step 6.1.25.

2. PT-403, RCS Wide Range Pressure Transmitter, fails low. Crew responds to PK05-07, Subcooling Margin Lo/Lo-Lo and PK05-09, RVLIS Lo Lvl RVLIS/SCMM Trouble and identifies affected instrumentation. Shift Foreman addresses TS 3.3.3.A, Post Accident Monitoring Instrumentation and ECG 7.8, Accident Monitoring Instrumentation.

3. Component Cooling Water Pump CCW 1-2 trips on overcurrent and CCW 1-3 must be started manually (auto-start blocked) per direction in PK01-09 or as directed by OP AP-11, Malfunction of Component Cooling Water System, Section A. T.S. 3.7.7, Vital Component Cooling Water (CCW) System, is entered for one loop of CCW inoperable.

4. AC Lube Oil Pump trips on thermal overload. Crew responds to PK12-16, Turbine Lube Oil System and is directed to OP AP-29, Main Turbine Malfunction to start the DC Backup Pump (autostart failed).

5. PT-507, Steam Generator Header Pressure Transmitter, slowly fails low causing Group I dumps to close.

Crew diagnoses the failure and takes manual control of Hand Controller HC-507. OP AP-5, Malfunction of Eagle 21 Protection or Control Channel is used to address the failure and return primary and secondary to normal bands.

6. 60 gpm RCS leak develops on Loop 1, ramping in over 1 minute. Crew evaluates plant symptoms and enters OP AP-1, Excessive Reactor Coolant System Leakage, which directs starting of a second charging pump to maintain pressurizer level. Shift Foreman enters T.S. 3.4.13.A, RCS Operational Leakage based on the estimated leak size.

7. 700 gpm SBLOCA on Loop 1 cold leg. Auto Safety Injection (SI) fails to actuate, requiring manual SI (Critical Task E-0D: Manually initiate Safety Injection before transitioning to any E-1, E-2, or E-3 series procedure)**.

8. Crews attempt to trip reactor from the control room is unsuccessful. Shift Foreman enters EOP E-0 (Reactor Trip or Safety Injection) and transitions to EOP FR-S.1, Response to Nuclear Power Generation

/ ATWS.

9. On SI, running CCPs trip on overcurrent. Remaining ECCS CCP fails to autostart, but can be started manually. (Critical Task E-0I: Establish flow from at least one high-head ECCS pump before transition out of E-0)**.

10. After addressing ATWS condition, crew transitions through E-0 (Reactor Trip or Safety Injection) and E-1 (Loss of Reactor or Secondary Coolant) to E-1.2 (Post LOCA Cooldown and Depressurization).

The scenario is terminated at entry into E-1.2, Post LOCA Cooldown and Depressurization.

L121 NRC ES-D-1-01 r2.doc Page 3 of 3 Rev 2

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 1 Page 1 of 30 Event

Description:

Raise reactor power from 10E8 to 2%

Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.

(OP L2, Secondary Plant Startup, starting at step 6.1.26)

SRO Reads NOTE regarding PK0403 (Tave deviation from Tref) prior to step 6.1.26 ATC (6.1.26) Slowly raises power to 2% by pulling control rods, observing 3 step pull and wait administrative limit.

SRO Reads NOTE regarding indications for point of adding heat Lowering startup rate Rising steam dump demand, pressurizer level, Tave SRO Provides reactivity oversight while raising power.

ATC (6.1.26.a) Verifies proper plant response at point of adding heat:

Steam dumps begin to modulate AFW flow rises to maintain SG level at programmed level (68%)

ATC (6.1.26.b) Continuously monitors Tave, T, and NI response while raising power.

ATC Stabilizes power at approximately 2% reactor power.

SRO/BOP (6.1.27) Places RM2 High Alarm Setpoint select switch in the MODES 1&6 position.

Proceed to next event after RM2 High Alarm Setpoint select switch set to Mode 1&6 position, per lead examiner.

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 4 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 2 Page 2 of 30 Event

Description:

PT403, RCS Wide Range Pressure Transmitter, Fails Low Time Position Applicants Actions or Behavior Note: AR PK0507, SUBCOOLING MARGIN LO/LOLO and AR PK0509, RVLIS LO LVL, RVLIS/SCMM TROUBLE, both alarm. SRO may use either PK to address the issue provided all applicable TS and ECGs are identified.

All Diagnoses PT403 has failed high from one or more of the following (VB2):

PK0507, SUBCOOLING MARGIN LO/LOLO PK0509, RVLIS LO LVL, RVLIS/SCMM TROUBLE VB3 Indications:

PR403, LOOP 4 HOT LEG PRESS - WIDE RANGE = 0 psig (bottom of scale low)

YI31, SUBCOOL MARGIN MON - TRAIN B = 40oF (bottom of scale low)

If AR PK0507 is entered; otherwise this section is N/A SRO/ATC (1.0) Identifies inputs 1152 (Subcooled Mon Lo Margin From RVLIS A or B) and 1600 (Subcooled Mon LoLo Margin from RVLIS Train B) and goes to section 2.1 for General Actions SRO Reads NOTE regarding P10 prior to step 2.1 SRO/BOP (2.1.1) Observes diverse RCS pressure and temperature indications and determines subcooled margin is NOT low. Identifies PR403 reading bottom of scale as indication of failed instrument (PPC, CC1, CC2, VB2)

SRO (2.1.2) Determines RCS is NOT approaching a saturated condition and continues to next step ALL (2.1.3) Confirms specific instrument failure as PT403:

o (2.1.4.a) Determines failure is associated with RVLIS/SCMM, Train B o (2.1.4.b) Checks trainspecific subcooling indications to confirm failure (PPC, SPDS Train B, YI31 on VB2, PAM4 Display - may use any)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 5 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 2 Page 3 of 30 Event

Description:

PT403, RCS Wide Range Pressure Transmitter, Fails Low (cont)

Time Position Applicants Actions or Behavior (AR PK0507, continued)

SRO Reads NOTE regarding possible Thermocouple Monitoring System failure (PK0515) and determines it doesnt apply SRO (2.1.3) Confirms specific instrument failure as PT403 (continued):

o (2.1.3.c) Notes PK0515 is NOT in alarm and continues to next step o (2.1.3.d) References AP5, Malfunction of Protection or Control Channel as time permits (described later in this section)

SRO (2.1.4) Reviews ECG 7.8, Accident Monitoring Instrumentation for applicability.

Determines LCO is meet (required number of channels and minimum channels operable =1)

If AR PK0509 is entered; otherwise this section is N/A SRO/ATC (1.0) Identifies inputs 1208 (Reactor Vessel Level Lo Train B) and 1209 (RVLIS/SCMM Trouble Train B); goes to section 2.1 for General Actions SRO Reads NOTE regarding O/E on erroneous RVLIS low level alarms prior to step 2.1.1 SRO/BOP (2.1.1) Checks RVLIS on PAM 4 and determines low subcooled margin reading is causing the alarm (PAM4 is located in area behind vertical boards)

SRO (2.1.2) Determines RVLIS is NOT low and continues to next step SRO/BOP (2.1.3) Observes diverse RCS pressure and temperature indications and determines subcooled margin is NOT low (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 6 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 2 Page 4 of 30 Event

Description:

PT403, RCS Wide Range Pressure Transmitter, Fails Low (cont)

Time Position Applicants Actions or Behavior (AR PK0509, continued)

ALL (2.1.4) Identifies specific instrument failure as PT403:

o (2.1.4.a) Determines failure is associated with RVLIS/SCMM, Train B o (2.1.4.b) Checks PAM4 (Train B) I/O Summary Screen inputs and identifies failed pressure transmitter (PAM4 is located in area behind vertical boards)

SRO (2.1.5) Enters TS 3.3.3.A,Post Accident Monitoring Instrumentation for inoperable channel associated with RCS Pressure (Wide Range) and Reactor Vessel Level Indicating System (RVLIS)functions. Required action: restore to operable status within 30 days If OP AP5 is referenced; otherwise this section is N/A Note: PT403 provides no controlling functions. Shift Foreman may go directly to OP AP5, Attachment 4.1 to identify / confirm previous identification of applicable Tech Specs and ECGs.

SRO Enters TS 3.3.3.A,Post Accident Monitoring Instrumentation for inoperable channel associated with RCS Pressure (Wide Range) and Reactor Vessel Level Indicating System (RVLIS)functions. Required action: restore to operable status within 30 days.

Reviews ECG 7.8, Accident Monitoring Instrumentation for applicability. Determines LCO is meet (required number of channels and minimum channels operable =1)

SRO/BOP Places Out of Service stickers on the following affected equipment:

PR403 (VB2)

RVLIS TRAIN B (PAM 1, behind VB5)

Subcooled Margin Monitor (PAM4, behind VB3)

Proceed to the next event once Tech Specs have been addressed per lead examiner

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 7 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 3 Page 5 of 30 Event

Description:

Component Cooling Water Pump 12 Overcurrent Trip Time Position Applicants Actions or Behavior ATC Observes PK0109 (CCW Pumps) alarming and informs the Shift Foreman.

ATC/BOP Observes the CCW Pp 12 has a blue OC light illuminated (VB1, left side), and reports condition to Shift Foreman.

Note: The Shift Foreman may implement AR PK0109, or enter OP AP11, "Malfunction of Component Cooling Water System "

(If AR PK0109 is entered; otherwise this section is N/A)

SRO/ATC (1.0) Identifies input 432 (CCW Pps OC Trip) and goes to section 2.4 SRO/BOP (2.4.1) Determines standby CCW pump did not start; (BOP) takes CCW Pp 13 to MAN and starts pump SRO/BOP (2.4.2) Confirms blue indicating light for overcurrent trip is illuminated for CCW Pp 12 (VB1)

SRO (2.4.3) Notes standby CCW Pp 13 has been started and continues to next step SRO/BOP (2.4.4) Dispatches operator to walkdown 4kV Bus G SRO (2.4.4a,b,c) Recognizes breaker reclose attempt is not appropriate (may refer to Ops Policy B2). Directs maintenance to investigate (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 8 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 3 Page 6 of 30 Event

Description:

Component Cooling Water Pump 12 Overcurrent Trip (cont)

Time Position Applicants Actions or Behavior (AR PK0109, continued)

SRO (2.4.5) Enters Tech Spec 3.7.7.A - One vital CCW loop inoperable. Required actions:

restore vital loop to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Notes applicability of LCO 3.0.4 (entry into Mode 1 is not allowed until 3.7.7.A exited)

(If OP AP11, Malfunction of Component Cooling Water System, is entered; otherwise this section is N/A)

SRO Determines SECTION A, LOSS OF A CCW PUMP/HIGH CCW SYSTEM TEMP, is the appropriate section SRO/BOP (1) Ensures at least two CCW pumps running; (BOP) takes CCW Pp 13 to MAN and starts it. (VB1, far left side)

SRO/BOP (2) Checks CCW HX outlet temperature is normal (VB1) (It is)

SRO Enters Tech Spec 3.7.7.A - One vital CCW loop inoperable. Required actions: restore vital loop to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Proceed to the next event once standby CCW pump has been started and Tech Specs have been addressed per lead examiner.

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 9 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 4 Page 7 of 30 Event

Description:

AC Lube Oil pump Trips on Thermal Overload Time Position Applicants Actions or Behavior Note: PK1216, Turbine Lube Oil System, will come in prior to PK1206, Turbine. The SRO may elect to follow guidance from either annunciator response as both will direct the crew to OP AP29, Main Turbine Malfunction for problem resolution.

All Diagnoses AC Lube Oil Pump trip from one or more of the following :

VB3 Indications:

AR PK1216, TURBINE LUBE OIL SYSTEM and AR PK1206, TURBINE.

VB4 Indications:

Main Turbine Turning Gear - Supervisory Screen indicates 0 RPM, Turning Gear amps =

0, MN TURB TURN GEAR, MODE SELECT indicator is GREEN (off)

AC Bearing Oil status light indicates pump is not running; PI846, MN TURB BRG OIL PRESS = 0 psig Note: Emergency DC Bearing Oil Pump has 10 psig autostart setpoint. Following appropriate diagnostics, crew may manually start pump prior to procedural direction described in the following steps.

(If AR PK1216 is entered; otherwise this section is N/A)

SRO/ATC (1.0) Identifies inputs 719 (High or low bearing oil header pressure) and 726 (Turb Gen Brg Oil Pp 11 AC OC or UV) and goes to section 2.1 (General Actions)

BOP (2.1.1) Determines Emergency DC Bearing Oil Pump did not automatically start; may start pump manually (VB4, lower left skirt)

SRO (2.1.2) Notes PK0921 is NOT in alarm and continues to next step SRO (2.1.3) Transitions to OP AP29, "Main Turbine Malfunction" (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 10 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 4 Page 8 of 30 Event

Description:

AC Lube Oil pump Trips on Thermal Overload Time Position Applicants Actions or Behavior Note: If Emergency DC Bearing Oil Pump has been started, PK1206 will clear.

(If AR PK1206 is entered; otherwise this section is N/A)

SRO/ATC (1.0) Identifies input 697 (Main Turb Lo Speed and Turning Gear Selected) and goes to section 2.1 (General Actions)

SRO (2.1.1 & 2.1.2) Determines input condition is not applicable and continues to next step SRO (2.1.3) Transitions to OP AP29, "Main Turbine Malfunction" (OP AP29, Main Turbine Malfunction")

SRO (1) Checks AR PK1211 TURBINE TRIP is OFF (it is)

Note: If crew has not yet started Emergency DC Bearing Oil Pump, AR PK1206 will still be ON. Crew should recognize this as a symptom, not a cause and proceed on to appropriate input.

SRO (2) Checks AR PK1206 TURBINE is OFF. (status dependent on prior actions; see note above)

SRO (3) Checks AR PK1216 TURBINE LUBE OIL SYSTEM is ON; continues to Appendix 3.2 (OP AP29, Appendix 3.2 - TURBINE LUBE OIL SYSTEM (PK1216) )

Note: If crew Emergency DC Bearing Oil Pump was started, step is N/A as input will have cleared. SRO may elect to review Appendix 3.2 to verify all required actions have been completed.

SRO (3) Responds to input 719 (PPC Lube Oil Pressure Alarm)

SRO/BOP (3.1) Determines lube oil pressure is low (VB4, PI846)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 11 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 4 Page 9 of 30 Event

Description:

AC Lube Oil pump Trips on Thermal Overload Time Position Applicants Actions or Behavior (OP AP29, Appendix 3.2 , continued)

SRO/BOP (3.2.1) Starts Emergency DC Bearing Oil pump manually (VB4, lower left skirt)

SRO/BOP (3.2.2) Checks lube oil pressure has returned to normal band (VB4, PI846) (It has)

SRO (4) Responds to input 724 (Turbine Generator Emergency Bearing Oil Pump Running)

SRO/BOP (4.1) Checks bearing oil pressure greater than 20 psig (VB4, PI846). (It is reading slightly over 20 psig)

SRO (5) Responds to input 726 (AC or DC Bearing Oil Pump OC or UV)

SRO (5.1) Contacts maintenance to determine cause of pump trip Proceed to the next event when once Lube Oil Pressure restored per Lead Examiner

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 12 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 5 Page 10 of 30 Event

Description:

Steam Header Pressure Transmitter PT507 Slow Failure Low Time Position Applicants Actions or Behavior All Diagnoses PT507 failed low from one or more of the following:

CC2 Indications:

Tave, Pressurizer level, Pressurizer pressure rising CC3 Indications:

HC507 demand lowers to 0%

VB3 Indications:

Group I 40% Steam Dump (PCV1, 3, 6, 8) - go closed Dump Demand (UI500) lowers to 0%.

SRO/ATC Takes manual control of HC507 and reopens Group I dump valves to stabilize plant SRO Enters OP AP5, "Malfunction of Eagle21 Protection or Control Channel" (OP AP5, Malfunction of Eagle21 Protection or Control Channel)

SRO/ATC (1) Confirms that Steam Generator pressure was NOT controlling properly in Auto and has been taken to manual (CC3, HC507). Directs Tave be returned to prior steadystate value SRO/BOP (2) Determines that the failure is not Eagle21 related (PK0601 and PK0603 are OFF)

SRO/ATC (3) Determines failure is not associated with a T channel (VB2)

SRO (4) Verifies steam dumps are not open as result of instrument failure or spurious actuation. (Dumps SHOULD be open to maintain temperature for current 2% power conditions. Shift Foreman SHOULD NOT enter RESPONSE NOT OBTAINED column)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 13 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 5 Page 11 of 30 Event

Description:

Steam Header Pressure Transmitter PT507 Slow Failure Low Time Position Applicants Actions or Behavior (OP AP5, Malfunction of Eagle21 Protection or Control Channel, cont.)

SRO (5) Notifies I&C of the PT507 failure, as time permits SRO Reads CAUTION prior to step 6 SRO (6) Notes requirements to take channel OOS prior to maintenance SRO/BOP (7) Places Outof -Service (OOS) stickers on affected indicators:

o May reference Attachment 4.1 to verify there are no Reactor Trip or Emergency Safeguard Bistable channels that must be tripped per Tech Specs.

o May review Attachment 4.2 for PT507 control functions and indications; places OOS sticker on PR507 (VB3).

Proceed to the next event when crew has stabilized temperature, per the lead examiner.

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 14 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 12 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg Time Position Applicants Actions or Behavior ALL Diagnoses RCS leak from one or more of the following:

Drain and/or Sump high level alarms (PK0117, PK1501)

Pzr level lowering (PPC, CC2 recorder, VB2 meters)

Pzr level high; charging flow demand and/or low level deviation alarms (PK0521)

Containment parameters slowly rising (temp, press) (PPC, VB1 recorder, PAMS panels)

Note: Leak ramps in over 1 minute. The crew may raise charging by opening FCV128 and adjusting HCV142 (CC2) in order to maintain pressurizer level prior to entering OP AP1, "Excess RCS Leakage".

SRO Enters OP AP1, "Excess RCS Leakage" (OP AP1, Excess RCS Leakage)

SRO/ATC (1) Determines charging flow and/or pressurizer level NOT normal o Charging flow is elevated and pressurizer level is slowly lowering (CC2)

(1) Adjusts charging and seal flow to maintain pressurizer level o Adjusts seal flows using HCV142 (CC2) to maintain 813 gpm o May raise charging in manual using master level controller (HC459D)(CC2) or flow controller (FCV128)(CC2)

Note: Monitoring Pressurizer level and charging flow NORMAL is a Continuous Action. Associated RNO steps are performed when crew reports applicable conditions exist (i.e. unable to maintain pressurizer level).

SRO/ATC (1) Determines pressurizer level is still lowering (Continuous Action to Monitor)

SRO/BOP (1 RNO) Starts second charging pump (VB2, Lower middle skirt)

(1 RNO) May isolate letdown as pressurizer level continues to drop o Closes 8149C, and closes LCV459/460 (VB2, upper middle skirt)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 15 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 13 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg (Continued)

Time Position Applicants Actions or Behavior (OP AP1, Excess RCS Leakage, continued)

ATC (1 RNO) Checks for continuing decrease in pressurizer level o Readjusts charging and seal flow (CC1) o Determines pressurizer level is stable (PPC, VB2, CC2) (Continuous Action to Monitor)

SRO/ATC (2) Checks RCS pressure greater than 2210 psig and stable or rising (VB2) ( 22202250 psig)

SRO/ATC (3) Determines CVCS Makeup can keep up with leak o Makeup Control is in AUTO (CC2) o VCT Level is being maintained within the control band (PPC, VB2 RCDR4 just below DRPI) o Continuous Action to Monitor VCT Level Note: Step (4) actions are directed at identifying and isolating the leak.

SRO/BOP (4.a) Rules out Seal Table leak o RE7 not in alarm(PPC) o No audible alarm from MIDS panel (back of VBs)

SRO/BOP (4.b) Rules out S/G Tube Leak o Main Steam Line Rad Monitors RM71/72/73/74 not in alarm (VB2/PPC) o SJAE Rad Monitor RM15/15R not in alarm (VB2/PPC) o S/G Blowdown Rad Monitor RM23 not in alarm (VB2/PPC) o S/G sample activity RM19 not in alarm (VB2/PPC) o PK1106/17/18 are all out (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 16 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 14 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg (Continued)

Time Position Applicants Actions or Behavior (OP AP1, Excess RCS Leakage, continued)

SRO/BOP (4.c) Rules out RCS inleakage to CCW o CCW Surge Tank Pressure is not in alarm (PK0114) o CCW Surge Tank Level is stable (VB1, upper left just below Monitor Light Box B) o CCW Rad Monitors RM17A/B not in alarm (PPC) (PK1121) o CCW surge tank vent, RCV16, remains open (VB1, lower left)

SRO/BOP (4.d) Rules out pressurizer steam space leak through safeties and PORVs o Pressurizer safety valves and PORVs closed (VB2, upper right panel) o PORV tailpipe temperature is less than 200oF (TI463: VB2, upper right panel)

SRO/BOP (4.e) Notes no indications (indicator or alarm) of reactor vessel flange leakage (VB2 indicator and PK1102 alarm)

SRO/BOP (4.f) Observes that RCP seal leakage is normal (VB2, PPC)

SRO/BOP (4.g) Notes no indication of RCS valve packing leakage (PK0508 alarm)

ALL (4.h) Observes several containment environmental indicators - NOT normal o CFCU drip pan drain level in alarm (PK0117) o Containment sump and reactor cavity sump levels rising (PAM1) o Containment radiation monitors RM11 and RM12 trending upward (PPC) o Containment air temperature/pressure may be slightly elevated (VB1, upper left)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 17 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 15 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg (Continued)

Time Position Applicants Actions or Behavior (OP AP1, Excess RCS Leakage, continued)

SRO/BOP (4.h.1 RNO) Contacts Chemistry to sample Reactor cavity samples for increased activity SRO (4.h.1 RNO) Considers making Containment entry to pinpoint sources of RCS leak Note 1: Following step performed if crew diagnostics has not ruled out CVCS leak inside Containment.

Note 2: Letdown isolation may have been completed earlier as part of step 1 RNO, continuous action.

SRO/BOP (4.h.3.ab RNO) Isolates letdown (VB2, upper skirt) o Closes 8149A, B, and C o Closes LCV459 and 460 (4.h.3.c RNO) Isolates charging (VB2, lower skirt) o Closes 8107 and 8108 Note: Performed if letdown/charging isolated in previous step, else, N/A.

SRO/ATC Throttles back charging to stabilize Pressurizer level (CC2)

Reestimates leakrate by throttling FCV128 for flow and maintaining RCP seals 813 gpm using HCV142 (CC2)

Determines leak was not isolated If TS has already been addressed, proceed to the next event once crew determines leak is not isolated, per the lead examiner, else continue to next page

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 18 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 16 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg (Continued)

Time Position Applicants Actions or Behavior (OP AP1, Excess RCS Leakage, continued)

Note: If isolated, charging and/or letdown may be placed back in service (as time permits).

SRO/BOP (5.a RNO) Opens 8107 and 8108 (charging header isolation valves) (VB2)

SRO/ATC (4.h.1 RNO) Throttles charging to control pressurizer level (CC2)

Note: If directed to restore letdown, board operators will implement OP B1A:XII, Section 6.2, otherwise section is N/A (continue on next page).

BOP (6.2.2) Ensures adequate pressurizer level o Checks pressurizer level greater than 17% (VB2 upper right, PPC) o Checks PK0521, low level alarm input (544) NOT in o Checks PK0421, high HX room temp (1161) NOT in (6.2.3) Places TCV130 in manual and adjusts to 35%40% demand (VB2, lower middle).

(6.2.4) Ensures letdown isolation valve 8152 is open (VB2, upper middle skirt)

(6.2.5.6) Places letdown back pressure control valve, PCV135, in manual and opens to 50% (VB2, lower middle)

(6.2.7) Opens letdown isolation valves LCV459 and LCV460 (VB2, middle upper skirt)

ATC (6.2.810) Checks FCV128 in manual and raises charging to 87 gpm while maintaining RCP seal injection flow to between 8 GPM and 13 GPM per RCP using HCV142 (CC2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 19 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 17 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg (Continued)

Time Position Applicants Actions or Behavior (OP AP1, Excess RCS Leakage, letdown restoration (OP B1A:XII) continued)

BOP Reads CAUTION prior to step 6.2.11 regarding high letdown temperature and the potential for lifting RV8117.

(6.2.1216) While monitoring PI135 (VB2, upper middle) o Opens letdown orifice isolation valve 8149C to establish flow (VB2, upper middle skirt) o Adjusts PCV135 to control at 350 psig (VB2, lower middle) o Checks letdown flow and pressure stable (approximately 75 gpm with pressure less than 400 psig) (VB2, upper middle) o Returns PCV135controller to AUTO o Checks RV8117 tailpipe temperature to verify relief valve did not lift (TI129, VB2 middle)

ATC (6.2.18) Adjusts FCV128 to return pressurizer level on reference (CC2)

BOP (6.2.20,21) Adjusts TCV130 to maintain normal letdown temperature, then returns controller to AUTO (VB2, lower middle)

(remainder of OP AP1 continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 20 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 6 Page 18 of 30 Event

Description:

60 gpm RCS Leak - Loop 1 Cold Leg (Continued)

Time Position Applicants Actions or Behavior (OP AP1, Excess RCS Leakage, continued from page 16)

Note: Leak size estimate and entry into TS may have been performed earlier at SRO's discretion .

SRO/ATC (5) Estimates leak size (STP R10C and/or available indications)

SRO (5 RNO) Compares leak estimate with T.S. 3.4.13 limits o Enters Tech Spec 3.4.13.A - RCS operational leakage not within limits for reasons other than pressure boundary leakage or primary to secondary leakage.. Required actions: 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 /> Proceed to the next event once TS addressed, per the lead examiner.

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 21 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 7,8,9 Page 19 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 Running Charging Pumps trip on SI, Autostart Fails (CT)

ATWS, Both manual and 13D/E Fail to Open Time Position Applicants Actions or Behavior ALL Diagnoses change in RCS leak from one or more of the following:

Pzr level dropping rapidly (PPC, CC2 recorder, VB2 meters)

Pzr pressure dropping (PPC, CC2 recorder, VB2 meters)

Containment parameters rising (temp, press) (PPC, VB1 recorder, PAMS panels)

Increased rate of change on sump levels (PAMS panel)

Note: Leak ramps in over 1 minute. If not previously done, crew may attempt to isolate letdown prior to initiating a manual Safety Injection (SI).

SRO/ATC ** Initiates manual SI (CC2, far right)

(Critical Task E0D to manually initiate Safety Injection before transitioning to any E1, E2, or E3 series procedure) **

(EOP E0, Reactor Trip or Safety Injection")

Note: Attempts to manually trip the reactor may be done prior to entry into EOP E0 or as part of E0, step 1 RNO.

ALL Performs immediate actions:

(1) Ensure reactor trip:

o Identifies reactor is NOT tripped based on the following:

Rx Trip breakers did NOT open (VB2)

NIs are NOT lowering (CC1)

Rod bottom lights are NOT lit(VB2); moves to step 1 RNO (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 22 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 8 Page 20 of 30 Event

Description:

ATWS, Both manual and 13D/E Fail to Open (Continued)

Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection", continued)

ATC Attempts trip using manual switch (CC1 or VB2)

BOP Notes that manual trip already attempted (or may retry manual reactor trip VB2)

Observes that reactor is still critical (same indications as when trip attempted)

Opens breakers for busses 13D and 13E (VB5, lower panel 480 vac bus breakers) to de energize the rod drive MGs; breakers will not open May dispatch operator to open reactor trip breakers locally SRO Notes reactor is still not tripped. Verifies that attempt to manually open 13D/E was unsuccessful and transitions to EOP FRS.1 (EOP FRS1, "Response to Nuclear Power Generation / ATWS")

SRO/ATC (1) Inserts control rods(CC1); SRO directs local opening of RTA/RTB. (May have already been directed by BOP)

SRO/BOP (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)

SRO/BOP (3) Checks AFW status

a. Both MDAFPs running (VB3, left skirt)

b. TDAFP is off and may be started ( VB3, center skirt)

SRO Reads CAUTION prior to step 4.a regarding Main Feed Pumps tripping on SI; SI is already in and Main Feed Pumps are tripped (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 23 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 8 Page 21 of 30 Event

Description:

ATWS, Both manual and 13D/E Fail to Open (Continued)

Time Position Applicants Actions or Behavior (EOP FRS1, "Response to Nuclear Power Generation / ATWS", continued)

Note 1: Valves are already aligned for Emergency Boration as result of SI, however CCP 13 and the running ECCS charging pump (started in Event 6 as part of OP AP1) tripped just after the SI; the remaining ECCS CCP failed to autostart.

Note 2: The Critical Task to start ECCS CCPs (Event #9) is NOT associated with establishing Emergency Boration flow to the RCS since power is < 5% based on initial plant conditions. Criteria to manually start ECCS CCPs is defined by DCPP Critical Task Identification Number E0I, and is associated with a SBLOCA where RCS pressure is below highhead ECCS pump shutoff head and both highhead ECCS CCPs failed to start automatically. Details for this Critical Task can be found on page 23.

SRO/BOP (4.a) Checks Emergency Boration initiated:

1. 8805A OR 8805B OPEN (VB2center skirt; both are open)

2. LCV112 B OR LCV112C CLOSED (VB2center skirt; both are closed)

3. Verifies AT LEAST 90 GPM charging flow (charging injection flow: VB2just left of DRPI)

Manually starts available ECCS CCP (CCP1 1 or CCP 12 (if failed autostart not previously identified) (VB2 - center skirt)

Checks for adequate flow SRO/BOP (4.b) Checks pressurizer pressure less than 2335 PSIG (VB2, upper right)

SRO/BOP (5) Verifies Containment Vent Isolation (CVI) by checking CVI valve positions on VB4 or far right portion of Monitor Light Box B on VB1 (all valves are closed)

SRO/BOP (6.a) Checks no personnel in Containment (was part of Turnover; may not voice)

(6.b) Announces ATWS on Public Address System (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 24 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 8 Page 22 of 30 Event

Description:

ATWS, Both manual and 13D/E Fail to Open (Continued)

Time Position Applicants Actions or Behavior (EOP FRS1, "Response to Nuclear Power Generation / ATWS", continued)

Note: Portions of EOP E0 are implemented in parallel with EOP FRS.1. The implemented steps of EOP E0 appear below. Body of EOP FRS.1 is continued on page 24.

SRO (7) Notes SI actuated and directs RO (usually the BOP) to IMPLEMENT the following:

o EOP E0, Steps 1 through 4 o EOP E0, Appendix E, Steps 1 through 10 (Implementation of EOP E0, Steps 14)

BOP (1) Verifies reactor trip (trip bkrs open (VB2 upper left), rods on bottom (VB2 upper left DRPI panel), NIs decreasing (CC1 left))

BOP (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)

BOP (3) Checks vital 4kv busses (VB4, vital busses F/G/H have white lights on mimic busses)

BOP (4.a) Checks if SI actuated (PK0821 ON)

(4.b) Checks VB1 red light and/or train equipment to verify both trains actuated)

(Implementation of EOP E0,Appendix E, Steps 110)

BOP (1a) Checks no personnel in Containment (part of turnover; may not voice)

(1b) Announces trip/SI on PA system Note: Unit is currently aligned for backfeed from 500kV. Tripping the Unit will result in transfer to Start Up (230 kV).

BOP (2) Checks main generator - tripped (PK1401 ON, output bkrs open, and exciter field bkr open, CC3 right side); Determines generator is NOT tripped (2 RNO) Determines Unit is still backfeeding (PK1401 if OFF) and goes to step 3 (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 25 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 8 Page 23 of 30 Event

Description:

ATWS, Both manual and 13D/E Fail to Open (Continued)

Time Position Applicants Actions or Behavior (Implementation of EOP E0,Appendix E, Steps 110, continued)

BOP (3 & 4) Verifies Phase A and containment vent isolation complete (VB1, Monitor Light Box B status lights, red lights ON, white lights OFF)

Note: Critical Task to start ECCS CCP may have be completed during Emergency Boration (step 4 of FRS.1) or by crew if identified earlier as failed autostart.

BOP (5) Verifies ESF (SI) actuation complete (Monitor Light Box CSI, red light ON, white lights, some ON) o Identifies white lights associated with ASW and ECCS charging pumps

• • Manually starts available ECCS CCP (CCP1 1 or CCP 12)

(Critical Task E-0-I: Establish flow from at least one highhead ECCS pump before transition out of E0) **

BOP (6) Verifies Feedwater isolation complete (normal FWI portion is complete, with red light ON, and white lights OFF) (S/G portion: red light is ON, white lights OFF)

BOP (7 & 8) Checks containment spray, Phase B, and main steam isolation - NOT required (red lights are OFF for ESF for these on VB1, and white lights are OFF)

BOP (9) Checks AFW status (MDAFPs running, TDAFP is off and not required, VB3 center area); verifies either min of 435 gpm flow (VB3 center) or S/G level > 15% (VB3 center)

BOP (10) Verifies ECCS flows (charging injection (VB2 upper panel left), SI, RHR (both on VB1 upper panel); expected is that only CCPs will be delivering flow at current RCS pressure (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 26 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 8 Page 24 of 30 Event

Description:

ATWS, Both manual and 13D/E Fail to Open (Continued)

Time Position Applicants Actions or Behavior (Implementation of EOP E0,Appendix E, Steps 110, continued)

BOP Reports ESF and AFW status to SFM (EOP FRS1, "Response to Nuclear Power Generation / ATWS", continued from page 22)

SRO/ATC (8) Checks expected trips have occurred

a. Rx Trip Breakers OPEN (VB2, upper left)

b. Reverifies all four turbine stop valves CLOSED (CC3 HMI or VB2, RPS indicator lamps)

SRO/ATC (9) Checks Rx Subcritical

a. Power Range NI's LESS THAN 5% (CC1)

b. Negative startup rate on Intermediate Range Channels (CC1)

c. Goes to Step 19 (procedurally directed)

Note: Actions of Step 19 (Shutdown Margin verification) are directed by SRO through Shift Manager.

SRO/BOP (19) Verifies adequate Shutdown Margin

a. Contacts Chemistry to sample RCS for Boron Concentration

b. Requests performance of STP R19, Shutdown Margin Calculation

c. Notes need to borate to shutdown concentration (accomplished through ECCS injection from RWST).

SRO (20) Returns to first step of E0, REACTOR TRIP OR SAFETY INJECTION

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 27 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 7,9 Page 25 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 (continued)

Running Charging Pumps trip on SI, Autostart Fails (continued) (CT)

Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection")

SRO Implements EOP E0, Reactor Trip or Safety Injection ALL Crew reverifies E0 immediate actions (normal response, now that trip bkrs are open) o Verifies reactor trip (trip bkrs open, rods on bottom, NIs decreasing) o Verifies turbine trip (stop valves closed (CC3 HMI or VB2 RPS indicator lamps) o Checks vital 4kv busses (VB4, vital busses F/G/H have white lights on mimic busses) o Checks SI actuated (PK0821 ON)

Note: Steps 110 may have been implemented earlier and do not need to be repeated.

SRO (5) Directs App E implemented (usually to BOP)

BOP Implements App E:

(1a) Checks no personnel in Containment (part of turnover; may not voice)

(1b) Announce trip/SI on PA system (2) Checks main generator - tripped (PK1401 ON, output bkrs open, and exciter field bkr open, CC3 right side); Determines generator is NOT tripped (2 RNO) Determines Unit is still backfeeding (PK1401 if OFF) and goes to step 3 (3 & 4) Verifies Phase A and containment vent isolation complete (VB1, Monitor Light Box B status lights, red lights ON, white lights OFF)

(5) Verify ESF (SI) actuation complete (ESF/SI red light ON, white lights some ON);

o Identifies white lights associated with ECCS charging pumps

• • Manually starts available ECCS CCP (CCP1 1 or CCP 12)

(Critical Task E-0-I: Establish flow from at least one highhead ECCS pump before transition out of E0)**

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 28 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 8&9 Page 26 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 (continued)

Time Position Applicants Actions or Behavior (EOP E0, Appendix E, continued)

BOP (6) Verifies Feedwater isolation complete (normal FWI portion is complete, with red light ON, and white lights OFF) (S/G portion: red light is ON, white lights OFF)

(7 & 8) Checks containment spray, Phase B, and main steam isolation - NOT required (red lights are OFF for ESF for these on VB1, and white lights are OFF)

(9) Checks AFW status (MDAFPs running, TDAFP does not start; verifies either min of 435 gpm flow (VB3 center) or S/G level > 15% (VB3 center)

(10) Verifies ECCS flows (charging injection (VB2 upper panel left), SI, RHR (both on VB1 upper panel)

(11) Reports ESF and AFW status to the Shift Foreman (12 & 13) Checks excess letdown - not in service (8166/8167 closed); turns on aux bldg vent charcoal filter preheater (VB4 lower panel, left side)

(14) Checks secondary systems (MFPs tripped (VB2, green lights ON), verifies only one CB Pp set running, condenser is available) (VB3)

(15) Verifies proper operation of Aux Bldg and Control Rm vent systems (VB4 vent status light panel white lights); verifies containment iodine fans secured (VB4, lower panel)

(16 21) Verifies available DGs running normally (VB4, freq (60), volts (120), speed (900)); verifies vital batteries supplied by chargers (charger and bus volts on VB5, upper panel middle/lower area); verifies MSRs reset (CC3 Triconex HMI); throttles RCP seal injection flows to normal (FCV128, to 813 gpm each, CC2); checks PK1104 NOT IN (SFP alarm); notifies Shift Foreman of completion (EOP E0, Reactor Trip or Safety Injection", continued)

SRO/ATC (6) Checks RCS temperature - stable (temps may be dropping due to SBLOCA/ECCS flows; AFW may be throttled back (VB2 meters, upper panel lower area)

SRO/ATC (7) Checks Pzr PORVs and Pzr safeties (closed) / PORV block valves (all open), and no sonic flows on safeties/PORVs (tailpipe temps might be slightly elevated, but consistent with containment temperatures from the SBLOCA) (VB2 - upper panel, far right); checks Pzr sprays closed (CC2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 29 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 7 Page 27 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 (continued)

Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection", continued)

Note: RCPs may already be tripped based on E0 fold out page guidance for RCP Trip Criteria SRO/ATC (8) Checks RCP trip criteria - observes RCS pressure (may or may not be < 1300 psig; stops RCPs if < 1300 psig (VB1 and VB2) (Continuous Action)

ATC/BOP (9) Checks for faulted S/Gs o Faulted - checks all S/G pressures on VB3 (no uncontrolled drop or depressurized)

ATC/BOP (10) Checks ruptured S/Gs Ruptured - checks RE71/72/73/74 and RE15/19 recorders on VB2 (and PPC); (all normal), and PK1106/17/18 (all OFF); may request samples SRO/ALL (11) Checks RCS intact (it is not) (note: only one valid abnormal reading needed to transition from E0) o (11a) Checks containment pressure normal (it is elevated) (VB1 meters, PPC) o (11b) Checks containment sump level normal (already be elevated) (VB1 meters, PAMS) o (11c) Checks containment radiation normal (elevated) (PK1121 and PK1119)

(11 RNO) Places 2nd ASW/CCW HX in service (opens FCV603 and FCV431, VB1 far left)

SRO Checks Critical Safety Function Status Trees and transitions to EOP E1, Loss of Reactor or Secondary Coolant (continued on next page)

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 30 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 7 Page 28 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 (continued)

Time Position Applicants Actions or Behavior (EOP E1, "Loss of Reactor or Secondary Coolant")

SRO/ATC (1) Checks RCPs tripped (already done, VB2)

(1) Continues to maintain RCP seal flows 813 gpm (FCV128) (CC2)

SRO/ALL (2 & 3) Checks for faulted/ruptured S/Gs o Faulted - checks all S/G pressures on VB3 (not uncontrolled drop/depressurized; all are dropping slowly, as the primary is now the heat sink for the secondary) o Ruptured - checks RE71/72/73/74 and RE15/19 recorders on VB2 (and PPC; no upward trends or spikes, unless containment shine is noted), and PK1106/17/18 (alarms not in); requests chemistry to sample S/Gs for activity (as follows, if done):

Verifies phase A containment isolation reset (VB1)

Opens FCV584 (air to containment) (VB4, lower left)

Opens blowdown isolation valves inside containment (FCV760, 761, 762, 763)

May require blocking low steamline pressure MSI/SI (due to low steamline pressures); two block switches on CC2 taken to block position BOP (4) Maintains S/G levels 20 [25] 65% (VB3, AFW controls)

SRO/ATC (5) Check Pzr PORVs (closed) / blocks (open/powered) (VB2 - upper panel, far right)

SRO/ATC (6) Verifies containment spray in service (PK0118 OFF, containment spray is not in service, and not required) (VB1)

SRO/ALL (7) Checks ECCS termination criteria (not met, SCM is < 20F, Pzr level is also below 12% [40%])

(continued on next page

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 31 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 7 Page 29 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 (continued)

Time Position Applicants Actions or Behavior (EOP E1, "Loss of Reactor or Secondary Coolant", continued)

Note: If RCS pressure is still stabilized at this point, RHR pumps will be shut down [until needed later] (if pressure going down, they will be left in service); either condition is satisfactory for now.

SRO/ATC (8) Maintains RHR pumps running, and aligns cooling (may open FCV364 and 365 now

[will open in later step], VB1 far left lower)

SRO/ALL (9) Checks S/G pressures (VB3) and RCS pressure consistent with LOCA (they are, although RCS pressure may be almost stable at saturation)

SRO/BOP (10) Check if DGs should be stopped (busses are powered from Aux and S/U, so they can be secured) (VB4)

SRO/ATC (11.a, b) Verifies recirc capability (RHR Pps have power (VB1), checks aux bldg rad levels (RM04, 06, 10, 13 show no elevated readings) (PPC, back RMS panels), and checks RHR systems alarms (PK0216 and PK0217 off) for intersystem LOCA (ISLOCA no indications other than for SBLOCA)

SRO/ATC (11.c) Checks RHR Pps running, and establishes cooling to the heat exchangers (by opening FCV364/365, as noted above), if not already open (and pumps running) (all on VB1)

SRO/ALL (11.d) Implements App P (2nd/manual check of ESF status lights; may be a lower priority)

ALL (11.e, f, g) Requests RCS samples; monitors turbine status (oil Pps, coastdown, etc),

checks SFP status (continued on next page

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 32 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 1 Event No.: 7 Page 30 of 30 Event

Description:

700 gpm SBLOCA on Loop 1 (continued)

Time Position Applicants Actions or Behavior (EOP E1, "Loss of Reactor or Secondary Coolant", continued)

SRO (12) Determines that post LOCA cooldown procedure is appropriate (RCS pressure is >

300 psig [VB2, PPC, CC2], and no RHR flow [VB2])

SRO Transitions to EOP E1.2, PostLOCA Cooldown and Depressurization, and may perform a procedure transition brief Terminate the scenario once transition is made to EOP E-1.2, per the lead examiner.

• • Critical Task L121 NRC Sim Exam 01 r1.doc Page 33 of 39 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD1 Facility: Diablo Canyon (PWR) Scenario No.: 4 OpTest No.: L121NRC Examiners: Operators:

Initial Conditions: 100%, MOL, 961 ppm boron Turnover: Bus H Work Week: AFW 12 OOS, D/G 11 OOS Maintenance in progress on PCV20.

CCP 11 In Service.

Event Malf Event Type* Event No No. Description 1 XMT_CVC20_3 I (SRO, BOP) VCT level transmitter LT114 gradually fails high causing letdown flow to divert to the LHUTs. Automakeup commences when actual level falls to 14% (AP19);

2 MAL_SEI1 .15 delay=0 ramp=5 C (SRO, BOP) Pressurizer Pressure Control Valve PCV456 slowly drifts VLV_PZR5_2 0.25 delay=0 open following small seismic and can not be closed.

ramp=5 Associated block valve is closed to isolate the PORV (AP13)

(TS 3.4.11.B, CT) 3 R(ALL) Call from Grid Control Center for Unit 1 backdown order to shed 350 MW within 10 minutes due to grid disturbance (AP25) 4 MAL_ROD3A_ROD B10 C (ALL) Dropped rod and urgent failure at 855 MW inhibits auto rod MAL_ROD3A STATIONARY motion and requires rods to be taken to manual (AP12C)

(TS 3.1.4.B).

5 MAL_SEI1 .17 delay=0 ramp=6 M (ALL) Second seismic results in full load rejection. Rods are still in MAL_SYD3 56 delay=3 manual and crew must trip Rx based on first step of AP2.

ramp=30 6 MAL_SEI1 .3 delay=0 ramp=6 C(SRO, BOP) Loss of Startup immediately following Rx Trip. D/G 13 fails MAL_SYD2 0 to auto start but can be manually started.

7 MAL_RCS1D 50%_dba M (ALL) Strong aftershock results in LBLOCA. ECCS Charging pumps MTRF 15 cd='jpplsia or jpplsib' and Safety Injection Pump 11 trip on overcurrent reducing the amount of high head injection.

PMP_SIS1_MTRF 15.0 cd='jpplsia or jpplsib' 8 PMP_RHR1 BLOCK_AUTO_STRT C (BOP) Residual Heat Removal Pump 11 and Containment Spray PMP_CSS1 BLOCK_AUTO_STRT Pump 11 fail to autostart, but may be manually started (CTs).

L121 NRC ESD104 r2.doc Page 1 of 3 Rev 2

Appendix D (rev 9) Required Operator Actions Form ESD1

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES3014) Actual Attributes

1. Total malfunctions (5-8) (Events 1,2,4,5,6,7,8) 7

2. Malfunctions after EOP entry (1-2) (Events 6,7,8) 3

3. Abnormal events (2-4) (AP19, AP25, AP12C, AP2) 4

4. Major transients (1-2) (Events 5&7) 2

5. EOPs entered/requiring substantive actions (1-2) (E0.1, E1) 2

6. EOP contingencies requiring substantive actions (0-2) (ECA0.3) 1

7. Critical tasks (2-3)(See Scenario Summary) 3 L121 NRC ESD104 r2.doc Page 2 of 3 Rev 2

SCENARIO

SUMMARY

- NRC #4

1. Volume Control Tank (VCT) level channel LT114 fails high, causing letdown to divert to the LHUTs.

Automatic reactor makeup will maintain VCT level above 14%. The crew diagnoses the level channel failure by comparing other VCT parameters, and addresses issue following OP AP19, Malfunction of the Reactor Makeup Control System guidance. LCV112A control is set to the VCT position.

2. Small seismic causes Pressurizer Pressure Control Valve PCV456 to slowly drift open and must be isolated using the associated 8000C block valve. Shift Forman enters TS 3.4.11.B Pressurizer Power Operated Relief Valves (PORVs). (Critical Task: Isolate PORV prior to pressurizer pressure lowering to 1950 psig (low pressurizer pressure Rx trip setpoint)).

3. Grid Control Center (GCC) calls with a backdown order for DCPP due to grid disturbance. Shift Manager directs Unit 1 to shed 350 MW in the next 10 minutes. Crew commences ramp using guidance of OP AP 25, Rapid Load Reduction or Shutdown to reduce load.

4. At 855 MW, a Rod Control Urgent Failure occurs and rod B10 is drops. Crew places rod control in manual and enters OP AP12C, Dropped Control Rod. Turbine is used to return Tave to Tref. Shift Foreman enters TS 3.1.4.B Rod Group Alignments.

5. A large seismic event occurs, resulting in a 500kV grid instability/underfrequency condition. Unit separates from the grid. Crew enters OP AP2, Full Load Rejection, and trips the reactors based on unavailability of auto rod control.

6. Crew enters E0, Reactor Trip or Safety Injection, and transitions into E0.1, Reactor Trip Response to stabilize the plant. Startup power is lost and D/G 13 fails to autostart due to a shutdown relay, reducing vital 4kV power to a single bus (D/G 11 out of service from initial conditions). ECA0.3, Restore 4kV Buses is implemented in parallel with E0.1. D/G 13 shutdown relay is reset from the control room and the diesel started in manual.

7. A large aftershock occurs resulting in a LBLOCA. ECCS CCPs (High Head Injection) and SIP 11 (Intermediate Head Injection) all trip on overcurrent. Crew reenters E0, Reactor Trip or Safety Injection, and transitions to E1, Loss of Reactor or Secondary Coolant.

8. RHRP 11 (Low Head Injection) and CSP 11 (Containment Spray) fail to autostart, but may be manually started (Critical Task E0H: Manually start at least one low head ECCS pump before transition out of E0 and Critical Task E0E: Manually actuate at least the minimum required complement of containment cooling equipment before an extreme (redpath) challenge develops to the containment critical safety function.)

The scenario is terminated once crew has completed actions of EOP E1 and is waiting to transition to Cold Leg Recirc.

L121 NRC ESD104 r2.doc Page 3 of 3 Rev 2

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 1 Page 1 of 27 Event

Description:

VCT Level Control Channel LT114 Slow Failure High Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.

ALL Diagnoses LT114 failing high using one or more of the following indications:

VCT level and pressure lowering (diverse indicators of actual level change) (PPC, VB2 upper center)

LI112 (VB2, meter upper right) and LI114 (PPC point L0112A) fail to channel check VCT level control valve LCV11A diverting to LHUT (VB2 center skirt; amber light illuminated)

Automakeup if actual VCT level lowers 14% (CC2)

SRO Implements OP AP19, "Malfunction of Reactor Makeup Control System" (OP AP19, "Malfunction of Reactor Makeup Control System")

SRO/ATC (1) Checks Makeup Controller in set for desired mode (usually AUTO) and selected to START (CC2)

SRO/BOP (2) Verifies Makeup System pumps and valves are properly aligned and in AUTO (VB2, bottom right skirt)

ALL (3) Determines LI112 and LI114 do NOT channel check (LT114 failed High) o L0112A (PPC point for LI114) is reading 100%, LI112 (VB2) is reading between 14%50% (depending on actions taken by crew) o May dispatch Turbine Watch to check LI114 reading at HSDP (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 4 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 1 Page 2 of 27 Event

Description:

VCT Level Control Channel LT114 Slow Failure High (cont)

Time Position Applicants Actions or Behavior Note: AR PKs referenced in RNO do not alarm - transmitter failed at 100%, but NOT overranged (OOR)

SRO/BOP (3 RNO) References associated PKs and Appendices o (a) May reference AR PK0621 (Process Control System Trouble) and AR PK06 22 (Process Control System (PCS) Channel OOS); no actions directed by PKs o (b) Refers to Appendix A guidance to identify failed transmitter (1.a) Checks PCS HMI to determine which channel has failed (located to left of PPC large display)

(1.b) Reviews control functions/indications for LT112 and LT114 o (c) Determines LT114 has failed high SRO/ATC (4) Verifies suction alignment for running charging pump o CCP 11 amps, discharge flow (VB2, Under DRPI)(CC2) o VCT level and pressure are within normal bands SRO/BOP (5) Contacts I&C to investigate failure (6) Realigns LCV112A divert valve to VCT (VB2, right skirt)

Proceed to the next event once AP19 actions complete, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 5 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 2 Page 3 of 27 Event

Description:

Pressurizer Pressure Control Valve PCV456 (PORV) Drifts Open Following Seismic (CT)

Time Position Applicants Actions or Behavior ALL Diagnoses PCV456 open using one or more of the following indications:

PK0520, "PZR RELIEF/SAFETY VLVS OPEN" in alarm PK0523, "PZR SAFETY OR RELIEF LINE TEMP" in alarm Pressurizer pressure lowering (CC2, VB2), back up heaters on (CC1), sprays closed (CC2)

Both RED and GREEN position indicator lights illuminated on PCT456 (VB2, far right, lower)

PORV discharge temperature elevated (TI463) (VB2, far right, middle)

SRO/BOP Takes action to manually close PCV456 (unsuccessful)

• • Closes associated block valve (8000C)

(Critical Task: Isolate PORV prior to pressurizer pressure lowering to 1950 psig (low pressurizer pressure Rx trip setpoint))**

Note: PK0523 will redirect crew to PK0520 for guidance (PK0520, Pressurizer Relief/Safety Valves Open) if entered, else N/A SRO/ATC (1) Identifies input 1211 (Pzr Relief Vlv PCV456 Open) and goes to section 2.1, General Actions SRO (2.1.1) Notes requirement to enter EOP E0, "Reactor Trip or Safety Injection" if reactor trips at any time.

Reads NOTE regarding isenthalpic steam release corresponding to a PORV tailpipe temperature of approximately 230oF; May direct board operator to check current PORV discharge temp (TI463) (VB2, far right, middle)

(2.1.2) Checks for indications of rapid drop in actual pressurizer pressure; may transition to OP AP13 (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 6 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 2 Page 4 of 27 Event

Description:

Pressurizer Pressure Control Valve PCV456 (PORV) Drifts Open Following Seismic, (continued)

Time Position Applicants Actions or Behavior (OP AP13, "Malfunction of Reactor Pressure Control System") if entered; else N/A SRO (1) Notes there are no load changes in progress SRO/BOP (2) Checks all PORVs closed (PCV474, 455C, 456) (VB2, far right, lower) o Notes PCV456 position lights indicate valve is open (2 RNO) Checks pressurizer pressure less than 2335 psig (it is);

o May reattempt closing PCV456 (valve remains off its seat) o Checks associated block valve 8000C is closed SRO/BOP (3) Checks pressurizer safety relief valves closed (VB2, far right, middle) o Sonic flow reading zero (they are) o Tailpipe temperature 185oF (they are)

ALL Reads CAUTION regarding potential need for stopping RCPs if spray valve has failed (4.a) Checks normal pressurizer spray valves closed (PCV455A/B) (CC2, upper middle right) (green lights On, both are closed)

(4.b) Checks aux spray valves closed (8145 & 8146) (VB2, far right skirt) (both are closed)

SRO/ATC (5) Checks pressurizer backup heater status (far left CC1)

(5.a) Heaters are lined up to normal power (normal power indicating lights are illuminated (CC1)

(5.b,c) Status of heaters will depend on pressure transient from PORV opening If pressurizer pressure > 2250 psig, ensures all heaters turned off If pressurizer pressure < 2210 psig, ensures all heaters turned on (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 7 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 2 Page 5 of 27 Event

Description:

Pressurizer Pressure Control Valve PCV456 (PORV) Drifts Open Following Seismic, continued Time Position Applicants Actions or Behavior (OP AP13, "Malfunction of Reactor Pressure Control System", continued)

SRO (6) Determines all pressure control channels are OPERABLE SRO/ATC (7) Restores pressurizer pressure to normal band (22102260 psig)

SRO Reviews Tech Specs and enters Tech Spec 3.4.11.B - One PORV inoperable for reasons other than excessive seat leakage.

o Required actions:

Close associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Remove power from associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Restore Class I PORV to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 8 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 3 Page 6 of 27 Event

Description:

Grid Disturbance - Grid Control Center Backdown Order to Shed 350 MW Time Position Applicants Actions or Behavior Cue: (from Shift Manager) I have just received a valid backdown order from the Grid Control Center (GCC) due to a grid disturbance. Per Ops Policy B1, ramp unit 1 down 350 MW in the next 10 minutes.

SRO Implements OP AP25, Rapid Load Reduction (OP AP25, Rapid Load Reduction)

SRO Enters OP AP25, Rapid Load Reduction (1.a) Determines runback/programmed ramp is not in progress (may not vocalize, since this ramp is initiated by the crew)

SRO/BOP Ramp is started (guidance is also on lamicoid pegboard on CC3):

o (1.b) MW and IMP feedbacks are placed in service (all on Triconex turbine HMI, CC3) o (1.c) 840 MWe (1190350, approximate) load target is entered into Triconex HMI o (1.d) Sets ramp rate to 35 mw/min (approximate rate; actual rate dictated by Shift Foreman) o (1.e) Pushes GO SRO/BOP o (1.f) May make calls to chemistry if/when 15%/hr shut down rate is exceeded ATC (2) Verifies that control rods are inserting properly in AUTO (CC1)

(3) Turns Pressurizer heaters on (CC1)

(4) Checks charging adequate to prevent flashing in the letdown system; may take manual control to ensure adequate flow (CC2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 9 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 3 Page 7 of 27 Event

Description:

Grid Disturbance - Grid Control Center Backdown Order to Shed 350 MW (cont)

Time Position Applicants Actions or Behavior (OP AP25, "Rapid Load Reduction", continued)

SRO/BOP (5) Ensures DFWCS is controlling S/G levels in AUTO (MFW control/bypass valves; MFPs all in AUTO) (CC2)(VB3)

Note: Boration values described below are representative of the conditions given, but will vary based on the actual ramp rate and target specified by SRO. Total gallons boron required for shutdown is determined from Reactivity Handbook.

SRO/ATC (6) Performs boration (the following guidance is on the boration checklist in the reactivity handbook) o Presses STOP on M/U Ctrl HMI (CC2) o Presses BORATE on HMI o Sets target gallons for boration (expected approx. 50100 gallons for first batch); verifies batch is reset o Sets boric acid flowrate (expected value 20 gpm) o Presses START, and monitors boration o Once stopped, either returns to AUTO (presses AUTO, then START), or performs additional boration per the Shift Foreman(CC2)

SRO/BOP (7) Checks MFP suction pressure greater than 260 psig (VB3)

SRO/ATC (8) Checks Tave trending to Tref (PPC, CC1)

(9) Checks Pressurizer pressure and level trending to programmed band (PPC, CC2)

Proceed to the next event when generation = 855 MW, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 10 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 4 Page 8 of 27 Event

Description:

Rod Control Urgent Failure / Dropped Rod Time Position Applicants Actions or Behavior ALL Diagnoses dropped control rod / rod control urgent failure using one or more of the following indications:

PK0317, "ROD CONT URGENT FAILURE" in alarm PK0321, "DRPI FAILURE/ROD BOTTOM" in alarm PK0310, "PWR RNG DEV/QPTR" in alarm Dropped rod indicated on DRPI (VB2)

Auto rod motion stops (CC1)

I and power range deviation in area of NI42 SRO Implements OP AP12V, "Dropped Control Rod" (OP AP12C, "Dropped Control Rod")

SRO/BOP (1) Determines single control rod dropped (control bank D, rod B10) (DRPI, VB2)

SRO/ATC (2) Places rod control in manual (CC1)

SRO/BOP (3) Stops any load changes in progress (CC3) o Places ramp on hold, if still in progress o If ramp complete, removes MW and Impulse feedbacks and resets VPL SRO/ATC Reads NOTE regarding impact dilution would have on initial shutdown margin determination (4) Stops boration if still in progress (Makeup Control HMI, CC2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 11 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 4 Page 9 of 27 Event

Description:

Rod Control Urgent Failure / Dropped Rod Time Position Applicants Actions or Behavior (OP AP12C, "Dropped Control Rod", continued)

SRO/BOP (5) Checks Tave within +/- 1.5oF Tref; adjusts turbine load as needed to bring within band (CC3)

SRO (6) Checks Axial Flux Difference (AFD) within T.S. 3.2.3 limits (it is)

Note: May request SM assign performance of STP R25 to other available personnel SRO (7) Verifies QPTR is less than 1.02 (it is)

Note: May request SM assign performance of STP R19 to other available personnel.

SRO (8) Performs STP R19, Attachment 9.4 within an hour to verify SDM within limits of COLR SRO (9.a. RNO) Identifies Rod Control Urgent Failure has occurred (a.1 RNO) Directs crew not to move rods or reset Urgent Failure (a.2 RNO) Contacts maintenance for troubleshooting (a.3 RNO) Refers to AR PK0317, "Rod Control Urgent Failure" (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 12 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 4 Page 10 of 27 Event

Description:

Rod Control Urgent Failure / Dropped Rod (continued)

Time Position Applicants Actions or Behavior (AR PK0317, "Rod Control Urgent Failure")

SRO Reviews Annunciator General Actions o May note actions already completed as part of OP AP12C o Reviews applicable Tech Specs and ECGs Enters Tech Spec 3.1.4.B - One rod not within alignment limits Required actions:

o Restore rod to within alignment limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR o Verify or restore SDM to be within COLR limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> along with series of actions to verify SDM is maintained Proceed to the next event once T.S. addressed, per Lead Examiner

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 13 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5 Page 11 of 27 Event

Description:

FullLoad Rejection / Reactor Trip Time Position Applicants Actions or Behavior ALL Diagnoses loss of load (fullload rejection) using one or more of the following indications:

PK1405, "Generator Underfrequency" in alarm PK1424, "Unit's 500 kV Breakers Open" in alarm PK2025 500 "kV Switchyard" in alarm Group I and II steam dumps armed, open, and steaming (VB3)

Main generator output breakers tripped open (CKT BKRs 632 and 532) (CC3, far right)

Note: Step 1 of OP AP2, "Full Load Rejection" directs crew to trip the Rx and go to EOP E0 if control rods fail to insert in auto. Shift Foreman may elect to trip reactor based on plan conditions and enter EOP E0 directly.

SRO Implements OP AP2, "Full Load Rejection" (OP AP2, "Full Load Rejection") if entered; else N/A SRO/ATC (1) Determines control rods are not inserting in Auto (1 RNO) Shift Foreman directs Reactor Trip and transitions to EOP E0, "Reactor Trip or Safety Injection" (EOP E0,"Reactor Trip or Safety Injection")

ALL Crew enters EOP E0 on Rx Trip and silently performs immediate actions:

Verifies reactor trip (trip bkrs open, rods on bottom, NIs decreasing)

Verifies turbine trip (stop valves closed (CC3 HMI or VB2 RPS indicator lamps)

Checks vital 4kv busses (VB4, vital busses F/G/H have white lights on mimic busses)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 14 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5,6 Page 12 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Loss of Startup Power Time Position Applicants Actions or Behavior (EOP E0,"Reactor Trip or Safety Injection")

SRO/ATC (1) Verifies reactor trip (trip bkrs open, rods on bottom, NIs decreasing)

SRO/ATC (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)

SRO/BOP (3) Checks vital 4kv bus status (VB4, white lights on mimic; only vital bus G is illuminated) o Determines only one vital bus is energized (Bus G, which is powered by D/G 1 2)

Buses F and H are deenergized (white lights out on VB4 mimic)

May note loss of 230kV and failure of D/G 13 to start (shutdown relay tripped)

May note D/G 11 OOS since beginning of shift Note: Shift Foreman may elect to postpone implement EOP ECA0.3 until review of immediate actions has been completed and priorities evaluated based on plant conditions. (see pg 16 for actions)

SRO/BOP (3.a.2 RNO) Directs operator to IMPLEMENT EOP ECA0.3, "Loss of All Vital AC Power" SRO/ATC (4) Checks for SI actuated (PK0821: ON) o (4.a RNO) Determines SI is neither actuated nor required PK0202 is OFF Safeguards bistable status lights are out (logic for SI is not made up)

(VB1, left upper area, just below PK01 and PK02) o (4.a.2. RNO) Announces Reactor Trip on PA (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 15 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5 Page 13 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Time Position Applicants Actions or Behavior (EOP E0,"Reactor Trip or Safety Injection", continued)

SRO/ATC o (4.a.3 RNO) Controls AFW flow to reduce cooldown while maintaining a secondary heat sink Checks for adequate secondary heat sink (S/G level 15% in at least 1 S/G or total AFW flow 435 gpm) (VB3, upper right)

Monitors RCS Loop Tcolds for indications of cooldown (VB2, lower center chart recorders or PPC); throttles feedflow if cooldown continues (VB3, lower left)

SRO Transitions to E0.1 ("Reactor Trip Response")

(EOP E0.1,"Reactor Trip Response")

Note: Step 1 of E0.1 partially repeats last direction given in E0 (reduce cooldown/maintain heat sink), but also looks at potential for heatup. Actual actions required will depend on length/depth of pretrip transient.

SRO/ATC (1) Checks RCS temperature stable or trending to 547oF based on RCS Loop Tcolds (RCPs tripped) (VB2, lower center chart recorders or PPC) o If RCS temp < 547oF and decreasing :

checks steam dumps (VB3, indicator lights middle) and S/G blowdown isolation valves outside containment (VB3, lower left skirt) all closed.

Also checks MSRs reset on on Turbine Control HMI (CC3) throttles AFW feedflow as needed to stop cooldown while maintaining heat sink (S/G level 15% in at least 1 S/G or total AFW flow 435 gpm) (VB3, upper right) o RCS temp > 547oF and increasing If required, sets 10% dump controllers to 1005 psig, (83.8% setpoint)

(VB3, lower left) verifies dumps modulate open to control temperature at 547oF Monitoring of RCS temperature stable assigned as Continuous Action (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 16 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5 Page 14 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Time Position Applicants Actions or Behavior (EOP E0.1,"Reactor Trip Response", continued)

Note: If Tave is still greater than 554oF, feedwater isolation will NOT be in (dependent on pretrip transient)

SRO/ATC (2) Checks Feedwater Status (a) RCS temperature < 554oF (VB2, lower center chart recorders or PPC)

(b) Checks Feedwater Isolation has occurred Feedwater Isolation portion of Monitor Light Box C (VB1)

(Red lights ON / White lights ON for FCV438, 440, and 441 due to bus F and H power loss); contacts Turbine Watch to close valves (c) Checks total AWF flow greater than 435 GPM (VB3, upper middle)

SRO/ATC (3) Checks Rods fully inserted (VB2DRPI)

SRO/ATC (4) Checks Pressurizer level controls o (a) Level greater than 17% (VB2, middle right) o (b) Charging in service with adequate flow (VB2)(CC2) o (c) Letdown in service (VB2, upper middle skirt) o (d) Pressurizer level trending to 22% (VB2, middle right)

(may adjust charging to maintain level 22% to 60%)

o (e) May energize pressurizer heaters (CC1, lower left)

SRO/ATC Reads CAUTION regarding Aux Spray and notes as N/A (Aux Spray not in service)

(5) Checks Pressurizer pressure control o (a) Pressure greater than 1850 psig (VB2, far right) o (b) Pressure stable or trending to 2235 psig (VB2)(CC2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 17 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5 Page 15 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Time Position Applicants Actions or Behavior (EOP E0.1,"Reactor Trip Response", continued)

SRO/ATC (6) Checks S/G NR levels greater than 15%

o (a) Reports all S/G NR levels greater than 15% (VB3, upper middle) o (b) Will control AFW flow to maintain S/G NR levels between 20% and 65%

o (c, d) Checks TD AFW Pump required for heat removal Reports TD AFW pump is required for heat removal (only running AFW pump until bus F power restored) (VB3, center skirt)

Monitoring of S/G levels assigned as Continuous Action Proceed to the next event once 4kV Bus F is reenergized, per Lead Evaluator

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 18 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5,6 Page 16 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Loss of Startup Power Time Position Applicants Actions or Behavior Note 1: Implementation of EOP ECA0.3 may be assigned to individual control operator (typically the BOP) and performed in parallel with actions of crew.

Note 2: The following actions are directed as part EOP E0, step 3 RNO (Ensure Vital 4kV Bus Status), directed on page 12 of this outline.

(EOP ECA0.3,"Restore 4kV Buses")

BOP Reads CAUTION regarding risk of hazards assoicated with significant electrical fault conditions Reads CAUTION regarding safety of local operators if bus is reenergized during stipping of loads (1) Checks availability of D/Gs associated with denergized vital buses o May contact electrical maintenance and/or work control to expedite return of D/G 11 o Identifies D/G 13 Shutdown Relay actuated (PK1815 in alarm); no other problems indicated on bus F May dispatch operator to walk down D/G 13 May take D/G 13 mode select switch to MAN (if not taken to manual, reset of shutdown relay will result in Autostart of D/G and loading of Bus F equipment) (VB4, below and to left of Shutdown Relay Reset)

(1.a) Starts D/G 13 o Resets D/G 13 Shutdown Relay and Alarm Reset (VB4, far right center - yellow lamicoid, just below D/G 13 tach) o Verifies Shutdown Relay resets (PK1815 clears)

If mode select switch was taken to manual, manually starts D/G 13 (VB4 below and to left of Shutdown Relay Reset)

(1.b) Verifies Bus F energized o Informs Shift Foreman D/G 13 is running and bus F energized Note: May continue on in ECA 0.3 while waiting for report back from field on D/G 13 status.

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 19 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5,6 Page 17 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Loss of Startup Power Time Position Applicants Actions or Behavior (EOP ECA0.3,"Restore 4kV Buses", continued)

BOP Reads NOTE prior to step 2 regarding D/G running with deenergized bus (2) Prepares buses for return of offsite power o (a) Places AUTO TRANSFER to STARTUP CUTOUT switches to CUTOUT position for all 4kV and 12kV buses ( VB4 and VB5 skirt, switches located directly above corresponding AUTO XFR RESET pushbuttons (Blue lights illuminated) (7 switches) o (b) Depresses AUTO XFR RESET pushbuttons on all 4kV and 12kV buses and verifies blue lights go out (VB4 and VB5 skirt, next to illuminated blue lights) o (c) Places condensate booster pump selector switches to MAN position (VB3, lower right skirt)

Reads CAUTION to not open breaker supplying power to a bus o (d) Opens all Aux and Startup Feeder Breakers to Deenergized 4kV Vital Buses (VB4 skirt)

Opens 52HH13 (Aux XFMR 12 to 4kV Bus H)

Opens 52HH14 (S/U XFMR 12 to 4kV Bus H)

Opens 52HF13 (Aux XFMR 12 to 4kV Bus F)

Opens 52HF14 (S/U XFMR 12 to 4kV Bus F) o (e) Opens all Aux and Startup Feeder Breakers to Deenergized 4kV NonVital Buses (VB5 skirt)

Opens 52HE2 (Aux XFMR 12 to 4kV Bus E)

Opens 52HE3 (S/U XFMR 12 to 4kV Bus E)

Opens 52HD15 (Aux XFMR 12 to 4kV Bus D)

Opens 52HD14 (S/U XFMR 12 to 4kV Bus D) o (f) Opens all Aux and Startup Feeder Breakers to Deenergized 12kV Buses (VB5 skirt)

Opens 52VD8 (Aux XFMR 12 to 4kV Bus E)

Opens 52VD4 (S/U XFMR 12 to 4kV Bus E)

Opens 52VE2 (Aux XFMR 12 to 4kV Bus D)

Opens 52VE6 (S/U XFMR 12 to 4kV Bus D)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 20 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 5,6 Page 18 of 27 Event

Description:

FullLoad Rejection / Reactor Trip (continued)

Loss of Startup Power Time Position Applicants Actions or Behavior (EOP ECA0.3,"Restore 4kV Buses", continued)

BOP (3) Verifies SI is Reset (notes SI not actuated or required)

Note: If contacted, Generation Control Center (GCC) will report both 230kV and 500kV lines are out of service as result of earthquake; scope of damage is still being evaluated and return to service time is yet to be determined.

BOP Reads NOTE regarding Shift Foreman discretion for selecting preferred offsite power source o May consult with Shift Foreman regarding preferred source o May contact Generation Control Center (GCC) to determine status of 500kV and/or 230 kV power (4) Checks 500 kV Power Available o May use sync switch on 500kV circuit breakers (532 or 632) to check power availability (CC3, far right) o Determines 500 kV is not available (5) Checks 230 kV Power Available to either Unit o Notes 230kV Bus indicator light is not lit (far right, top of skirt, VB5) o Determines 230 kV is not available Proceed to the next event once 4kV Bus F is reenergized, per Lead Evaluator

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 21 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7,8 Page 19 of 27 Event

Description:

Large Break LOCA RHR and Containment Spray Pump Autostart Failures (CT)

Time Position Applicants Actions or Behavior Note: The DBA LBLOCA will occur rapidly, causing an immediate Safety Injection; no actions are expected other than recognition of the earthquake and SI prior to reentry into E0, starting at step 1.

(EOP E0,"Reactor Trip or Safety Injection")

SRO/ATC (1) Verifies reactor trip (trip bkrs open, rods on bottom, NIs decreasing)

SRO/ATC (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)

SRO/BOP (3) Checks vital 4kv bus status (VB4, white lights on mimic; buses F and G are both illuminated) o Determines two vital buses energized (Bus G and F, both powered by respective D/Gs) o May note D/G 11 OOS since beginning of shift Note: Critical task to manually start at least one low head ECCS pump must be completed before transition out of E0. Action is addressed as part of App E, step 5 alignment verification, but may be addressed as soon as failure is identified.

SRO/ATC (4) Checks SI actuated (PK0821 ON, also checks VB1 red train light ON and/or train equipment to verify both trains actuated) o Both trains of SI actuated as indicated by PK, SI red light o May report SI pumps NOT running (SI Pp 11 tripped on OC; SI Pp 12 has no power - Bus H deenergized) o May report RHR pump status (RHR Pp 11 did not auto start, may have been started manually**; RHR Pp 12 has no power - Bus H deenergized)

• • Critical Task E0H: Manually start at least one low head ECCS pump before transition out of E0 (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 22 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7,8 Page 20 of 27 Event

Description:

Large Break LOCA RHR and Containment Spray Pump Autostart Failures (CT)

Time Position Applicants Actions or Behavior (EOP E0,"Reactor Trip or Safety Injection", continued)

SRO (5) Directs implementation of App E (usually given to BOP)

Note: Critical task to manually start at least one low head ECCS pump must be completed before transition out of E0; may have been addressed during performance of immediate actions BOP Implements App E (ESF Auto Actions, Secondary and Auxiliaries Status):

(1a) Checks no personnel in Containment (part of turnover; may not voice)

(1b) Announces trip/SI on PA system (2) Checks main generator - tripped (PK1401 ON, output bkrs open, and exciter field bkr open, CC3 right side)

(3 & 4) Verifies Phase A and Containment Vent Isolation complete (VB1, Monitor Light Box B: red lights ON, white lights OFF) o Notes only white light is associated with seal water Phase A isolation valve, inside containment; outside containment valve is closed (5) Verifies ESF (SI) actuation complete (SI Portion of Monitor Light Box C: red light ON, white lights some ON);

(5.a RNO) Determines CCP 11, 12, and SI 11 are tripped on overcurrent o Notes CCW 13, RHR 12, SI 12, and CFCU 14 not running due to loss of Bus H o Identifies RHR 11 autostart failure; manually starts pump** (if not previously identified)

• • Critical Task E0H: Manually start at least one low head ECCS pump before transition out of E0 (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 23 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7,8 Page 21 of 27 Event

Description:

Large Break LOCA RHR and Containment Spray Pump Autostart Failures (CT)

Time Position Applicants Actions or Behavior (EOP E0, Appendix E, continued)

Note: If Feedwater Isolation activated during E0.1 (RCS temp < 554oF), manual isolation may already be complete BOP (6) Verifies Feedwater isolation complete (F.W. Isolation and S.G. Level Portions of Monitor Light Box C: red lights ON, white lights OFF)

(6.a RNO)Notes white light ON for FW Isolation Valve FCV440 (also bus H);

contacts Turbine Watch to close valve (may wait to contact until after Shift Foreman status update at step 11)

Note: Critical task to start Containment Spray Pump (CSP) 11 may have been addressed during performance of immediate actions BOP (7) Determines Containment Spray and Phase B Isolation is required (Contmt Isol, Phase B portion of Monitor Light Box D: red lights are ON)

(7.a.1 RNO) May attempt to manually initiate Containment Isolation Phase B/Spray (VB1, directly below containment environment indications)

(7.a.2 RNO) Notes white lights on for Containment Spray Pump 12, Containment Spray valves 8994B and 9001B, and CCW valves: FCV746, FCV357, FCV749 are all due to loss of bus H. Identifies failed autostart of Containment Spray Pump 11; manually starts pump**

(7.a.3 RNO) Maintains RCP seal injection between 813 gpm (may need to start CCP 13)

(7.a.4 RNO) Notes RCPs are already tripped due to loss of 12 kV power

• • Critical task E0E: manually actuate at least the minimum required complement of containment cooling equipment before an extreme (redpath) challenge develops to the containment critical safety function. Minimum required complement of containment cooling equipment is defined as 2 Containment Fan Cooling Units (CFCUs) and 1 Containment Spray Pump.

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 24 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7 Page 22 of 27 Event

Description:

Large Break LOCA Time Position Applicants Actions or Behavior (EOP E0, Appendix E, continued)

BOP (8) Checks Main Steamline Isolation complete (Main Steam Isolation portion of Monitor Light Box D: red light ON, white light are OFF)

Note: Step to control AFW to limit cooldown may have already been completed (E0, step 6 RNO) by other crew members; actions taken in Appendix E should reflect overall mitigation strategy (9) Checks AFW status o AFW Pp 13 and TDAFP both running o Reverifies min of 435 gpm flow (VB3 center) or S/G level > 25% (adverse containment) (VB3 center)

BOP (10) Checks ECCS flows (charging injection (VB2 upper panel left), SI, RHR (both on VB1 upper panel); notes RHR 11 is the only available and running ECCS pump (11) Reports ESF and AFW status to the Shift Foreman (Shift Foreman may direct operator to continue on in Appendix E, or redirect to higher priority tasks)

BOP (12 & 13) Checks excess letdown - not in service (8166/8167 closed); turns on aux bldg vent charcoal filter preheater (VB4 lower panel, left side)

(14) Checks secondary systems (MFPs tripped (VB2, green lights ON), stops all but one CB Pp set, takes LCV12 control switch to CONT ONLY. Determines Condenser is NOT available (MSIVs are closed) and directs field operators to break vacuum when turbine is less than 200 rpm (15) Verifies proper operation of Aux Bldg and Control Rm vent systems (VB4 vent status light panel white lights); verifies containment iodine fans secured (VB4, lower panel)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 25 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7 Page 23 of 27 Event

Description:

Large Break LOCA Time Position Applicants Actions or Behavior (EOP E0, Appendix E, continued)

(16) Verifies available DGs running normally (VB4, freq (60), volts (120), speed (900))

(17) Verifies vital batteries supplied by chargers (charger and bus volts on VB5, upper panel middle/lower area);

(18) Verifies MSRs reset (CC3 Triconex HMI)

(19) Throttles RCP seal injection flows to normal if needed (FCV128, to 813 gpm each, CC2)

(20) Checks PK1104 NOT IN (SFP alarm)

(21) Notifies Shift Foreman of completion (EOP E0, Reactor Trip or Safety Injection", continued)

SRO/ATC (6) Checks RCS temperature stable or lowering to 547oF o Notes temperature has dropped significantly due to LBLOCA,(VB2, upper panel lower area) o May throttle AFW back, but with no impact - may verbalize secondary no longer functioning as heat sink (VB3, lower left skirt)

SRO/ATC (7) Checks Pzr PORVs and Pzr Safeties and Spray Valves o Safeties closed (closed); no sonic flow, tailpipe temperature is elevated, but consistent with containment environment (VB2 - upper panel, far right) o PORVs closed and associated block valves open, with exception of PCV456 failure from earlier which has already been addressed (VB2 - upper panel, far right) o Pzr Sprays closed (green lights on) (CC2)

SRO/ATC (8) Checks RCP trip criteria; notes RCPs already tripped from loss of 12 kV (VB2)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 26 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7 Page 24 of 27 Event

Description:

Large Break LOCA Residual Heat Removal and Containment Spray Pump Autostart Failures Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection", continued)

SRO/ATC (9) Determines S/G are NOT faulted o May note S/Gs are depressurizing, but as consequence of LBLOCA cooldown o None are completely depressurized SRO/ATC (10) Determines S/G are NOT ruptured Checks RE71/72/73/74 and RE15/19 recorders onVB2 (and PPC); (all normal)

PK1106/17/18 (all OFF)

May request samples SRO/ALL (11) Checks RCS intact (it is not) (note: only one valid abnormal reading needed to transition from E0)

(11a) Determines containment pressure is NOT normal (it is elevated) (VB1 meters, PPC)

(11b) Determines containment sump levels NOT normal (they are elevated) (VB1 meters, PAMS)

(11c) Determines containment radiation is NOT normal (RM11, 02, 07 are all in alarm)

(11 RNO) Places 2nd ASW/CCW HX in service (opens FCV603 and FCV431, VB1 far left), and transition to EOP E1, "Loss of Reactor or Secondary Coolant" (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 27 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7 Page 25 of 27 Event

Description:

Large Break LOCA Time Position Applicants Actions or Behavior (EOP E0, Reactor Trip or Safety Injection", continued)

SRO Performs procedure transition brief for E1, and implements CSFST (if required)

Note: A CSFST MAGENTA path may occur prior to EOP E1 entry or before the end of the scenario (FRP.1 on PTS); If its occurs, it will be a short entry (perform a single step and exit)

SRO Implements FRP.1, Imminent PTS (if MAGENTA path occurs)

(ONLY IF FRP.1, Imminent PTS, is entered; otherwise, this section is N/A)

SRO/ATC (1) Checks RCS pressure (low), and RHR flow (normal); exits to procedure in effect SRO Implements EOP E1, Loss of Reactor or Secondary Coolant (EOP E1, Loss of Reactor or Secondary Coolant)

SRO/ATC (1) Checks RCPs tripped (already done, VB2)

ATC/BOP (2 & 3) Checks for faulted/ruptured S/Gs o Faulted - checks all S/G pressures on VB3 (not uncontrolled drop/depressurized; all are dropping slowly, as the primary is now the heat sink for the secondary) o Ruptured - checks RE71/72/73/74 and RE15/19 recorders on VB2 (and PPC; no upward trends or spikes, unless containment shine is noted), and PK1106/17/18 (alarms not in); requests chemistry to sample S/Gs for activity (as follows, if done):

Verifies phase A containment isolation reset (VB1)

Opens FCV584 (air to containment) (VB4, lower left)

Opens blowdown isolation valves inside containment (FCV760, 761, 762, 763) if requested for sampling (continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 28 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7 Page 26 of 27 Event

Description:

Large Break LOCA Time Position Applicants Actions or Behavior (EOP E1, Loss of Reactor or Secondary Coolant)

BOP (4) Maintains S/G levels 2065%

(5) Reverifies PORVs closed and associated block valves open (PCV456 failure BOP addressed earlier) (VB2 - upper panel, far right)

ATC (6) Determines Containment Spray should remain in service o (a) PK0118 is ON o (b) Containment radiation levels are above normal (PK1121 is ON, RE2/RE7 in alarm (b RNO) Verifies spray system still in service (VB1, middle skirt)

ATC (7) Determines ECCS flow should NOT be reduced o (a) RCS subcooling is less than 20oF (SCMM YI31, lower center VB2)

SRO/ATC Reads CAUTION regarding running RHR pump with cooling to associated heat exchanger; may note Hx already in service (8) Determines RHR pump should NOT be stopped o (a.1) Notes pressure is less than 300 psig (a.1 RNO) Checks all available RHR pumps running, continues to step 10 SRO/BOP (10) Determines D/G should NOT be stopped o (a) Offsite power is not available, Bus F and G currently supplied by respective D/Gs (a.1 RNO) May implement OP AP26, "Loss of Offsite Power" (Offsite power will not be returned; observable Control Room actions repeat steps of ECA 0.3 performed earlier in the scenario)

(continued on next page)

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 29 of 35 Rev 1

Appendix D (rev 9) Required Operator Actions Form ESD2 OpTest No.: L121NRC Scenario No.: 4 Event No.: 7 Page 27 of 27 Event

Description:

Large Break LOCA Time Position Applicants Actions or Behavior (EOP E1, Loss of Reactor or Secondary Coolant)

SRO/ATC (10.b) Resets SI (VB1, center, below PK2)

SRO/ALL (11) Evaluates Plant Status o (a) Verifies cold leg recirculation capability - power available to RHR 11 o (b) Checks Aux building radiation monitor - all are Normal o (c) Checks if running RHR pump is on recir - it is not o (d) Directs RO to Implement Appendix P, Monitor Light Box Verification (checks ECCS valve lineup) o (e) Contacts Chemistry to sample the RCS and place H2 analyzers in service o (f) Checks Turbine status (oil pumps, coast down, etc) o (g) Checks for alarms on Spent Fuel Pool level and temperature SRO/ATC (12) Determines that post LOCA cooldown procedure (EOP 1.2) is not appropriate o (RCS pressure is < 300 psig (VB2, PPC, CC2) o RHR flow > 100 gpm (VB2)

Stays in E1, awaiting transition to Cold Leg Recirc (RWST @ 33%)

The scenario is terminated once crew has completed actions of EOP E1 and is waiting to transition to Cold Leg Recirc, per Lead Evaluator

• • Critical Task L121 NRC Sim Exam 04 r1.doc Page 30 of 35 Rev 1

ES-301 Transient and Event Checklist Form ES-301-5 Group I (I1, I2, R1)

Facility: Diablo Canyon Date of Exam: August 8 2014 Operating Test Number: L121 A E Scenarios P V 1(I2,I1,R1) 2(Spare) 3(I1,I2,R1) 4(I1,R1,I2)

P E T M L N CREW CREW CREW CREW O I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T O R T O R T O R T O U T P O C P O C P O C P O C P M(*)

E R I U RX 1 3 2 1 1 0 RO NOR 1* 1 1 1 1 SRO-I I/C 5,6 *,2,3,4 1,2,4,6 9 4 4 2 SRO-U MAJ 7,8 5,7 5,7 6 2 2 1 TS 1,3 2,4 4 0 2 2 RX 3 3 2 1 1 0 RO NOR 3* 1 1 1 1 SRO-I I/C *,4,5,6 1,3 1,2,4,6,8 10 4 4 2 SRO-U MAJ 7,8 5,7 5,7 4 2 2 1 TS 2,3,6 3 0 2 2 RX 3 1 1 1 0 RO NOR 3* 1 1 1 1 SRO-I 1,2,3,4,6, I/C *,4,6,9 8

4 10 4 4 2 SRO-U MAJ 7,8 5,7 5,7 6 2 2 1 TS 0 0 2 2 RX 1 1 0 RO NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301, Page 26 of 27 Rev 2 Final Submittal

ES-301 Transient and Event Checklist Form ES-301-5 Group II (I1, R2, R3)

Facility: Diablo Canyon Date of Exam: August 8 2014 Operating Test Number: L121 A E Scenarios P V 1(I3,R3,R2) 2(Spare) 3(Sur,I3,R2) 4(I3,R2,R3)

P E T M L N CREW CREW CREW CREW O I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T O R T O R T O R T O U T P O C P O C P O C P O C P M(*)

E R I U RX 3 3 2 1 1 0 RO NOR 3* 1 1 1 1 SRO-I I/C *,4,5,6 1,3 1,2,4,6 9 4 4 2 SRO-U MAJ 7,8 5,7 5,7 6 2 2 1 TS 2,3,6 2,4 5 0 2 2 RX 3 1 1 1 0 RO NOR 3* 1 1 1 1 SRO-I 1,2,3,4,6, I/C *,4,6,9 8

4 10 4 4 2 SRO-U MAJ 7,8 5,7 5,7 6 2 2 1 TS 0 0 2 2 RX 1 3 2 1 1 0 RO NOR 1* 1 1 1 1 SRO-I I/C 5,6 *,2,4,6,8 6 4 4 2 SRO-U MAJ 7,8 5,7 4 2 2 1 TS 0 0 2 2 RX 1 1 0 RO NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301, Page 26 of 27 Rev 2 Final Submittal

ES-301 Transient and Event Checklist Form ES-301-5 Group III (U1, R4, R5)

Facility: Diablo Canyon Date of Exam: August 8 2014 Operating Test Number: L121 A E Scenarios P V 1(U1,R5,R4) 2(Spare) 3(U1,R4,R5) 4(-,-,-)

P E T M L N CREW CREW CREW CREW O I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T O R T O R T O R T O U T P O C P O C P O C P O C P M(*)

E R I U RX 0 1 1 0 RO NOR 3* 1 1 1 1 SRO-I I/C *,4,5,6 1,2,3,4 7 4 4 2 SRO-U MAJ 7,8 5,7 4 2 2 1 TS 2,3,6 1,3 5 0 2 2 RX 3 1 1 1 0 RO NOR 3* 1 1 1 1 SRO-I I/C *,4,6,9 1,3 5 4 4 2 SRO-U MAJ 7,8 5,7 4 2 2 1 TS 0 0 2 2 RX 1 1 1 1 0 RO NOR 1* 1 1 1 1 SRO-I *,2,3,4,6, I/C 5,6 8 7 4 4 2 SRO-U MAJ 7,8 5,7 4 2 2 1 TS 0 0 2 2 RX 1 1 0 RO NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301, Page 26 of 27 Rev 2 Final Submittal

ES-301 Transient and Event Checklist Form ES-301-5 Group VI (U2, R6, R7)

Facility: Diablo Canyon Date of Exam: August 8 2014 Operating Test Number: L121 A E Scenarios P V 1(U1,R5,R4) 2(Spare) 3(U1,R4,R5) 4(-,-,-)

P E T M L N CREW CREW CREW CREW O I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T O R T O R T O R T O U T P O C P O C P O C P O C P M(*)

E R I U RX 0 1 1 0 RO NOR 3* 1 1 1 1 SRO-I I/C *,4,5,6 1,2,3,4 7 4 4 2 SRO-U MAJ 7,8 5,7 4 2 2 1 TS 2,3,6 1,3 5 0 2 2 RX 3 1 1 1 0 RO NOR 3* 1 1 1 1 SRO-I I/C *,4,6,9 1,3 5 4 4 2 SRO-U MAJ 7,8 5,7 4 2 2 1 TS 0 0 2 2 RX 1 1 1 1 0 RO NOR 1* 1 1 1 1 SRO-I *,2,3,4,6, I/C 5,6 8 7 4 4 2 SRO-U MAJ 7,8 5,7 4 2 2 1 TS 0 0 2 2 RX 1 1 0 RO NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301, Page 26 of 27 Rev 2 Final Submittal

ES-301 Competencies Checklist Form ES-301-6 Facility: Diablo Canyon Date of Examination: Aug 8, 2014 Operating Test No.: L121 GROUP 1 APPLICANTS RO RO RO1 RO SRO-I1 SRO-I2 SRO-I SRO-I Competencies SRO-U SRO-U SRO-U SRO-U SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/ Diagnose 2,3,4,5, 6,7,8 1,2,3,4, 1,2,4,5, 2,3,4,5, 5,7,8 6,7 6,7,8 1,2,3,4, 1,2,4,5, 2,3,4,5, 5,7 6,7,8 6,7,8,9 1,2,3,4, 1,2,4,5, 5,6,7,8 7 Events and Conditions Comply With and Use 1,2,3,5, 6,7,8 1,2,3,4, 1,2,3,4, 1,2,3,4, 5,7,8 5,6,7 5,6,7,8 1,3,5,7 1,2,3,4, 2,3,4,6, 5,6,7,8 7,8,9 1,2,3,4, 1,3,4,5, 5,6,7,8 7 Procedures (1)

Operate Control 1,5,6,7, 8 1,3,5 1,3,4,6, 3,4,6,8, 7,8 9 1,2,3,4, 5,6,7,8 3,4,5,7 Boards (2)

Communicate 1,2,3,5, 6,7,8 1,2,3,4, 1,2,3,4, 1,2,3,4, 5,7,8 5,6,7,8 5,6,7,8 1,3,5,7 1,2,3,4, 2,3,4,5, 5,6,7,8 6,7,8,9 1,2,3,4, 1,2,3,4, 5,6,7,8 5,7 and Interact Demonstrate 1,2,3,4, 1,2,3,4, 1,2,3,4, 5,7,8 5,6,7,8 5,6,7,8 Supervisory Ability (3)

Comply With and 1,3 2,4 2,3,6 Use Tech Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-301, Page 27 of 27 Rev 1

ES-301 Competencies Checklist Form ES-301-6 Facility: Diablo Canyon Date of Examination: Aug 8, 2014 Operating Test No.: L121 GROUP II APPLICANTS RO RO2 RO3 RO SRO-I3 SRO-I SRO-I SRO-I Competencies SRO-U SRO-U SRO-U SRO-U SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/ Diagnose 2,3,4,5, 6,7,8 1,2,3,4, 1,2,4,5, 2,3,4,5, 5,7 6,7 6,7,8,9 1,2,3,4, 1,2,4,5, 2,3,4,5, 5,6,7,8 7 6,7,8 1,2,4,5, 6,7,8 Events and Conditions Comply With and Use 1,2,3,4, 5,6,7,8 1,3,5,7 1,2,3,4, 2,3,4,6, 5,6,7 7,8,9 1,2,3,4, 1,3,4,5, 1,2,3,5, 5,6,7,8 7 6,7,8 1,2,3,4, 5,6,7,8 Procedures (1)

Operate Control 1,3,5 3,4,6,8, 9

1,2,3,4, 5,6,7,8 3,4,5,7 1,5,6,7, 8

1,3,4,6, 7,8 Boards (2)

Communicate 1,2,3,4, 5,6,7,8 1,3,5,7 1,2,3,4, 2,3,4,5, 5,6,7,8 6,7,8,9 1,2,3,4, 1,2,3,4, 1,2,3,5, 5,6,7,8 5,7 6,7,8 1,2,3,4, 5,6,7,8 and Interact Demonstrate 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 Supervisory Ability (3)

Comply With and 2,3,6 2,4 Use Tech Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-301, Page 27 of 27 Rev 1

ES-301 Competencies Checklist Form ES-301-6 Facility: Diablo Canyon Date of Examination: Aug 8, 2014 Operating Test No.: L121 GROUP III APPLICANTS RO RO4 RO5 RO SRO-I SRO-I SRO-I SRO-I Competencies SRO-U1 SRO-U SRO-U SRO-U SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/ Diagnose 2,3,4,5, 6,7,8 1,2,3,4, 5,7,8 2,3,4,5, 6,7,8,9 1,2,3,4, 5,7 2,3,4,5, 6,7,8 1,2,3,4, 5,6,7,8 Events and Conditions Comply With and Use 1,2,3,4, 5,6,7,8 1,2,3,4, 5,7,8 2,3,4,6, 7,8,9 1,3,5,7 1,2,3,5, 6,7,8 1,2,3,4, 5,6,7,8 Procedures (1)

Operate Control 3,4,6,8, 9 1,3,5 1,5,6,7, 8

1,2,3,4, 5,6,7,8 Boards (2)

Communicate 1,2,3,4, 5,6,7,8 1,2,3,4, 5,7,8 2,3,4,5, 6,7,8,9 1,3,5,7 1,2,3,5, 6,7,8 1,2,3,4, 5,6,7,8 and Interact Demonstrate 1,2,3,4, 5,6,7,8 1,2,3,4, 5,7,8 Supervisory Ability (3)

Comply With and 2,3,6 1,3 Use Tech Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-301, Page 27 of 27 Rev 1

ES-301 Competencies Checklist Form ES-301-6 Facility: Diablo Canyon Date of Examination: Aug 8, 2014 Operating Test No.: L121 GROUP III APPLICANTS RO RO6 RO7 RO SRO-I SRO-I SRO-I SRO-I Competencies SRO-U2 SRO-U SRO-U SRO-U SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/ Diagnose 2,3,4,5, 6,7,8 1,2,3,4, 5,7,8 2,3,4,5, 6,7,8,9 1,2,3,4, 5,7 2,3,4,5, 6,7,8 1,2,3,4, 5,6,7,8 Events and Conditions Comply With and Use 1,2,3,4, 5,6,7,8 1,2,3,4, 5,7,8 2,3,4,6, 7,8,9 1,3,5,7 1,2,3,5, 6,7,8 1,2,3,4, 5,6,7,8 Procedures (1)

Operate Control 3,4,6,8, 9 1,3,5 1,5,6,7, 8

1,2,3,4, 5,6,7,8 Boards (2)

Communicate 1,2,3,4, 5,6,7,8 1,2,3,4, 5,7,8 2,3,4,5, 6,7,8,9 1,3,5,7 1,2,3,5, 6,7,8 1,2,3,4, 5,6,7,8 and Interact Demonstrate 1,2,3,4, 5,6,7,8 1,2,3,4, 5,7,8 Supervisory Ability (3)

Comply With and 2,3,6 1,3 Use Tech Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-301, Page 27 of 27 Rev 1