Revision as of 09:27, 30 October 2019

Text

Draft Operating Exam (Section a, Section B, Section C) (Folder 2)
	ML17013A462
Person / Time
Site:	Susquehanna
Issue date:	11/14/2016
From:	; Operations Branch I
To:	;
Shared Package
ML16076A438	List: IR 05000387/2016301; ML16155A069; ML16315A244; ML17013A454; ML17013A455; ML17013A457; ML17013A458; ML17013A459; ML17013A460; ML17013A461; ML17013A462; ML17102A838; ML17102A839;
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{{#Wiki_filter:SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: __c. . o. ......m.. .,p. . .,1..... et......e_A_b.._o.....rt.....e_d_E_v_o......lu=t"""'io;...;..n"'""L""'"o'"""g.___ _ _ _ _ _ _ _ _ _ _ __ JPM#: OO.AD.21017.001 Revision:_o;;;....____ Date: 09/23/2016 Applicability: ~ RO ~ SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic KIA Number 2.1.20 KIA Importance 2.1.20 Alternate Path: D YES ~ NO Time Critical DYES ~ NO Validation Time (min): _ _2..._5__ Examinee Name:

                      --                       ----------------

Last, First Ml Employee Number Exam Date: Exam Duration (Min): _ _ _ _ _ _ _ __

            ---------

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator: _ _ _ _ _ _ _ _ _ __ Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.21017.001 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES OP-133-001 Chemical Addition to Turbine Building Chilled Water System (Rev. 37) marked up to step 2.5.10 (2.5.10 only circled, not slashed) OP-AD-002 Standards for Shift Operation (Rev. 63) Blank Aborted Evolution Control Log (AECL) OP-AD-002-3 Attachment B Ill. TASK CONDITIONS Unit 1 is in Mode 1 All Plant Equipment required for Mode 1 is in operation Turbine Building Chilled Water System in Service The Turbine building NPO is performing a Chemical Addition to Turbine Building Chilled Water System IAW OP-133-001 Section 2.5. During step 2.5.10 TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened. Maintenance will not be available until dayshift tomorrow to support opening the 188003 valve. You are the Unit 1 PCOM IV. INITIATING CUE Your Supervisor directs you complete the necessary administrative documentation to turn this information over to the on-coming shift. V. TASK STANDARD Aborted Evolution Control Log identifies TB Chilled Wtr Chem Add Tank Out In valve 188003 could not be opened. Unit 1 turbine bldg. NPO, and Control Room Supervisor notified to make turnover sheet entries referencing the Aborted evolution. Plant operator turnover sheet entry referencing the Aborted evolution is made.

TQ-106-Lr.:> 10 Revision 1 Page 3 of 9 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step .
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
The time clock starts when the candidate acknowledges the Initiating Cue .
This JPM can be performed in the simulator, classroom or other similar environment.
Mark-up a copy of OP-133-001 filled out up to step 2.5.10 (2.5.10 only circled, not slashed) .
Replacement pages for JPM: Section 5. 7 of OP-AD-002 and blank Aborted Evolution Control Log (AECL) OP-AD-002-3 Attachment B EVALUATOR CUE Record JPM start time:

Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OP-AD-002, S/U controlled copy. Standards for shift operations. 2 Selects the correct procedure section to perform. Performs OP-AD-002 section 5. 7, Aborted S/U OP-AD-002 Section 5. 7 Evolution Control Log (AECL) 3 Completes OP-AD-002 Attachment B Completes OP-AD-002 Attachment B when : S/U

An evolution is aborted prior to completion and will not be resumed prior to shift turnover.
Equipment is left in an abnormal lineup and additional information is essential to the oncoming shift.

  *4  Completes OP-AD-002 Attachment B                      Completes Attachment B as follows:                  S/U

Line 1; Date, Time, and name .
Line 2; System number 133 and system name Turbine Building Chilled Water System

                                                            * *Line 3; Procedure number OP-133-001, Revision 37, step 2.5.10
                                                             *  *Line  4; TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened

TQ-106-lJ;:) 10 Revision 1 Page 4 of 9 EVALUATOR NOTE Due to the nature of this JPM, the information provided by the candidate in the next 2 steps may vary from the information scripted in the STANDARD column. Evaluator judgment may need to be applied to information provided by the candidate. 5 Completes OP-AD-002 Att B cont'd

Line 5, NONE S/U
Line 6, notes to resume procedure OP-133-001 beginning at step 2.5.10
Line 7, Left Blank

 *6    Documents and communicates AECL data

Each AECL activity shall be referenced S/U on the Turnover Sheet of the Operator performing the evolution and be reviewed as part of the Turnover process until such time as the AECL is no longer required, or in control

                                                              *   *Informs Turbine building NPO of Administrative requirements for the aborted evolution.

0 Reference the aborted evolution IAW the AECL form And 0 Review the AECL as part of the turnover to the oncoming shift EVALUATOR CUE Role-play as Turbine building NPO acknowledge the report

 *7    Notifies Unit Supervisor                               Informs Unit Supervisor to:

Reference the aborted evolution IAW the AECL form S/U AND
Review the AECL as part of the turnover to the oncoming shift EVALUATOR CUE Role-play as Turbine building NPO acknowledge the report

TQ-106-D-;j 10 Revision 1 Page 5 of 9 8 Identifies requirement to log the equipment failure Informs Unit 1 Control room Supervisor to: in the shift log and initiate a Condition Report.

a Narrative Log entry must be made S/U a Condition Report must be initiated EVALUATOR NOTE I CUE Role-play as Unit Supervisor acknowledge the report EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM. EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 7 of 9 REVISION

SUMMARY

JOB PERFORMANCE MEASURE OO.AD.21017.001 Revision Description/Purpose of Revision 0 New JPM, Replaced OO.AD.038.001

Page 8 of 9 EVALUATOR COPY: TASK CONDITIONS Unit 1 is in Mode 1 All Plant Equipment required for Mode 1 is in operation Turbine Building Chilled Water System in Service The Turbine building NPO is performing a Chemical Addition to Turbine Building Chilled Water System IAW OP-133-001 Section 2.5. During step 2.5.10 TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened. Maintenance will not be available until dayshift tomorrow to support opening the 188003 valve. You are the Unit 1 PCOM INITIATING CUE Your Supervisor directs you complete the necessary administrative documentation to turn this information over to the on-coming shift.

Page 9 of 9 EXAMINEE COPY: TASK CONDITIONS Unit 1 is in Mode 1 All Plant Equipment required for Mode 1 is in operation Turbine Building Chilled Water System in Service The Turbine building NPO is performing a Chemical Addition to Turbine Building Chilled Water System IAW OP-133-001 Section 2.5. During step 2.5.10 TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened. Maintenance will not be available until dayshift tomorrow to support opening the 188003 valve. You are the Unit 1 PCOM INITIATING CUE Your Supervisor directs you complete the necessary administrative documentation to turn this information over to the on-coming shift.

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Perform Validation of Heat Balance at 90% Power JPM#: OO.AD.20927.101 Revision: O Date: 9/25/2016

                                                           -----

Applicability: ~SRO Setting: Classroom NUREG-1123 E/APE I Sys_G-=----- KIA Number_2_._1_.7_ _ _K/A Importance _4..;..;'.;...7_ __ Alternate Path: DYES ~ NO Time Critical DYES ~ NO Validation Time (min):__..;;;2=5_ _ q(l?(/J 1 /z_(, bl,

                                                                            /
                                                                'f /J=.f / It Approval: _ _   ru

___l.....;j"""'--~

                               . . . . . . .- - - - Date:

Nuclear Training Supervisor Cf* l7* lb Examinee Name:

                 ~-----------------

Last, First Ml Employee Number Exam Date: _ _ _ _ _ _ _ __ Exam Duration (Min): _ _ _ _ _ _ _ __ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator: _ _ _ _ _ _ _ _ _ __ Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.20927.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. RE-1 TP-026, VALIDATION OF CORE THERMAL POWER HEAT BALANCE (REV 12) III. TASK CONDITIONS

1. A plant startup is in progress on Unit 1.

2. APRMs indicate as follows: #1 - 89.9%, #2 - 90.1%, #3 - 92.2%, and #4 - 90.3%.

3. % Core Thermal Power (OD-3) is 90%.

4. LPRM arithmetic average from Pl is 46.5.

5. All LPRMs used in the arithmetic average are valid.

6. HPTE pressure at entrance of the A Moisture Seperator (TEP02) is 187 psig.

7. HPTE pressure at entrance of the B Moisture Seperator (TEP03) is 188 psig.

8. Computer Point NBA14 is 93.026 %PWR.

9. Computer Point NBA 15 is 93.329 %PWR.

10. Computer Point NBA16 is 94.7 %PWR.

11. Computer Point NBA17 is 93.16.

12. Computer Point NFA50 is 15.5011 MLBS/H.

IV. INITIATING CUE Perform RE-1TP-026, Validation of Heat Balance. Determine what action, if any, is required. Document conclusions, as necessary, on this cue sheet. V. TASK STANDARD Completes RE-1TP-026, determines the Heat Balance cannot be validated, and contacts STA and Reactor Engineering to perform RE-1TP-026 Attachment C.

TQ-106-us1 o Revision 1 Page 3 of 10 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step.
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
The time clock starts when the candidate acknowledges the initiating cue.
Ensure the following material is available to support this JPM; RE-1TP-026 and a calculator.

EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Obtain a controlled copy of RE-1 TP-026 Controlled copy obtained from evaluator sru 2 Selects correct procedure section(s). Determines section 4.2 and Attachment B S/U applies 3* Record the % CTP as determined by Heat Balance Records the % CTP on Attachment B step 4.2.1 as 90 S/U (i.e., OD-3) on Attachment B. 4 Validate % CTP based on HPTE pressure to the A Records the HPTE pressure at entrance of Moisture Separator. the A moisture separator (Computer Point TEP02) on Attachment B step 4.2.2.a as 187 SIU Record the HPTE pressure at entrance of the A moisture separator (Computer Point TEP02) on Attachment B. 5 Plot Computer Point TEP02 and % CTP (Step Plots Computer Point TEP02 and % CTP 4.2.1) on Attachment G "High Pressure Turbine (Step 4.2.1) on Attachment G "High S/U Exhaust vs. Heat Balance % Power." Pressure Turbine Exhaust vs. Heat Balance

                                                              % Power."

6 Record Computer Point NBA 14 (Alternate % CTP) Records Computer Point NBA14 (Alternate on Attachment B. % CTP) on Attachment B step 4.2.2.c as SIU 93.026.

TQ-106-us1 o Revision 1 Page 4of10 7* Confirm that the plotted point is within the valid Determines that the plotted point for HPTE region OR % CTP is within +/- 2% of the Computer pressure to the A Moisture Separator is NOT Point NBA14 Attachment B. within valid region. S/U Determines that % CTP is NOT within +/- 2% of Computer Point NBA14. 8 Validate % CTP based on HPTE pressure to the B Records the HPTE pressure at entrance of Moisture Separator. the B moisture separator (Computer Point TEP03) on Attachment B step 4.2.3.a as 188. S/U Record the HPTE pressure at entrance of the B moisture separator (Computer Point TEP03) on Attachment B. 9 Plot Computer Point TEP03 and % CTP (Step Plots Computer Point TEP03 and % CTP 4.2.1) on Attachment G "High Pressure Turbine (Step 4.2.1) on Attachment G "High S/U Exhaust vs. Heat Balance % Power. Pressure Turbine Exhaust vs. Heat Balance

                                                      % Power.

10 Record Computer Point NBA 15 (Alternate % CTP) Records Computer Point NBA 15 (Alternate on Attachment B. % CTP) on Attachment B step 4.2.3.c as S/U 93.329. 11* Confirm that the plotted point is within the valid Determines that the plotted point for HPTE region OR % CTP is within +/- 2% of the Computer pressure to the B Moisture Separator is NOT Point NBA 15. Record on Attachment B. within valid region. S/U Determines that % CTP is NOT within +/- 2% of Computer Point NBA 15.

TQ-106-lJ,j 10 Revision 1 Page 5 of 10 12 Validate % CTP based on LPRM average. Indicates need to obtain LPRM current readings, identify non-valid LPRMs, and calculate arithmetic average of the valid Obtain a printout of the current LPRM readings LPRMs SIU (OD-8). Identify non-valid LPRMs. EVALUATOR NOTE If the candidate indicates the need to obtain printout of LPRM readings and calculate the arithmetic average of the valid LPRMs, tell her I him to use the value obtained from the Pl program. 13 Record arithmetic average of the valid LPRM values Records arithmetic average of the valid (Pl program may be used to obtain the LPRM LPRM values (Pl program is not available) S/U average) on Attachment B. on Attachment B step 4.2.4.c as 46.5. 14 Plot the LPRM arithmetic average and % CTP (Step Plots the LPRM arithmetic average and % 4.2.1) on Attachment F "LPRM Average vs. % CTP (Step 4.2.1) on Attachment F "LPRM S/U Power (Heat Balance)." Average vs.% Power (Heat Balance)." 15 Record Computer Point NBA17 (Alternate% CTP) Records Computer Point NBA 17 (Alternate on Attachment B. % CTP) on Attachment B step 4.2.4.e as S/U 93.16. 16* Confirm that the plotted point is within the valid Determines that the plotted point for LPRM region OR % CTP is within +/- 2% of the Computer arithmetic average is NOT within valid Point NBA17. Record on Attachment B region. S/U Determines that % CTP is NOT within +/- 2% of Computer Point NBA17. 17 Attach copy of LPRM readings to Attachment B Indicates need to attach copy of LPRM S/U readings to Attachment B EVALUATOR NOTE If the candidate indicates the need to obtain printout of LPRM readings and attach to Attachment B, tell her I him that another operator will attach the LPRM readings once the Attachment B is complete.

TQ-106-tJ~10 Revision 1 Page 6of10 18 Validate % CTP based on Feedwater Flows. Records Feedwater Flow (Computer Point NFA50) on Attachment B step 4.2.5.a as 15.5011. S/U Record Feedwater Flow (Computer Point NFA50) on Attachment B. 19 Plot Computer Point NFA50 and% CTP (Step Plots Computer Point NFA50 and% CTP 4.2.1) on Attachment H "Feedwater Flow vs. % (Step 4.2.1) on Attachment H "Feedwater S/U Power (Heat Balance)." Flow vs.% Power (Heat Balance)." 20 Record Computer Point NBA16 (Alternate% CTP) Records Computer Point NBA 16 (Alternate on Attachment B. % CTP) on Attachment B step 4.2.5.c as S/U 94.7. 21* Confirm that the plotted point is within the valid Determines that the plotted point for FW region OR % CTP is within +/- 2% of the Computer Flow is NOT within valid region. Point NBA16. Record on Attachment B. S/U Determines that % CTP is NOT within +/- 2% of Computer Point NBA 16. 22* Confirm that the Heat Balance is within the valid Determines that the Heat Balance is NOT regions of any one of the previous four methods (+/- valid for any of the four methods. S/U 2% CTP from OD-3). Record on Attachment B. 23* IF the Heat Balance cannot be validated, Contact Indicates need to contact Reactor Reactor Engineering and the STA to perform Engineering and/or STA to perform S/U Attachment C. Attachment C. EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 8of10 REVISION

SUMMARY

JOB PERFORMANCE MEASURE OO.AD.20927.101 Revision Description/Purpose of Revision 0 New JPM, from OO.AD.3658.101

Page 9 of 10 EVALUATOR COPY: TASK CONDITIONS

1. A plant startup is in progress on Unit I.

2. APRMs indicate as follows: #1 - 89.9%, #2 - 90.l %, #3 - 92.2%, and #4 - 90.3%.

3. % Core Thermal Power (OD-3) is 90%.

4. LPRM arithmetic average from Pl is 46.5.

5. All LPRMs used in the arithmetic average are valid.

6. HPTE pressure at entrance of the A Moisture Seperator (TEP02) is 187 psig.

7. HPTE pressure at entrance of the B Moisture Seperator (TEP03) is 188 psig.

8. Computer Point NBA14 is 93.026 %PWR.

9. Computer Point NBA15 is 93.329 %PWR.

10. Computer Point NBA16 is 94.7 %PWR.

11. Computer Point NBAl 7 is 93.16.

12. Computer Point NF A50 is 15.5011 MLBS/H.

INITIATING CUE Perform RE-1 TP-026, Validation of Heat Balance. Determine what action, if any, is required. Document conclusions, as necessary, on this cue sheet.

Page 10of10 EXAMINEE COPY: TASK CONDITIONS

1. A plant startup is in progress on Unit 1.

2. APRMs indicate as follows: #1 - 89.9%, #2 - 90.1 %, #3 - 92.2%, and #4 - 90.3%.

3. % Core Thermal Power (OD-3) is 90%.

4. LPRM arithmetic average from PI is 46.5.

5. All LPRMs used in the arithmetic average are valid.

6. HPTE pressure at entrance of the A Moisture Seperator (TEP02) is 187 psig.

7. HPTE pressure at entrance of the B Moisture Seperator (TEP03) is 188 psig.

8. Computer Point NBA14 is 93.026 %PWR.

9. Computer Point NBA15 is 93.329 %PWR.

10. Computer Point NBAl 6 is 94. 7 %PWR.

11. Computer Point NBAl 7 is 93.16.

12. Computer Point NFA50 is 15.5011 MLBS/H.

INITIATING CUE Perform RE-1 TP-026, Validation of Heat Balance. Determine what action, if any, is required. Document conclusions, as necessary, on this cue sheet.

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Perform LPRM Upscale Alarm Operability Tracking & Determine Required Actions JPM#: OO.AD.20958.101 Revision: 0

                                               -------- Date:    09/26/2016 Applicability: [8] RO [8] SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic KIA Number_2_._2._14          _ _ _ K/A Importance 3.9/4.3 Alternate Path:    0 YES [8] NO        Time Critical DYES [8] NO Validation Time (min):_4'"""'5"---_

Date: crb-1L1t Operations Re~: _/ Date: z/c~ !_,~,_ validated: .,!CJ_Cf~ Date: °t/%(/t Approval: lV\ Lr::J ~ Date: °J-:L°f*l&- Nuclear TraininQUPervisor Last, First Ml Employee Number Exam Date: Exam Duration (Min): ________________

            ---------------

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:

          ------------------

Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.20958.101 I. SAFETY CONSIDERATIONS A All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A 01-078-001, LPRM Status Control Rev. 18 B. S0-100-008, Weekly Surveillance Operating Log Rev. 33 C. Technical Specification 3.3.1.1 Rev. 3 Ill. TASK CONDITIONS Unit 1 is in MODE 1 at 80 percent power. APRM 2 is INOP and bypassed. APRM Gain Calibration was last performed 5 days ago. LPRM detector 40-57A caused a downscale alarm l&C determined the detector failed. Reactor Engineering requested bypassing the detector. The PCOP has just bypassed LPRM detector 40-57A in the Lower Relay Room. IV. INITIATING CUE Perform LPRM Upscale Alarm operability tracking for LPRM detector 40-57A in accordance with 01-078-001. SRO Only Determine the required action(s) based on your findings V. TASK STANDARD For RO and SRO: Zone 8 is identified as having LESS THAN 50% upscale alarms operable. APRM Channel 1 determined to be INOPERABLE based on < 3 operable LPRM inputs to the "A" Level. For SROs only: Determine that LCO 3.3.3.1 IS NOT MET for APRM required channels, and TS action A.1 is required; place channel in trip within 12.

TQ-106-u~10 Revision 1 Page 3 of 12 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step.
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
The time clock starts when the candidate acknowledges the initiating cue.
This JPM can be performed in the classroom.
Provide a clean copy of 01-078-001. Additionally, markup copies of Attachments A, B and C with LPRM status. Have a clean copy and SO-100-008.

EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OI-078-001, S/U controlled copy. Section 4. 2 Determine current LPRM status Refers to the previously completed copy of S/U Attachments A and B 3 Complete new Attachment A Performs the following

Enters 1 for Unit S/U
Transfers the previous LPRM data to the new Attachment A

  *4   Enter a check ('1) in column (2) for LPRM alarms      Places a checkmark in column 2 adjacent to determined inoperable or bypassed for all other       LPRM detector 40-57A in Zone 8                     S/U reasons.

EVALUATOR NOTE All LPRM Upscale Alarms with a check in column (1) or (2) of Attachment A are inoperable.

TQ-106-Q;y10 Revision 1 Page 4of12

5 Determine if~50% ofLPRM Upscale alarms in Performs the following each zone are operable and circle YES or NO as
Circles YES for zone 1, 2, 3, 4, 5, 6, 7, applicable and9 S/U
Determines that there are LESS THAN 50% operable LPRMs in zone 8, AND circles NO for zone 8.

6 Notify Reactor Engineering of all LPRM upscale Identifies Reactor Engineering previously alarms determined inoperable informed ofLPRM 40-57A status as stated SIU in JPM task conditions. 7 Evaluate the need to place placard to 1C651 Determines that placard is required. indicating < required # of LPRM Upscale Alarms. S/U (requires completion of Attachments C & D, which appears in Step 11, below.)

8 Complete an LPRM vs. APRM Status Control Log Performs the following (Attachment B) each time LPRM operability status
Transfer the previous LPRM data to the is changed. new Attachment B SIU
Circle LPRM detector 40-57 A for APRM 1, under the column 'A' Level, and enter today's date

TQ-106-lJ;j 10 Revision 1 Page 5 of 12

*9 Refer to weekly surveillance S0-100-008 to       Compare the following criteria to current confirm APRM operability requirements maintained APRM/LPRM operability status:
                                                    * < 20 total operable LPRMs per APRM channel
                                                    * <3 LPRM inputs per level (A, B, C, or D)

9 LPRMs inop since last APRM gain

S calibration (after date provide~ in task S/U conditions)

                                                    * *Determine that APRM channel 1 does
                                       -               NOT meet operability requirements due to LESS THAN 3 operable level "A" LPRMs. (The only operable Level A LPRMs in APRM 1 are 40-17A and 08-49A)

10 Track operability of OPRM cells. Performs the following
Transfers the previous LPRM data to the new Attachment C and circles "A LEVEL" for LPRM 40-57.
Determines it inputs to APRMl Cell 03 .
Transfers the previous LPRM data to the new Attachment D and circles LPRM S/U 40-57A in the Cell 03 row, in the LPRM#2 column.
Determines OPRM cell is INOPERABLE due fewer than two operable LPRMs.
Determines OPRM is OPERABLE due to having 22 or more OPERABLE cells

TQ-106-lM10 Revision 1 Page 6 of 12 EVALUATOR CUE For RO examinees, this completes the JPM EVALUATOR CUE For SRO examinee, provide the SRO examinee sheet that addresses determining required actions

*11   Identifies Tech Spec 3.3.1.1 for RPS               Performs the following:

Instrumentation and TR 3.1.3 for Control Rod Block * *Refer to Tech Spec 3.3.1.1 and Instrumentation is not met. determine that a minimum of 3 operable APRM channels are required in MODE 1 per table 3 .3 .1.1-1, therefore action A. l is required; place channel in trip within 12 hours.

                                                         * *Refer to TRM 3 .1.3 and determine that a minimum of 3 operable APRM S/U channels are required in MODE 1 per table 3.1.3-1, therefore action B.2 is required; place 1 channel in tripped condition within 7 days.

Refer to TRM 3.3.9 and determine that a placard will have to be posted at 1C651 indicating less than required number of LPRM upscale alarms, if OPRMs are subsequently declared INOPERABLE EVALUATOR NOTE I CUE That completes the JPM.

EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 8of12 REVISION

SUMMARY

JOB PERFORMANCE MEASURE OO.AD.20958.101 Revision Description/Purpose of Revision 0 New JPM, Revised from Loe 26 1

Page 9 of 12 EVALUATOR COPY: TASK CONDITIONS Unit 1 is in MODE 1 at 80 percent power. APRM 2 is INOP and bypassed. APRM Gain Calibration was last performed 5 days ago. LPRM detector 40-57A caused a downscale alarm l&C determined the detector failed. Reactor Engineering requested bypassing the detector. The PCOP has just bypassed LPRM detector 40-57A in the Lower Relay Room. INITIATING CUE Perform LPRM Upscale Alarm operability tracking for LPRM detector 40-57A in accordance with 01-078-001

Page 10of12 EXAMINEE COPY: TASK CONDITIONS Unit 1 is in MODE 1 at 80 percent power. APRM 2 is INOP and bypassed. APRM Gain Calibration was last performed 5 days ago. LPRM detector 40-57A caused a downscale alarm l&C determined the detector failed. Reactor Engineering requested bypassing the detector. The PCOP has just bypassed LPRM detector 40-57A in the Lower Relay Room. INITIATING CUE Perform LPRM Upscale Alarm operability tracking for LPRM detector 40-57A in accordance with 01-078-001

Page 11 of 12 SRO EVALUATOR COPY: INITIATING CUE Determine the required action(s) based on your findings

Page 12of12 SRO EXAMINEE COPY: INITIATING CUE Determine the required action(s) based on your findings

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Perform Jet Pump Operability Check JPM#: OO.S0.20992.101 Revision:Q Date:08/08/2016 Applicability: IZI RO IZI SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic KIA Number 2.2.12 KIA Importance 3.7/4.1, Alternate Path: DYES IZI NO Time Critical DYES IZI NO Validation Time (min):25 Testing Method: D Simulate Date: 08/08/2016

                     ~--=~'=!:=.::::::::::===...... Date: c;/zi/u~

I' , Validated: _'-'--"....._..............~..-'+----- Date: C[(fJ.b / lb Approval: _*_1fA____..._f~0""""'--Le ____ Date: CJ '2 9 -/ft,.

               'NUCfear ¥raining Supervisor Last, First Ml                                               Employee Number Exam Date: _ _ _ _ _ _ _ __                             Exam Duration (Min): _ _ _ _ _ _ _ __

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:

          -----------

Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.S0.20992.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment~such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

11. REFERENCES A. S0-100-007, DAILY SURVEILLANCE LOG, REV 75 Ill. TASK CONDITIONS A. Unit 1 is operating at 100% power.

B. Both Reactor Recirc pumps and loops are in operation. C. The necessary data to perform the daily surveillance for Recirc pump and jet pump operability has been taken and recorded on Attachment C, PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG. D. No Tech Spec LCO action statements are in effect. IV. INITIATING CUE Using the data provided on Attachment C, Performance Data Sheet Recirculation System Dual Loop, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG:

Complete the remaining items in Attachment C.

V. TASK STANDARD Recirculation pumps declared OPERABLE; Jet pumps declared OPERABLE

TQ-106-lJ.j10 Revision 1 Page 3 of 16 INFORMATION FOR EVALUATOR --

Marking a step as UNSAT requires written comments on respective step .
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
The time clock starts when the candidate acknowledges the initiating cue.
This JPM should be performed in the classroom.
Provide a partially completed S0-100-007 attachment C (Page 1, a-i)
"Candidate's Data Sheet #2" (1 page) is not given to the candidate until they identify the need to evaluate jet pump delta Ps.

EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Obtain a controlled copy of S0-100-007. Controlled copy obtained from evaluator. S/U 2 Selects correct procedure section. Selects Item 1. S/U 3 To determine Recirc Pumps/Jet Pumps and Flow Selects Attachment C Biased Simulated Thermal Power Upscale (RPS) OPERABLE, Complete APPLICABLE Attachments: S/U IF in Dual Loop Operation, Complete Attachment C. For Recirc Pumps and Jet Pumps

TQ-106-l.1010 Revision 1 Page 4 of 16 4* Recirc pumps operable if loop jet pump flow On Attachment C PERFORMANCE DATA mismatch maintained within a or b: Enter N/A for SHEET RECIRCULATION SYSTEM DUAL item that does not apply. LOOP:

a. 5 Mlbm/hr with core flow ;::: 75 Mlbm/hr Compares line g to h.

b. 10 Mlbm/hr with core flow < 75 Mlbm/hr Determines that the mismatch between Loop A and Loop B is 2 Mlbm/hr.

Records: 2 Mlbm/hr on SR 3.4.1.1 line a. Records: N/A on SR 3.4.1.1 line b. SIU Determines Recirc Pumps are operable. Circles YES and places his/her initials under Confirm column on SR 3.4.1.1 line . Records: SAT on Recirc Pumps line of item 1 of S0-100-007 Daily Surveillance Log Attachment A

TQ-106-0~10 Revision 1 Page 5 of 16 5* When recirc pumps operating with flow within limits On Figure 1 RECIRC PUMP A FLOW VS. of a or b above, jet pumps operable if no two (2) SPEED TWO LOOP OPERATION of following conditions exist simultaneously: ATTACHMENT C: Recirculation loop drive flow versus recirculation Plots a point corresponding to: generator speed differs > 10% from established RECIRC GENERATOR A SPEED (SI patterns. (Plot applicable performance data on 14032A) of 87% figures 1 and 2 of this attachment) AND RECIRC PUMP A FLOW (KGPM) of 38 KGPM On Figure 2 RECIRC PUMP B FLOW VS. S/U SPEED TWO LOOP OPERATION of ATTACHMENT C: Plots a point corresponding to: RECIRC GENERATOR B SPEED (SI 140328) of 88% AND RECIRC PUMP B FLOW (KGPM) of 33 KGPM Circles YES and places his/her initials under Confirm column SR 3.4.2.1 line a.

TQ-106-us10 Revision 1 Page 6 of 16 6* Recirculation loop drive flow versus total core flow On Figure 3 TOTAL CORE FLOW VS. differs > 10% from established patterns. (Plot RECIRC PUMP A FLOW TWO LOOP applicable performance data on Figures 3 and 4 of OPERATION of ATTACHMENT C: this attachment) Plots a point corresponding to: RECIRC PUMP A FLOW (KGPM) (FR-831-1R614) of 38 KGPM AND TOTAL CORE FLOW ML8/HR of 92 ML8/HR On Figure 4 TOTAL CORE FLOW VS. S/U RECIRC PUMP 8 FLOW TWO LOOP OPERATION of ATTACHMENT C Plots a point corresponding to: RECIRC PUMP A FLOW (KGPM) (FR-831-1R614) of 33 KGPM AND TOTAL CORE FLOW ML8/HR of 92 ML8/HR Circles NO and places his/her initials under Confirm column SR 3.4.2.1 line b.

TQ-106-u-;::, 10 Revision 1 Page 7 of 16 7 Notifies Reactor Engineering directly that Contacts Reactor Engineering directly and surveillance parameters differ from established notifies that surveillance parameters differ values by more than 5% or notifies SRO to contact from established values by more than 5%. Reactor Engineering. OR Notifies SRO to contact Reactor S/U Engineering. OR Contacts Operator to get additional Jet Pump data. EVALUATOR CUE Role-play Reactor Engineering, SRO, or Operator and acknowledge the report. EVALUATOR CUE Provide the candidate with the Candidate Data Sheet #2 (1 page) (Jet pump delta Ps).

TQ-106-u~10 Revision 1 Page 8 of 16 8 1 Calculates LOOP A JET PUMP ~p PERCENT Records the following data on Attachment C DEVIATION FROM THE AVERAGE to be used in LOOP A JET PUMP ~p PERCENT Plotting applicable performance data on figure 1 of DEVIATION FROM THE AVERAGE: attachment I. 1. JP11_34_[(JP11 - A) +A] X 100 =_-.87_

2. JP12_35_[(JP12 -A)+ A] X 100=_2.04_

3. JP13_34_[(JP13 - A) +A] X 100=_-.87_

4. JP14_35_[(JP14 -A)+ A] X 100 =_2.04_

5. JP15_35_[(JP15 - A) +A] X 100 =_2.04_

6. JP16_35_[(JP16 -A)+ A] X 100 =_2.04_

7. JP17_34_[(JP17 -A)+ A] x 100 =_-.87 _ IsI u

8. JP18_34_[(JP18 - A) +A] X 100 =_-.87_

9. JP19_35_[(JP19 - A) +A] X 100 =_2.04_

10. JP20_32_[(JP20 - A)+ A] X 100 =_-

6.71 A=_343 X 0.1 = _34.3_ (Sum of ~P%) JP11 thru 20 EVALUATOR NOTE The candidate may round these numbers to the nearest tenth.

TQ-106-b~ 10 Revision 1 Page 9 of 16 9 1 Calculates LOOP B JET PUMP LiP PERCENT Records the following data on Attachment C DEVIATION FROM THE AVERAGE to be used in LOOP B JET PUMP LiP PERCENT Plotting applicable performance data on figure 2 of DEVIATION FROM THE AVERAGE: attachment I. 1. JP1_39_[(JP1 - A) +A] X 100 =_3.17_

2. JP2_39_[(JP2 -A)+ A] X 100 =_3.17 _

3. JP3_37_[(JP3-A) +A] X 100 =_-2.12_

4. JP4_39_[(JP4 - A)+ A] X 100 =_3.17_

5. JP5_39_[(JP5 - A) +A] X 100 =_3.17_

6. JP6_39_[(JP6 - A) +A] X 100 =_3.17 _

7. JP7_30_[(JP7 - A)+ A] X 100 =_-20.63_ S/U

8. JP8_39_[(JP8 - A) +A] X 100 =_3.17_

9. JP9_39_[(JP9 - A) +A] X 100 =_3.17_

10. JP10_38_[(JP10 - A) +A] X 100 =_.53_

A =_378 X 0.1 = _37.8_ (Sum of LiP%) JP1 thru 10 EVALUATOR NOTE The candidate may round these numbers to the nearest tenth.

TQ-106-b-;)10 Revision 1 Page 10of16 10* Each jet pump to lower plenum differential pressure On Figure 1 TWO LOOP JET PUMP differs by > 20% from the established patterns, (Plot DISTRIBUTION LOOP A of ATT I applicable performance data on figures 1 and 2 of Plots the following points: attachment I. JP11 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP12 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP13 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP14 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP15 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE S/U JP16 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP17 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP18 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP19 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP20 and -6.71 % DEVIATION FROM THE MEAN DELTA P VALUE Determines that all points are within _:t20% from the established patterns.

EVALUATOR NOTE Plotting of points is not critical in this step.

TQ-106-lJ~ 10 Revision 1 Page 11 of 16 10* Each jet pump to lower plenum differential pressure On Figure 2 TWO LOOP JET PUMP (con) differs by > 20% from the established patterns, (Plot DISTRIBUTION LOOP B of ATT I applicable performance data on figures 1 and 2 of Plots the following points: attachment I. JP1and3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP2 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP3 and -2.12 % DEVIATION FROM THE MEAN DELTA P VALUE JP4 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JPS and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JPG and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP7 and-20.63 % DEVIATION FROM THE MEAN DELTAP VALUE JPS and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP9 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP10 and .53 % DEVIATION FROM THE MEAN DELTA PVALUE Circles NO and places his/her initials under Confirm column SR 3.4.2.1 line c.

EVALUATOR NOTE Plotting of points is not critical in this step.

TQ-106-tr;) 10 Revision 1 Page 12 of 16 11* When recirc pumps operating with flow within limits Determines Jet pumps are operable based of a or b above, jet pumps operable if no two (2) on two (2) of the conditions under SR following conditions exist simultaneously: 3.4.2.1 being met simultaneously. Circles YES and places his/her initials under S/U Confirm column SR 3.4.2.1. Records: SAT on Jet Pumps line of item 1 of S0-100-007 Daily Surveillance Log Attachment A. EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 0 Page 14 of 16 REVISION

SUMMARY

JOB PERFORMANCE MEASURE OO.S0.20992.101 Revision Description/Purpose of Revision 0 New JPM, From OO.S0.003.051

Page 15 of 16 EVALUATOR COPY: TASK CONDITIONS A. Unit 1 is operating at 100% power. B. Both Reactor Recirc pumps and loops are in operation. C. The necessary data to perform the daily surveillance for Recirc pump and jet pump operability has been taken and recorded on Attachment C, PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG. D. No Tech Spec LCO action statements are in effect. INITIATING CUE Using the data provided on Attachment C, Performance Data Sheet Recirculation System Dual Loop, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG:

Complete the remaining items in Attachment C.

Page 16 of 16 EXAMINEE COPY: TASK CONDITIONS A. Unit 1 is operating at 100% power. B. Both Reactor Recirc pumps and loops are in operation. C. The necessary data to perform the daily surveillance for Recirc pump and jet pump operability has been taken and recorded on Attachment C, PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG. D. No Tech Spec LCO action statements are in effect. INITIATING CUE Using the data provided on Attachment C, Performance Data Sheet Recirculation System Dual Loop, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG:

Complete the remaining items in Attachment C.

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: _ _ __..D:;.. ;e;;..;;te=r;..;;.;m;.;;..;;i. ;.;;.n. ;;;..e. . ;;;;O"'"'p=e.;. ;;ra=b--il=it;.£. y. . ;;;;o;.;;.. f=M=S;.;;...IV;;.......;;..;;ls=o=la=f=10...;;.;;n;...;.A"""'c;;..;;t=ua=t=io=n=--------- JPM#: OO.AD.20933.101 Revision:-'2"'--___ Date: 09/23/2016 Applicability: iZI RO iZ1 SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic KIA Number 2.2.22 KIA Importance 4.7 Alternate Path: DYES iZI NO Time Critical DYES IZI NO Validation Time (min):_---.45..___ Testing Method: D Simulate IZI Perform Author:: * !ta lthf Operations Review: validated: J?o M 1/ Date: Date: Date: 1/:26 (_; b

                                                                                                                                            ~./l~!ty or/2tllt Approval: __1V\_    ........._\. . .~'-"""'.... L. . . . . ...______ Date: °l'"-7*/(£_                                                        ' '
               "NUCiear Traillil19SUPervisor Examinee Name:
                   --            ----------------

Last, First Ml Employee Number Exam Date: _ _ _ _ _ _ _ __ Exam Duration (Min): _ _ _ _ _ _ _ __ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:

          -----------

Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.20933.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required arid/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. Sl-183-312, Quarterly Calibration of Main Steam Line Pressure Channels PSL-B21-1N015A, B, C, D Rev 18 B. NDAP-QA-0312, Control of LCOs, TROs and Safety Function Determination Program Rev 20 C. NDAP-QA-0722, Surveillance Test Program Rev 26 D. Technical Specification 3.3.6.1 Ill. TASK CONDITIONS Unit 1 is operating at 80 percent power. l&C is performing Sl-183-312, Quarterly Calibration of Main Steam Line Pressure Channels PSL-B21-1N015A, B, C, D. l&C notifies you that Pressure Switch PSL-B21-1N015C tripped at 838 psig. They were unable to adjust the setting, and it has failed their surveillance. IV. INITIATING CUE Determine system operability and take appropriate actions. V. TASK STANDARD Examinee determines that LCO 3.3.6.1 is NOT met for MSIV Isolation Actuation Surveillance. Declares channel INOPERABLE, makes notifications and documents LCO entry per NDAP-QA-0312. Performs LOSF, determines no loss of safety function exists.

TQ-106-0';) 'I 0 Revision 1 Page 3of11 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step .
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
The time clock starts when the candidate acknowledges the Initiating Cue.
This JPM can be performed in the classroom setting.
Mark-up a copy of Sl-183-312.

EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of TS 3.3.6.1-1. S/U controlled copy.

  *2   Evaluate the condition and identify appropriate       Using Tech Specs, compare test results with         S/U LCO                                                   allowable value in Table 3.3.6.1-1
  *3   Determine the actions required to be taken            Performs the following:                             S/U

Declare the channel INOPERABLE in accordance with TS 3.3.6.1 Condition A Recognize that the TRIP SYSTEM must be placed in the TRIP condition within 24 hours in accordance with TS 3.3.6.1 Required Action A.1 4 Identifies need to initiate a Condition Report to Directs l&C to generate a Condition Report. S/U document the condition EVALUATOR CUE Acknowledge direction to initiate a CR 5 Notifies Management and support personnel In accordance with OP-AD-002 performs the S/U following:
Notify Duty Manager Notify appropriate support personnel

TQ-106-l.i-;J 10 Revision 1 Page 4of11 EVALUATOR CUE Acknowledge communications. 6 Determines that LCO/TRO Log entry is required States requirement to make an entry into SIU SOMs LCO module. EVALUATOR CUE SOMs LCO module is unavailable. Per NDAP-QA-0312 document the information required to complete a LCOTR when SOMs is restored on the Answer Sheet. Answer any questions about what information is expected on each line of the Answer Sheet. EVALUATOR NOTE Date/time of entry is not critical. Required action date/time is critical based on date/time of entry recorded by examinee.

   *7   Records applicable TS/TRM, Condition, and                Performs the following:                          S/U Required Action and required action time                 Completes Answer Sheet with information listed on Answer Key at a minimum
   *8   Determines no loss of safety function exists             Performs the following:                          S/U

Determines TS 3.6.1.3 MSIV and MSL drain NSSS isolation is the supported system
Determines that all MSIVs and MSL drains are operable in both inboard and outboard NSSSS Determines no loss of safety function exists in TS 3.6.1.3 EVALUATOR CUE If the examinee does not proceed to document the safety function determination on Attachment E, but did mark Y for application of TS 3.0.6 on the Answer Sheet, ask the examinee what the result of applying LOSF.

TQ-106-lr~10 Revision 1 Page 5 of 11 9 Documents a Loss of Safety Function Completes Attachment E of NDAP-QA-0312 S/U Determination per NDAP-QA-0312 as follows:

Records TS 3.6.1.3 MSIVs and MSL drains (or similar) as Supported Component or System
Records status of supported system as OPERABLE
Records status of opposite division of the supported system as OPERABLE (Optional) Records TS 3.6.1.3 as the LCO where a loss of safety function was evaluated EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM. EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 7of11 REVISION

SUMMARY

JOB PERFORMANCE MEASURE OO.AD.20933.101 Revision Description/Purpose of Revision 0 NewJPM 1 Revise for TQ procedures, minor editorial corrections

Page 8of11 EVALUATOR COPY: TASK CONDITIONS Unit 1 is operating at 80 percent power l&C is performing Sl-183-312, Quarterly Calibration of Main Steam Line Pressure Channels PSL-821-1 N015A, B, C, D. l&C notifies you that Pressure Switch PSL-B21-1N015C tripped at 838 psig. They were unable to adjust the setting, and it has failed their surveillance INITIATING CUE Determine system operability and take appropriate actions, including completing the required documentation

Page 9of11 EXAMINEE COPY: TASK CONDITIONS Unit 1 is operating at 80 percent power l&C is performing Sl-183-312, Quarterly Calibration of Main Steam Line Pressure Channels PSL-821-1 N015A, B, C, D. l&C notifies you that Pressure Switch PSL-B21-1N015C tripped at 838 psig. They were unable to adjust the setting, and it has failed their surveillance INITIATING CUE Determine system operability and take appropriate actions, including completing the required documentation

Page 10 of 11 ANSWER KEY Initiating Condition: PSL-821-1 N015C Inoperable Unit 1 TSrrR Number(s) TS 3.3.6.1 Condition(s) A Condition Description(s) One or more required channels inoperable Entry Daterrime Today I now Action Statement A.1 Number(s) Required Action(s) Place channel in trip TSrrR Completion Time 24 hours Entry Daterrime Today I now Action Daterrime Tomorrow I now Chem/HP Sample Log Y/N Required Support System Invoking TS 3.0.6 LOSF YIN Determination?

Page 11 of 11 ANSWER SHEET Initiating Condition: Unit TS/TR Number(s) Condition(s) Condition Description(s) Entry Date/Time Action Statement Number(s) Required Action(s) TS/TR Completion Time Entry Date/Time Action Date/Time Chem/HP Sample Log YIN Required Support System Invoking TS 3.0.6 LOSF YIN Determination?

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: _ _ _....:.A...;.;:c=t~iv=at=e'-'t=h=e-=-F...;.;:ir--=-e-=B=r~igl,;:;;a=d=e_ _ _ _ _ _ _ __ JPM#: 00.AD.21022.101 Revision: 0 09/23/2016

                                                                      ------- Date:

Applicability: ~ RO ~ SRO Setting: Simulator NUREG-1123 E/APE I Sys Generic KIA Number 2.4.27 KIA Importance 3.4/4.9 Alternate Path: DYES ~ NO Time Critical DYES ~ NO Validation Time (min):_---"-1__ 0 __ Testing Method: D Simulate ~ Perform Author:: ~C<_ju,J. / Date: Cf/~~ Llt Operations Review: -~~==::::,4J~1======- Date: z)~/l,Y Validated: s(lcr kft-!- Date: 1/:J'1/Jh Approval: 1'1 k.'.) L Date: '7*17*/~ Nuclear Training Supervisor Examinee Name:

                 --      ----------------

Last, First Ml Employee Number Exam Date: Exam Duration (Min): _ _ _ _ _ _ _ __

            ---------

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:

          -----------

Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.21022.101 1 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. ON-013-001 Response To Fire, (rev. 45) B. FP-013-132 Common Refueling Floor, (rev. 4) C. AR-SP-002 pages 57, 70, (rev. 33) D. OP-099-004, Station Alarm System (rev. 7) Ill. TASK CONDITIONS Unit 1 is in MODE 1 at 80% Power. SIMPLEX fire alarms have been acknowledged in accordance with OP-013-002. The following VALID SIMPLEX data print out is available: FIRE DET X112_Z5 ALM 12:14 MON 06-DEC-10 818 U1 REFUEL FLOOR FIRE DET X114_Z2 ALM 12:16 MON 06-DEC-10 818 U1 REFUEL FLOOR An NPO confirms that a fire exists on Unit 1 Reactor Building 818'. IV. INITIATING CUE Activate the Fire Brigade and select the appropriate Pre-Fire Plan. V. TASK STANDARD Fire brigade activated in accordance with ON-013-001, "Response to Fire", and Pre-Fire Plan FP-013-132 selected.

TQ-106-(r;j10 Revision 1 Page 3of9 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step .
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
The time clock starts when the candidate acknowledges the Initiating Cue.
This JPM must be performed in the simulator. Any IC can be used for simulator setup.

BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of AR-SP-002. S/U controlled copy. EVALUATOR NOTE: The alarm response procedure identifies the Pre-Fire Plan FP-013-132 2 Identifies appropriate alarm response Selects AR-SP-002, Fire Det X112_Z5 S/U ALM,818 U1 Refuel Floor and Fire Det X114_Z2 ALM 818 U1 Refuel Floor 3 Enters Off Normal Procedure Obtains a copy of ON-013-001, Response to S/U Fire and performs Attachment L, Fire Brigade Normal Response

  *4   Dispatch Fire Brigade Leader                          Contact the Field Unit Supervisor as Fire           S/U Brigade Leader using the plant page or radio.

AND Inform the Fire Brigade Leader a fire is confirmed in Unit 1 Reactor Building 818'

TQ-106-0~:n 0 Revision 1 Page 4 of 9

 *5   Activate Fire Brigade Pagers                             Activate the Fire Brigade pagers using the     S/U central desk phone set by pressing blue button and lifting the handset for at least 45 seconds.
 *6   Sound Fire Alarm for -10 seconds.

Pull Out the Pistol Grip EVACUATION S/U ALARM switch
Turn the Pistol Grip EVACUATION ALARM switch to PLANT ALARM
Place the SIREN TONE GENERATOR switch to FIRE (SIREN)
Push In the Pistol Grip EVACUATION ALARM switch to initiate the alarm
Pull Out the Pistol Grip EVACUATION ALARM switch to stop the alarm
Turn the Pistol Grip EVACUATION ALARM switch to the OFF position
Push In the Pistol Grip EVACUATION ALARM switch

 *7    Make plant page announcement                            Key the plant page and announce:               S/U  Announcement should be "ATTENTION ALL PERSONNEL: THERE                   repeated.

IS A FIRE ON THE REFUEL FLOOR, REACTOR BUILDING ELEVATION 818'. STATION FIRE BRIGADE HAS BEEN ACTIVATED; STAY CLEAR OF AFFECTED AREAS." EVALUATOR CUE Role-play as fire brigade leader. Inform the candidate you will be setting up the command post at Fire Brigade Shed #2 - Unit 2.Tool Room 676', and radio OPS Channel 1 will be used.

TQ-106-0010 Revision 1 Page 5 of 9

-
  *8  Directs a Fire Brigade Member to take Pre-Fire  Designate one fire brigade member to take   S/U plan for the applicable building to the Command RB Pre-Fire Plan (FP-013-132) to the Post                                            command post at Fire Brigade Shed #2 -

Unit 2 Tool Room 676" 9 Inform Security of fire and OPS radio channel Contacts Security at extension 3114 or 3115 S/U being used and inform them of the fire and the radio channel being used. EVALUATOR CUE Record JPM stop time: EVALUATOR CUE That completes the JPM. EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 7 of 9 REVISION

SUMMARY

JOB PERFORMANCE MEASURE 00.AD.21022.101 Revision Description/Purpose of Revision 0 New JPM From LOC 26 JPM EPP-RO

Page 8 of 9 EVALUATOR COPY: TASK CONDITIONS Unit 1 is in MODE 1 SIMPLEX fire alarms have been acknowledged in accordance with OP-013-002. The following VALID SIMPLEX data print out is available: FIRE DET X112_Z5ALM 12:14 MON 06-DEC-10 818 U1 REFUEL FLOOR FIRE DET X114_Z2ALM 12:16 MON 06-DEC-10 818 U1 REFUEL FLOOR An NPO confirms that a fire exists on Unit 1 Reactor Building 818'. INITIATING CUE Activate the Fire Brigade and select the appropriate Pre-Fire Plan.

Page 9 of 9 EXAMINEE COPY: TASK CONDITIONS Unit 1 is in MODE 1 SIMPLEX fire alarms have been acknowledged in accordance with OP-013-002. The following VALID SIMPLEX data print out is available: FIRE DET X112_Z5ALM 12:14 MON 06-DEC-10 818 U1 REFUEL FLOOR FIRE DET X114_Z2 ALM 12:16 MON 06-DEC-10 818 U1 REFUEL FLOOR An NPO confirms that a fire exists on Unit 1 Reactor Building 818'. INITIATING CUE Activate the Fire Brigade and select the appropriate Pre-Fire Plan.

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Classify an Emergency Condition and Complete Emergency Notification Report JPM#: OO.EP.1132.180 Revision: 2

                                                          - - - - Date:        09/23/2016 Applica.bility: IZI RO IZI SRO Setting:     Classroom NUREG-1123 E/APE I Sys                         Generic        KIA Number       2.4.41

KIA Importance 2.4.41 Alternate Path: IZI YES D NO Time Critical DYES IZI NO Validation Time (min):_----'-1~5-

        --r7~~....,..--,.q--- Date: r/;;G(/ k Date: (/z<r ~
            --...........................---.....,....___ _ Date: er /~j /It Approval:       Jv\ Lo:J ~                                           Date:   °t

7- 7 ' l 4 Nuclear Training Supervisor Examinee Name:

                     ---------------------------

Last, First Ml Employee Number Exam Date: Exam Duration (Min): _ _ _ _ _ _ _ __

              ---------

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:

           ~-------------

Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.EP.1132.180 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. EP-PS-100, CR Emergency Director (revision 34) B. EP-RM-004, EAL CLASSIFICATION BASES (Revision 9) C. EP-PS-001, EMERGENCY PLANNING FORMS AND SUPPLEMENTARY INSTRUCTIONS (Revision 11) Ill. TASK CONDITIONS Each examinee evaluated in the SRO position for a scenario will be required to classify the event once the scenario concludes. Task Conditions for each scenario are provided on the cue sheet. IV. INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan. V. TASK STANDARD Classify the event at the appropriate level on the correct EAL and complete the Emergency Notification Report.

TQ-106-0;:n 0 Revision 1 Page 3 of 16 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step .
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
The time clock starts when the candidate acknowledges the Initiating Cue .
Ensure that a copy of EP-RM-004, EP-PS-100 and blank ENR and PAR forms are available .

EVALUATOR NOTE This is a TIME CRITICAL JPM. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Obtains copy of EP-PS-100, Emergency Director, Obtains copy of EP-PS-100, Emergency SIU Control Room and EP-RM-004, EAL Classification Director, Control Room and EP-RM-004, Bases. EAL Classification Bases. 2 Refers to classification matrix. Selects the correct Table. SIU

  *3   Chooses appropriate emergency action level.          Declares the correct event level per the JPM        SIU key for the scenario within 15 minutes of start time.

4 Determines appropdate procedure section. Identifies the appropriate procedure SIU attachment for the event classification of EP-PS-100.

  *5   Documents and communicates the Emergency             Announces the following:                            SIU Classification.

I am assuming duties of the Emergency Director

                                                            *  [Event]  declared based on [EAL summary]

Time and Date of Classification 6 If not performed earlier appoints an Emergency Appoints an Emergency Plan Communicator SIU Plan Communicator. and instructs communicator to immediately perform EP-PS-126, E-Plan Communicator.

TQ-106-Q;yfQ Revision 1 Page 4.of 16 7 If not performed earlier, appoints an NRC Appoints an NRC Communicator and SIU communicator. instructs communicator to perform EP-PS-135, NRC Communicator.

   *8  Initiates an ENR form.                                Performs the following:                        SIU

Refers to ENR Form under Att J and IF necessary EP-PS-001-4 for instructions on filling out the form
Records*cR-1 as the control#*
Line 1, places checkmark in THIS IS A DRILL box EVALUATOR NOTE The time recorded on Line 3 of the ENR form is compared to the start time recorded at the beginning of the JPM to determine if the examinee is successful in meeting the 15 minute event declaration requirement of the JPM.

   *9  Completes Line 3 of the ENR                            Performs the following:                       SIU

Places checkmark in the correct event box
Places checkmark in the correct unit box
Records declaration time and date
Places checkmark in INITIAL DECLARATION box 10 Completes Line 4 of the ENR Performs the following: SIU
Records EAL in Classification Description
Records a brief non-technical description of EAL or applies appropriate sticker marked-up to reflect actual event

TQ-106-0.,-10 Revision 1 Page 5of16

*11   Completes Line 5 of the ENR                     Performs the following:                      S/U

Refers to EP-PS-001-48 Att. QQ for guidance in determining if there is a radiological release in progress due to the event
Places checkmark in release box as appropriate

*12   Completes Lines 6 and 7 of the ENR              Performs the following:                      S/U

Records wind direction, wind speed .
Places checkmark in THIS IS A DRILL box

*13   Approves the ENR.                               Signs the ENR and records the current date   S/U and time.

14 Provides the ENR to the Emergency Plan Performs the following: S/U Communicator.

Provides the approved ENR to the Emergency Plan Communicator.
Reviews the ENR with the Communicator

'*

Directs the Communicator to complete the notification within 15 minutes of the event declaration time EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM. EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 7 of 16 REVISION

SUMMARY

JOB PERFORMANCE MEASURE OO.EP.1132.180 Revision Description/Purpose of Revision 0 NewJPM 1 Minor editorial changes Updated references and individual scenario task conditions to accommodate 2 the LOC 28 NRC exam.

Page 8of16 EVALUATOR - SCENARIO 1 TASK CONDITIONS Unit 1 was at 95% power Unit 1 was manually scrammed resulting in an A TWS. Unit 1 experienced the following conditions:

E0-000-113 actions are being performed
Standby Liquid Control is injecting
ES-158-002 has been dispatched, rods are being inserted manually INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.

Page 9of16 EXAMINEE - SCENARIO 1 TASK CONDITIONS Unit 1 was at 95% power Unit 1 was manually scrammed resulting in an A TWS. Unit 1 experienced the following conditions:

E0-000-113 actions are being performed
Standby Liquid Control is injecting
ES-158-002 has been dispatched, rods are being inserted manually INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.

Page 10of16 EVALUATOR-SCENARIO 2 TASK CONDITIONS Unit 1 Reactor Power was approximately 80% during a startup A manual scram is inserted due to a low level condition Unit 1 experienced the following conditions:

Loss of Offsite Power
RPV pressure and level are being maintained by SRVs and RCIC.
A small RCS leak develops in the drywell
RPV level goes below TAF
ADS fails to initiate
Emergency Depressurization is performed
Manual initiation of ECCS systems required due to a failure to auto initiate INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.

Page 11 of 16 EXAMINEE - SCENARIO 2 TASK CONDITIONS Unit 1 Reactor Power was approximately 80% during a startup A manual scram is inserted due to a low level condition Unit 1 experienced the following conditions:

Loss of Offsite Power
RPV pressure and level are being maintained by SRVs and RCIC.
A small RCS leak develops in the drywell
RPV level goes below TAF
ADS fails to initiate
Emergency Depressurization is performed
Manual initiation of ECCS systems required due to a failure to auto initiate INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.

Page 12of16 EVALUATOR - SCENARIO 3 TASK CONDITIONS Unit 1 Reactor Power was approximately 33%. A shutdown was in progress for an unplanned maintenance outage Unit 1 experienced the following conditions:

A loss of ESS Bus 1C occurred
A manual scram is inserted due to a leak in the drywell resulting in an ATWS
ARI is initiated, drifting rods in.
SDV drains fail to close.
Rad levels in the CRD HCU area and RCIC room rad levels exceed Max Safe levels
Emergency depressurization is conducted INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.

Page 13of16 EXAMINEE - SCENARIO 3 TASK CONDITIONS Unit 1 Reactor Power was approximately 33%. A shutdown was in progress for an unplanned maintenance outage Unit 1 experienced the following conditions:

A loss of ESS Bus 1C occurred
A manual scram is inserted due to a leak in the drywell resulting in an A TWS
ARI is initiated, drifting rods in.
SDV drains fail to close.
Rad levels in the CRD HCU area and RCIC room rad levels exceed Max Safe levels
Emergency depressurization is conducted INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.

Page 14of16 EVALUATOR- SCENARIO 4 TASK CONDITIONS Unit 1 Reactor Power was approximately 90% A small steam leak developed in the drywell Unit 1 experienced the following conditions:

A manual scram is inserted
Plant Aux load shed occurs
RPV level is maintained using HPCI
Suppression chamber and Drywell sprays are in service
RPV flooding is required due to erratic pressure instruments
Level is steady at +30" prior to the loss of level indication INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.

Page 15of16

EXAMINEE - SCENARIO 4 TASK CONDITIONS Unit 1 Reactor Power was approximately 90%

A small steam leak developed in the drywell Unit 1 experienced the following conditions:

A manual scram is inserted
Plant Aux load shed occurs
RPV level is maintained using HPCI
Suppression chamber and Drywell sprays are in service
RPV flooding is required due to erratic pressure instruments
Level is steady at +30" prior to the loss of level indication INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.

Page 16of16 JPM KEY Scenario Classification EAL Release 1 SAE MS3 No 2 SAE FS1 No 3 SAE FS1 Yes 4 Alert FA1 No

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Determine LCO Applicability to Bypass Secondary Containment Zone 2 Isolation JPM#: 34.0P.21505.201 Revision:____.O'----- Date: 09/26/2016 Applicability: 12] SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic KIA Number _2=*--.3.;;..;.1_,,3_ _ _ K/A Importance _3............ 8 __ Alternate Path: DYES 12] NO Time Critical DYES 12] NO Validation Time (min):_2=5"'--_ 12] Perform Author:: J/ Date:

                                                         -------

Operations Review: L---- Date: 7._~ Jfo Validated: , £a ,J.A..µ (/ Date: °f /:Lt//b Approval: _fu~~___;W~;.__:~=;r:--.::::;_____ Date: °J ' Z°t

lk NUCiear Traini~rvisor Last, First Ml Employee Number Exam Date: _ _ _ _ _ _ _ __ Exam Duration (Min): _ _ _ _ _ _ _ __

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator: _ _ _ _ _ _ _ _ _ __ Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 34.0P.21505.201 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

11. REFERENCES A. OP-234-002, Reactor Building HVAC Zones 2 and 3 (Rev. 15)

B. NDAP-QA-0321, Secondary Containment Integrity Control (Rev. 13) 1 111. TASK CONDITIONS A. Unit 2 is shutdown. B. All rods were inserted 4 hours ago. C. Plant cool down and equipment shutdown are in progress in preparation for start of a refueling outage. D. C RHR Pump is in service in Shutdown Cooling. E. A and B ESW pumps and 2A RHRSW Pump is in service providing cooling to the RHR system. R. Reactor coolant temperature is 194 °F and lowering. G. Cask Storage Gates are removed. H. All other equipment is operable. I. I & C has requested the Secondary Containment Zone 2 Isolation bypassed to support work. IV. INITIATING CUE Determine the ability to bypass the Secondary Containment Zone 2 Isolation. Record your findings, including any applicable references. Document your approval I disapproval of the request. Specify actions required for bypass. V. TASK STANDARD Candidate determines Unit 2 Tech Spec 3.6.4.1 is Not Applicable to Mode 4, and may continue with Bypass of Secondary Containment Isolation signal for Zone 2. Candidate authorizes bypassing the Zone 2 Isolation IAW OP-234-002 and NDAP-QA-0321.

TQ-106-u~ 10 Revision 1 Page 3 of 9 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step.
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
The time clock starts when the candidate acknowledges the initiating cue.
This JPM may be performed in the classroom.
Ensure the following material is available; OP-234-002, NDAP-QA-0321, and Tech Specs EVALUATOR CUE Record JPM start time:

Step Action Standard Eva I Comments 1 Obtain a controlled copy of the procedure Obtains a controlled copy of the applicable S/U procedure(s). 2 Selects the correct section to perform Selects:

OP-234-002 section 2.12 and/or
NDAP-QA-0321 section 6.4 S/U and/or
Technical Specification 3.6.4.1/3.6.4.2.

3 Review NDAP-QA-0321 section 6.4 Determines nothing in NDAP-QA-0321 prohibits bypassing the Secondary Containment Zone 2 Isolation. S/U Determines OP-234-002 and Technical Specifications should be referenced. 4 Review OP-234-002 section 2.12 Determines must evaluate Technical S/U Specifications 3.6.4.1 and 3.6.4.2. EVALUATOR NOTE Candidate may refer to TRO 3. 7 .10 which addresses cross-tying the Fuel Pools. Candidate may also initially refer to G0-200-006 regarding the precautions for SC Integrity.

TQ-106-u-,,-10 Revision 1 Page 4 of 9

   *5 I Evaluate Unit 2 Tech Spec 3.6.4.1.                    Determines plant is currently in Mode 4.

Review Technical Specification 3.6.4.1 and determines operability of Secondary Containment is NOT required in Mode 4. Determines irradiated fuel movement and I SI U OPDRVs are not in progress based on initial conditions. Determines Technical Specification 3.6.4.1 allows bypassing of Secondary Containment Zone 2 Isolation in present plant conditions. EVALUATOR NOTE I CUE If asked about irradiated fuel movement, inform candidate that no irradiated fuel movement is in progress. EVALUATOR NOTE I CUE If asked about OPDRVs, inform candidate that no OPDRVs are in progress.

   *6 I Evaluate Unit 2 Tech Spec 3.6.4.2.                    Determines plant is in currently in Mode 4.

Determines Secondary Containment Isolation Valve operability is NOT required in Mode 4. Determines irradiated fuel movement and I SI U OPDRVs are not in progress based on initial conditions. Determines Technical Specification 3.6.4.2 allows bypassing of Secondary Containment Zone 2 Isolation in present plant conditions EVALUATOR CUE If a,sked about irradiated fuel movement, inform candidate that no irradiated fuel movement is in progress.

TQ-106-u~ 10 Revision 1 Page 5 of 9 EVALUATOR CUE If asked about OPDRVs, inform candidate that no OPDRVs are in progress. EVALUATOR CUE If asked about release paperwork (OP-234-002 Att J), inform candidate that OP-234-002 Attachment J has been completed and is being maintained by the Operations Outage Manager (QOM).

   *7  Complete OP-234-002 Attachment F                     Indicates need to fill out OP-234-002 Attachment F and indicates they would direct an operator to complete it.

S/U Indicates that after this form is completed, they would authorize isolation bypass. EVALUATOR NOTE Provide a blank copy of OP-234-002 Attachment F upon request. EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 7of9 REVISION

SUMMARY

JOB PERFORMANCE MEASURE 34.0P.21505.201 Revision Description/Purpose of Revision 0 New JPM, Revised from 34.0P.2683.201 1

Page 8 of 9 EVALUATOR COPY: TASK CONDITIONS A. Unit 2 is shutdown. B. All rods were inserted 4 hours ago. C. Plant cool down and equipment shutdown are in progress in preparation for start of a refueling outage. D. C RHR Pump is in service in Shutdown Cooling. E. A and B ESW pumps and 2A RHRSW Pump is in service providing cooling to the RHR system. R. Reactor coolant temperature is 194°F and lowering. G. Cask Storage Gates are removed. H. All other equipment is operable. I. I & C has requested the Secondary Containment Zone 2 Isolation bypassed to support work. INITIATING CUE Determine the ability to bypass the Secondary Containment Zone 2 Isolation. Record your findings, including any applicable references. Document your approval I disapproval of the request. Specify actions required for bypass.

Page 9of9 EXAMINEE COPY: TASK CONDITIONS A. Unit 2 is shutdown. B. All rods were inserted 4 hours ago. C. Plant cool down and equipment shutdown are in progress in preparation for start of a refueling outage. D. C RHR Pump is in service in Shutdown Cooling. E. A and B ESW pumps and 2A RHRSW Pump is in service providing cooling to the RHR system. R. Reactor coolant temperature is 194°F and lowering. G. Cask Storage Gates are removed. H. All other equipment is operable. I. I & C has requested the Secondary Containment Zone 2 Isolation bypassed to support work. INITIATING CUE Determine the ability to bypass the Secondary Containment Zone 2 Isolation. Record your findings, including any applicable references. Document your approval I disapproval of the request. Specify actions required for bypass.

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Reset Recirculation Pump Limiter #2 Run back, RRP B Runout JPM#: 64.0N.67049.101 Revision:Q Date:07/07/2016 Applicability: ll?J RO ll?l SRO Setting: Simulator NUREG-1123 E/APE I Sys 202002 KIA Number A2.05 KIA Importance 3.8/4.0 Alternate Path: DYES ll?J NO Time Critical DYES ll?l NO Validation Time (min):20 Testing Method: Author::Greg van den Operations Review: c~&--~~ D Simulate

                                             /    ll?l Perform Date: 07/07/2016 Date:    7  /t[ /1~<o Validated:       {1cr_..£tAd                                          Date:  q/#/,/1/,

Approval: _,_1V\__._---=-f;"""""~""'""""--fbp___.___*_ _ _ Date: 1*:l1 *I l Nuclear Training Supervisor Last, First Ml Employee Number Exam Date: Exam Duration (Min....:_ _ _ _ _ _ _ __

              ---------

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:

         -----------

Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 64.0N.67049.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. 'ON-RECIRC-101, Reactor Recirculation Malfunction (Rev. 1) B. AOP-164-001, Reactor Recirculation Abnormal Operating Procedure (Rev. 0) Ill. TASK CONDITIONS Unit 1 is in Mode 1. A trip of Condensate Pump 1D has caused a Reactor Recirculation runback to occur. ON-RECIRC-101, Reactor Recirculation Malfunction, has been completed up to step C.18.d. A Critical Brief has been performed 1D Condensate Pump has been restored. IV. INITIATING CUE Reset the Recirculation Pump limiter #2 run back for both Recirculation Pumps in accordance with AOP-164-001, Attachment B. V. TASK STANDARD Recirc,LIM2 runback is reset for Reactor Recirc Pump IA and lB.

SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 64.0N.67049.101 NOTE: It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

Reset the simulator to an exam-specific IC if prepared.
Configure an exam-specific IC as follows:

o Reset to IC-18 o Perform the following expert command to trip Condensate Pump D:

              !OR diHS10510D f:STOP

Place the simulator in RUN.
Allow plant conditions to stabilize.
Perform actions of ON-RECIRC-101 through step C.14
Perform the following expert command to delete the Condensate Pump D trip malfunction: DOR diHS10510D f:START
Restart Condensate Pump lD
Perform the following expert command to load RRP A(B) speed as a Monitored Parameter i nsmp rrnlp40la insmp rrnlp401b

TQ-106-lM 10 Revision 1 Page 4of12 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step .
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
The time clock starts when the candidate acknowledges the initiating cue.
This JPM must be performed in the simulator.
Configure the Simulator per the Simulator Setup Instructions .

BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Verifies AOP-164-001 Att. B is the controlling Controlled copy of AOP-164-001 obtained, S/U document. select Att. B. 2 Verifies Condenser Pressure is <5 .5 HgA. Verifies Condenser Pressure is <5 .5 HgA at S/U panel 1C668B 3 Determines RFP(s) indicated flow.

Observe Feedwater flow on the Feedwater Flow Overview.

S/U

Determines that RFP discharge flows are all <0.9Mlbm/hr (> 16.4%).

4 Ensures associated IND RFP FLOW< 16.4%

On the RRP A HMI screen, determines Limiter# 2 Input(s) to Rx Recirc Runback Circuit is IND FLOW <16.4% is ENABLED.

S/U ENABLED.

On the RRP B HMI screen, determines IND FLOW <16.4% is ENABLED.

EVALUATOR NOTE The Limiter #2 RESET buttons will not become active until Controller Output indication is ~ 27.10% and initiating condition has cleared (with the exception of CWP Trip/High Condenser Pressure and/or Condensate Pump trips). 5 Ensure a Critical Brief has been conducted Verifies initial conditions state that the S/U Critical Brief has been conducted.

TQ-106-l,;;,10 Revision 1 Page 5 of 12 6* I RESET Limiter #2 Runback on 'A' Reactor Performs the following: Recirculation Pump

VERIFY SY-B31-1R621A % Controller Output Signal is approximately 27.10%.

                                                           *   *TOUCH DEC button RECIRC PUMP lA SPEED SY-B31-1R621A Controller

Observes a change in the following:

o Lowering of Gen 1A Speed or on SI 14032A (TRA036) o Lowering of Gen 1A Demand, on I SIU XI 14032A (TRA040) o Lowering of Scoop Tube 1A Position (TRA044) o Lowering of Loop 1A Drive Flow (APMF01)

OBSERVE HS-B31-1S12A RX RECIRC LIMITER #2 (48%)

RUNBACK RESET button is ACTIVE EVALUATOR NOTE One minute time delay allows for Scoop Tube Positioner to make the final (0.111 %) position adjustment 7* I Depress the RX RECIRC LIMITER #2 (48%) *TOUCH HS-B31-1S12A RX RECIRC RUNBACK RESET button. LIMITER #2 (48%) RUNBACK RESET button S/U AND

                                                           *TOUCH RESET LIMITER #2 button 8 I Monitor Recirc Pump A speed.                         Observe GEN lA SPEED SI-14032A remains steady.

TQ-106-u~ 10 ' Revision 1 Page 6of12 9 Observes Recirc Pump A LIM2 runback resets. Observe the following:

                                                           * # 2 LIMITER INITIATED status block background changes from RED to         S/U GRAY

AR-102-CO 1 annunciator clears 1O* RESET Limiter #2 Runback on 'B' Reactor Performs the following:

Recirculation Pump

VERIFY SY-B31-1R621B % Controller Output Signal is approximately 26.90%.

                                                           *   *TOUCH DEC button RECIRC PUMP lA SPEED SY-B31-1R621B Controller

Observes a change in the following:

0 Lowering of Gen 1A Speed or on

SI 14032A {TRA037) 0 Lowering of Gen 1A Demand, on S/U XI 14032A (TRA041) 0 Lowering of Scoop Tube 1A Position {TRA045) 0 Lowering of Loop 1A Drive Flow (APMF02) OBSERVE HS-B31-1S12B RX RECIRC LIMITER #2 (48%) RUNBACK RESET button is ACTIVE EVALUATOR NOTE One minute time delay allows for Scoop Tube Positioner to make the final (0.111 %) position adjustment

TQ-106-tJ-;j 10 Revision 1 Page 7 of 12 11* Depress the RX RECIRC LIMITER #2 (48%) *TOUCH HS-831-1S128 RX RECIRC RUN8ACK RESET button. LIMITER #2 (48%) RUN8ACK RESET button S/U AND

                                               *TOUCH RESET LIMITER #2 button 12 Monitor Recirc Pump B speed.                Observe GEN lB SPEED SI-14032B is raising.                             SIU 13 Observes Recirc Pump B LIM2 runback resets. Observe the following:
                                               * # 2 LIMITER INITIATED status block background changes from RED to GRAY

AR-102-C04 annunciator clears

TQ-106-lJ~ 10 Revision 1 Page 8 of 12 14* RESET Limiter #2 Runback on 'B' Reactor Performs the following: Recirculation Pump

VERIFY SY-B31-1R621B % Controller Output Signal is approximately 26.90%.

                                                      *  *TOUCH DEC button RECIRC PUMP IA SPEED SY-B31-1R621B Controller

Observes a change in the following:

0 Lowering of Gen 1A Speed or on SI 14032A (TRA037) 0 Lowering of Gen 1A Demand, on XI 14032A (TRA041) 0 Lowering of Scoop Tube 1A Position (TRA045) 0 Lowering of Loop 1A Drive Flow (APMF02)

OBSERVE HS-B31-1S12B RX RECIRC LIMITER #2 (48%)

RUNBACK RESET button is ACTIVE EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 10 of 12 REVISION

SUMMARY

JOB PERFORMANCE MEASURE 64.0N.67049.101 Revision Description/Purpose of Revision 0 NewJPM 1 This JPM was created by modifying 64.0N.2131.151.

Page 11 of 12 EVALUATOR COPY: TASK CONDITIONS Unit 1 is in Mode 1. A trip of Condensate Pump 1D has caused a Reactor Recirculation runback to occur. ON-RECIRC-101, Reactor Recirculation Malfunction, has been completed up to step C.18.d. A Critical Brief has been performed 1D Condensate Pump has been restored INITIATING CUE Reset the Recirculation Pump limiter #2 runback for both Recirculation Pumps in accordance with AOP-164-001, Attachment B.

Page 12of12 EXAMINEE COPY: TASK CONDITIONS Unit 1 is in Mode 1. A trip of Condensate Pump 1D has caused a Reactor Recirculation runback to occur. ON-RECIRC-101, Reactor Recirculation Malfunction, has been completed up to step C.18.d. A Critical Brief has been performed 1D Condensate Pump has been restored INITIATING CUE Reset the Recirculation Pump limiter #2 runback for bofh Recirculation Pumps in accordance with AOP-164-001, Attachment B.

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Implement RFP Post Scram Recovery JPM#: 45.0P.21388.102 Revision:

                                                                 -------

1 Date: 7/27/2016 Applicability: ~ RO ~ SRO Setting: _ _..;;;S=im=u=l--a..... to....r _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ NUREG-1123 E/APE I Sys 259001 KIA Number _A_3_.0_7_ _ _ _K/A Importance 3.2 I 3.2 Alternate Path: DYES ~ NO Time Critical DYES ~ NO Validation Time (min):__..;;;2=0_ _ Date: TJP-~L1&. Date:

                                                                       'CJk0
                                                                         .     ~

b}c Date: Cff~1,Ll6 I Approval: ____.11/\_....__0--=-*--~-+...;;;;.....__ _ __ Date: °1 1 21*!~ Nuclear TralniifgSupervisor Examinee Name:

                    --           ----------------

Last, First Ml Employee Number Exam Date: Exam Duration (Min): _ _ _ _ _ _ _ __

             ---------

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:

          -----------

Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 45.0P.21388.102 I. SAFETY CONSIDERATIONS A All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A OP-145-001, RFP AND RFP LUBE OIL SYSTEM (Rev. 84) Ill. TASK CONDITIONS Unit 1 scrammed from approximately 70 percent power. All 3 RFPs tripped on a spurious high RPV level signal following the scram. RPV level is being maintained at approximately -5" using RCIC and CRD IV. INITIATING CUE Restart a RFP and maintain RPV level -40" to -50". V. TASK STANDARD Places a RFP in-service in Discharge Pressure Mode and establishes a rising RPV level trend by injection through the HV-10641

SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 45.0P.21388.102 NOTE: It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

1. Configure an exam-specific IC as follows

Reset to IC-20
Insert a recirc LIM2 runback, allow to stabilize
Place mode switch to Shutdown
Trip all 3 Feed Pumps
Insert Ni's
Verify RCIC initiates (or initiate and return collar to not armed)
Stabilizes RPV level at approximately -45"
Trip 2 Condensate Pumps (to prevent condensate pump damage)
Reset Generator Lockouts
Override AR-108-E02

TQ-106-u-.:> 10 Revision 1 Page 4of11 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step.
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
The time clock starts when the candidate acknowledges the Initiating Cue.
This JPM must be performed in the simulator. Reset to exam-specific IC, or configure the simulator per the Simulator Setup Instructions.

EVALUATOR CUE Record JPM start time: BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN. BOOTH OPERATOR CUE Adjust the RCIC flow controller setpoint to maintain RPV water level -60" to -50" during performance of the JPM. Step Action Standard Eva I Comments 1 Verifies OP-145-001 Attachment Bis governing Controlled copy of OP-145-001 obtained, S/U procedure and obtains controlled copy. select Attachment B. EVALUATOR NOTE The following step is critical only if more than two Condensate Pumps are running. This 'step is not required to be performed for successful completion of the JPM if only two Condensate Pumps are running in the simulator IC. 2* Stops 2 Condensate Pumps. Depress 1P102A(B)(C)(D), CONDENSATE PUMP, STOP PB as necessary to leave 2 S/U Condensate Pumps running. 2 Ensures all HV-10603A(B)(C) RFP A(B)(C) Observe HV-10603A(B)(C) RFP A(B)(C) S/U Discharge lso Viv closed. DISCHARGE ISO VLV indicate full closed. 3 Ensures all HV-10651A(B)(C) RFP A(B)(C) Startup Observe HV-10651A(B)(C) RFP A(B)(C) S/U lso Viv closed. STARTUP ISO VLV indicate full closed.

TQ-106-(J;:>-10 Revision 1 Page 5of11 4 Ensures controller LIC-C32-1 R602, FW Lo Load On controller LIC-C32-1R602, FW LO Demand Signal to LV-10641, in MANUAL and 0 LOAD DEMAND SIGNAL TO LV-10641, percent output. perform the following:

Depress MAN PB SIU
Depress single- or double-DEC PB until

                                                         % CONTROLLER OUTPUT indicates 0 percent 5 Ensures 2 NR RPV level instruments indicate <54" Observe any 2 of NAR RNG A(B)(C)

S/U on FW HMI. indicate less <54". 6* Open RFPT A(B)(C) steam supply isolation valves. At 1C668, depress RFPT A(B)(C) LP ISO S/U HV-12709A(B)(C) OPEN PB. EVALUATOR NOTE The RESET A(B)(C) RFPT TRIP PB must be depressed for approximately 5 seconds to reset the RFPT. 7* Reset RFPT A(B)(C) trip. Perform the following:

Select RFP_A(B)(C) screen I
Depress A(B)(C) RFPT TRIPPED PB
On overlay HS-12745A2(82)(C2), RFPT A(B)(C) TRIP RESET SWITCH, depress S/U RESET PB
Depress ENABLE RESET PB
Depress and hold RESET A(B)(C) RFPT TRIP PB until RFP A(B)(C) icon indicates Reset 8* Places RFPT A(B)(C) valve control in AUTO Depress the A(B)(C) RFPT AUTO VLV CTL S/U

                                                      ,PB and observes it backlit YELLOW.

TQ-106-0siO Revision 1 Page 6of11

*9 Places RFPT A(B)(C) in Idle mode.               Perform the following:

Observe controller FIC-10604A(B)(C) RX FEED PUMP A(B)(C) RECIRC FLOW in AUTO

                                                   * *Depress A(B)(C) IDLE MODE PB and then depress I OLE MODE PB

On controller FIC-10604A(B)(C), RX FEED PUMP A RECIRC FLOW, depress the MAN PB and then the single- and S/U double-chevron INC PB as necessary to raise RFP flow as indicated on Fl-10604A, RFP FLOW, > 600 gpm

                                                   * *When RFP A(B)(C) recirc flow indicates
                                                     > 600 gpm, depress 1,000 RPMS PB

On controller FIC-10604A(B)(C), RX FEED PUMP A RECIRC FLOW, depress the AUTO PB 10* Stops RFP A turning gear when RFPT A speed is Observe RFPT A turning gear is OFF and in S/U

   > 100 rpm and then returns to AUTO.             AUTO.

11* Places RFPT A(B)(C) in Discharge Pressure Mode. Perform the following:

Selects RFP_A(B)(C) screen

                                                   * *Depress the A(B)(C) RFPT DSCH PRESS MODE PB AND then depresses the INITIATE DSH PRSS MODE PB

After 30 seconds, observe A(B)(C) RFPT SIU DSCH PRESS MODE PB YELLOW
Observe HV-10651A(B)(C) stroke FULL OPEN
Observe RFP A(B)(C) pressure rise approximately 120 psig above reactor pressure.

TQ-106-CJ;;; I 0 Revision 1 Page 7of11 EVALUATOR CUE It is required to raise RFP A discharge pressure for DPM per Step 17 of the hard card. (Only needed for time compression, if cue not given skip step 13) 12* Establishes RFPT A(B)(C) discharge pressure for On controller SIC-C32-1 R601A(B)(C) RFP DPM. A(B)(C) SPD CTL/DEMAND SIGNAL perform the following:

Depress MAN PB S/U
Depress single- and/or double-chevron INC and DEC PB as necessary to obtain approximately 55% on SPD DMD (STPT)
Depress AUTO PB 13* Adjusts LV-10641 FW LO LOAD VALVE Perform the following on controller LIC-C32-1 R602 controller to slowly raise reactor LIC-C32-1R602 FW LO LOAD VALVE water level.
Depress single- and double-chevron INC S/U PB as necessary to raise controller output to desired level EVALUATOR CUE When flow is indicated from RFP A, inform the examinee RCIC has been secured and that the examinee S/U has control of RPV level.

BOOTH OPERATOR CUE S/U When flow is indicated from RFP A, place the RCIC flow controller to manual at O percent output. EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE

Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 9of11 REVISION

SUMMARY

JOB PERFORMANCE MEASURE 45.0P.21388.102 Revision Description/Purpose of Revision 0 NewJPM Revised to modify faulted JPM 45.0P.4677.152. This revision eliminates 1 the faulted aspect of the JPM. A JPM without a fault could not be found for this task, therefore this is a modified JPM.

Page 10of11 EVALUATOR COPY: TASK CONDITIONS Unit 1 scrammed from approximately 70 percent power. All 3 RFPs tripped on a spurious high RPV level signal following the scram. RPV level is being maintained at approximately -50" using RCIC and CRD INITIATING CUE Restart a RFP and restore RPV level -40" to -50".

Page 11 of 11 EXAMINEE COPY: TASK CONDITIONS Unit 1 scrammed from approximately 70 percent power. All 3 RFPs tripped on a spurious high RPV level signal following the scram. RPV level is being maintained at approximately-50" using RCIC and CRD INITIATING CUE Restart a RFP and restore RPV level -40" to -50". (

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Open MSIVs During Reactor Startup (All Rods In) JPM#: 84.0P.24667.151 Revision:! Date:07/07/2016 Applicability: ~ RO ~ SRO Setting: Simulator NUREG-1123 E/APE I Sys239001 KJA Number A4.01 KJA Importance 4.2 Alternate Path: ~YES 0 NO Time Critical DYES ~ NO Validation Time (min):25 Testing Method: D Simulate Date: 07/07/2016 Date: cJ/z(,,,/((yz Validated: --;~.=.;:;~~__:::::;.....__ ____ Date: 1b "i (/t Approval: ___!_~k...... .....~.._.---- Date: 11,..._,....,..lA.....,)......._J2 7'

Z. 'J' 16 Nuclear Training Supervisor Last, First Ml Employee Number Exam Date: _ _ _ _ _ _ _ __ Exam Duration (Min): _ _ _ _ _ _ _ __

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:

          -----------

Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 84.0P.24667.151 I. SAFETY CONSIDERATIONS A All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. G0-100-002, Plant Startup, Heatup and Power Operations (Rev 105) B. OP-184-001, Main Steam System (Rev 37) C. ON-193-001, Turbine EHC System Malfunction (Rev 24) Ill. TASK CONDITIONS Unit 1 startup is in progress in accordance with G0-100-002. The reactor is at the POAH. Reactor startup will continue after the MSIV s are open. Reactor pressure is 10 psig and reactor coolant temperature is 240 °F. The operator will perform all control room actions. IV. INITIATING CUE Open the MSIVs per OP-184-001 Section 2.3. V. TASK STANDARD Open MSIVs for reactor startup. Close the MSIV's when the turbine bypass valves fail open.

SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 84.0P.24667.151 NOTE: It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

1. Reset the simulator to a hot startup IC at POAH. Scram the reactor and then reset the scram.

Establish reactor pressure and stabilize no higher than 10 psig.

2. Run scenario file EVAL840P24667151.scn

  ;Overides alarm horns on oc653 and lc668 IOR do0C653HRN1 f:OFF IOR do0C653HRN2 f:OFF IOR do1C668HRN f:OFF
  ;Fails A EHC PT to 1000 psig
  ;Cause all the BPVs to open

{Key[l]} IMF mfTC193002A f:1000

3. Other Adjust RWCU blowdown flow if necessary to stabilize reactor level at approximately 35" and place the RWCU blowdown flow controller back to AUTO.

T0,106-0;:,*10 Revision 1 Page 4of12 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step .
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
The time clock starts when the candidate acknowledges the initiating cue.
This JPM must be performed in the simulator. Reset to exam-specific IC, or configure the simulator per the Simulator Setup Instructions.

EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Refers to OP-184-001 Section 2.3. Obtains controlled copy. controlled copy of OP-184-001 and selects S/U section 2.3.

  *2   Reset Main Steam Line Isolation logic                 Performs the following

Ensure All MSIV control switches in CLOSE position
Reset Main Steam Line Isolation by Depressing Mn Stm Line Div 1 Iso Reset S/U HS B21 1S32 push button.
Reset Main Steam Line Isolation by Depressing Mn Stm Line Div 2 Iso Reset HS B21 1S33 push button.

3 Enters TRO 3.8.2.1 Informs Unit Supervisor to take TRO S/U 3.8.2.1. EVALUATOR CUE TRO 3.8.2.1 taken.

TQ-106-0;n 0 Revision 1 Page 5 of 12 4 Place MOY overloads in service. Performs the following:

Place AC MOY OL BYPS HS-B21-1S37A Keyswitch to TEST Position. S/U
Place DC MOY OL BYPS HS-B21-1S37B Keyswitch to TEST Position.
5 Open outboard MSIV s Performs the following:
Place Mn Stm Line A OB Iso HV-141-F028A control switch to AUTO.
Place Mn Stm Line B, OB Iso HV-141-F028B, control switch to AUTO.
Place Mn Stm Line C, OB Iso HV-141-F028C, control switch to AUTO.
Place Mn Stm Line D, OB Iso S/U HV-141-F028D, control switch to AUTO.
Check Outboard MSIV OPENS by observing Red indicating light ILLUMINATED.

0 HV-141-F028A OPEN 0 HV-141-F028B OPEN 0 HV-141-F028C OPEN 0 HV-141-F028D OPEN 6 Open Main Steam Line Drains Open following Main Steam Line Drain Valves: S/U

Mn Stm Line IB Drain HV-141-F016
Main Stm Line OB Drain HV-141-F019

TQ-106-0.:> I 0 Revision 1 Page 6of12 7 Bypass MOV overloads WAIT 2 minutes, THEN:

Place AC MOV OL BYPS HS-B21-1S37A Keyswitch to NORM position S/U
Place DC MOV OL BYPS HS-B21-1S37B Keyswitch to NORM position 8 Drain Main Steam lines Performs the following:
Jog Open Mn Stm Line Drain To Cdsr HV-141-F021.
AFTER 1 minute, Close Mn Stm Line S/U Drain To Cdsr HV-141-F021.
Open Mn Steam Line Warmup HV-141F020.
9 Open Inboard MSIV s Performs the following
Place in MANUAL LV-10641 FW STARTUP CONTROL VLV.

                         * *Open Inboard MSIV by Placing Mn Stm Line A IB Iso HV-141-F022A control switch to AUTO.

WHEN power, pressure, level stabilizes THEN Open Inboard MSIV's as follows:

0 *Place Mn Stm Line B, IB Iso HV - S/U 141-F022B, control switch to AUTO. 0 *Place Mn Stm Line C, IB Iso HV - 141-F022C, control switch to AUTO. 0 *Place Mn Stm Line D, IB Iso HV-141-F022D, control switch to AUTO. Check each Inboard MSIV OPENS by observing Red indicating light ILLUMINATED.

TQ-106-0.:>-IO Revision 1 Page 7 of 12 FAULT STATEMENT AFTER THE LAST INBOARD MSIV HAS BEEN OPENED, THE "A" EHC PRESSURE TRANSMITTER OUTPUT WILL FAIL TO 1000 PSIG WHICH WILL CAUSE ALL THE TURBINE BYPASS VALVES TO OPEN AND DEPRESSURIZE THE REACTOR. BOOTH OPERATOR CUE After the last inboard MSIV has been opened, depress Key 1 to initiate bypass valves opening due to failure of the 'A' EHC pressure transmitter. 10 Recognize EHC malfunction Observes the following:

Alarm - MAIN TURBINE BYPASS VALVES OPEN (AR 105 106) SIU
All turbine bypass valves open
Reactor pressure lowering EVALUATOR NOTE Due to the failure of the EHC system to automatically control reactor pressure, the operators are authorized to close MSIV s without a procedure reference in order to mitigate the effects of the failure. ON-193-00lstep 3.7 provides procedural direction to close MSIVs and scram the reactor if the reactor is startup and <861 psig.

11 Scram the Reactor Places the Mode Switch to Shutdown S/U

TQ-106-0.:> I 0 Revision 1 Page 8of12

*12   Close MSIV's.                                  Prior to reactor pressure going below 0 psig, close MSIV' s and drains by performing the following:

Place MN STM Line A, OB ISO HV 141 F028A, Control Switch to CLOSE.
Place MN STM Line BOB ISO HV 141 F028B Control Switch to CLOSE.
Place MN STM Line C, OB ISO HV 141 F028C, Control Switch to CLOSE.
Place MN STM Line D OB ISO HV 141 F028D, Control Switch to CLOSE.

SIU

Place MN STM Line A IB ISO HV 141 F022A Control Switch to CLOSE.
Place MN STM Line BIB ISO HV 141

                                     '                     F022B Control Switch to CLOSE.
                                                       *, Place MN STM Line C IB ISO HV 141 F022C Control Switch to CLOSE.

Place MN STM Line D IB ISO HV 141 F022D Control Switch to CLOSE.
Check Inboard MSIV Opens by Observing Red Indicating Light ILLUMINATED.

EVALUATOR NOTE I CUE That completes the JPM. - EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 10of12 REVISION

SUMMARY

JOB PERFORMANCE MEASURE 84.0P.24667.151 Revision Description/Purpose of Revision 0 New JP,M I JPM revised to incorporated referenced document revisions. Also, revised to 1 put JPM in the new format.

Page 11of12 EVALUATOR COPY: TASK CONDITIONS Unit 1 startup is in progress in accordance with G0-100-002. The reactor is at the POAH. Reactor startup will continue after the MSIV s are open. Reactor pressure is 10 psig and reactor coolant temperature is 240 °F. The operator will perform all control room actions. INITIATING CUE Open the MSIVs per OP-184-001 Section 2.3.

Page 12of12 EXAMINEE COPY: TASK CONDITIONS Unit 1 startup is in progress in accordance with G0-100-002. The reactor is at the POAH. Reactor startup will continue after the MSIV s are open. Reactor pressure is 10 psig and reactor coolant temperature is 240 °F. The operator will perform all control room actions. INITIATING CUE Open the MSIVs per OP-184-001 Section 2.3.

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Shutdown Cooling Temperature Control JPM#: 49.0N.20294.151 Revision:3 Date:07/07/2016 Applicability: ~ RO ~ SRO Setting: Simulator NUREG-1123 E/APE I Sys223002 KIA Number K1.08 KIA Importance 3.4/3.5 Alternate Path: ~ YES 0 NO Time Critical DYES ~ NO Validation Time (min):25 Testing Method: D Simulate ~ ~erform Author::Greg van den Berg ~ Date: 07/07/2016 Operations Review: C..~ . . ._ Date: r/u b~ Validated: -..-~-C-~--. .Mf

                         . ____/________ Date: cr1~~I It Approval:     ~ l ~ .fLe                            Date:    '7 ""lC7

IC, Nuclear Training Supervisor Last, First Ml Employee Number Exam Date: Exam Duration (Min~=---------

            ---------

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:

         "'-------------

Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 49.0N.20294.151 1 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

11. REFERENCES A. ON-SDC-101, Loss of Shutdown Cooling (Rev. 1)

B. OP-149-002, RHR Shutdown Cooling (Rev. 72) C. AOP-149-001, RHR Abnormal Operating Procedure (Rev 0) Ill. TASK CONDITIONS Unit 1 is in MODE 4, 2 days into an outage. Reactor coolant temperature is 170 °P. Time to 200 °P is approximately 45 minutes. Section 2.22 (Operation of SDC in Mode 4 or 5) of OP-149-002 has NOT been performed. TRO 3.8.2.1 has been entered for SDC temperature control. An operator has been assigned to perform a S0-100-011 during the cooldown. IV. INITIATING CUE Lower reactor coolant temperature to 140°P in accordance with OP-149-002, Attachment E, step 6. V. TASK STANDARD Manipulate RHR to lower reactor coolant temperature. Restore SDC following SOC isolation.

SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 49.0N.20294.151 NOTE: It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

1. Reset the simulator to IC 272 'B' Loop of RHR in Shutdown Cooling

Place the simulator in RUN.
Open RHR F048B
Adjust RHR flow to 10,000 gpm and RHRSW flow to 9000 gpm.

2. Run scenario file EVAL490N20294151 IC SETUP.SCN to lower ESW temperature. The scenario will take 5 min to complete.

00:00:00 IRF r fE N009002 f:45 00:00:01 IRF rfEN100005 f:45 00:00:02 set ypxfstctwbasin=100 00:00:03 set ypxfsttsprpond=100 00:05:02 set ypxfstctwbasin=l 00:05:03 set ypxfsttsprpond=l

3. Run scenario file EVAL490N20294151.SCN IMF cmfMV01_HV151F007A

{Key[l]} IMF cmfMV05_HV151F009 c:20

TQ-106-u~ 10 Revision 1 Page 4of11 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step .
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
The time clock starts when the candidate acknowledges the initiating cue.
This JPM must be performed in the simulator. Reset to exam-specific IC, or configure the simulator per the Simulator Setup Instructions.

EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OP-149-002 S/U controlled copy. Att. E, SDC Temperature Control. 2 Ensure TRO 3.8.2.1 is entered. Confirms TRO 3.8.2.1 is entered per initial S/U conditions 3 Places HS-Ell-1S62B RHR LOOP B MOV OL Place keyswitch to TEST S/U BYPS keyswitch to TEST EVALUATOR NOTE Due to RHR conditions (F003B and F047B open and RHRSW and RHR at maximum flow), the only option for 'lowering temperature is to throttle closed F048B)

  *4    Operates RHR B to lower reactor coolant               Throttle Closed on HV-151-F048B RHR HX S/U temperature                                           B SHELL SIDE BYPS 5 AFTER 2 minutes, Place HS-El l-1S62B RHR                 AFTER 2 minutes, place keyswitch to S/U LOOP A MOV OL BYPS keyswitch to OPERATE               NORM

TQ-106-CJ..110 Revision 1 Page 5 of 11 FAULT STATEMENT HV-151-F009, SDC SUCTION OB ISOLATION VAL VE SPURIOUS CLOSURE OCCURS WHILE LOWERING REACTOR COOLANT TEMPERATURE BOOTH OPERATOR CUE After reactor coolant temperature begins to lower (indicated by RHR HX Inlet temperature) or when directed by the evaluator, depress Key 1 to initiate spurious isolation of F009 and cause a loss of SDC. EVALUATOR NOTE Examinee will investigate isolation ofHV-151-F009 6 Enters and obtains a copy of ON-SDC-101 for Loss Enters ON-SDC-101 based on isolation of S/U of Shutdown Cooling for automatic isolation of HV- HV-151-F009 and loss of SDC flow. 151-F009. EVALUATOR CUE If the applicant does not recognize to enter ON-SDC-101, ask, "What procedure will the SRO direct you to enter in this condition?" Then direct Entry for ON-SDC-101. EVALUATOR CUE Once the examinee has determined that HV -151-F009 is closed, provide report as the US that "Electrical maintenance has determined that F009 experienced a spurious closure. The cause of the spurious closure has been found and corrected." If the examinee does not recognize that a quick recovery can be performed due to the F009 being closed, as the US direct the examinee to "Restore shutdown cooling in accordance with ON-SDC-101." 7 Determines cause for the loss of RHR was due to Performs the following spurious isolation of HV -151-F009.

Recognizes that Condition B of ON- S/U SDC-101 is applicable to restore RHR Loop B to shutdown cooling.

EVALUATOR CUE If candidate begins to perform the surveillance, S0-100-011 in the next step, provide a cue that another operator will perform the surveillance.

TQ-106-0~ I 0 Revision 1 Page 6 of 11 8 Perform S0-100-011 Determines another operator is performing S0-100-011. 9 Comply with Tech Specs Notifies US to comply with Mode 4 LCO 3.4.9 EVALUATOR CUE If candidate begins to perform Attachment B in the next step, provide a cue that another operator will perform the attachment to determine time to 200°F. 10 Determines time to 200°F Determines another operator will perform attachment B. EVALUATOR CUE If candidate begins to determine if reactor coolant circulation is established in the next step, provide a cue that another operator will maintain reactor coolant circulation. 11 Establish reactor coolant circulation Determines another operator will maintain reactor coolant circulation EVALUATOR CUE Once the examinee has determined that a quick recovery can be performed due to the F009 being closed, as the US direct the examinee to "Restore shutdown cooling in accordance with AOP-149-001, Att A." 12 Restore previously in-service loop ofRHR to SDC Determines AOP-149-001, Att A will govern a quick recovery of the previously in-service SDC loop

TQ-106-0~ I 0 Revision 1 Page 7 of 11 13 Verify valve alignment prepared for SDC

Ensure HV-151-F015B CLOSED .

restoration.

Ensure HV-151-F049 Radwaste OB Isolation CLOSED.

Ensure HV -151-F040 Radwaste IB Isolation CLOSED. S/U
Ensure HV-151-F007B RHR PUMPS B&D DISCHARGE MIN FLOW VLV TO SUPP POOL is CLOSED and DEACTIVATED.

14 Determines that loop voiding is not suspected Marks step 7 as N/A S/U

*15   Opens shutdown cooling suction isolation valve

Ensure Open HV-151-F008 OPEN F009. SHUTDOWN CLG SUCT OB ISO.

S/U

Ensure Open HV-151-F009 SHUTDOWN CLG SUCT IB ISO.

*16   Lines up RHR injection valves for pump start.

Close HV-151-F017B RHR INJ FLOW CTL. S/U
OpenHV-151-F015B RHRINJ OB ISO .

*17   Starts an RHR pump                              Starts RHR PUMP 1P202B or D.         S/U
*18   Establishes approximately 5000 GPM ofRHR        Throttle OPEN HV-151-F017B RHR INJ flow.                                           FLOW CTL to promptly establish flow  S/U approximately 5,000 gpm.

EVALUATOR NOTE I CUE I That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 9of11 REVISION

SUMMARY

JOB PERFORMANCE MEASURE 49.0N.20294.151 Revision Description/Purpose of Revision 0 NewJPM 3 Updated to match new format of ON-SDC-101 and AOP-149-001.

Page 10of11 EVALUATOR COPY: TASK CONDITIONS Unit 1 is in MODE 4, 2 days into an outage. Reactor coolant temperature is 170 °F. Time to 200 °F is approximately 45 minutes. Section 2.22 (Operation of SOC in Mode 4 or 5) of OP-149-002 has NOT been performed. TRO 3.8.2.1 has been entered for SOC temperature control. An operator has been assigned to perform a S0-100-011 during the cooldown. INITIATING CUE Lower reactor coolant temperature to 140°F in accordance with OP-149-002, Attachment E, step 6.

Page 11 of 11 EXAMINEE COPY: TASK CONDITIONS Unit 1 is in MODE 4, 2 days into an outage. Reactor coolant temperature is 170 °F. Time to 200 °F is approximately 45 minutes. Section 2.22 (Operation of SOC in Mode 4 or 5) of OP-149-002 has NOT been performed. TRO 3.8.2.1 has been entered for SOC temperature control. An operator has been assigned to perform a S0-100-011 during the cooldown. INITIATING CUE Lower reactor coolant temperature to 140°F in accordance with OP-149-002, Attachment E, step 6.

RB HVSUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Re-establish RB HVAC IAW ES-134-003 JPM#: 34.E0.20802.151 Revision:§ Date:07/06/2016 Applicability: ~ RO ~ SRO Setting: Simulator NUREG-1123 E/APE I Sys295032 KIA Number EA1 .03 KIA Importance 3.7/3.7 Alternate Path:~ YES D NO Time Critical DYES ~ NO Validation Time (min):20 Testing Method: Operations Review: D Simulate Author::Greg van den Berg j ~ Perform _L~=:.,**~(}b_=======:::::.... Date: 07/06/2016 Date: ~(.,,J y Validated: fJ{Xfe& Date: 'f/~~(/k Approval: --~----'W..___-~---.;;;;=:=---- Nuclear Training Supervisor Date: 9

Z CJ, fC, Examinee Name:

                 ------------------

Last, First Ml Employee Number Exam Date: Exam Duration (Min....:_ _ _ _ _ _ _ __

             ---------

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:----~~~~~~~~~- Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 34.E0.20802.151 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. .Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. ES-134-003, Re-Establishing Reactor Building HVAC (Revision 24) Ill. TASK CONDITIONS

The Plant has experienced a loss of normal feed and makeup. The Reactor is shut down, with water level at -65", pressure is 900 psig.
A primary and secondary containment isolation has occurred due to level being< -38". The isolations are verified to be completed IAW ON-159-002.
RPV control is IAW E0-100-102. Primary containment parameters are all normal (i.e.,

pressure, temperature and suppression pool level).

E0-100-104, Secondary Containment Control, has been entered due to Zone I HVAC not being in service for four hours.
HPCI is unavailable, RCIC is being restored and expected to be lined up feeding the vessel in approximately 30 minutes. RCIC had been down for repairs, which are now complete.
Both loops of ESW are in service.
A control structure chiller is in service.
All Individual room cooler fans are running.
Service water is available IV. INITIATING CUE Re-establish Reactor Building HVAC in accordance with ES-134-003, Re-establishing Reactor Building HV AC V. TASK STANDARD Zone 1 ISO SIGNALS LOCKOUT RELAYS re-tripped

SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 34.E0.20802.151 NOTE: It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

1. Reset the simulator to any rated-power IC.

2. Setup the simulator as follows:

a. Both loops of ESW in service with at least one pump running in both loops

b. Take the Mode Switch to SHUTDOWN

c. Ensure RB HVAC isolation trip on low level and maintain reactor water level <-50"

d. Start all room coolers with a cooling source

3. Insert the following malfunctions

a. IMF cmfPM01_1V202A Zone 1 fans do not start

b. IMF cmfPM01_1V2028 Zone 1 fans do not start

4. Other

TQ-106-CJ~ 10 Revision 1 Page 4of12 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step .
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
The time clock starts when the candidate acknowledges the initiating cue.
This JPM must be performed in simulator.
Configure the Simulator per the Simulator Setup Instructions .

EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy ofES-134-003. S/U controlled copy. EVALUATOR NOTE It will not be necessary to obtain any of the required equipment in the next step. This JPM deals with the control room actions ONLY. 2 Reviews, required equipment, precautions and Identifies Shift managers office as the S/U limitations location for obtaining the special equipment. EVALUATOR CUE Inform the student that any required equipment will be SIMULATED. 3 Ensure Service Water is available for restoration of Determines from task conditions that Reactor Building chillers prior to bypassing service water is available S/U isolations

TQ-106-u-310 Revision 1 Page 5of12 4 Ensure following conditions exist: Determines from task conditions:

Both loops ofESW in operation in accordance with
Both loops ofESW are in operation OP-054-001.
Control Structure Chiller in operation in accordance
Control structure chiller is in service SIU with OP-030-001.
All individual room cooler fans that have cooling
All individual room coolers are source in operation in accordance with OP-134-002.

runnmg EVALUATOR NOTE With Reactor Building HVAC isolation signal present, the following will be performed to bypass High Drywell Pressure/Low RPV Water Level HVAC Interlocks.

TQ-106-0s1 0 Revision 1 Page 6of12 5 Confirm automatic actuations per Attachment A Completes Attachment A:

RECIRC SYS TO ZONE I SUP SYS DMP HD-l 7657A- OPEN
ZONE I EXH SYS TO RECIRC SYS DMP HD-17602A-OPEN
ZONE I FILT EXH TO RECIRC SYS DMP HD-17601A-OPEN
ZONE I EXH SYS ISOLATION DMP HD-l 7576A- CLOSED
ZONE I EQUIP COMPT EXH SYS DMP HD-l 7524A-CLOSED
ZONE I SUPP SYS ISOLATION DMP HD-l 7586A- CLOSED S/U RECIRC SYS TO ZONE I SUP SYS DMP

                                                      ". HD-17657B-OPEN

ZONE I EXH SYS TO RECIRC SYS DMP HD-17602B-OPEN
ZONE I FILT EXH TO RECIRC SYS DMP HD-17601B-OPEN
ZONE I EXH SYS ISOLATION DMP HD-17576B-CLOSED
ZONE I EQUIP COMPT EXH SYS DMP HD-17524B-CLOSED
ZONE I SUPP SYS ISOLATION DMP HD-17 5 86B - CLOSED 6* On 1C681 Heat & Ventilation Control Panel, Place Inserts key and Places ZONE 1 HVAC ZONE 1 HVAC LOCA ISO BYPASS HS 17551A LOCA ISO BYPASS HS 17551A keylock SIU keylock switch to BYPASS switch to BYPASS 7 Observe Zone 1 HV AC LOCA ISO BYPASSED Verifies Zone 1 HVAC LOCA ISO BYPASSED annunciator AR-127 D09 alanns SIU annunciator AR-127 D09 alarms 8* On 1C681 Heat & Ventilation Control Panel, Place Inserts key and Places ZONE 1 HVAC Zone 1 HVAC LOCA ISO BYPASS HS-17551B LOCA ISO BYPASS HS 17551B keylock S/U keylock switch to BYPASS switch to BYPASS

TQ-106-u~10 Revision 1 Page 7of12 9 Observe Zone 1 HV AC LOCA ISO BYPASSED Verifies Zone 1 HVAC LOCA ISO BYPASSED annunciator AR-128 D09 alarms. S/U annunciator AR-128 D09 alarms 10* Reset Zone 1 ISO SIGNALS LOCKOUT RELAY Turns the lockout relay clockwise UNTIL it SIU XY07551A remains in the vertical position 11

Reset Zone 1 ISO SIGNALS LOCKOUT RELAY Turns the lockout relay clockwise UNTIL it S/U XY07551B remains in the vertical position FAULT STATEMENT THE ZONE I FANS DO NOT RETURN TO NORMAL OPERATION.

12 Ensure Reactor Building Ventilation System Verifies RB Zone 1 NO Vent AR-127-C09 is Division I and Division II fans for Zone 1 return to STILL LIT Contacts the RB NPO to determine the S/U normal operation in accordance with OP-134-002 status of the RB Ventilation system EVALUATOR CUE Acknowledge request and report, "Both RB ventilation fans are tripped and neither can be restarted." EVALUATOR NOTE The operator should continue to step 5.1.3.b.7 to restore the line-up. 13* On 1C681 Heat & Ventilation Control Panel, Place Places ZONE 1 HV AC LOCA ISO ZONE 1 HVAC LOCA ISO BYPASS HS-1755 lA BYPASS HS-17551A keylock switch to S/U keylock switch to NORMAL NORMAL 14 Observe Zone 1 ISO SIGNALS LOCKOUT Verifies Zone 1 ISO SIGNALS LOCKOUT RELAY XY07551A trips RELAY XY07551A-pointing to~ 10 o'clock S/U position with the RED semaphore visible 15 Observe Zone 1 HV AC LOCA ISO BYPASSED Verifies Zone 1 HVAC LOCA ISO BYPASSED alarm AR-127 D09 - SLOW FLASHING S/U alarm AR-127 D09 clears 16* On 1C681 Heat & Ventilation Control Panel, Place Places ZONE 1 HV AC LOCA ISO Zone 1 HV AC LOCA ISO BYPASS HS-17551B BYPASS HS-17551B keylock switch to S/U keylock switch to NORMAL NORMAL

TQ-106-lJ310 Revision 1 Page 8 of 12 17 Observe Zone 1 ISO SIGNALS LOCKOUT Verifies Zone 1 ISO SIGNALS LOCKOUT RELAY XY07551B trips RELAY XY07551B - pointing to~ 10 o'clock S/U position with the RED semaphore visible 18 Observe Zone 1 HVAC LOCA ISO BYPASSED Verifies Zone 1 HVAC LOCA ISO BYPASSED alarm AR-128 D09 - SLOW FLASHING SIU alarm AR 128 D09 clears 19 Notify Technical Support Coordinator attempts to Contacts TSC restart RB HV AC have failed and to determine S/U additional actions required to restart HVAC or shed electrical loads to reduce heat load EVALUATOR CUE Role-play the TSC coordinator, and acknowledge the request. 20 Exit this procedure Exits the procedure SIU EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 10of12 REVISION

SUMMARY

JOB PERFORMANCE MEASURE 34.E0.20802.151 Revision Description/Purpose of Revision 0 NewJPM 5 Revised to new JPM format.

Page 11 of 12 EVALUATOR COPY: TASK CONDITIONS

The Plant has experienced a loss of normal feed and makeup. The Reactor is shut down, with water level at-65", pressure is 900 psig.
A primary and secondary containment isolation has occurred due to level being< -38". The isolations are verified to be completed IAW ON-159-002.
RPV control is IAW E0-100-102. Primary containment parameters are all normal (i.e.,

pressure, temperature and suppression pool level).

E0-100-104, Secondary Containment Control, has been entered due to Zone I HVAC not being in service for four hours.
HPCI is unavailable, RCIC is being restored and expected to be lined up feeding the vessel in approximately 30 minutes. RCIC had been down for repairs, which are now complete.
Both loops of ESW are in service.
A control structure chiller is in service.
All Individual room cooler fans are running.
Service water is available INITIATING CUE Re-establish Reactor Building HVAC in accordance with ES-134-003, Re-establishing Reactor (

Building HVAC

Page 12 of 12 EXAMINEE COPY: TASK CONDITIONS

The Plant has experienced a loss of normal feed and makeup. The Reactor is shut down, with water level at -65", pressure is 900 psig.
A primary and secondary containment isolation has occurred due to level being< -38". The isolations are verified to be completed IAW ON-159-002.
RPV control is IAW E0-100-102. Primary containment parameters are all normal (i.e.,

pressure, temperature and suppression pool level).

E0-100-104, Secondary Containment Control, has been entered due to Zone I HVAC not being in service for four hours.
HPCI is unavailable, RCIC is being restored and expected to be lined up feeding the vessel in approximately 30 minutes. RCIC had been down for repairs, which are now complete.
Both loops of ESW *are in service.
A control structure chiller is in service.
All Individual room cooler fans are running.
Service water is available INITIATING CUE Re-establish Reactor Building HVAC in accordance with ES-134-003, Re-establishing Reactor Building HVAC

\\

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Energize "Dead" 4KV ESS Bus '20' JPM#: 04.0N.20641.251 Revision:~ Date:07/06/2016 Applicability: ~ RO ~ SRO Setting: Simulator NUREG-1123 E/APE I Sys262001 KIA Number A2.07K/A Importance 3.0/3.2 Alternate Path:~ YES D NO Time Critical DYES ~ NO Validation Time (min):25 Testing Method: D Simulate ~ f rform Author::Greg van den c~G/2016 Operations Re1f: *~ '*Date: z/-v~,dy Validated: //10 . ~ Date: q(j_4//? ' Approval: __..~ ___~------ Date: _____Lr:.:......_.:) q,:z.1~1,h NUclearTrainill9s';ervisor Examinee Name:

                   ------------------

Last, First Ml Employee Number Exam Date: Exam Duration (Min): _ _ _ _ _ _ _ __

               ---------

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:

            -----------

Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 04.0N.20641.251 I. SAFETY CONSIDERATIONS A All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. AOP-004-001, Energizing Dead 4KV ESS Bus (Rev. 1)

8. AOP-024-001, Diesel Generator AOP (Rev. 0)

C. AR-016-001, DIG D, ESW, RWMU, and Misc Load Center (Rev 61) Ill. TASK CONDITIONS A. Unit 2 is at rated power.

8. An Electrical transient has occurred on the 2D ESS bus.

C. DG D failed to auto start. It is now in LOCAL, repaired, and available to be started and loaded. D. No electrical Bus fault is present. E. You are the On-Shift U2 PCOP F. Both loops of ESW are operational IV. INITIATING CUE Implement AOP-004-001 Attachment A to re-energize the 2D ESS bus from the 'D' EOG V. TASK STANDARD ESS Bus 20 is re-energized from DG 'D' IAW AOP-004-001 (Energizing Dead 4KV ESS Bus) recognizing that the DG trips and must be shutdown.

SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 04.0N.20641.251 NOTE: It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

1. Reset the simulator to IC-18 or an IC with Unit 2 SID.

2. Insert the following malfunctions

a. IMF cmfBR05_2A20401 Bkr 01 Fails Asis

b. IMF cmfBR03_2A20408 Bkr 08 Overcurrent Trip

c. IOR di43CMD_Q f:LOCAL 'D' EDG 43CM to LOCAL

3. Have the following keys assigned

a. {Key[31]} IOR di5ESD_Q f:STOP Depress 5ES Pushbutton

b. {Key[32]} DOR di5ESD_Q f:STOP Depress 5ES reset P/B

c. {Key[32]} IOR di5ESRD_Q f:RESET Depress 5ES reset P/B

     -cl. {Key[33]} IOR diOC521DRST_Q f:RESET c:5 Annunciator reset

e. {Key[34]} IOR di43GMD_Q f:ISO Switch to iso on EOG

f. {Key[35]} IOR di1LD_Q f:START Starts the 'D' EOG

4. Activate the following ET to trip the'D' EOG on overspeed after it starts

a. ET-040N1203251

b. di1LD_Q.CurrValue=#OR.di1LD_Q.START

c. IMF mfDG024008D d:10

5. Other

TQ-106-Ui.J I 0 Revision 1 Page 4 of 12 EVALUATOR INSTRUCTIONS

Marking a step as UNSAT requires written comments on respective step .
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
The time clock starts when the candidate acknowledges the Initiating Cue .
This JPM must be performed in the simulator. Reset to exam-specific IC or configure the simulator per the Simulator Setup Instructions .
Have a copy of AOP-004-001 .

EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. - EVALUATOR CUE Record JPM start time: BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN. Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of AOP-004-001. S/U controlled copy. 2 Review sections 1-5 Determines that step 5.1 starts with S/U attachment A EVALUATOR NOTE The following steps prevent inadvertent auto breaker closure by mismatching semaphores. This is performed on the de-energized 4KV ESS bus only. 3* Place XFMR 101 TO BUS 2D BKR 2A20401 Places 2A20401 switch to CLOSE. Verifies switch to CLOSE Red light OFF, Amber light LIT, Green light SIU LIT. 4* Place XFMR 201 TO BUS 2D BKR 2A20408 Places 2A20408 switch to CLOSE. Verifies switch to CLOSE Red light OFF, Amber light LIT, Green light S/U LIT.

TQ-106-L_ ,Q Revision 1 Page 5 of 12 5 Check the status oflockout relays on Bus 2D (86A- Directs an NPO to check the status of Bus SIU 204, 86Al-204, and 86A2-204) 2D lockout relays EVALUATOR CUE Acknowledge request and report NO lockout relays are tripped on the 2D ESS Bus. EVALUATOR NOTE Steps 3, 4, and 5 of Attachment A determine which Attachment of the procedure is required to energize the bus. Step 3 and 5 are not applicable due to no Bus lockouts and the availability of the 'D' EDG. The given sections of the procedure have the applicable Attachments for all three steps so not to cue the operator. 6 Determines step 4 is applicable Proceeds to attachment M S/U 7 Determines step 1 is not applicable N/As step 1 SIU 8 Verify XFMR 101 TO BUS 2D BKR 2A20401, Verifies breakers 2A20401, 2A20408, and XFMR 201 TO BUS 2D BKR 2A20408, and Diesel 2A20404 are open by Green flags S/U Generator B(E) Output Breaker 2A20404 are OPEN EVALUATOR NOTE The following step can be verified using R *Time screen or sending an NPO to verify 9 Ensure the following breakers are OPEN: Dispatches an NPO to verify breaker

2A20402, RHR Pump 2P202D positions
2A20403, CRD Wtr Pump 2P132B S/U
2A20405, CS Pump 2P206D 2A20409, Turbine Bldg Chiller 2K102B EVALUATOR CUE Acknowledge request and report, "At 2A204, breakers 2, 3, 5, and 9 are open."

10 Determines step 3 is not applicable N/As step 3 S/U 11

At OC521D, Place DG D Control Mode Select Determines this step has been completed S/U Switch to LOCAL

TQ-106-lJ~10 Revision 1 Page 6 of 12 12* At OCS21D, Depress SES Emergency Stop Directs NPO to depress SES Pushbutton on S/U Pushbutton 'D'EDG BOOTH OPERATOR CUE When directed by the floor, insert Key 31 EVALUATOR CUE Acknowledge request, Direct booth to insert Key 31, and report SES pushbutton has been depressed 13 At OCS21D, Verify the following: Directs NPO to report status of the

Remote light NOT illuminated indicating lights S/U
Local light illuminated DG D Available for emergency light not illuminated EVALUATOR CUE Acknowledge request and report, "The Remote light is NOT illuminated, Local light is illuminated, and DG D Available for emergency light is not illuminated."

14 Determines step 4.b and care not applicable N/As step 4.b and c S/U lS Verifies ESW is available Determines ESW pumps are running S/U 16* At OCS21D, Depress SES Emergency Stop Reset Directs NPO to depress SES Reset S/U pushbutton Pushbutton on 'D' EDG EVALUATOR CUE Acknowledge request, Direct booth to insert Key 32, and report SES reset pushbutton has been depressed BOOTH OPERATOR CUE When directed by the floor, insert Key 32 17* At OCS21D, Depress Annunciator and System Reset Directs NPO to depress Annunciator and-S/U pushbutton ' System Reset Pushbutton on 'D' EDG EVALUATOR CUE Acknowledge request, Direct booth to insert Key 33, and report Annunciator and System reset pushbutton has been depressed

TQ-106-u~ 10 Revision 1 Page 7of12 BOOTH OPERATOR CUE When directed by the floor, insert Key 33 18* At OC521D, Place Governor mode select switch to Directs NPO to Place 'D' EDG Governor S/U ISOCHRONOUS mode select switch to ISOCHRONOUS EVALUATOR CUE Acknowledge request, Direct booth to insert Key 34, and report Governor mode select switch is in ISOCHRONOUS BOOTH OPERATOR CUE When directed by the floor, insert Key 34 FAULT STATEMENT 10 SECONDS AFTER THE DG IS STARTED, THE ENGINE WILL OVERSPEED AND TRIP THE EDG. 19* At OC521D, Depress DG D Engine Directs NPO to Start the 'D' EDG S/U Control START P/B EVALUATOR CUE Acknowledge request, Direct booth to insert Key 35, and report The 'D' diesel has started BOOTH OPERATOR CUE When directed by the floor, insert Key 35 20 Verify 2A20404 DG D(E) TO BUS 2D Verifies that 2A20404 closes and the ESS S/U automatically closes. Bus available light is Illuminated. EVALUATOR NOTE When the EDG trips the operator may perform actions per AR-016-001 or per AOP-004-001 att M step D.5. The below sequence is from the AR. Continue at step 24 if AOP-004-001 is followed. 21 Ensure automatic actions Verifies 2A20404 DG D(E) TO BUS 2D SIU opens and the EDG stops EVALUATOR CUE Inform the student that another operator will finish the AR and they are to continue with AOP-004-001

TQ-106-L __ , 0 Revision 1 Page 8 of 12 22 Enter AOP-024-001 Obtains AOP-024-001 S/U 23 Determine attachment D is applicable Reads the procedure to see Attachment D is S/U for the 'D' EDG. 24 Verify 43CM DG D Control mode switch is in Contacts NPO to verify position of 43CM. S/U LOCAL EVALUATOR CUE Acknowledge request and report, "The 'D' DG mode switch is in LOCAL." EVALUATOR NOTE The operator may or may not depress the SES Stop Pushbutton depending on which procedure they use. Since the ID ESS bus has power, it is not essential that the SES Stop P IB is depressed. EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 10of12 REVISION

SUMMARY

JOB PERFORMANCE MEASURE 04.0N.20641.251 Revision Description/Purpose of Revision 0 NewJPM Updated to new JPM format, revised task number and updated referenced 2 procedures.

Page 11 of 12 EVALUATOR COPY: TASK CONDITIONS

Unit 2 is at rated power.
An Electrical transient has occurred on the 20 ESS bus.
DG D failed to auto start. It is now in LOCAL, repaired, and available to be started and loaded.
No electrical Bus fault is present.
You are the On-Shift U2 PCOP
Both loops of ESW are operational INITIATING CUE Implement AOP-004-001 Attachment A to re-energize the 20 ESS bus from the 'D' EDG

Page 12of12 EXAMINEE COPY: TASK CONDITIONS

Unit 2 is at rated power.
An Electrical transient has occurred on the 20 ESS bus.
DG D failed to auto start. It is now in LOCAL, repaired, and available to be started and loaded.
No electrical Bus fault is present.
You are the On-Shift U2 PCOP
Both loops of ESW are operational INITIATING CUE Implement AOP-004-001 Attachment A to re-energize the 20 ESS bus from the 'D' EOG

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: APRM Gain Adjustment Revision: 5 JPM#: 78.0P.27731.101

                                         --"---- Date:      09/23/2016 Applicability:~ RO ~SRO Setting:    Simulator NUREG-1123 E/APE I Sys        215005      KIA Number      A1 .07     KIA Importance  3.0/3.4 Alternate Path: DYES ~ NO           Time Critical DYES~ NO Validation Time (min): _ _...;;.1.;;;..5_

cr/2~11~ J/it-// (,

                                                      'j/;)_'i flt 2; l q, llp Examinee Name:
                 --  ----------------

Last, First Ml Employee Number Exam Date: Exam Duration (Min): _ _ _ _ _ _ _ __

            ---------

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:. _ _ _ _ _ _ _ _ _ __ Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 78.0P.27731.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

11. REFERENCES A. OP-178-002, PRNMS (Revision 9)

Ill. TASK CONDITIONS APRM Channel 3 is reading approximately 70%. Core thermal power from the OD-3 heat balance has been verified to be 73% APRM Channel 3 has already been bypassed by the PCO. IV. INITIATING CUE Perform a manual APRM GAF adjustment of APRM 3 IAW OP-178-002 Section 2.2.5. V. TASK STANDARD Successfully perform manual APRM GAF adjustments for APRM 3.

SIMULATOR SETUP INSTRUCTIONS

1. Reset Simulator to any power IC and adjust reactor power to 73%.

Adjust APRM 3 GAF to indicate ~70%
Bypass APRM 3.

SIMULATOR SETUP INSTRUCTIONS FOR LOC 28 NRC EXAM

1. Reset the simulator to IC 390.

2. Verify conditions above.

TQ-106-ll;:, 10 Revision 1 Page 4of10 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step .
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
The time clock starts when the candidate acknowledges the Initiating Cue .
This JPM must be performed in the simulator. Reset to ~xam-specific IC, or configure the simulator per the Simulator Setup Instructions .
A replacement copy of OP-178-002 section 2.2.

BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OP-178-002, S/U controlled copy. determines section 2.2.5 applies. Verifies prerequisites and precautions are met. EVALUATOR NOTE Role-play as PCO or SRO to avoid using plant page system during the JPM 2 Establish communications with PCO Establishes communications using plant S/U page. EVALUATOR CUE State that all communications will be with examiner role playing as PCO or SRO to avoid using plant page system during the JPM EVALUATOR CUE When operator is confirming BYPASS LED status state, "Channel 13 BYPASSED LEDs for APRM 11, 12, and 14 are lit." 3 Verifies APRM 3 bypassed Confirms all four 2/4 voters, BYPASSED SIU LEDs for bypassed APRM are illuminated

  *4   Adjust the display to the proper screen                Press ETC button to display ENTER SET             S/U MODE
  *5   Accept the proper display screen                       Press ENTER SET MODE key                          S/U
  *6   Enter the password                                     Enter password "1234" and press ENT               S/U

TQ-106-us1 o Revision 1 Page 5of10 7 Confirm mode Confirm OPER SET mode indicated on SIU APRM or ODA

 *8  Setup display for gain adjustment

Using the cursor keys, highlight the S/U APRM GAIN
Press SET PARAMETERS key Verify APRM indicates SET PARAMETERS:

APRM GAIN

 *9  Adjust APRM 3 GAF to the target gain                      Performs the following IAW section 2.2.5:         S/U

Adjust the APRM GAIN DESIRED UNTIL PROJECTED FLUX (%) is+/- 2%

of calculated CTP using using Ui) CURSOR keys to scroll

Press the ACCEPT key 10 Confirm APRM 3 target gain is selected
Confirm the APRM GAIN PRESENT S/U changes to equal the APRM GAIN DESIRED Confirm ACTUAL FLUX (%) is +/- 2% of calculated CTP 11 Exit the setup displays
Press EXIT key S/U
Press EXIT SET MODE key Press YES key 12 Confirms APRM 3 display indicates OPERATE Confirms APRM upper display section S/U indicates OPERATE on top right corner of display 13 Ensures indications are within 2% of APRM Ensure reading on NMSB display and S/U reading APRM ODA reading within 2% of desired APRM reading EVALUATOR NOTE When Applicant either calls the control room or is returning to the control room to verify indications, end the JPM.

TQ-106-u-s10 Revision 1 Page 6 of 10 EVALUATOR CUE Record JPM stop time: EVALUATOR CUE That completes the JPM. EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 8of10 REVISION

SUMMARY

JOB PERFORMANCE MEASURE 78.0P.27731.101 Revision Description/Purpose of Revision 0 NewJPM 1 Revise for TQ procedures, minor editorial corrections 2 NRC revised based on facility comments 3 Revised for format change from NRC format to SSES format 4 Minor editorial changes. Revised power level to accommodate JPM pairing. 5 Updated to new format and updated referenced procedure revisionss

Page 9of10 EVALUATOR- SCENARIO 1

TASK CONDITIONS APRM Channel 3 is reading approximately 70%. Core thermal power from the 00-3 heat balance has been verified to to be 73% APR_M Channel 3 has already been bypassed by the PCO. INITIATING CUE Perform a manual APRM GAF adjustment of APRM 3 IAW OP-178-002 Section 2.2.5.

Page 10of10 EXAMINEE - SCENARIO 1 TASK CONDITIONS APRM Channel 3 is reading approximately 70%. Core thermal power from the OD-3 heat balance has been verified to to be 73% APRM Channel 3 has already been bypassed by the PCO. INITIATING CUE Perform a manual APRM GAF adjustment of APRM 3 IAW OP-178-002 Section 2.2.5.

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Implement Placing Alternate TBCCW Pump In Service JPM#: 15.0P.20688.151 Revision:~ Date:07/07/2016 Applicability: 1:8] RO 1:8] SRO Setting: Simulator NUREG-1123 E/APE I Sys400000 KIA Number A2.01 KIA Importance 3.3/3.4 Alternate Path: 1:8] YES 0 NO Time Critical DYES 1:8] NO Validation Time (min):10 Testing Method: D Simulate 1:8] Perform Author::Greg van den Berg

                           '\                         Date ;j71~;

Date: L~ Validated: -.v.-t-~~~~---- Date: q(2. c;(/? Approval: ~ L;:) ~ Date: ~ '.l- '7, /'2 Nuclear Training Supervisor Last, First Ml Employee Number Exam Date: Exam Duration (Min): _ _ _ _ _ _ _ __

             ---------

Evaluation Result: 0 Satisfactory 0 Unsatisfactory Evaluator:

          -----------

Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE I5.0P.20688.I5I I. SAFETY CONSIDERATIONS A All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

11. REFERENCES A. OP-I I5-00I, Turbine Building Closed Cooling Water System (Revision 26)

B. ON-TBCCW-IOI, Loss of Turbine Building Closed Cooling Water (Revision I) C. AR-I23-G02, TBCCW PUMP B MOTOR TRIP (Revision 27) D. AR-I23-G04, TBCCW HEAT EXCHANGER HEADER LO PRESS (Revision 27) 111. TASK CONDITIONS TBCCW Pump IA is in service, TBCCW Pump IB is in standby. TBCCW Pump IA is to be removed from service for planned maintenance. IA TBCCW HTX is in-service. Pre-start checks for TBCCW Pump IB are sat. An NPO is stationed in the Unit I TBCCW pump area. IV. INITIATING CUE Place TBCCW Pump IB in service and shutdown TBCCW Pump IA, IAW OP-I I5-00I section 2.2. V. TASK STANDARD TBCCW Pump IA restarted and supplying cooling to TBCCW loads

SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 15.0P.20688.151 NOTE: It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

Reset the simulator to IC-18, or an exam-specific IC 389.
Insert the following Event Triggers ETEVAL 150P20688151 tw_lp103a(l) = 0 & twvp114011 > 0.9 aet ETEVAL150P20688151A ETEVAL 150P20688151A diHS11405A.CurrValue = #OR.diHS11405A.RUN

 +30 IOR di1C140ACK_Q f:ACK
 +2 MOR dilC140ACK_Q f:NORMAL
 +2 DOR di1C140ACK_Q
 +2 IOR dilC140RST_Q f:RESET
 +2 MOR di1Cl40RST_Q f:NORMAL
 +2 DOR di1C140RST_Q IRF rfIA119003 f:RESET

Perform the following expert commands IMF cmf PM04_1P103A
Perform the following expert commands to assign keys to perform the required operator actions for the JPM.

{Key[26]} IRF rfTW115001 f:0 ' {Key[27]} IRF rfTW115001 f:100

TQ-106-lM 10 Revision 1 Page 4 of 10 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step.
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
The time clock starts when the candidate acknowledges the initiating cue.
This JPM must be performed in the simulator. Reset to exam-specific IC-389, or configure the simulator per the Simulator Setup Instructions.

EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies OP-115-001 Section 2.2 is governing Obtains controlled copy of OP-115-001 S/U procedure and obtains controlled copy. obtained, selects Section 2.2. 2* Starts TBCCW Pump 1B Depresses TBCCW PP 1P103B RUN PB S/U 3 Closes TBCCW Pump lA discharge valve Directs NPO to slowly close 114011, S/U TBCCW PUMP A DSCH BOOTH OPERATOR CUE Depress KEY 26 to close 114011. EVALUATOR CUE 114011 is closed. 4 Checks TBCCW Pump lB discharge pressure 86- Performs the following: 100 psig.

Requests from NPO current indication on PI-11405B, TBCCW PUMP B DSCH S/U PRESS.
Confirms value is within 86-100 psig band.

TQ-106-D~10 Revision 1 Page 5 of 10 EVALUATOR CUE PI-I I 405B indicates 98 psig. 5* Stops TBCCW Pump IA. Depresses TBCCW PP IPI03A STOP PB. SIU 6 Checks TBCCW HX IA outlet temperature 92- Performs the following: 98 °P.

Requests from NPO current indication on TI-I I 407 A, TBCCW HX A OUTLET SIU TEMP.
Confirms value is within 92-98 °P band.

EVALUATOR CUE TI-I I 407A indicates 95 °P. 7 Checks TBCCW system pressure stabilizes at Observes PI-I 1409, TB CCW HX OUTLET approximately 64-66 psig. HEADER, indicates approximately 64- SIU 66 psig. EVALUATOR NOTE The following step is a critical step only if the TBCCW Pump IA discharge valve was closed in the preceding steps. FAULT STATEMENT TBCCW PUMP lB TRIPS WHEN TBCCW PUMP lA DISCHARGE VAL VE IS STROKING OPEN. 8* Opens TBCCW Pump IA discharge valve. Performs the following:

Directs NPO to open I I 40 I I, TBCCW PUMPADSCH
Observes AR-I23-G02, TBCCW PUMP SIU B MOTOR TRIP, in alarm.
Informs Unit Supervisor of TBCCW Pump IB trip.

BOOTH OPERATOR CUE

Depress KEY 27 to open I I40I I.
Ensure Event Trigger ETEVALI50P20688I5I fires as I I40I 1 strokes open to trip TBCCW Pump IB.

TQ-106-lJ010 Revision 1 Page 6 of 10 EVALUATOR CUE As NPO: 114011 is open. As Unit Supervisor: Respond per procedure. As NPO if contacted about TBCCW Pump lB status: TBCCW Pump lB tripped. I don't know why. EVALUATOR NOTE Direction to start TBCCW Pump lA is provided in AR-123-G02, AR-123-G04, or ON-TBCCW-101. 9* I Starts TBCCW Pump lA. I Depresses TBCCW PP 1P103A RUN PB. SIU BOOTH OPERATOR CUE Ensure Event Trigger ETEVAL150P20668151A fires when TBCCW Pump lA is re-started to reset I/A and S/A compressors. EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 8 of 10 REVISION

SUMMARY

JOB PERFORMANCE MEASURE 15.0P.20688.151 Revision Description/Purpose of Revision 0 NewJPM Revised for the new template and to update referenced procedures. ON-2 115-001 is now ON-TBCCW-101, Loss of Turbine Building Closed Cooling Water

Page 9 of 10 EVALUATOR COPY: TASK CONDITIONS TBCCW Pump 1A is in service, TBCCW Pump 1B is in standby. TBCCW Pump 1A is to be removed from service for planned maintenance. lA TBCCW HTX is in-service. Pre-start checks for TBCCW Pump 1B are sat. An NPO is stationed in the Unit 1 TBCCW pump area. INITIATING CUE Place TBCCW Pump lB in service and shutdown TBCCW Pump lA, IAW OP-115-001 section 2.2.

Page 10of10 EXAMINEE COPY: TASK CONDITIONS TBCCW Pump 1A is in service, TBCCW Pump 1B is in standby. TBCCW Pump 1A is to be removed from service for planned maintenance. IA TBCCW HTX is in-service. Pre-start checks for TBCCW Pump 1B are sat. An NPO is stationed in the Unit 1 TBCCW pump area. INITIATING CUE Place TBCCW Pump IB in service and shutdown TBCCW Pump IA, IAW OP-I I5-00I section 2.2.

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Hydraulically Remove a HCU from Service in Accordance With OP-155-001 JPM#: 55.0P.20241.102 Revision: --""----- 0 Date: 09/23/2016 Applicability: ~ RO ~ SRO Setting: Plant NUREG-1123 E/APE I Sys 201001 KIA Number ----"""A-""-1"""".0'""'6_____K/A Importance 3.4/3.4 Alternate Path: DYES ~ NO Time Critical DYES ~ NO Validation Time (min):___,;1;...;;.0_ _ Testing Method: ~Simulate D Perform Author:: ~o.._.IA..J<_f // Date:~ Operations ~eview: CM - ., Date:~ Validated: (?a ,tcJ1.1 _......_,,__..__.____-=--'------- Date: CfI /2?//6 I Approval: ~21.Ac L0 k Nuclear Training Supervisor Date: q ' J_7

I (o Examinee Name:

                      --      ----------------

Last, First Ml Employee Number Exam Date: ______ __ ___..;. Exam Duration (Min): _ _ _ _ _ _ _ __ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator: _ _ _ _ _ _ _ _ _ __ Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 55.0P.20241.102 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. OP-155-001 Control Rod Drive Hydraulic System (Revision 69) Ill. TASK CONDITIONS A. Unit 1 is in Mode 4; all rods in. B. CRD System is aligned for normal operation. C. Tech Specs 3.1.3, 3.1.4, and 3.1.5 have been referenced and all appropriate actions are being followed. IV. INITIATING CUE Isolate HCU 30-47 IAW OP-155-001 section 2.17. DO NOT drain OR depressurize the HCU. V. TASK STANDARD HCU 30-47 is Hydraulically isolated.

TQ-106-lJ~ I 0 Revision 1 Page 3 of 9 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step .
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
The time clock starts when the candidate acknowledges the Initiating Cue.
This JPM must be performed in the plant. Obtain Shift Manager authorization to proceed. This JPM requires access to the RB.
Have a copy of OP-155-001section2.17 .
A different HCU may be selected for the JPM prior to the start if in-plant situations require changing it. (High rad, protected area, etc) Prior approval of the supervisor is required and the JPM may be pen and inked to identify the change.

EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OP-155-001 S/U controlled copy. section 2.17. 2 Review the prerequisites and precautions Reviews prerequisites and precautions. S/U EVALUATOR CUE S/U All prerequisites have been met. 3 Comply with following: Determines all appropriate actions are being followed from the initial conditions. S/U TS 3.1.3, TS 3.1.4, TS 3.1.5. ' EVALUATOR NOTE Following is applicable to all Hydraulic Control Units 1S239. Three (3) digit standard HCU valve numbers are used.(i.e. instead of 147101-3047 it will say 101)

    *4   Close 101, CRD Insert lso.                            Closes 101, CRD Insert lso by turning the S/U handwheel clockwise.

EVALUATOR CUE If turned clockwise, the valve moved and is now closed. S/U If turned counter-clockwise, the valve did not move.

     *5  Close 102, CRD Withdrawal lso.                        Closes 102, CRD Withdrawal lso by turning S/U the handwheel clockwise.

TQ-106-u~ 10 Revision 1 Page 4 of 9 EVALUATOR CUE If turned clockwise, the valve moved and is now closed. S/U If turned counter-clockwise, the valve did not move.

    *6  Close 113, Charging Water lso                  Closes 113, Charging Water lso by turning S/U the handwheel clockwise.

EVALUATOR CUE If turned clockwise, the valve moved and is now closed. S/U If turned counter-clockwise, the valve did not move.

    *7  Close 104, Cooling Water lso.                  Closes 104, Cooling Water lso by turning the handwheel clockwise.                    SIU EVALUATOR CUE If turned clockwise, the valve moved and is now closed.                                             S/U If turned counter-clockwise, the valve did not move.
    *8  Close 103, Drive Header lso.                   Closes 103, Drive Header lso by turning the handwheel clockwise.                        S/U EVALUATOR CUE If turned clockwise, the valve moved and is now closed.                                             S/U If turned counter-clockwise, the valve did not move.
    *9  Close 105, Exhaust Header lso.                 Closes 105, Exhaust Header lso by turning the handwheel clockwise.                    SIU EVALUATOR CUE If turned clockwise, the valve moved and is now closed.                                             S/U If turned counter-clockwise, the valve did not move.
  *10   Close 112, Scram Discharge Header lso.         Closes 112, Scram Discharge Header lso by turning the handwheel clockwise.         SIU

TQ-106-0~ *1 0 Revision 1 Page 5 of 9 EVALUATOR CUE If turned clockwise, the valve moved and is now closed. S/U If turned counter-clockwise, the valve did not move. EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 7of9 REVISION

SUMMARY

JOB PERFORMANCE MEASURE 55.0P.20241.102 Revision Description/Purpose of Revision 0 New JPM,- Revised from 55.0P.003.102

Page 8 of 9 EVALUATOR COPY: TASK CONDITIONS A. Unit 1 is in Mode 4; all rods in. B. CRD System is aligned for normal operation. C. Tech Specs 3.1.3, 3.1.4, and 3.1.5 have been referenced and all appropriate actions are being followed. INITIATING CUE Isolate HCU 30-47 IAW OP-155-001section2.17. DO NOT drain OR depressurize the HCU.

Page 9 of 9 EXAMINEE COPY: TASK CONDITIONS A. Unit 1 is in Mode 4; all rods in. B. CRD System is aligned for normal operation. C. Tech Specs 3.1.3, 3.1.4, and 3.1.5 have been referenced and all appropriate actions are being followed. INITIATING CUE Isolate HCU 30-47 IAW OP-155-001section2.17. DO NOT drain OR depressurize the HCU.

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Start RPS MG Set 2S237A(B) from Local Control Panel 2G201A(8) IAW OP-258-001 JPM#: 58.0P.26824.201 Revision: 3

                                                ------- Date:      09/23/2016 Applicability: 1Z! RO IZI SRO Setting: -'P_l.....

an"""t_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ NUREG-1123 E/APE I Sys 212000 KIA Number A2.02 KIA Importance 3.7/3.9 Alternate Path: DYES IZI NO Time Critical DYES IZI NO Validation Time (min):_--=2.;;;..5_

~~;::: Met~~~PeITonn Date:~

Operations RevieW:C~--- Date: CJ/z~ O~ Validated: (}er ,f,edcJ Date: 1/2~ /It Approval:-~-=--\-"....)_&+?_ . . .*____ Date: NUclear Training Supervisor Examinee Name:

                     --    ----------------

Last, First Ml Employee Number Exam Date: _ _ _ _ _ _ _ __ Exam Duration (Min): _ _ _ _ _ _ _ __ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:

          -----------

Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE

58. OP.26824.201 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. OP-258-001, RPS SYSTEM (Rev. 62) Ill. TASK CONDITIONS RPS MG Set 2S237A(B) has been de-energized for emergent maintenance on the normal supply EPA breakers. The 120V RPS Power Distribution Panel 2Y201A(B) is on Alternate Power. Maintenance has been completed on the RPS A(B) MG Set, and all clearance orders have been removed. All 480V AC and 125V DC power systems are in operation. CL-258-0011 is complete. Electrical Maintenance is available to support this evolution. Initial conditions at the RPS MG set are

Motor On light (red) is EXTINGUISHED
Motor Off light (green) is ILLUMINATED
Generator Output breaker (on the MG Set) is open
The MG voltmeter and ammeter indicate 0
Both EPA breakers (2CBS003A-A and 2CBS003A-C) are open
All four red indicating lights on the EPA breakers are extinguished IV. INITIATING CUE Start Unit 2 RPS MG Set A(B) and close the associated EPA breakers IAW OP-258-001 Sections 2.1 and 2.2.

V. TASK STANDARD Unit 2 RPS MG Set A(B) started p~r OP-258-001 Section 2.1 and normal supply EPA breakers closed per OP-258-001 Section 2.2.

TQ-106-u~*10 Revision 1 Page 3 of 12 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step .
Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
The time clock starts when the candidate acknowledges the Initiating Cue .
This JPM must be performed in the plant. Obtain Shift Manager authorization to proceed. This JPM requires access to Unit 2 RB RPS MG set
This JPM can be performed on either Unit 2 RPS MG set
Have a copy of OP-258-001 Section 2.1 and 2.2 .

EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OP-258-001 S/U controlled copy. sections 2.1 and 2.2. EVALUATOR NOTE The Operator will require a key for the EPA breakers later. They may choose to obtain a 235, 1235, or 2235 key from Control Room or the FUS. If they ask now, they now have a 2235 key. 2 Unlock AND rotate Voltage Adjust potentiometer to At 2G201A(B), REACTOR PROT SYS M-G S/U full counter-clockwise position. SET A(B) GENERATOR, local control panel performs the following

Loosens locking device set screw.

Rotates the potentiometer to the full counter-clockwise position EVALUATOR CUE Voltage adjust potentiometer unlocked Voltage adjust potentiometer is in the full counter-clockwise position EVALUATOR NOTE Motor has automatic reset of thermal overloads. If examinee releases PB before MOTOR ON PB cued as ON, such that motor would fail to come up to speed, thermal overloads should be allowed time to reset prior to initiating another start sequence.

   *3   Depress AND hold MOTOR ON pushbutton                  Depresses the MOTOR ON PB and                     S/U maintains it depressed

TQ-106-C.r;:>10 Revision 1 Page 4of12 EVALUATOR CUE Motor On PB is depressed

   *4  Release Motor On PB when Motor On red               Observes the MOTOR ON red light is                 S/U indicating light Illuminates.                       illuminated and releases the MOTOR ON PB EVALUATOR CUE Motor On red light is lit and when released, the Motor On PB releases 5  Observes MG Set comes up to speed                   Observes MG Set comes up to speed                  S/U EVALUATOR CUE MG set running at speed EVALUATOR NOTE The Motor On pushbutton must be depressed again in order to reset the overvoltage trip. There is no visible indication that it has reset.
   *6  Resets OV relay                                     Depresses MOTOR ON PB                              S/U

.EVALUATOR CUE Motor On PB depressed and released 7 Verifies RPS MG set voltage at 120V AC Observes RPS MG Set A(B) voltmeter. S/U I EVALUATOR CUE RPS MG set voltmeter indicates 11 OV AC

   *8  Adjusts voltage output to 120V AC.                  Turns the VOLTAGE ADJUST                           S/U potentiometer clockwise until 120V AC EVALUATOR CUE RPS MG set voltmeter indicates 120V AC 9   Locks Voltage Adjust potentiometer.

Tightens the locking set screw on the S/U VOLTAGE ADJUST potentiometer.

  *10   Closes MG set generator output breaker              Lifts the GENERATOR OUTPUT breaker                S/U operating paddle to the full up position.

TQ-106-uv *10 Revision 1 Page 5of12 EVALUATOR CUE

Generator Output breaker is closed. 11 Observes EPA breaker 2CBS003A-A(B-B).lnput At 1CBS003A-A (B-B), RPS MG SET A(B) S/U Power Available red light ILLUMINATES EPA BREAKER, observes POWER IN MOTOR GEN red light illuminated. EVALUATOR CUE Power In Motor Gen red light is lit. EVALUATOR NOTE Section 2.1 is complete. Remaining steps are in Section 2.2.

*12   Obtains 235, 1235, or 2235 key from Control           Indicates keys available from Control S/U Room.                                                 Room, FUS office.

EVALUATOR CUE You have a 2235 key.

*13   Inserts key in 2CBS003A-A(B-B), RPS MG Set            At 2CBS003A-A (B-B), RPS MG SET A(B)  S/U A(B) EPA Breaker, Oper/Reset switch.                  EPA BREAKER, inserts key in OPER/RESET switch EVALUATOR CUE Key inserted.
*14   Resets 2CBS003A-A(B-B), RPS MG Set A(B)               Momentarily places OPER/RESET Switch  S/U EPA Breaker.                                          to RESET.

EVALUATOR CUE EPA breaker reset.

*15   Place 2CBS003A-A(B-B), RPS MG Set A(B) EPA            Places OPER/RESET switch to OPER      S/U Breaker, in Operate EVALUATOR CUE Oper/Reset switch is in OPER

TQ-106-u~ 10 Revision 1 Page 6 of 12

*16   Confirm overvoltage, undervoltage, and               Observes OVERVOLTAGE,                      S/U underfrequency lights are not illuminated            UNDERVOLTAGE and UNDERFREQUENCY lights are extinguished.

EVALUATOR CUE Overvoltage, Undervoltage And Underfrequency lights are out. 17 Removes key from 2CBS003A-A(B-B), RPS MG Removes key from OPER/RESET switch SIU Set A(B) EPA Breaker, Oper/Reset switch. EVALUATOR CUE Key removed.

*18   Close 2CBS003A-A(B-B), RPS MG Set A(B) EPA           Lifts the 2CBS003A-A(B-B), RPS MG SET      S/U Breaker                                              A(B) EPA BKR, operating paddle to the full up position EVALUATOR CUE EPA breaker is closed.

19 Observe EPA breaker 2CBS003A-C(B-D).lnput Observes 2CBS003A-C(B-D), RPS MG S/U Power Available red light ILLUMINATES SET A(B) EPA BKR, POWER IN MOTOR GEN red light illuminated EVALUATOR CUE Power In Motor Gen red light is lit.

*20   Inserts key in 2CBS003A-C(B-D), RPS MG Set           At 2CBS003A-C(B-D), RPS MG SET A(B)        S/U A(B) EPA Breaker, Oper/Reset switch.                  EPA BREAKER, inserts key in OPER/RESET switch EVALUATOR CUE Key inserted.
*21   Resets 2CBS003A-C(B-D), RPS MG Set A(B)               Momentarily places OPER/RESET Switch      S/U EPA Breaker.                                          to RESET.

EVALUATOR CUE EPA breaker reset.

TQ-106-0.:> 1.0 Revision 1 Page 7of12

*22   Place 2CBS003A-C(B-D), RPS MG Set A(B) EPA             Places OPER/RESET switch to OPER              S/U Breaker, in Operate                                    Observes OVERVOLTAGE, UNDERVOLTAGE and UNDERFREQUENCY lights are extinguished.

EVALUATOR CUE Oper/Reset switch is in OPER

*23   Confirm overvoltage, undervoltage, and                 Observes OVERVOLTAGE,                         S/U underfrequency lights are not illuminated              UNDERVOLTAGE and UNDERFREQUENCY lights are extinguished.

EVALUATOR CUE Overvoltage, Undervoltage And Underfrequency lights are out. I

*24   Remove key from 2CBS003A-C(B-D), RPS MG                Removes key from OPER/RESET switch            S/U Set A(B) EPA Breaker, Oper/Reset switch.

EVALUATOR CUE Key removed.

*25   Closes 2CBS003A-C(B-D), RPS MG Set A(B)                Lifts the 2CBS003A-C(B-D), RPS MG SET         S/U EPA Breaker                                            A(B) EPA BKR, operating paddle to the full up position EVALUATOR CUE EPA breaker is closed.

26 Verifies Generator A(B) Feed to RPS Bus A(B) Contacts Control Room to observe at S/U white indicating light illuminated at 2C610. 2C610 GENERATOR A (B) FEED TO RPS BUS A(B) white indicating light illuminated. EVALUATOR CUE Generator A(B) feed to RPS Bus A(B) white light is lit at 2C610. EVALUATOR CUE Record JPM stop time:

TQ-106-{J~ I 0 Revision 1 Page 8 of 12 EVALUATOR CUE That completes the JPM. EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 10of12 REVISION

SUMMARY

JOB PERFORMANCE MEASURE 58.0P.26824.201 Revision Description/Purpose of Revision 0 NewJPM 1 Revision history unknown Changed to new TQ format 2 Updated procedures to latest revision

Page 11 of 12 EVALUATOR - SCENARIO 1 TASK CONDITIONS RPS MG Set 2S23 7A(B) has been de-energized for emergent maintenance on the normal supply EPA breakers. The 120V RPS Power Distribution Panel 2Y201A(B) is on Alternate Power. Maintenance has been completed on the RPS A(B) MG Set, and all clearance orders have been removed. All 480V AC and 125V DC power systems are in operation. CL-258-0011 is complete. Electrical Maintenance is available to support this evolution Initial conditions at the RPS MG set are

Motor On light (red) is EXTINGUISHED
Motor Off light (green) is ILLUMINATED
Generator Output breaker (on the MG Set) is open
The MG voltmeter and ammeter indicate 0
Both EPA breakers (2CBS003A-A and 2CBS003A-C) are open
All four red indicating lights on the EPA breakers are extinguished INITIATING CUE Start Unit 2 RPS MG Set A(B) and close the associated EPA breakers IA W OP-258-001 Sections 2.1 and 2.2.

Page 12of12 EXAMINEE - SCENARIO 1 TASK CONDITIONS RPS MG Set 2S237A(B) has been de-energized for emergent maintenance on the normal supply EPA breakers. The 120V RPS Power Distribution Panel 2Y201A(B) is on Alternate Power. Maintenance has been completed on the RPS A(B) MG Set, and all clearance orders have been removed. All 480V AC and 125V DC power systems are in operation. CL-258-0011 is complete. Electrical Maintenance is available to support this evolution Initial conditions at the RPS MG set are

Motor On light (red) is EXTINGUISHED
Motor Off light (green) is ILLUMINATED
Generator Output breaker (on the MG Set) is open
The MG voltmeter and ammeter indicate 0
Both EPA breakers (2CBS003A-A and 2CBS003A-C) are open
All four red indicating lights on the EPA breakers are extinguished INITIATING CUE Start Unit 2 RPS MG Set A(B) and close the associated EPA breakers IAW OP-258-001 Sections 2.1 and 2.2.

SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET I Task Title: Place RHR In Suppression Pool Colling at Remote Shutdown Panel JPM#: 49.0P.20301.201 Revision:_"""2'---- Date: 09/23/2016 Applicability: ~ RO ~ SRO Setting: Plant NUREG-1123 E/APE I Sys 219000 KIA Number"""'A~2.;....;.1..;;;..3_ _ _ _ K/A Importance 3.5/3.7 Alternate Path: 0 YES ~ NO Time Critical DYES ~ NO Validation Time (min):--=2=0_ _ Testing Method: D Si~mulate D Perform Author:: tj'a ~ // Date: ql~sL1t Operations Re!: 12/L Date: c;.,lc. ~,/,,re_ Validated: ___.,..._0!:_......._Cf_........,]j&}_"----"""-------- Date: 1/9-~//t Approval: -~---I_ 0:)_~---- Date: °l*17*/~ Nuclear"Trainifi9Supervisor Last, First Ml Employee Number Exam Date: Exam Duration (Min): _ _ _ _ _ _ _ __

             ---------

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator: _ _ _ _ _ _ _ _ _ __ Name Signature Comments:

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 49.0P.20301.201 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. ON-200-009, Control Room Evacuation (Rev 37) B. OP-249-005, RHR Operation in Suppression Pol Cooling Mode (Rev 32) Ill. TASK CONDITIONS Unit 2 was operating at rated power when the Control Room was evacuated due to a hazardous atmosphere. Operators completed all actions in ON-200-009, Control Room Evacuation, before evacuating the Control Room. Unit 2 RSDP transfer switches have been aligned per ON-200-009. RPV level control is with RCIC, stable at -40". RPV pressure is being maintained with SRVs 800-1050 psig. RHR was in the normal standby alignment when the Control Room was evacuated. ESW is in operation. RHRSW is in operation, supplying the 2A RHR heat exchanger. Condensate Transfer is in operation. IV. INITIATING CUE Place RHR A in Suppression Pool cooling from the Unit 2 RSDP IAW OP-249-005 section 2.4. V. TASK STANDARD RHR A operating in Suppression Pool cooling per OP-249-005 at :510,000 gpm flow, with all flow through the RHR heat exchanger.

TQ-106-0~10 Revision 1 Page 3of10 INFORMATION FOR EVALUATOR

Marking a step as UNSAT requires written comments on respective step .
Critical .steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
The time clock starts when the candidate acknowledges the initiating cue.
This JPM must be performed in the plant. Obtain Shift Manager authorization to proceed. This JPM requires access to Unit 2 RB RSDP.
Have a copy of OP-249-005 section 2.4 and ON-200-009 .

EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OP-249-005 S/U controlled copy. section 2.4. 2 Review prerequisites and precautions. Reviews prerequisites and precautions. S/U 3 Ensure ESW in operation. Observes ESW in operation is specified in S/U Task Conditions. 4 Place RHRSW in operation. Observes RHRSW in operation to the S/U 2A RHR HX is specified in Task Conditions.

  *5   Verifies that RHR Pump 1A not running.                 Contacts Unit 1 RSDP to determine RHR S/U Pump 1A status.

EVALUATOR CUE S/U RHR Pump 1A is in standby.

  *6   Ensure HV-251-F048A, Hx A Shell Side Byps, is          Observes HV-251-F048A, HX A SHELL S/U open.                                                  SIDE BYPS, indicates full open.

EVALUATOR CUE S/U HV-251-F048A indicates red light ON, amber light OFF.

  *7   Open HV-251-F028A, Supp Chmbr Spry Test                Places HS HV-251-F028A, SUPP CHMBR Shutoff.                                               SPRY TEST SHUTOFF, to the OPEN                     S/U position

TQ-106-u;) 10 Revision 1 Page 4 of 10 EVALUATOR CUE SIU HV-251-F028A indicates red light ON, amber light OFF.

 *8  Ensure HV-251-FOO?A, RHR PP A/C Min Flow, is        Observes HV-251-FOO?A, RHR PP A/C S/U open.                                               MIN FLOW, indicates full open.

EVALUATOR CUE S/U HV-251-FOO?A indicates red light ON, amber light OFF. 9 Determines no potential for RHR discharge loop Observes Condensate Transfer in operation S/U voiding. is specified in Task Conditions. EVALUATOR CUE S/U RHR A was in the normal standby lineup when the Control Room was evacuated.

*10  Ensure RHR A filled and vented.                     Directs NPO to vent RHR A using 251821, RHR DIV 1 DRYWELL SPRAY VENT                S/U VALVE, per OP-249-001 Step 2.4.10.

EVALUATOR CUE ' S/U RHR A fill and vent complete.

*11  Start RHR Pump A, 2P202A                            Places HS RHR PUMP A 2P202A to the START position and observes breaker         S/U closed.

EVALUATOR CUE S/U RHR Pump A indicates red light ON, amber light OFF.

*12  Throttle Open HV-251- F048A HX A SHELL SIDE         Performs the following:

BYPS to establish a system flow between 3,000

Places HS HV-251- F048A HX A gpm and 3,500 gpm as indicated on RHR SYSTEM SHELL SIDE BYPS, to the OPEN FLOW INDICATOR Fl-25105 position in 500 gpm increments followed by a 20 second pause. S/U
Observes Fl-25105, RHR SYSTEM FLOW, indicates 6000 gpm

Releases HS HV-251-F024A, TEST LINE CTL

TQ-106-u~10 Revision 1 Page 5 of 10 EVALUATOR CUE HV-251-F048A indicates red light ON, amber light ON. S/U Fl-25105 indicates 3500 gpm.

*13  Throttle Open HV-251- F048A HX A SHELL SIDE     Performs the following:

BYPS to establish RHR loop flow between 11,000

Places HS HV-251- F048A HX A .

gpm and 12,000 gpm as indicated on RHR SHELL SIDE BYPS, to the OPEN SYSTEM FLOW INDICATOR Fl-25105 position and establishes 11, 000 to 12, 000 gpm as indicated on RHR SYSTEM SIU FLOW INDICATOR Fl-25105

Observes Fl-25105, RHR SYSTEM FLOW, indicates 11,000 gpm
Releases HS HV-251-F024A, TEST LINE CTL

 *14  Throttle Closed HV-251-F024A TEST LINE CTL to

Places HS HV-251-F024A TEST LINE maintain ::::; 10,000 gpm as indicated on RHR CTL, to the CLOSED position SYSTEM FLOW INDICATOR Fl-25105
Maintains ::::; 10,000 gpm as indicated on S/U RHR SYSTEM FLOW INDICATOR Fl-25105 EVALUATOR CUE S/U HV-251-F024A indicates red light OFF, amber light ON.

 *15  Fully Open HV-251-F048A HX A SHELL SIDE        Performs the following:

BYPS

Places HS HV-251- F048A HX A S/U SHELL SIDE BYPS, to the OPEN position EVALUATOR CUE HV-251-F048A indicates red light ON, amber light OFF. S/U Fl-25105 indicates 9700 gpm.

 *16  Open HV-251-F047A RHR HX A SHELL SIDE          Performs the following:

INLET

Places HS HV-251- F047A RHR HX A S/U SHELL SIDE INLET, to the OPEN position

TQ-106-CJ~iO Revision 1 Page 6of10 EVALUATOR CUE HV-251-F047A indicates red light ON, amber light OFF. EVALUATOR CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

TQ-106-0310 Revision 1 Page 8 of 10 REVISION

SUMMARY

JOB PERFORMANCE MEASURE 49.0P.20301.201 Revision Description/Purpose of Revision 0 NewJPM Changed to new TQ format 1 Updated to latest procedure revisions 2 Updated to latest procedure revisions

Page 9of10 EVALUATOR COPY: TASK CONDITIONS Unit 2 was operating at rated power when the Control Room was evacuated due to a hazardous atmosphere. Operators completed all actions in ON-200-009, CONTROL ROOM EVACUATION, before evacuating the Control Room. Unit 2 RSDP transfer switches have been aligned per ON-200-009. RPV level control is with RCIC, stable at-40". RPV pressure is being maintained with SRVs 800-1050 psig. ' RHR was in the normal standby alignment when the Control Room was evacuated. ESW is in operation. RHRSW is in operation, supplying the 2A RHR heat exchanger. Condensate Transfer is in operation. INITIATING CUE Place RHR A in Suppression Pool cooling from the Unit 2 RSDP IAW OP-249-005 section 2.4.

Page 10of10 EXAMINEE COPY: TASK CONDITIONS Unit 2 was operating at rated power when the Control Room was evacuated due to a hazardous atmosphere. ' Operators completed all actions in ON-200-009, CONTROL ROOM EVACUATION, before evacuating the Control Room. Unit 2 RSDP transfer switches have been aligned per ON-200-009. RPV level control is with RCIC, stable at-40". RPV pressure is being maintained with SRVs 800-1050 psig. RHR was in the normal standby alignment when the Control Room was evacuated. ESW is in operation. RHRSW is in operation, supplying the 2A RHR heat exchanger. Condensate Transfer is in operation. INITIATING CUE Place RHR A in Suppression Pool cooling from the Unit 2 RSDP IAW OP-249-005 section 2.4.

SUSQUEHANNA NUCLEAR, LLC OPERATIONS TRAINING PROGRAM SCENARIO EXAMINATION GUIDE CONTROL ROD PATTERN ADJUSTMENT/ RFP LUBE OIL PUMP SWAP/ RFP VIBRATION/ LOSS OF RBCCW/ HYDRAULIC-BLOCK ATWS SCN# LOC28-NRC-01 Revision 1 04/14/2016 Examination Material

LOC28-NRC-01 Lesson Information Title Control Rod Pattern Adjustment/ RFP lube oil pump swap/ RFP Vibration/ Loss of RBCCW/ Hydraulic-Block A TWS Vision ID Accredited *YES o NO Training ID LOC28-NRC-01 Revision 11 Date I 04/14/2016 Prerequisites Teaching Time 65 Minutes Approval CBT Approval 1 N/A Date N/A Preparer Date Review (lnstructor/SME) Date Nuclear Engineering 1 N/A Date N/A Training Supervision Date Line Management Date 1 If required, otherwise N/A This simulator scenario has been reviewed and satisfies management expectations for inclusion of OE, Department Fundamentals and HuP, error-reduction techniques and safety standards. Specific applications and/or opportunities for reinforcement of management expectations are noted in the scenario guide or Attachment(s) where applicable. Copyrighted by Nuclear Training Group, SUSQUEHANNA NUCLEAR, LLC, 2016. All rights reserved, no part of this training material may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, recording or otherwise, without the prior permission of the Nuclear Training Group. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

2

LOC28-NRC-01 Revision History Revision Date Comments 0 03/17/2014 New exam Revised to new template format. Changed event number 1 to the lube oil pump transfer. Removed some RWCU malfunctions. Clarified the event going 1 04/14/2016 into the scram. Changed the reports to match procedures and actual guidance. Changed the scram from high RRP temperature to a RBCCW rupture. Event 3 is just a setup for Event 4 and actions are removed due to the fast nature of the RFP trip. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 3

LOC28-NRC-01 Table of Contents Scenario Overview................................................................................................................................5 Objectives .............................................................................................................................................7 A. Terminal Objective ................................................................................................................7 B. Generic Performance Objectives ...........................................................................................7 C. Simulator Performance Objectives ........................................................................................8 D. Task List. ............................................................................................................................. 1O Scenario Attributes .............................................................................................................................12 A. Critical Tasks ....................................................................................................................... 12 B. Scenario Malfunctions ......................................................................................................... 13 C. Abnormal Events and Major Transients ............................................................................... 14 D. EOP and EOP Contingencies Used .................................................................................... 14 E. Technical Specifications ...................................................................................................... 15 References ..........................................................................................................................................16 Setup Instructions ..............................................................................................................................18 A. Required Materials .............................................................................................................. 18 B. Simulator Initialization ......................................................................................................... 18 C. Simulator Preparation .......................................................................................................... 19 D. Document Training and Performance Feedback ................................................................. 19 E. Scenario Execution ............................................................................................................. 19 F. Simulator Files .................................................................................................................... 19 Event 1 - RFP 'A' Main Lube Oil Pump Swap .................................................................................... 22 Event 2 - Control Rod Pattern Adjustment .......................................................................................23 Event 3 - '8' RFP vibration .................................................................................................................25 Event 4 - 'B' RFP trip ..........................................................................................................................25 Event 5 - RBCCW TCV fails ................................................................................................................28 Event 6 - Complete loss of RBCCW ..................................................................................................30 Event 7 - Hydraulic block ATWS .......................................................................................................32 Event 8 - SLC pump trips ...................................................................................................................32 Event 9 - Wide Range level instrument fails .....................................................................................32 Event 1O - In-service RFP trips ..........................................................................................................37 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

4

LOC28-NRC-01 Scenario Overview The scenario begins with Unit 1 at 95 percent power, 500 days into the operating cycle. Preparations are set for performing a control rod pattern adjustment. HPCI is in day 2 of a planned 4-day system outage window. Diesel Generator E is substituted for DG A for a system outage window. The RFP lube oil conditioner was swapped from the RFP A reservoir to the B reservoir last shift. A severe thunderstorm watch is in effect for Luzerne County for the next 12 hours. The first task for the crew is to test the RFP A main lube oil pumps, and perform a pump swap in the process, per OP-145-003. NPOs will report the RFP lube oil conditioner is in-service on the RFP B reservoir once the lube oil pump swap is complete. When the RFP main lube oil Pump swap is complete the crew will withdraw control rods in accordance with the Reactivity Maneuver Request provided by Reactor Engineering, then proceed to raise power with recirc flow. The pattern adjustment will raise reactor power approximately 3 percent. When the reactivity maneuver has been completed, 'B' RFP will experience a rising vibration trend. Vibration will quickly rise to the alarm setpoint and then to the RFP trip setpoint. The crew is not expected to be able to respond to vibration trip. The crew will respond per off-normal procedures to the RFP trip and recirc LIM2 runback. Control rod insertion may be performed due to margin to the MELLA rod-line. The Recirc loop 'A' drive flow inputs to APRM flow channels 'C' and 'D' (APRMs 2 and 3) will drift high during the runback, resulting in a RBM flow compare control rod withdrawal block. The inoperable flow-biased scram and rod-block functions of the two APRMs will require entry into TS 3.3.1.1 and TRO 3.1.3. When the crew has lowered power below the MELLA rod-line, the RBCCW TCV will malfunction resulting in a loss of cooling to RBCCW. RBCCW temperature will quickly rise. The RBCCW TCV bypass valve will be stuck closed. The crew will be required to place RBCCW on ESW which bypasses the RBCCW TCVs and will restore cooling to RBCCW loads. Entry into TS 3.7.2 will be required for the loop of ESW made inoperable when aligned to the RBCCW HX. Once the crew has placed ESW in-service to RBCCW the return valve HV11024A2 will fail closed after approximately 5 minutes, due to its solenoid failing, resulting in a total loss of RBCCW cooling. Recirc Pump A lower motor bearing temperature will rise rapidly on the second loss of cooling, requiring a reactor scram and tripping of the Recirc Pump. If the reactor is not scrammed before the recirc pump is tripped, Region 1 of the power-flow map will be entered and the reactor will automatically scram on OPRMs. The reactor scram will result in a hydraulic-block A TWS. The crew will trip both Recirc Pumps and reduce level to the A TWS band to lower power. The crew will perform the ES to bypass RPS trips, allowing the scram to be reset to drain the SDV and scram again. The crew will be able to insert control rods using RMCS. The first SLC pump started will trip shortly after starting, requiring the second pump to be started. As reactor level is lowered one channel of Wide Range reactor level will fail, requiring the crew to diagnose the failure and raise FW flow to maintain reactor level within the ATWS band. The in-service RFP will trip after the scram is reset. RCIC can be used to maintain reactor level as the standby RFP is placed in service. The first attempt at draining the SDV and re-inserting a scram will result in limited control rod motion. The crew should reset the scram and allow the SDV to drain again while continuing control rod insertion. The scenario may be terminated when RPV water level is stable in the ATWS band, the 'A' RFP has tripped, and the Scram has been reset twice OR at the lead evaluator's discretion. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 5

LOC28-NRC-01 Objectives Mastery of the training content shall be demonstrated by individual and/or crew performance evaluation as specified in this training material and the applicable training program description, in accordance with training procedures. A. Terminal Objective Perform all system operations required to maintain the plant operating safely, or place the plant in a safe condition if a plant shutdown is required During the specified mode of plant I system operation Without error and in accordance with site procedures and management expectations

8. Generic Performance Objectives

1. For all activities, exhibit use of the Human Performance Tools, demonstrating the ability to:

Use HU tools to effectively control the plant during normal, abnormal, and emergency conditions Use of HU tools will be observable per the standards in HU-AD-003 (SRO) Take every opportunity to coach the team when HU standards are not being met and provide feedback to the team when the HU standards are being met

2. For all activities, exhibit proper use of procedures by:

Applying the correct procedure to operate equipment and respond to abnormalities Ensuring procedures are detailed enough to allow precise control of plant evolutions. Demonstrating the ability to: Apply the correct procedure to the situation Use place keeping for accurate implementation Identify any and all areas for procedure improvement Take ownership of and complete the improvement, whenever an area for procedure improvement is identified

3. Base actions and decisions with a bias toward conservative, safe operation of the plant, demonstrating the ability to:

Assure all plant evolutions and work are assessed for Radiological Safety, Industrial Safety, Nuclear Safety, Environmental Safety, or Corporate Safety Once a risk is determined, take appropriate actions to mitigate or minimize risk Request assistance for any activity which requires additional planning, special precautions, and management oversight to adequately manage the risks (SRO) Champion activities that are biased conservatively LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 6

LOC28-NRC-01

4. Demonstrate complete understanding of plant design and system interrelationships, demonstrating the ability to:

Work effectively as a team to interpret plant indications and determine an effective response Understand the bases for, and the plant response to, actions being taken

5. Maintain continuous awareness of critical parameters, demonstrating the ability to:

Validate parameters by observing multiple independent indications Relay parameter values with value, units, and trend; and include action being taken for an abnormal value or trend Notify supervision of any change to critical parameters (SRO) Assure critical parameters for operational conditions are understood by the team

6. Operate plant systems and equipment within design and operational limits, maintaining relevant parameters within assigned operating bands, demonstrating the ability to:

Anticipate the impact of component operation prior to its operation, and then verify that the expected effects occur during and following the operation Take manual actions (in accordance with procedure direction) when automatic actions do not occur Take prompt action to adjust system operating controls before assigned operating bands are exceeded Make reactivity and mode changes as directed by detailed operating procedures and approved reactivity plans C. Simulator Performance Objectives

1. Operational Actions and Annunciator Response Correctly identify plant annunciators and indications and perform appropriate remedial actions

2. System Operation, Controls and Instrumentation Accurately identify plant instrumentation and correctly interpret instrument readings to respond to normal, abnormal, and emergency conditions

3. Facility Design and Operating Characteristics Demonstrate the following:

An understanding of facility operating characteristics
The ability to safely control the operating characteristics of the facility within prescribed operating boundaries LOC28-NRC-01 Rev 1 Examination Material 04/14/2016
7

LOC28-NRC-01

4. System Loss and Component Level Malfunctions Perform system control manipulations to obtain desired operating results and demonstrate the ability to correctly respond to malfunction/loss of components and the impact of the malfunction/loss on interfacing plant systems

5. Heat Removal Component Operation Safely operate the plant's heat removal components and demonstrate knowledge of the relationship between the heat removal systems and the operation of facility to prevent exceeding System, Structure, or Component (SSC) design limits which include:

Primary coolant systems
Emergency coolant systems
Decay heat removal systems

6. Auxiliary and Emergency Component Operations Safely operate the plant's auxiliary and emergency components I systems to include the controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment to control release of radioactivity within regulatory limits

7. Reactivity Management Demonstrate knowledge of how reactivity is affected by plant operation and ability to respond to the change in reactivity to protect the safety and integrity of the reactor core

8. Technical Specifications During plant operation with the plant or system in a condition requiring Technical Specification action Identify the deviation and any required actions I notifications

9. Emergency Plan (if required)

During plant operation in an emergency condition Recognize conditions covered by the Emergency Plan (SRO) Demonstrate the ability to:

Identify and Implement the appropriate Emergency Action Level
Use the applicable bases to support an Event Classification on the specified Emergency Action Level

10. Control Room Duties Demonstrate the knowledge and ability to assume the appropriate responsibilities (for the assigned position) associated with the safe operation of the facility LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

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LOC28-NRC-01

11. Control Room Team Work Demonstrate the ability to function within the Control Room team to comply with station procedures and limits of facility license and respond to plant events using appropriate human performance tools to support safe operation of the facility D. Task List Task Title ID Licensed Operator Apply Technical Specification (TS) And Technical Requirements Manual (TRM) Requirements S-C00-00-1185 Implement Reactivity Manipulations Standards and Communication Requirements S-C00-00-2784 Implement Appropriate Portions Of Operations Standards S-C00-00-1081 For System and Equipment Operation Implement Operations Standards For Error And Event S-ADM-00-1091 Prevention Implement Standards for Shift Operations S-C00-00-2780 Implement Appropriate Portions of Conduct of Operations S-C00-00-1015 Implement Appropriate Portions of Secondary Containment Integrity Control S-C00-00-1020 Implement EOP Cautions S-C00-00-2566 Implement Operations Directives S-C00-00-3130 Ensure Plant Operates IAW the Operating License, Technical Specifications (TS}, and Technical S-C00-00-1183 Requirements Manual (TRM)

Implement HUMAN PERFORMANCE (HuP) - Standards for Error and Event Prevention S-EPP-00-3068 Reactor Operator Implement Withdraw Control Rod One Notch S-201002-01-005 Implement Test of Standby Main and Emergency Oil Pumps S-259001-01-100 Operate a Single Reactor Feed Pump in Manual S-259001-01-037 Perform Speed Adjustment of Reactor Recirc Pump During Normal Operation S-202001-01-008 Direct RBCCW Heat Exchanger Manual Transfer Of S-276000-01-003 Service Water And Emergency Service Water Inhibit ADS from actuating S-218000-01-006 Bypass the MSIV and CIG Interlocks S-239001-01-025 Inject Liquid Poison Using Pump 1P208A(B)/2P208A(B) S-211000-01-006 Perform the Required Actions to Maximize CRD Flow S-201001-01-044 Start an Individual Reactor Feed Pump Turbine following a Trip S-259001-01-045 Perform a Manual Startup of RCIC Using Turbine Trip and Throttling Valve S-217000-01-035 Perform Actions Required to Override RCIC Injection S-217000-01-060 Perform HPCI System Override Injection S-206000-01-062 Direct the Actions for Unanticipated Reactivity Change S-201002-01-009 Direct Actions for Core Flux Oscillations S-215005-01-017 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 9

LOC28-NRC-01 Task Title ID Direct Actions for Loss of RBCCW Flow S-208000-01-007 Direct the Actions for RPS and ARI Trip Bypass S-212000-01-038 Perform Required Actions for a Reactor Recirculation Pump Runback S-202002-01-022 Enter EOP RPV Control S-EOPRR-01-006 Enter Level/Power Control EO Procedure S-EOPRPV-01-004 Confirm Reactor Scram S-EOPRPV-01-002 Confirm Reactor Shutdown S-EOPRPV-01-003 Ensure All Isolations and Actuations Occur S-EOPRPV-01-005 Enter Primary Containment Control S-EOPPCC-01-002 Scram the Reactor S-EOPRR-01-005 Senior Reactor Operator Direct Entry into Loss of Reactor Recirculation Flow S-202001-02-004 Direct Required Actions for a Trip of Both Reactor Recirculation Pumps S-202001-02-009 Direct Entry into Unanticipated Reactivity Change S-201002-02-001 Direct Entry into Loss of Reactor Building Closed Cooling Water (RBCCW) S-208000-02-001 Direct and Coordinate Implementation of Level Power Control (ATWS) 000000-02-1154 Direct Performance of RPS and ARI Trip Bypass S-212000-02-002 Direct the Operation of a Single Reactor Feed Pump in Manual (ICS) S-259001-02-024 Direct a Reactor Feed Pump Turbine A(B)(C) Trip S-259001-02-035 Direct Speed Adjustment of Reactor Recirc Pump During Normal Operation S-202001-02-002 Direct Inhibiting the Automatic Depressurization System from Actuating S-218000-02-001 Direct Performance of the Required Actions to Maximize CRD Flow S-201001-02-007 Direct Start of an Individual Reactor Feed Pump Turbine Following a Trip S-259001-02-030 Direct Performance of Overriding RCIC Injection S-217000-02-010 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 10

LOC28-NRC-01 Scenario Attributes A. Critical Tasks

1. Inject SLC Early boron injection has the following benefits:

Safety Significance

Stop or prevent large magnitude Limit Cycle Oscillations which can lead to core damage.
Limit fuel damage from uneven flux patterns that could result from partial rod inserts.

Failure to inject Boron can result in Consequences for Failure

Cycle Oscillations which can lead to core damage .

to Perform Task

Fuel damage from uneven flux patterns that could result from partial rod inserts.

Indications/Cues for Event A TWS with initial reactor power level greater than 5% APRM power. Requiring Critical Task Inject SLC by inserting key into keylock switch and turning to start Performance Criteria selected SLC pump, fire the Squib valves and close the Reactor Water Cleanup isolation valve. Successful SLC injection would be indicated by a lowering SLC tank level Performance Feedback and a corresponding power level decrease.

2. Lowers RPV level to <-60" and maintains until E0-000-113 directs otherwise Core damage due to unstable operation can be prevented or at least Safety Significance mitigated by promptly reducing Feedwater flow so that level is lowered below the Feedwater spargers.

A General Electric Company study (NED0-32047) indicates that the Consequences for Failure major threat to fuel integrity from ATWS is caused by large-amplitude to Perform Task power/flow instabilities. The power oscillations can become large enough to cause melting of fuel in high-power bundles. Indications/Cues for Event A TWS with initial reactor power level greater than 5% APRM power. Requiring Critical Task Lower reactor water level by manually controlling injection rate from Performance Criteria Feedwater, HPCI and/or RCIC. Reducing vessel injection will result in Wide Range level indications lowering to -60 to -110 inches and will result in power level lowering as Performance Feedback indicated on the Average Power Range Monitors. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

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LOC28-NRC-01

3. Insert Control Rods IAW E0-000-113 Safety Significance Control rod insertion initiates power reduction immediately.

Consequences for Failure Failure to insert control rods allows power to remain elevated with to Perform Task resultant power oscillations and potential core damage. Indications/Cues for Event Exceeding a RPS scram setting with NO reactor scram signal, or Requiring Critical Task RPS/ARI fail to fully insert all control rods. Insert Control Rods by one or more of the following methods: Performance Criteria

Drive control rods after bypassing RWM
Reset and Scram again by performing ES-158-002 Bypass RPS logic trips Successful insertion of control rods will be indicated by:
Rod position full in indication for manual insertion of control rods Performance Feedback
Rod position showing control rod insertion after resetting scram, draining scram discharge volume and re-scram
Power level lowering as indicated on the Average Power Range Monitors B. Scenario Malfunctions Event Malfunction Operator Action in Response 1 Swap 'A' RFP main lube oil pumps N/A (OP-145-003) 2 N/A Withdraw control rods to raise reactor power 3 percent. (OP-AD-338, G0-100-012) 3 'B' RFPT vibration rises and 'B' RFPT trips on mfFW145 0078 high vibration, Recirc LIM2 runback (ON-164-002) 4 cmITR03_FTB31 APRM 2 and 3 'A' Recirc Loop drive flow fails 1N014C high during LIM2 runback (TS 3.3.1.1) 5 RBCCW TCV fails, ESW placed in-service to restore RBCCW cooling (ON-114-001), ESW cmfAV04_TV11028 loop declared inoperable when aligned to RBCCW (TS 3.7.2) 6 Complete loss of RBCCW, High RRP cmfAV01_HV11024A2 temperatures, Manual Scram 7 Hydraulic-block ATWS mfRD155 017 (E0-100-113, OP-145-005, ES-158-002)

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 12

LOC28-NRC-01 8 cmfPM03_ 1P208A SLC pump trips after start, standby SLC pump cmfPM03_ 1P208B successfully injects boron (OP-153-001) 9 Wide Range level instrument fails, RFP flow cmfTR01_L T14201A must be raised to maintain reactor level in A TWS band 10 In-service RFPT trips after first scram, RCIC mfFW148002 restored to maintain RPV level while standby RFPT placed in-service C. Abnormal Events and Major Transients Malfunction Description R Withdraw control rods to raise reactor power 3 percent. (OP-AD-338, G0-100-012) N Swap 'A' RFP main lube oil pumps (OP-145-003) AE1 RBCCW TCV fails, ESW placed in-service to restore RBCCW cooling (ON-114-001) AE2 RBCCW ruputure (ON-114-001) MT1 Hydraulic-block A TWS TS1 APRM 2 and 3 'A' Recirc Loop drive flow fails high during LIM2 run back (TS 3.3.1.1) TS2 ESW loop declared inoperable when aligned to RBCCW (TS 3.7.2) SLC pump trips after start, standby SLC pump successfully injects boron (OP-153-MAE1 001) Wide Range level instrument fails, RFP flow must be raised to maintain reactor level MAE2 in ATWS band In-service RFPT trips after first scram, RCIC restored to maintain RPV level while MAE3 standby RFPT placed in-service D. EOP and EOP Contingencies Used EOPs EOP Contingencies IZI E0-000-102, RPV Control D E0-000-102, Alternate Level Control IZI E0-000-103, Primary Containment Control D E0-000-102, Steam Cooling D E0-000-104, Secondary Containment Control D E0-000-112, Emergency Depressurization D E0-000-105, Radioactivity Release Control IZI E0-000-113, Power/Level Control D E0-000-114, RPV Flooding LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

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LOC28-NRC-01 E. Technical Specifications

1. TS 3.3.1.1, Instrumentation Reactor Protection System (RPS)

2. TS 3.7.2, Plant Systems Emergency Service Water System

3. TRM 3.1.3, Reactivity Control Systems Control Rod Block Instrumentation LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 14

LOC28-NRC-01 References

1. OP-AD-001 Operations Standards for System and Equipment Operation

2. OP-AD-004 Operations Standards for Error and Event Prevention

3. OP-AD-300 Administration of Operations

4. OP-AD-338 Reactivity Manipulations Standards and Communication Requirements

5. OP-111-001 Service Water System

6. OP-145-001 RFP and RFP Lube Oil System

7. OP-145-005 Infrequent Manual RFP System Operations

8. OP-145-006 Feedwater HMI Operations

9. OP-153-001 Standby Liquid Control System

10. OP-156-001 Reactor Manual Control System RMCS

11. OP-183-001 Automatic Depressurization System and Safety Relief Valves

12. OP-184-001 Main Steam System

13. G0-100-012 Power Maneuvers

14. ON-SCRAM-101 Reactor Scram

15. ON-RBCCW-101 Loss of RBCCW

16. ON-PWR-101 Reactor Power

17. ON-REC IRC-101 Reactor Recirculation Malfunction

18. E0-000-102 RPV Control

19. E0-000-103 Primary Containment Control

20. E0-000-104 Secondary Containment Control

21. E0-000-112 Emergency Rapid Depressurization

22. E0-000-113 Power/Level Control

23. AR-101-A01 RWCU Filter Inlet Hi Temp Isa

24. AR-101-A10 RFPT A Trip

25. AR-101-A16 RFPT B Trip

26. AR-102-F03 Recirc Pump A Seal Clg Water Lo Flow

27. AR-103-E06 APRM Flow Reference Off Normal

28. AR-104-H03 Rod Out Block

29. AR-106-C09 Gen Volt Reg Auto To Man Set Point Unbalanced

30. AR-110-A01 ADS Logic A Timer Initiated

31. AR-110-A02 ADS Logic B Timer Initiated LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 15

LOC28-NRC-01

32. AR-100-A03 ADS Logic C Timer Initiated

33. AR-100-A04 ADS Logic D Timer Initiated

34. AR-123-E05 RBCCW Header Hi Temp

35. LA-1295-001 RWCU System Panel 1C295

36. EP-PS-100 Emergency Director Control Room Emergency Plan Position Specific Instruction

37. EP-RM-004 EAL Classification Bases

38. ES-158-002 RPS and ARI Trip Bypass 39.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 16

LOC28-NRC-01 Setup Instructions A. Required Materials

1. US Turnover Sheet

a. Unit 1

1) -95% power for control rod pattern adjustment, 500 days on-line

2) HPCI in day 2 of 4-day system outage window for steam side maintenance. LCO 3.5.1 condition D has been entered for the outage.

3) 'E' EOG substituted for 'A' EDG for 'A' system outage window

4) RFP lube oil conditioner was swapped from RFP 'A' reservoir to 'B' reservoir last shift

5) Perform control rod pattern adjustment per RMR

6) Test 'A' RFP main lube oil pump 'B' and swap to main lube oil pump 'B'

b. Common and Unit 2

1) Unit 2 at rated power.

2) Severe thunderstorm watch is in effect for Luzerne County for the next 12 hours

2. Supporting Documents

a. RMR (2 copies)

b. OP-145-003 (for the Normal Event)

B. Simulator Initialization

1. Reset to exam specific IC. If not available, setup IAW the following instructions

a. Reset to IC-20

b. Place the simulator in RUN

c. Reduce core power to 95% using RRPs. Match loop flows.

d. Isolate the HPCI steam supply by closing the F002 and F003 isolation valves.

e. Depressurize the HPCI steam supply line after F002 and F003 are closed by opening F054 valve. Close the F054 valve once the steam line is depressurized.

f. Run SCN file HPB_HPCIOOS.scn to tagout HPCI steam-side

g. Place the simulator in FREEZE

2. Run SCN file exam\LOC28-NRC-01.scn

3. Place the simulator in RUN LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 17

LOC28-NRC-01

4. Perform simulator activities

a. Place a status control tag on the HPCI Steam Supply Valves

b. Place protected equipment magnets around RCIC

c. Place the 'E' for 'A' EOG signs up

d. Ensure proper CRMs are inservice

e. Post the blue reactivity signs

5. Verify the simulator matches the following

a. 3 RFs and 1MF is in the list due to performing the HPCI setup MF RF OR ET CONDITIONS 7:7 4:4 0:0 8 15

6. Ensure FW Control is selected to LEFM

7. Reset ODAs and all Overhead, PICSY, HMI and RWM alarms

8. Ensure horns and annunciators are on

9. Ensure Overhead Lights Override is off C. Simulator Preparation

1. Ensure the EOL CRC Book is at the PCO Console D. Document Training and Performance Feedback

1. Record crew position assignments in G:\NTGOPS\LOR\REQUAL\lnfo Tracking\ (LOR)

2. Record crew position assignments per TQ-104 (ILO)

3. Complete simulator exam checklist E. Scenario Execution

1. Identify performance improvement actions that may be addressed during the scenario

2. Provide turnover to the crew using the US Turnover sheet

3. Direct the crew to walk down the Control Room panels

4. Inform the Shift Manager that the crew has the shift F. Simulator Files LOC28-NRC-01 changemp fx10FWCTRL_B21.0UT ,,%,FW MASTER LVL CTRL OUTPUT de Imp SCN rat_mp insmp fxlBRFP _BllS.OUT changemp fxlBRFP _BllS.OUT ,,%,RFP B DEMAND insmp ycpxftv03 changemp ycpxftv03 0,10,mils,RFP B VIBR insmp fxlBB_SM_Bl.OUT changemp fxlBB_SM_Bl.OUT ,,RPM,RFPT B SPEED insmp fx10FWCTRL_B21.0UT insmp fxlBRFP _BllS.MA LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

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LOC28-N RC-01 change mp fxlBRFP _BUS.MA ,,bool,RFPT B AUTO/MAN ; RBCCW HX TCV fails {Key[3]} IMF cmfAV04_TV11028 r:lO f:O insmp rwttll305 change mp rwttll305 ,,,RBCCW HX OUTLET TEMP ; Adjust RBCCW cooling {Key[4]} IMF cmfAV04_TV11028 d:lS r:30 f:5 insmp swvsptv11028 changemp swvsptv11028 ,,,RBCCW HX TCV POS ; RBCCW discharge header rupture {Key[S]} IMF mfRW114001 f:20 insmp aoTRSHB311R601D.CurrValue changemp aoTRSHB311R601D.CurrValue 0,300,DEG F,RRP A LO ; Byp CRD pump suet filter GUIDE BRG TEMP(PT4) {Key[6]} IRF rfRD155028 d:120 f:lOO insmp aoTRSHB311R6011.CurrValue ; Close CRD chrg wtr isol F034 changemp aoTRSHB311R6011.CurrValue 0,300,DEG F,RRPA #1 {Key[7]} IRF rfRD155017 d:120 f:O SEAL CAV TEMP

                                                               ; ES-158-002 - ARI insmp cuteg331n019                                              {Key[8]} IRF rfDC102129 f:OPEN d:120 changemp cuteg331n019 ,,DEG F,RWCU NRHX INLET                   {Key[8]} IRF rfDC102103 f:OPEN d:120

0-G alarms suppressed SDR ; ES-158-002 - Div 1 RPS IMF annAR106F15 f: ALARM_OFF {Key[9]} IRF rfRP158039 f:BYPASS d:120 IMF annAR131A04 f:ALARM_OFF {Key[9]} IRF rfRP158040 f:BYPASS d:120
E DG subst for A ; ES-158-002 - Div 2 RPS IRF rfDG024001 f: A {Key[lO]} IRF rfRP158041 f:BYPASS d:120

{Key[lO]} IRF rfRP158042 f:BYPASS d:120

Recirc loop A xmitter offset initialization IMF cmfTR03_FTB311N014C f: O ; Re-open CRD chrg wtr isol F034 IMF cmfTR03_FTB311N014D f:O {Key[ll]} IRF rfRD155017 d:120 f:lOO
Hyd-block ATWS ; X-Tie CIG and I/A IMF mfRD155017 {Key[l2]} IRF rfPC125001 f: OPEN
CRD PCV binding ; HPCI OOSVC - isolate and depress steam-side first IMF cmfMV07 _PV146F003 f: Asls {Key[40]} SCN exam\HPB_HPCIOOS
Recirc loop A channel D flow xmitter malfunctions aet ETLOC28-NRC01-B HPB.HPCIOOS

                                                               ;# HV-F002 BRKR OPEN (IB)

activate NRHX iso alarm on high temp IRF rfDB106236 f: OPEN aet ETLOC28-NRC01-C ;# HV-F003 BRKR OPEN (OB)

IRF rfDC188113 f:OPEN

align ESW to RBCCW HX ;# HPCI AOP BRK OPEN aet ETLOC28-NRC01-D IRF rfDC188128 f: OPEN

                                                               ;#LOSS OF PWR TO HV-FlOO SOLENOID

Activates ETLOC28-NRC01-J IMF cmfAVOl_HVlSSFlOO aet ETLOC28-NRC01-E
1st SLC pump trips ETLOC28-NRC01-B aet ETLOC28-NRC01-F fx1B_LIMITERS_B432.B001 = 1 aet ETLOC28-NRC01-G MMF cmfTR03_FTB311N014C r: 30 i:O f:21789 MMF cmfTR03_FTB311N014D r:30 i:O f:19876
Trips breaker for PV-146-F003 when operated aet ETLOC28-NRC01-H ETLOC28-NRC01-C
WR level A fails as-is cuteg331n019 > 145 aet ETLOC28-NRC01-I IMF annARlOlAOl f: ALARM_ON
RFP B vibration

{Key[l]} IMF mfFW145007B r:180 f:lO LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 19

LOC28-NRC-01 ETLOC28-N RCOl-D ETLOC28-N RCOl-G

SWITCH: RBCCW HX A SW-ESW CHANGEOVER ;SWITCH:SBLC MANUAL INITIATION diHS11024A.CurrValue =#OR.diHS11024A.EMERG diHSS14804.CurrValue = #OR.diHSS14804.START_B IMF cmfAV04_HV11024Al f:O IMF cmfPM03_1P208B d:45 IMF cmfAV04_HV11024A2 f:O cet ETLOC28-NRC01-F IRF rfSW111032 f:O IMF cmfCV02_110050

+5 DMF cmfAV04_HV11024Al ETLOC28-N RCOl-H DMF cmfAV04_HV11024A2 ;SWITCH:DRIVE WTR PRESS THTLG

diHS14603.CurrValue #OR.diHS14603.0PEN IMF cmfMVOl_PV146F003 ETLOC28-NRC01-E

SWITCH: MODE SWITCH diHSC72AlS01.CurrValue != #OR.diHSC72AlS01.RUN ETLOC28-NRC01-I aet ETLOC28-NRC01-J rrlwr < -50 IMF cmfTROl_LT14201A ETLOC28-NRC01-F
SWITCH: SBLC MANUAL INITIATION ETLOC28-N RCOl-J diHSS14804.CurrValue =#OR.diH5514804.START_A ;SWITCH:MODE SWITCH IMF cmfPM03_1P208A d:45 diHSC72AlS01.CurrValue != #OR.diHSC72AlS01.RUN & (

cet ETLOC28-NRC01-G rp_c721k14a = 1 I rp_c721k14b =1) & rp_c72lkla =0 IMF mfFW148002 d:120 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

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LOC28-NRC-01 Event 1 - RFP 'A' Main Lube Oil Pump Swap Instructor Activities Operator Activities Notes Booth Operator No additional actions required PCO Role Play D Identifies the following alarm windows: As NPO dispatched to 'A' RFP main lube oil pumps for AR-120-803 and AR-101-H10 pre-start checks, report D Dispatch NPO to perform pre-start Standing by for test and checks of RFPT 'A' main lube oil pump swap of 'A' RFP main lube oil pumps. D Depress and hold TEST pushbutton for RFPT A ALT MN L-0 PPS HS-11912A D Observes standby lube oil pump starts by appropriate Red light ILLUMINATED D Release TEST pushbutton HS-11912A D Depress RUN pushbutton for RFPT A MN L-0 PP 1P124B D Places 1P124A in Standby D Performs above steps again to test the auto start function of the 'A' lube oil pump us D Directs PCO to test the 'A' RFP main lube oil pumps and perform a pump swap IAW OP-145-003 Instructor Note If the student asks, all prerequistes are completed so that the evolution may proceed. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 21

LOC28-N RC-01 Event 2 - Control Rod Pattern Adjustment Instructor Activities Operator Activities Notes Booth Operator When control rod withdrawal is complete, Enter the Control Room as Reactor Engineering and update the CRC book with the. updated shutdown sequence sheets and current control rod pattern. When the CRC book has been updated, Perform the third role play as the booth or on the floor Initiate Event 3 as soon as the reactivity maneuver is completed. PCOM Role Play D Withdraws Control Rods 22-23, 38-39, As RE contacted for assistance, reply 38-23, and 22-39 from position 00 to Core Thermal limits are position 04 IAW OP-156-001 and within our predictions. You OP-AD-338 may proceed with the pattern adjustment. D Uses two finger operation to select the proper Control Rod by depressing the Role Play Control Rod Selection pushbuttons As SM contacted for approval to commence the reactivity D Verifies the correct Control Rod is manipulation, reply selected and in the proper position The Reactivity D Withdraws Control rods by depressing manipulation may proceed IAWtheRMR the "W/Draw Rod" pushbutton D When all 4 rods have been moved, Role Play verifies that the rods are in the proper As RE contact the Control position Room as stated in the booth operator section D Depress 'Rod Selct Clear' pushbutton Thermal Limits are sat per D Plots the power change on the step #4 of the RMR. We will bring the RMR for returning Power/Flow map to rated power with Recirc D Monitors diverse indications of reactor flow momentarily. The power IAW OP-AD-001 Att G updated CRC pages have been replaced. The PCOP maneuvering envelope is D Verifies control rods to be withdrawn still 90% to 100% power. as directed by RMR IAW OP-AD-338 Role Play D IAW OP-AD-300, nulls Manual and As GCC, acknowledge all Automatic regulars using Man Volt Reg power change updates Adjust HC-10002 potentiometer, as required D Maintains Load Set -100 MWe above actual generator loads IAW G0-100-012 by depressing Load Selector

                                     'Decrease' and 'Increase' pushbuttons, as required LOC28-NRC-01 Rev 1                               Examination Material                            04/14/2016. 22

LOC28-NRC-01 Event 2 - Control Rod Pattern. Adjustment Instructor Activities Operator Activities Notes us D Obtains permission from the Shift Manager prior to commencing reactivity manipulations D May, inform GCC of load change on Unit 1 D Conducts a Crew Update prior to commencing rod withdrawal D Directs Control Rod Withdrawal IAW OP-156-001, RMR, and G0-100-012 D Monitors control rod movement with independent copy of RMR Instructor Note The rod pattern adjustment should be completed before moving to Event 3. This will ensure that the rod-line is raised high enough to challenge the MELLA boundary during the runback for the RFP Trip. Instructor Cue Initiate Event 3 as soon as power has been raised 5% or on the Lead Examiner's direction. If ill>>) the next event is started before the RE explaination for the maneuvering envelope, the crew may decide to only use RRPs. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 23

LOC28-N RC-01 Event 3 & 4 - 'B' RFP vibration/ 'B' RFP trip Instructor Activities Operator Activities Notes Booth Operator When power has been raised 5% or at the Lead Examiner's direction, Insert Key 1 to initiate high vibrations on

'B' RFP.

{Key[1]} IMF mfFW145007B r:180 f:10 'B' RFP vibration Monitor 'B' RFP vibration in Monitored Parameters. Ensure Event Trigger ETLOC28-NRC01.-B fires when a Recirc LIM2 is actuated by the 'B' RFP trip, to fail the APRM 2 drive flow input from Recirc Loop 'A'. PCOM Role Play D Performs AR-101-A16 for 'B' RFP vibs As FUS/NPO dispatched to

'B' RFP, wait 2 minutes and     D Reports Reactor Power, pressure, and report                             water level The 'B' RFP sounds out-of-      D If directed, lowers 'B' RFP speed IAW balance and it feels like there are higher vibrations        OP-145-006 by taking manual control around the pump.                   and lowering speed D If directed, lowers Core power IAW Role Play OP-164-002 by manually lowering As FUS/NPO contacted for
'B' RFP status post-trip,          RRPs speed report                          D Observes AR-101-A12 and reports 'B'
'B' RFP is coasting down on the turning gear. I don't       RFP Tripped see anything abnormal.          D Plots position on Power/Flow map D Performs ON-PWR-101 to monitor Role Play OPRMs for instabilities As NPO dispatched to the Lower Relay Room to report      D If directed, inserts control rods IAW the status of APRMS, wait 2        OP-156-001 and OP-AD-338 minutes and report No APRMs indicate any           D Performs AR-104-H03 and AR-103-alarms.                            E06 for 'A' & 'B' RBM and APRM 2 D Directs NPO to investigate APRMs LOC28-NRC-01 Rev 1                             Examination Material                                 04/14/2016. 24

LOC28-N RC-01 Event 3 & 4 .- '8' RFP vibration/ '8' RFP trip Instructor Activities Operator Activities Notes PCOP Role Play D IAW AR-101-A16, Checks alarm As WWM contacted for assistance with 'B' RFP condition and trend on RFPT Vibration vibrations, wait 5 minutes and XRSH-12728 and observes rise in 'B' report RFP vibration Engineering is looking at the vibration data but D May direct NPO to report conditions at doesn't have a specific the 'B' RFP recommendation at this time. D Performs ON-RECIRC-101 and verifies a LIM2 runback occurred Role Play D Monitors Main Steam Line Radiation As WWM contacted. for Monitor, RR-D12-1 R603, and Offgas assistance with APRM flow reference abnormal alarm, Pretreatment Log Radiation Monitor, wait 5 minutes and report RR-D12-1R601 l&C reports that Recirc us Loop 'A' recirc flow transmitters 831-1 N014C D If time allows, directs lowering 'B' RFP and 1N014D are indicating speed IAW AR-101-A16 by either

-20,000 gpm higher than the other two 'A' Recirc           manual control of the 'B' RFP or Loop drive flow                    manual control of the RRPs transmitters.                    D Contacts WWM for assistance with the
                                   'B' RFP D Directs Transient Actions IAW OP-AD-300 when 'B' RFP trips D Directs entry into ON-RECIRC-101 and ON-LVL-101 D May direct control rod insertion to gain margin to MELLA rod-line IAW the Shutdown Control Rod Sequence package and ON-PWR-101 D Notifies Chemistry, RP, and RE of
                                   >15% power change in 1 hour IAW G0-100-012 D Contacts WWM for assistance with the APRM flow compare alarm LOC28-NRC-01 Rev 1                              Examination Material                 04/14/2016

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LOC28-NRC-01 Event 3 & 4 - 'B' RFP vibration/ 'B' RFP trip Instructor Activities Operator Activities Notes us D Enters Tech Specs 3.3.1.1 Condition

                                'A' for B31N014C and B31N014D Recirc Flow Transmitter inoperable in functions 2.b and 2.f AND TRM 3.1.3 Conditions 'A' and 'B' for Function 1.b Instructor Note The scenario may proceed to Event 5 after 1O minutes have elapsed or once the crew has evaluated the power/flow map and made a determination as to whether control rod insertion is required.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 26

LOC28-NRC-01 Event 5 - RBCCW TCV failure Instructor Activities Operator Activities Notes Booth Operator IAW Event 3 note, Insert KEY 3 to initiate a failure of the RBCCW HX TCV {Key[3]} IMF cmfAV04_TV11028 r:10 f:O RBCCW HX TCV fails Ensure Event Trigger ETLOC28-NRC01-C fires when RWCU NRHX inlet temperature reaches 145F to activate RWCU F/D inlet high temperature isolation alarm. Monitor RRP bearing temperature on Monitored Parameters. After RWCU isolates, if required to prevent RRP bearing temperatures exceeding 195F, Insert KEY 4. Adjust the severity of malfunction cmfAV04_TV11028 in 1% increments as necessary to slowly raise bearing temperatures toward the 195F limit without going over. {Key[4]} IMF cmfAV04_TV11028 d:15 r:30 f:S Ensure Event Trigger ETLOC28-NRC01-D fires when ESW is aligned to the RBCCW HX to complete the in-field valve alignments. PCOM Role Play D Reports Reactor power, pressure, and As NPO dispatched to RBCCW, wait 2 minutes water level The RBCCW HX TCV is PCOP almost full closed. D Performs AR-123-EOS and checks Role Play RBCCW HX DSCH temp and As NPO directed to open the controller RBCCW HX TCV bypass, D Dispatches NPO to RBCCW 110062, wait 1 minutes The RBCCW bypass valve, pump/heat exchanger area 110062, would not move. I D Performs ON-RBCCW-101 to verify do not hear flow noise RRP temperatures, TCV-11028 through the valve. operability, Bypass Valve 110062 Role Play operability, and swap RBCCW HX to As NPO directed to support ESW supply IAW OP-111-001 aligning 'A' ESW to 'A' D Aligns ESW to RBCCW HX 'A' IAW RBCCW HX, when asked to report local valve position OP-111-001 by starting ESW in one IAW OP-114-001 Step loop and depressing the RBCCW HX A 5.13.9b, report HV-11024A 1 and HV- SW/ESW SUP HA 11024 pushbutton 11024A2 are open, HV-11024A3 is closed. Role Play As NPO directed to RWCU filters, wait 2 minutes The RWCU filters are in hold LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 27

LOC28-NRC-01 Event 5 - RBCCW TCV failure Instructor Activities Operator Activities Notes us Role Play D Directs entry into ON-RBCCW-101 As NPO directed to close 11046 IAW step 5.13.9c, wait. D Contacts WWM for assistance with the 1 minute RBCCWTCV 110046 is closed D Directs aligning ESW to the RBCCW Role Play HX IAW OP-111-001, Service Water As WWM contacted for System assistance with RBCCW HX D Declares ESW loop to be aligned TCV, Wait 5 minutes l&C believes the positioner inoperable IAW OP-111-001 and is getting a close signal Enters TS 3.7.2 Condition C for 1 ESW from the controller. subsystem inoperable for reasons Additional investigation is required. other than Condition B Instructor Note

The RBCCW high temperature alarm is received -3 minutes after the TCV malfunction is inserted.
A total loss of RBCCW occurs in the next event.
Once ESW has been aligned to RBCCW HX 'A', proceed to Event 5 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016
28

LOC28-NRC-01 Event 6 - Complete loss of RBCCW/ SCRAM Instructor Activities Operator Activities Notes Booth Operator IAW Event 4 Note, Depress KEY 5 to insert a 20% rupture on the common discharge header of RBCCW {Key(5]} IMF mfRW114001 f:20 RBCCW discharge header rupture Perform first role play after inserting Key 5 Ensure Event Trigger ETLOC28-NRC01-E fires when the mode switch is placed in SHUTDOWN to activate Event Trigger ETLOC28-NRC01-J PCOM Role Play D If directed, trips 'A' RRP by depressing As NPO at RBCCW HX, when Key 5 is inserted, MG SET A ORV MTR BKR HS-contact the control room 14001 A STOP PB There is a rupture on the D Inserts a manual scram by placing the common discharge header of RBCCW. It is too large Mode Switch to Shutdown to quantify. D Identifies more than 1 control rod > position 00 Role Play As WWM contacted for D Reports A TWS assistance with RBCCW D Arms and Depresses the manual rupture, acknowledge Scram Pushbuttons request. D Performs Scram Report PCOP Role Play D Performs AR-201-F03 for 'A' RRP by As NPO requested to isolate monitoring motor bearing and seal the rupture, report The rupture cannot be cavity temperatures and trips RRP isolated. when seal cavity exceeds 195F D Initiates ARI by arming and depressing ARI pushbuttons and collars during the ATWS us D Before RRP 'A' temperatures exceed 195F, either Trips the 'A' RRP and scrams the reactor on OPRMs or Manually scrams the reactor and trips the 'A' RRP D IAW ON-RBCCW-101, performs a manual scram of the Unit. D Enters E0-000-102 and transitions to E0-000-113 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 29

LOC28-NRC-01 Event 6 - Complete loss of RBCCW/ SCRAM Instructor Activities Operator Activities Notes Instructor Note If the reactor is not scrammed before the recirc pump is tripped, Region 1 of the power/flow map will be entered and the reactor will automatically scram on OPRMs. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 30

LOC28-NRC-01 Event 7, 8 & 9- Hydraulic-block ATWS Instructor Activities Operator Activities Notes Booth Operator Ensure Event Trigger ETLOC28-NRC01-F(G) fires when the first SLC pump is started, to trip the running pump due to a motor fault after a time delay. Ensure Event Trigger ETLOC28-NRC01-H fires when the CRD PCV, PV-146-F003 is opened to trip the breaker. When directed, Insert KEY 6 to bypass CRD pump suction filter. Monitor sim RF count and report when complete. {Key[6]} IRF rfRD155028 d:120 f:100 Byp CRD pump suet filter When directed, Insert KEY 7 to close CRD charging water isolation valve 146-F034. Monitor sim RF count and report when complete {Key[7]} IRF rfRD 155017 d:120 f:O Close CRD chrg wtr isol F034 Ensure Event Trigger ETLOC28-NRC01-I fires when RPV level falls below -50" to fail Wide range level transmitter 14201A I* I Critical Task Inject SLC I Critical Task

Role Play Lowers RPV level to <-60" and maintains until E0-000-113 directs otherwise As NPO dispatched to CRD PCOM D If requested, reports reactor power >

5% PCV breaker 18227-024, wait 2 minutes D Performs actions IAW ON-SCRAM-18227 breaker 24 is tripped 101, Inserts IRMs and SRMS on magnetics D Trips both RRPs Role Play D Verifies HPCI is overridden If directed to open CRD PCV D Takes manual control of RFPs and bypass valve 146-F004, wait valves, as required, to stop and 2 minutes CRD PCV bypass valve prevent injection until water level 146-F004 is stuck closed lowers to -60" and then starts injecting Role Play to control level in band As WWM contacted for D Ensures only 2 Condensate pumps are assistance, acknowledge and running take no action LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 31

LOC28-NRC-01 E~ent 7, 8 & 9- Hydraulic~block ATWS Instructor Activities Operator Activities Notes PCOM D Injects SBLC IAW OP-153-001 by placing HS-14804 to 'A' or 'B' and then to the other pump when the first fails D Identifies Wide Range Level 'A' instrument channel failure. Maintains with 'B' Level indicator D Uses FW to maintain RPV water level within ATWS level band, initially -60" to

                           -110" PCOP D Ensures HV-144-F004 RWCU Inlet OB lso Closes D Inhibits ADS IAW OP-183-001 D If directed, Overrides RCIC by manually lowering flow until -2200 RPM D Bypasses MSIV and CIG interlocks IAW OP-184-001 by taking the 5 switches to BYPASS on 1C645 and 1C644 D Maximizes CRD by starting the standby pump, fully open CRD flow controller in MANUAL, fully open Drive water pressure valve us D Enters E0-000-113 D Directs PCOP to inhibit ADS D Directs PCOM to perform the A TWS HC D Gives PCOM a RPV water level band of -60" to -11 O" LOC28-NRC-01 Rev 1                     Examination Material                 04/14/2016

32

LOC28-NRC-01 Event 7, 8 & 9- Hydraulic-block ATWS Instructor Activities Operator Activities Notes us D Directs PCOP to bypass MSIV and CIG interlocks D Directs PCOP to maximize CRD to drift control rods D Directs PCOM to maintain reactor pressure 800-1050 psig using the main turbine D Contacts WWM for assistance with SBLC Instructor Note ES-158-002 actions are in Event 7A LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 33

LOC28-NRC-01 Event 7A - Control Rod Insertion Instructor Activities Operator Activities Notes Booth Op~rator When ES-158-002 is requested, Insert KEY 8. Monitor sim SCN count and when complete, perform the first role play and Key 9. {Key[8)} IRF rfDC102129 f:OPEN d:120 ES-158-002 ARI with 2 min TD {Key[8]} IRF rfDC102103 f:OPEN d:120 ES-158-002 ARI with 2 min TD When moving on to Div 1 RPS, Insert KEY 9. Monitor sim RF count and perform second role play when complete. {Key[9]} IRF rfRP158039J:BYPASS d:120 ES-158-002Div1 RPS {Key[9]} IRF rfRP158040 f:B'(PASS d:120 If requested to bypass DIV 2 RPS b.ecause the scram cannot be reset, Insert KEY 10. Monitor sim RF count and when complete perform fourth role-play. {Key(10]} IRF rfRP158041 f:BYPASS d:120 ES-158-002 Div 2 RPS {Key[10]} IRF rfRP158042 f:BYPASS d:120 IF requested, Insert KEY 11 to reopen CRD charging water isolation valve 146-F034. Monitor sim RF count and report when complete. {Key[11]} IRF rfRD155017 d:120 f:100 Re-open CRD chrg wtr isol F034 If directed to X-tie CIG and I/A, Wait 2 minutes, Insert KEY 12 to open 126172 and report when complete {Key[12]} IRF rfPC125001 f:OPEN X-Tie CIG and I/A Critical Task

Role Play Insert Control Rods IAW E0-000-113 As FUS performing ES-158-PCOM D Performs hard card for driving control rods 002 and ARI is bypassed ARI has been disabled. D Dispatch NPO to close charging water Proceeding to RPS Div 1. isolation valve 146F034 to attempt to Role Play restore drive water pressure As FUS performing ES-158- D Opens 146F034 when rods will not 002 and Div 1 RPS is insert bypassed RPS Div 1 has been D Resets Scram when directed bypassed, the scram can D Resets rod drift alarm by depressing be reset at this time. Let ROD DRIFT RESET pushbutton me know if the scram cannot be reset. D Reports when SDV hi-hi level alarm AR-103( 4 )-F02 clears LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 34

LOC28-NRC-01 Event 7A - Control Rod Insertion Instructor Activities Operator Activities Notes PCOM Role Play D When directed, inserts a manual scram As WWM contacted for assistance, acknowledge D Observes control rod motion by AR-request 104-H05, OD?, and 4-rod display D Resets the scram when directed a Role Play second time As FUS performing ES-158- PCOP 002 and Div 2 RPS is D Directs NPO to re-open charging water bypassed RPS Div 2 has been isolation valve 146F034 when scram is bypassed, the scram may reset be reset at this time, ES- us 158-002 section 5.3 is complete D Directs PCO to manually drive control rods D Directs FUS to perform ES-158-002 to defeat ARI and bypass RPS trips D Directs PCO to ensure charging water isolation valve 146F034 is open when the scram is reset D Directs PCOM to insert a manual scram when the SDV is drained D Directs the PCOM to reset the scram after the first attempt fails to fully insert all the control rods Critical Parameter The US should give a Critical Parameter to the PCOM to monitor SDV hi-hi level alarm AR-103(4)-F02 and inform the US when the alarm clears. Instructor Note

This scenario will terminate prior to all the control rods being inserted. The scenario

**          should not be terminated until the scram has been reset twice .

The charging water isolation valve 146F034 must be open to be able to have an effective scram. If the student has closed it and does not reopen the valve, they may not be able to clear the alarms. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

35

LOC28-NRC-01 Event 10 - RFP Trip Instructor Activities Operator Activities Notes Booth Operator Ensure Event Trigger ETLOC28-NRC01-J fires when the scram is reset. Trips the 'A' RFP after a time delay. PCOM Role Play D Observes and reports AR-101-A10 for As NPO dispatched to 'A' RFP, wait 2 minutes 'A' RFP trip

'A' RFP is coasting down. I     D Places the standby RFP in service by don't see any indication of       opening the HV-10603C valve, why it tripped.

Manually raising speed on the 'C' RFP Role Play until level is steady, and placing 'C' As WWM contacted for RFP and valves in automatic assistance, acknowledge PCOP request D If directed, uses RCIC to restore level until a RFP is restored by raising speed on the speed controller until the desired injection rate is established us D Directs PCO to place standby RFP in-service IAW OP-145-005 D Directs PCO to maintain RPV water level -60" to -110" using RCIC until Feedwater is restored D May direct using RCIC as the sole injection source if the plant can support D May direct RHR placed in Suppression Pool Cooling Instructor Activity - Termination

 -~     The scenario may be terminated when RPV water level is stable in the ATWS band, the 'A' RFP has tripped, and the Scram has been reset twice OR at the lead evaluator's discretion.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

36

UNIT SUPERVISOR TURNOVER SHEET UNIT 1 t"o-/dd/yy Date SHIFT 1900 to 0700 SHIFT 0700 to 1900 Start End Start End MODE MODE POWER LEVEL

                 - - - - -     %                   POWER LEVEL
                                                                         -------           %

GENERATOR OUTPUT 1270 MWe GENERATOR OUTPUT MWe CASK STORAGE GATE INSTALLED: YES/NO CASK STORAGE GATE INSTALLED: YES/NO REMARKS:

1) -95% power for control rod pattern adjustment, 500 days on-line

2) HPCI in day 2 of 4-day system outage window for steam-side maintenance

3) LCO 3.5.1 entered for HPCI outage

4) Diesel Generator E substituted for Diesel Generator A for a SOW

5) RFP lube oil conditioner was swapped from RFP A reservoir to B reservoir last shift

6) Test 'A' RFP main lube oil pump 'B' and swap to main lube oil pump 'B' for PMT.

Emergency pump is not required to be tested.

7) Perform control rod pattern adjustment per Reactivity Manipulation Package. Contact RxEng when complete for evaluation.

8) 9) 10 11) 12 13 14) 15) COMMON:

1) Unit 2 at rated power

2) Severe thunderstorm watch is in effect for Luzerne County for the next 12 hours 3) 4)

5 6) 7) 8 9) FORM OP-AD-003-7, DUPLEX Page 1 of 2 (Electronic Form) Examination Material NRC SCN 1

OFFGOING UNIT SUPERVISOR CHECKLIST: NRC CODE PRIOR TO 0800 FOXTROT DELTA BRAVO OSCAR NRC CODE AFTER 0800 FOXTROT UNIFORM HOTEL ROMEO 1900- 0700-0700 1900

1. Evolutions in progress and items to be completed during next shift, as noted in remarks, have been discussed with oncoming Unit Supervisor (including special evolutions, i.e. SICT/E, OPDRVs, etc.).

2. Problems encountered during past shift and abnormal plant conditions, as noted in remarks, have been discussed with oncoming Unit Supervisor.

3. Information in SOMS Log is complete and discussed with oncoming Unit Supervisor.

4. As applicable, turnover plastic Security Badge cover and CRS Monitor function to oncoming Unit Supervisor.

Offgoing Unit Supervisor ONCOMING UNIT SUPERVISOR CHECKLIST: 0700 1900

  -     -

1. LCOfTRO Log reviewed.

) 2. SOMS Log reviewed for entries made in past 24 hours.

3. Report any changes to license or medical status PER NDAP-QA-0723.

1900 - 0700 Oncoming Qualified Unit Supervisor POST RELIEF 0700 1900

1. Walk down Control Room panels with Unit Responsible PCO.

2. CRC Book reviewed and Reactivity Brief performed with PCO.

3. Completed System Status Operable audit for open PMT this shift.

4. From the OPS Web page, Review OPS Aggregate Index for Challenges, Work Arounds, and Deficiencies Reports for impact on scheduled work activities and compensatory actions. (2o)

Oncoming Unit Supervisor FORM OP-AD-003-7, DUPLEX Page 2 of 2 (Electronic Form) Examination Material NRC SCN 1

SUSQUEHANNA NUCLEAR, LLC OPERATIONS TRAINING PROGRAM SCENARIO EXAMINATION GUIDE REACTOR SHUTDOWN/ FW HEATER TUBE LEAK/ ESS BUS LOCKOUT/ ATWS/ FUEL FAILURE/ RCIC STEAM LEAK/ EMERGENCY DEPRESSURIZATION SCN# LOC28-NRC03 Revision 1 4/21/2016 Examination Material

LOC28-NRC03 Lesson Information Title Reactor Shutdown/ FW Heater Tube Leak/ ESS Bus Lockout/ A TWS/ Fuel Failure/ RCIC Steam Leak/ Emergency Depressurization Vision ID Accredited *YES D NO Training ID Revision j 1 Date j 4/21/2016 Prerequisites Teaching Time 75 minutes Approval CBT Approval 1 N/A Date N/A Preparer Date Review (lnstructor/SME) Date Nuclear Engineering 1 N/A Date N/A Training Supervision Date Line Management Date 1 If required, otherwise N/A This simulator scenario has been reviewed and satisfies management expectations for inclusion of OE, Department Fundamentals and HuP, error-reduction techniques and safety standards. Specific applications and/or opportunities for reinforcement of management expectations are noted in the scenario guide or Attachment(s) where applicable. Copyrighted by Nuclear Training Group, SUSQUEHANNA NUCLEAR, LLC, 2016. All rights reserved, no part of this training material may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, recording or otherwise, without the prior permission of the Nuclear Training Group. LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 2

LOC28-NRC03 Revision History Revision Date Comments 0 06/23/2014 New Scenario Placed in new template. Changed the setup conditions. Changed Event 8 to be a HPCI issue. Changed Event 9 to be triggered off of max safe 1 04/21/2016 Temperature. Removed an unanticipated start of an EOG. Changed the leak sizes to allow for operator actions. Adjusted the sim files to remove the CRD rad release. Swapped event 1 and 2. LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 3

LOC28-NRC03 Table of Contents Scenario Overview................................................................................................................................5 Objectives .............................................................................................................................................6 A. Terminal Objective ................................................................................................................6

8. Generic Performance Objectives ...........................................................................................6 C. Simulator Performance Objectives ........................................................................................ 7 D. Task List. ...............................................................................................................................9 Scenario Attributes .............................................................................................................................11 A. Critical Tasks ....................................................................................................................... 11 B. Scenario Malfunctions ......................................................................................................... 12 C. Abnormal Events and Major Transients ............................................................................... 12 D. EOP and EOP Contingencies Used .................................................................................... 13 E. Technical Specifications ...................................................................................................... 13 References ..........................................................................................................................................14 Setup Instructions ..............................................................................................................................15 A. Required Materials .............................................................................................................. 15

8. Simulator Initialization ......................................................................................................... 15 C. Simulator Preparation .......................................................................................................... 16 D. Document Training and Performance Feedback ................................................................. 16 E. Scenario Execution ............................................................................................................. 16 F. Simulator Files .................................................................................................................... 16 Event 1 - Test BPV #3 ........................................................................................................................19 Event 2- Insert Control Rods ............................................................................................................20 Event 3- FW 2C tube leak .................................................................................................................22 Event 4- ESS bus 1C lockout ...........................................................................................................24 Event 5- Electrical ATWS ..................................................................................................................25 Event 6 - RCIC injection fails ............................................................................................................25 Event 7 - Fuel failure with high MSL rads ........................................................................................27 Event 8 - HPCI steam leak .................................................................................................................28 Event 9- ED on 2 max safe temp ......................................................................................................30 LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 4

LOC28-NRC03 Scenario Overview The scenario begins with Unit 1 shutting down for an unplanned maintenance outage to identify and repair a small RCS leak in the Drywell, 300 days into the operating cycle. Unidentified OW leakage is steady at approximately 0.5 gpm. Reactor power is 33 percent with RFP A in-service in Flow Control Mode. HPCI is in day 2 of a 4-day unplanned maintenance window. The RFP lube oil conditioner is being placed on the RFP B reservoir after being removed from the RFP A reservoir last shift in preparation for a RFP A main lube oil pump test. Control rods 42-15 and 46-19 were declared slow during the last scram time test. The first task for the crew is to cycle Main Turbine Bypass valve #3 per S0-182-001 to demonstrate functionality of the valve prior to scram. The crew will then insert control rods to lower power to approximately 30 percent. When the reactivity maneuver has been completed, a tube leak will develop on the 2C Feedwater heater. The leak will initially be within the capability of the dump valve, but will continue to degrade until a heater isolation on high-high level occurs. The crew will respond to the isolation by isolating the extraction steam supplies to the 3C, 4C and SC heaters and other inputs in accordance with off-normal procedures, and verify the high FW heater levels clear within 15 minutes or trip the main turbine. Once the crew has completed off-normal procedures for the Feedwater heater isolation, Diesel Generator C will spuriously start. ESW Pump C will fail to automatically start and must be manually started to provide cooling to the DG. When the breaker for ESW Pump C closes, a fault in the breaker will result in an ESS Bus 1C lockout. The crew will align Instrument Air to Containment Instrument Gas to maintain AOVs in the Drywell functional. The leak in the Drywell will degrade coincident with the bus lockout, resulting in a more rapid rise in Drywell temperature and pressure. The crew should complete activities associated with the loss of ESS Bus 1C and insert a manual scram before an automatic scram on high Drywell pressure is received. When the reactor is scrammed RPS will fail to de-energize, resulting in an electrical ATWS. When ARI is initiated, control rods will slowly drift in when ARI is initiated, resulting in significant fuel cladding failure. The Scram Discharge Volume drains will be failed open, allowing the spread of highly radioactive coolant into the CRD HCU area. This will result in radiation levels rapidly exceeding the E0-104 maximum safe values. The magnitude of the fuel failure will also result in MSL high radiation signals that will require the MSIVs to be closed. RPV level and pressure control will be with RCIC and SRVs. The RCIC injection valve will fail to automatically open and must be manually opened. Reactor pressure may be lowered to 500-600 psig to allow Condensate to be used for reactor level control. Once RCIC has been initiated and the CRD HCU area radiation levels have exceeded the max safe value a steam leak will develop in the RCIC room. The isolation logic will fail and both isolation valves will fail to close automatically or manually. RCIC room radiation levels will quickly rise to maximum safe levels. With radiation levels in two areas above max safe, and an unisolable primary system leak outside the primary containment, E0-104 requires Emergency Depressurization. As reactor pressure lowers, the RCIC outboard isolation valve will stroke fully closed. This scenario may be terminated when RPV water level has been stabilized and actions are being taken to place RHR in Suppression Pool cooling OR at the direction of the Chief Examiner. LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 5

LOC28-NRC03 Objectives Mastery of the training content shall be demonstrated by individual and/or crew performance evaluation as specified in this training material and the applicable training program description, in accordance with training procedures. A. Terminal Objective Perform all system operations required to maintain the plant operating safely, or place the plant in a safe condition if a plant shutdown is required During the specified mode of plant I system operation Without error and in accordance with site procedures and management expectations B. Generic Performance Objectives

1. For all activities, exhibit use of the Human Performance Tools, demonstrating the ability to:

Use HU tools to effectively control the plant during normal, abnormal, and emergency conditions Use of HU tools will be observable per the standards in HU-AD-003 (SRO) Take every opportunity to coach the team when HU standards are not being met and provide feedback to the team when the HU standards are being met

2. For all activities, exhibit proper use of procedures by:

Applying the correct procedure to operate equipment and respond to abnormalities Ensuring procedures are detailed enough to allow precise control of plant evolutions. Demonstrating the ability to: Apply the correct procedure to the situation Use place keeping for accurate implementation Identify any and all areas for procedure improvement Take ownership of and complete the improvement, whenever an area for procedure improvement is identified

3. Base actions and decisions with a bias toward conservative, safe operation of the plant, demonstrating the ability to:

Assure all plant evolutions and work are assessed for Radiological Safety, Industrial Safety, Nuclear Safety, Environmental Safety, or Corporate Safety Once a risk is determined, take appropriate actions to mitigate or minimize risk Request assistance for any activity which requires additional planning, special precautions, and management oversight to adequately manage the risks (SRO) Champion activities that are biased conservatively LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 6

LOC28-NRC03

4. Demonstrate complete understanding of plant design and system interrelationships, demonstrating the ability to:

Work effectively as a team to interpret plant indications and determine an effective response Understand the bases for, and the plant response to, actions being taken

5. Maintain continuous awareness of critical parameters, demonstrating the ability to:

Validate parameters by observing multiple independent indications Relay parameter values with value, units, and trend; and include action being taken for an abnormal value or trend Notify supervision of any change to critical parameters (SRO) Assure critical parameters for operational conditions are understood by the team

6. Operate plant systems and equipment within design and operational limits, maintaining relevant parameters within assigned operating bands, demonstrating the ability to:

Anticipate the impact of component operation prior to its operation, and then verify that the expected effects occur during and following the operation Take manual actions (in accordance with procedure direction) when automatic actions do not occur Take prompt action to adjust system operating controls before assigned operating bands are exceeded Make reactivity and mode changes as directed by detailed operating procedures and approved reactivity plans C. Simulator Performance Objectives

1. Plant Shutdown Activities During plant operation in a shutdown condition Perform the activities associated with plant pre-start or shutdown procedures to ensure safe operation of station equipment including the operation of the controls associated with plant equipment that could affect reactivity

2. Operational Actions and Annunciator Response Correctly identify plant annunciators and indications and perform appropriate remedial actions

3. System Operation, Controls and Instrumentation Accurately identify plant instrumentation and correctly interpret instrument readings to respond to normal, abnormal, and emergency conditions LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 7

LOC28-NRC03

4. Facility Design and Operating Characteristics Demonstrate the following:

An understanding of facility operating characteristics
The ability to safely control the operating characteristics of the facility within prescribed operating boundaries

5. System Loss and Component Level Malfunctions Perform system control manipulations to obtain desired operating results and demonstrate the ability to correctly respond to malfunction/loss of components and the impact of the malfunction/loss on interfacing plant systems

6. Heat Removal Component Operation Safely operate the plant's heat removal components and demonstrate knowledge of the relationship between the heat removal systems and the operation of facility to prevent exceeding System, Structure, or Component (SSC) design limits which include:

Primary coolant systems
Emergency coolant systems
Decay heat removal systems

7. Auxiliary and Emergency Component Operations Safely operate the plant's auxiliary and emergency components I systems to include the controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment to control release of radioactivity within regulatory limits

8. Radiation Monitoring Component Operations Demonstrate or describe the use and function of the facility's radiation monitoring systems to maintain radiation levels within regulatory limits

9. Radiation Hazards Demonstrate knowledge of significant radiation hazards and ability to respond to the hazards to prevent exceeding regulatory limits

10. Reactivity Management Demonstrate knowledge of how reactivity is affected by plant operation and ability to respond to the change in reactivity to protect the safety and integrity of the reactor core

11. Technical Specifications During plant operation with the plant or system in a condition requiring Technical Specification action Identify the deviation and any required actions I notifications LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 8

LOC28-NRC03

12. Emergency Plan (if required)

During plant operation in an emergency condition Recognize conditions covered by the Emergency Plan (SRO) Demonstrate the ability to:

Identify and Implement the appropriate Emergency Action Level
Use the applicable bases to support an Event Classification on the specified Emergency Action Level

13. Control Room Duties Demonstrate the knowledge and ability to assume the appropriate responsibilities (for the assigned position) associated with the safe operation of the facility

14. Control Room Team Work Demonstrate the ability to function within the Control Room team to comply with station procedures and limits of facility license and respond to plant events using appropriate human performance tools to support safe operation of the facility D. Task List Task Title ID Licensed Operator Apply Technical Specification (TS) And Technical Requirements Manual (TRM) Requirements S-C00-00-1185 Implement Reactivity Manipulations Standards and Communication Requirements S-C00-00-2784 Implement Appropriate Portions Of Operations Standards For System and Equipment Operation S-C00-00-1081 Implement Operations Standards For Error And Event Prevention S-ADM-00-1091 Implement Standards for Shift Operations S-C00-00-2780 Implement Appropriate Portions of Conduct of Operations S-C00-00-1015 Implement Appropriate Portions of Secondary Containment Integrity Control S-C00-00-1020 Implement EOP Cautions S-C00-00-2566 Implement Operations Directives S-C00-00-3130 Ensure Plant Operates IAW the Operating License, Technical Specifications (TS), and Technical S-C00-00-1183 Requirements Manual (TRM)

Implement HUMAN PERFORMANCE (HuP) - Standards for Error and Event Prevention S-EPP-00-3068 Reactor Operator Insert a Control Rod One Notch S-201002-01-003 Perform the Monthly Turbine Bypass Valve Cycling S-241001-01-021 Manually Place Feedwater in Startup Level Control Following Reactor Scram S-259003-01-018 Confirm Automatic Initiation of RCIC S-217000-01-001 Perform the Actions of Fire Alarm Response S-286005-01-008 LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 9

LOC28-NRC03 Task Title ID Perform a Manual Operation of the Safety/Relief Valves S-218000-01-003 Initiate Suppression Chamber Sprays S-203000-01-088 Initiate Drywell Sprays S-203000-01-089 Operate the RHR System in the Suppression Pool Cooling Mode S-203000-01-093 Direct the Actions for Loss of Feedwater Heater String S-260000-01-007 Direct Actions of Loss of Emergency Service Water (ESW) S-276001-01-012 Direct the actions for a loss of a 4 KV ESS Bus S-262004-01-007 Direct the Actions for a Sustained Loss of 4KV ESS Bus 1C (2C) S-262001-01-025 Direct the Actions for a Loss of Containment Instrument Gas S-223002-01-005 Direct Actions for Excess Drywell Leakage S-00-005-01-001 Enter EOP RPV Control S-EOPRR-01-006 Direct the Actions for Increasing Offgas/MSL Rad Levels S-272000-01-037 Direct Actions for a +13 Inch Containment Isolation Actuation S-223002-01-006 Scram the Reactor S-EOPRR-01-005 Senior Reactor Operator Implement Appropriate Portions Of Plant Shutdown To Minimum Power 000000-02-1138 Direct Entry into Loss of Feedwater Heater String S-260000-02-002 Direct Entry into Loss of Emergency Service Water (ESW) S-276001-02-001 Direct Entry into Loss of 4KV ESS Bus 1(2)A(B)(C)(D) S-262001-02-010 Direct Entry into Loss of Containment Instrument Gas S-223002-02-001 Direct or Concur with entry into Excess Drywell Leakage S-00-005-02-001 Direct entry into ON-SCRAM-101 (201) Reactor Scram 000000-02-1147 Direct and Coordinate Implementation of RPV Control 000000-02-1125 Direct Entry into Increasing Offgas/MSL Rad Levels S-272000-02-006 Direct and Coordinate Implementation of Secondary Containment Control 000000-02-1127 Direct Entry into Containment Isolation S-223002-02-002 Direct and Coordinate Implementation of Emergency Depressurization 000000-02-1129 LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 10

LOC28-NRC03 Scenario Attributes A. Critical Tasks

1. Manually initiate ARI Safety Significance Control rod insertion initiates power reduction immediately.

Consequences for Failure Failure to insert control rods allows power to remain elevated with to Perform the Task resultant power oscillations and potential core damage. Indications/ Cues for Event Exceeding a RPS scram setting with NO reactor scram signal, or Requiring Critical Task RPS/ARI fail to fully insert all control rods. Arm and depress Division 1 and 2 ARI initiation pushbuttons, HS-Performance Criteria 147103A(B)1. ARI Division 1 and 2 vent valves open, block valves close. Rod position Performance Feedback full-in indication when control rod insertion complete.

2. Emergency Depressurize the reactor when two Secondary Containment Areas exceed Max Safe Temperature levels High energy leak in the Secondary Containment Area impacts the integrity of Secondary Containment. Failure of the Secondary Safety Significance Containment directly relates to the 1OCFR50.67 design criteria of dose to the General Public.

Consequences for Failure Failure to take actions to mitigate the energy released to the secondary to Perform the Task containment directly affects the radiation dose to the General Public. Indications/ Cues for Event Increasing area temperatures and alarms for RB Areas indicating levels Requiring Critical Task at Max Safe values. Perform an Emergency Depressurization per E0-000-112 when two or Performance Criteria more RB areas exceed max safe temperature per E0-000-104. Open 6 ADS SRVs. Initiating an emergency depressurization causes Reactor pressure to lower which lowers the driving force of any primary system breach. Verify Performance Feedback ADS valves are open using light red light indication, acoustic monitoring and lowering Reactor pressure and rising reactor water level. LOC28-NRC03 Rev 1 Examination Material 4/21/2016

11

LOC28-NRC03 B. Scenario Malfunctions Event Malfunction Operator Action in Response 1 N/A Test Turbine Bypass Valve #3 (S0-182-001) 2 N/A Insert Control Rods (OP-156-001, OP-A0-338) 3 cmfHX02_ 1E102C FW heater 2C tube leak (AR-120-C10, 010), Isolate FW heater extraction steam (ON-147-002), TS MCPR limits not applicable (TS 3.2.2) 4 cmfEB01_ 1A203 ESS Bus 1C lockout, Orywell leak severity rises, reactor scram required (ON-104-203, TS 3.8.7) mfRR164010 5 mfRP158003 Electrical ATWS (E0-000-113) ARI inserts control rods 6 cmfMV06_HV149F013 RCIC injection valve fails to open on initiation (OP-150-001) 7 mfRR179003 Fuel failure with high MSL radiation, MSIV isolation required (AR-103-001, AR-104-001) 8 cmfMV01_HV155F002 HPCI steam isolation valves fail to automatically cmfMV07_HV155F003 f:90 close (AR-108-F04, F05), manual isolation successful after reactor pressure reduced 9 mfRC150004 Unisolable RCS leak into Secondary Containment, 2 areas above Max Safe Temp (E0-000-104) C. Abnormal Events and Major Transients Malfunction Description R Insert Control Rods (OP-156-001, OP-A0-338) N Test Turbine Bypass Valve #3 (S0-182-001) AE1 FW heater 2C tube leak (AR-120-C10, 010), AE2 ESS Bus 1C lockout AE3 Electrical ATWS (E0-000-113) Unisolable RCS leak into Secondary Containment, 2 areas above Max Safe Rad MT1 (E0-000-104) MAE1 Fuel failure with high MSL radiation, MSIV isolation required LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 12

LOC28-NRC03 Malfunction Description MAE2 RCIC injection valve fails to open on initiation MAE3 HPCI steam isolation valves fail to automatically close TS1 TS MCPR limits not applicable (TS 3.2.2) TS2 ESS Bus 1C lockout (TS 3.8. 7) D. EOP and EOP Contingencies Used EOPs EOP Contingencies IZI E0-000-102, RPV Control D E0-000-102, Alternate Level Control D E0-000-103, Primary Containment Control D E0-000-102, Steam Cooling IZI E0-000-104, Secondary Containment Control IZI E0-000-112, Emergency Depressurization D E0-000-105, Radioactivity Release Control IZI E0-000-113, Power/Level Control D E0-000-114, RPV Flooding E. Technical Specifications

1. TS 3.8.1 AC Sources operating

2. TS 3.7.6 Plant Systems Main Turbine Bypass System

3. TS 3.2.2 Minimum Critical Power Ratio

4. TR 3.2.1 Core Operating Limits Report (COLR)

LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 13

LOC28-NRC03 References

1. OP-AD-300 Administration of Operations

2. OP-AD-338 Reactivity Manipulation Standards and Communication Requirements

3. OP-054-001 Emergency Service Water

4. OP-156-001 Reactor Manual Control System

5. S0-182-001 Monthly Turbine Bypass Valve Testing

6. ON-SCRAM-101 Reactor Scram

7. AOP-104-101 Energizing Dead 4KV ESS Bus

8. ON-4KV-101 Loss of 4KV bus

9. ON-125-001 Loss of Containment Instrument Gas

10. ON-147-002 Anticipated Loss of FW HTR String

11. ON-179-001 Increasing Offgas MSL Rad Levels

12. E0-000-102 RPV Control

13. E0-000-103 Primary Containment Control

14. E0-000-104 Secondary Containment Control

15. E0-000-105 Radioactivity Release Control

16. E0-000-112 Emergency Rapid Depressurization

17. E0-000-113 Power/ Level Control

18. ES-158-001 De-energizing Scram Pilot Solenoids

19. EP-PS-100 Emergency Director Control Room Emergency Plan

20. EP-RM-004 EAL Classification Bases

21. AR-106-F03 Offgas Hi Hi Radiation

22. AR-108-E05 RCIC Leak Detection Hi Temp/ Hi Diff Temp

23. AR-110-A01 ADS Logic A Timer Initiated

24. AR-110-A02 ADS Logic C Timer Initiated

25. AR-110-A03 ADS Logic B Timer Initiated

26. AR-110-A04 ADS Logic D Timer Initiated

27. AR-120-D10 FW HTR C Dump Viv Open

28. TS 3.8.1 AC Sources operating

29. TS 3.7.6 Plant Systems Main Turbine Bypass System

30. TS 3.2.2 Minimum Critical Power Ratio

31. TR 3.2.1 Core Operating Limits Report (COLR) 32.

LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 14

LOC28-NRC03 Set.up Instructions A. Required Materials

1. US Turnover Sheet

a. Unit 1

1) Reactor Power -33%

2) 1 RFP in FCM

3) Shutdown to identify and repair small RCS leak in Drywell. Unidentified leak is 0.5 gpm for last 36 hours. ON-100-005 actions are complete. 12 hour leakrate calculations are being performed.

4) Insert Control Rods IAW given RMR

5) Perform test of Bypass Valve #3 IAW S0-182-001 for valve functional test

b. Common and Unit 2

1) Unit 2 at rated power.

2. Supporting Documents

a. S0-182-001

b. G0-100-012

c. RMR (2 copies)

8. Simulator Initialization

1. Reset to exam specific IC, otherwise setup as follows

a. Reset to IC-20

b. Place the simulator in RUN

c. Insert a LIM2

d. Disable IND RFP FLOW< 16.4% LIM2 runback IAW OP-164-001

e. Select FWLC to VENTURI

f. Insert rfFW145032 to CLOSE for HWC to 'C' RFP

g. Place 'C' RFP in STANDBY IAW OP-145-001

h. Remove 2 condensate pumps from service (prefer 'C' and 'D') when suction pressure is >600 psig

i. Shutdown HWC IAW OP-145-002

j. Ensure proper number for filter/demins are in-service IAW OP-139-001

k. Insert control rods to <60% rod-line I. Lower reactor power to 37-38% using recirc LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 15

LOC28-NRC03

m. Place 'B' RFP in STANDBY and Trip 'C' RFP

n. Reduce RRP speed to <30%

o. Verify Load Set is -1 OOMWe above generator load

p. Place the simulator in FREEZE

2. Run SCN file exam\LOC28-NRC-03

3. Place the simulator in RUN

4. Perform simulator activities

a. Place the blue reactivity in progress signs up.

5. Verify the simulator matches the following MF RF OR ET CONDITIONS 16:16 4:4 0:0 8 12

6. Ensure FW Control is selected to VENTURI

7. Reset ODAs and all Overhead, PICSY, HMI and RWM alarms

8. Ensure horns and annunciators are on

9. Ensure Overhead Lights Override is off C. Simulator Preparation

1. Ensure the EOL CRC Book is at the PCO Console D. Document Training and Performance Feedback

1. Record crew position assignments in G:\NTGOPS\LOR\REQUAL\lnfo Tracking\ (LOR)

2. Record crew position assignments per TQ-104 (ILO)

3. Complete an IER 11-3 Operator Fundamentals Simulator Observer Aid

4. Complete simulator setup checklists E. Scenario Execution

1. Identify performance improvement actions that may be addressed during the scenario

2. Provide turnover to the crew using the US Turnover sheet

3. Direct the crew to walk down the Control Room panels

4. Inform the Shift Manager that the crew has the shift F. Simulator Files LOC28-NRC-03 insmp tcvpbv3 changemp tcvpbv3 ,,,BYPASS VALVE POSITION 3 de Imp insmp fwlt10303cl

SCN rat_mp changemp fwlt10303cl ,,,FWH 2C LEVEL LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 16

LOC28-NRC03 insmp ycpxnbtOl changemp ycpxnbtOl ,,DEG F,TFW A ; HPCI isol valve auto logic fail IMF cmfMV06_HV155F002 insmp ycpxghfOl IMF cmfMV06_HV155F003 changemp ycpxghfOl ,,,GEN H2 SUPPLY FLOW aet ETLOC28-NRC03-A ; terminate LOCA severity on insmp ycpxghpOl scram changemp ycpxghpOl ,,,GEN H2 PRESSURE aet ETLOC28-NRC03-B ; Fuel failure and spurious RCIC insmp ecvp033035 init on rod drift changemp ecvp033035 ,,,HYDROGEN EXCESS FLOW A INLET ISO VLV aet ETLOC28-NRC03-C ; Delete MSIV rad malfunction on MSIV closure insmp rdpic121r013 changemp rdpic121r013 ,,psig,SCRAM AIR HDR PRESS aet ETLOC28-NRC03-D ; RCIC room steam leak insmp ycpxpar02 aet ETLOC28-NRC03-E; HPCI room steam leak changemp ycpxpar02 ,,MR/HR,RCIC RM ARM LO-RNG aet ETLOC28-NRC03-F; HPCI F002 valve breaker trips when insmp ycpxpar57 stroked changemp ycpxpar57 ,,MR/HR,RCIC RM ARM Hl-RNG aet ETLOC28-NRC03-G ; HPCI F003 valve binds when insmp ycpxmarOl stroked changemp ycpxmarOl ,,R/HR,CTMT HI-RANGE ARM aet ETLOC28-NRC03-H ; HPCI F003 valve closes on insmp aoURSG331N605A.CurrValue blowdown changemp aoURSG331N605A.CurrValue 0,350,DEG F,RCIC Equip Area Temp

                                                              ; 2C FWH tube leak insmp aoURSG331N604D.CurrValue                                 {Key[l]} IMF cmfHX02_1E102C r:300 i:5 f:15 changemp aoURSG331N604D.CurrValue 0,350,DEG F,HPCI Equip Area Temp                                                ; 2C FWH tube leak degrades

{Key[2]} IMF cmfHX02_1E102C r:60 f:20

0-G alarms suppressed SDR # ; 2C FWH dump/drain 3C drain IMF annAR106F15 f: ALARM_OFF {Key[3]} SCN exam\LOC28-NRC03-A IMF annAR131A04 f:ALARM_OFF

                                                              ; lC ESS Bus Lockout

small dw leak {Key[4]} IMF mfDS104001C IMF mfRR164010 f: .1 IMF cmfTROl_LT16102A ; Xtie I/A to CIG IMF cmfTROl_LT16102B {Key[S]} IRF rfPC125001 f:OPEN IMF annAR107A05 f:ALARM_OFF IMF annAR107B05 f:ALARM_OFF ; Local Evac Alarm

{Key[G]} SCN exam\LOCAL_EVAC_ALARM

FWH trouble alarms defeated IMF annAR120H10 f: ALARM_ON ; ADS Keys IMF annAR120H07 f:ALARM_ON {Key[7]} IOR diHS14113G2 d:60 f:OPEN IMF annAR120H04 f:ALARM_ON {Key[7]} IOR diHS14113J2 d:66 f:OPEN

{Key[7]} IOR diHS14113K2 d:72 f:OPEN

HVAC Div 1&2 alarms locked in {Key[7]} IOR diHS14113L2 d: 78 f:OPEN IMF annAR106A16 f:ALARM_ON {Key[7]} IOR diHS14113M2 d:84 f:OPEN IMF annAR106B16 f:ALARM_ON {Key[7]} IOR diHS14113N2 d:90 f:OPEN
Electrical ATWS IMF mfRP158003
ARI outlets partially blocked IRF rfRD155030 f: l
RCIC F013 valve auto-open failure IMF cmfMV06_HV149F013 LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 17

LOC28-NRC03 LOC28-NRC03-A ETLOC28-N RC03-B IOR diLIC10306CD_Q f:MANUAL rdpic121r013 < 42 IOR diLIC10306CB_Q f:OPEN SCN exam\LOC28-NRC03-B IOR diLIC10302CD_Q f:MANUAL IMF mfRC150006 IOR diLIC10302CA_Q f:OPEN IOR diLIC10407CD_Q f:MANUAL IOR diLIC10407CB_Q f:CLOSE ETLOC28-NRC03-C msvsphv14lf022a < .1 & msvsphv14lf022b < .1 & msvsphv14lf022c < .1 & msvsphv14lf022d < .1 LOC28-NRC03-B MMF mfRM179004A r:300 f:SO c:300 IMF mfRR179003 i:2 f:S r:600 MMF mfRM179004B r:300 f:SO c:300

IMF cmfTR02 RIT13705 r: 68 f:lOOO MMF mfRM179004C r:300 f:SO c:300
IMF cmfTR02_RIT13706 r: S9 f:lOOO MMF mfRM179004D r:300 f:SO c:300
IMF cmfTR02_RIT13750 d: 45 r:30:00 f:65
IMF cmfTR02_RIT13751 d: 40 r:30:00 f:66 IMF mfRM179004A r:300 f:SOOOO ETLOC28-N RC03-D IMF mfRM179004B r:300 f:SOOOO rcvsphv150f045 > 0.1 IMF mfRM179004C r:300 f:SOOOO IMF mfRC150004 r:120 f:20 IMF mfRM179004D r:300 f:SOOOO ETLOC28-NRC03-E Sound Local Evac Alarm ;HPCI steam leak hpvsphvlSSfOOl > 0.1

+1 IOR di20A02A02S001B f:OUT IMF mfHP152009 r:120 f:20 +1 IOR di20A02A02S002 f:WARBLE IMF mfHP152003 r:360 f:20 +l IOR di20A02A02S001A f:6 +l IOR di20A02A02S001B f:IN ETLOC28-N RC03-F +5 IOR di20A02A02S001B f:OUT ;HPCI l/B F002 breaker trip +l IOR di20A02A02S001A f:4 diHS15502.CurrValue =#OR.diHS15502.CLS +1 IOR di20A02A02S002 f:SIREN IMF cmfMVOl_HV155F002 +1 IOR di20A02A02S001B f:IN DOR di20A02A02S001A ETLOC28-N RC03-G DOR di20A02A02S001B ;HPCI O/B F003 Binds DOR di20A02A02S002 diHS15503.CurrValue = #OR.diHS15503.CLS IMF cmfMV07 _HV155F003 f:90 ETLOC28-NRC03-A pcpdwg > 1.8 I diHSC72AlSOl.CurrValue != ETLOC28-NRC03-H

OR.diHSC72AlSOl.RUN rrpdome < 200 MMF mfRR164010 f:O.O MMF cmfMV07 _HV155F003 f:O r:60 c:70 LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 18

LOC28-NRC03 Event 1 - Turbine Bypass Valve #3 Test Instructor Activities Operator Activities Notes Booth Operator No additional activities required. PCOM Role Play D Monitor diverse indications of reactor As GCC/TCC informed of turbine bypa~s test power IAW OP-AD-001 Grid conditions are stable D As required, performs peer checks thank you for the PCOP notification. Inform us when testing is complete. D When directed, performs BPV #3 testing Role Play D Selects position 3 on the BPV TEST If required to prompt the crew

SELECT to perform t.he BPV testing, contact the control room as D Depress AND Hold TEST BYPASS the Shift Manager VALVE pushbutton Have we sta.rted the bypass valve testing? D Observes proper light indications and BPV #3 opens fully D Releases TEST BYPASS VALVE pushbutton D Observes proper light indications and BPV #3 closes us D Performs update for performing S0-182-001, Monthly Turbine Bypass Valve Cycling for BPV #3 D Directs PCOP to perform S0-182-001 LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 19

LOC28-NRC03 Event 2 - Control Rod insertion to lower power Instructor Activities Operator Activities Notes Booth Operator No additional activities are required. PCOM Role Play D Inserts Control Rods IAWOP-156-001, As RE contacted for assistance OP-AD-338, and the RMR to lower Core thermal limits are power to -30% within our predictions. You D Uses two-handed operation to select may proceed with the power reduction. the correct control rod D Inserts the selected control rod by Role Play depressing and holding the Insert As Shift Manager contacted for approval pushbutton The reactivity manipulation D Depress the Rod Selct Clear may proceed /AW the RMR. pushbutton when rod movement is complete D Plots power change on Power/ Flow map D Monitors diverse indications of reactor power IAW OP-AD-001 PCOP D Peer Checks the reactivity maneuver D IAW OP-AD-300, nulls Manual and Automatic regulators using MAN VOLT REG ADJUST HC-10002 D Maintains Load Set -1 OOMWe above actual generator load us D Obtains permission from the SM prior to commencing reactivity manipulations D Informs TCC/GCC of load changes on Unit 1 D Conducts crew update prior to commencing rod insertion D Directs control rod insertion IAW OP-156-001, RMR, and G0-100-012 D Monitors control rod movement with independent RMR LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 20

LOC28-NRC03 Event 2 - Control Rod insertion to lower power Instructor Activities Operator Activities Notes LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 21

LOC28-NRC03 Event 3 - FW Heater 2C Tube Leak Instructor Activities Operator Activities Notes Booth Operator When the bypass valve test circuit has been turned off, Insert KEY ,1 to initiate a tube leak in FW heater 2C. The tube leak will take 2-3 minutes to result in a noticeable rise in FW heater level. {Key[1]} IMF cmfHX02_1E102C r:300 i:5 f:15 FWH 2C tube leak Once the crew has diagnosed the tube leak and initiated actions to isolate FW heater 2C, if desired, lnse.rt KEY 2 to raise the severity of the leak {Key[2]} IMF cmfHX02_1E102C r:60 f:20 FWH 2C tube leak degrades When directed, Insert KEY 3 to configure FW heater 2C and 3C drains and dumps IAW ON-147-002 Step 3.8 {Key[3]} SCN exam\LOC28-NRC03-A RFP seal water iso PCOM Role Play D Monitors neutron instrumentation for As NPO dispatched to FWH

'C' panel 1C103, wait2               indication of core instability minutes                           PCOP The 2C FW heater level            D Performs AR-120-D10, FW HTR String control and emergency dump valves are                      'C' Dump VLV Full Open responding. Heater level is       D Dispatches NPO to 1C103 to ensure continuing to rise.

FW Heater 3C to 2C lso VLV is 100% Role Play OPEN and if FW level control valve As WWM contacted for 100% open assistance with FW heater D Performs ON-147-002 to isolate

'C', wait 5 minutes Engineering recommends               extraction steam supplies to 3C, 4C, removing the 2C FW heater            and 5C and to isolated FW heater from service and isolating           string 'C' it.

D Dispatches NPO to perform ON-147-Role Play 002 step 3. 7 to configure FW heater As NPOto check FWH level vent and drain valves after the isolation, wait 1 minute D Dispatches NPO to perform ON-147-The 2C FW heater level is 002 step 3.8 to close the RFP Seal slowly lowering Water Bleed Off HV-10244C us D Enters ON-147-002 for Anticipated Loss/Loss of Feedwater Heater String D Enters TS 3.2.2 Instructor Cue

-4>>)     When the SSE and MSEP drain valves are closed, proceed to Event 4 LOC28-NRC03 Rev 1                                 Examination Material                                  4/21/2016. 22

LOC28-NRC03 Event 3 - FW Heater 2C Tube Leak Instructor Activities Operator Activities Notes LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 23

LOC28-NRC03 Event 4 - ESS. Bus 1C lockout/ Reactor Scram Instructor Activities Operator Activities Notes Booth Operatol' .. When the crew has completed the isolation of 2C FW heater, Insert KEY 4 to initiate a lockout of 1C ESS Bus {Key(4]} IMF mfDS104001C 1C ESS Bus Lockout When directed, Wait 2 minut~s. Insert KEY 5 to cross-tie Instrument Air to CIG and report when complete {Key[S]} IRF rfPC125001 f:OPEN X-tie I/A to CIG Ensure Event Trigger ETLOC28-NRC03-A fires when the mode switch is placed i.n SHUTDOWN or DW pressure reaches 1.72 psig to terminate the rise in DW leak severity. PCOM Role Play D When directed, inserts a manual scram As NPO dispatched to ESS Bus 1C, wait 2 minutes by placing the Mode Switch to The '1C' ESS bus has a SHUTDOWN differential trip lockout. D Identifies more than 1 control rod > Role Play position 00 As NPO directed to perform D Performs Scram report post start checks on the 'C' PCOP EOG, wait 2 minutes Post Start checks on the 'C' D IAW ON-104-203, directs NPO to diesel are SAT. crosstie I/A to CIG D Performs ON-4KV-101 D Informs US of rising OW pressure D Ensures cooling to the 'C' EOG us D Enters ON-4KV-101 D Enters ON-125-001 D Enters TS 3.8.7.A for a required AC distribution system inoperable D Contacts WWM for assistance with the 1C ESS Bus D Prior to 1. 72# in the OW, directs a manual SCRAM Critical Parameter The US should direct updates of Drywell Pressure and an action to scram the Unit prior to

1. 72#. Preffered update is every 0.2 psig and preffered scram is at 1.2 psig.

LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 24

LOC28-NRC03 Event 5, 6 - Electrical ATWS Instructor Activities Operator Activities Notes Bootll Operator Ensure Event Trigger ETLOC28-NRC03-B fires when scram air header pressure falls below 42 psig to initiate I* I a spurious RCIC initiation and fuel failure. Critical Task Manually initiate ARI PCOM I Role Play D Arm and Depress Manual Scram As NPO dispatched to vent the scram air header, wait 3 Pushbuttons on 1C651 minutes D Inserts IRMs and SRMs I am having issues with the D If directed, Lowers RRP speed to scram air header cap. I am going to get a pipe wrench. Minimum D If directed, trips RRPs one at a time Role Play D If directed, Injects SBLC with HS-As NPO sent to scram air 14804 header, 2 minutes after the above report D Maintains RPV water level within the I still can't get the cap off. I ATWS band am going to get maintenance support. D Reports Control Rods drifting and "All Rods in" when ARI completes Role Play PCOP As FUS contacted to D Initiates ARI by Arming and implement ES-158-001, acknowledge the request Depressing HS-147103A1 & 81 D If directed, inhibits ADS D If directed, maximizes CRD D If directed, Bypasses MSIV and CIG interlocks us D Enters E0-000-102, RPV control D Transitions to E0-000-113, Level/ Power Control D Transitions back to E0-000-102 when all rods are inserted D May direct PCOP to Inhibit ADS D May direct PCOM to perform the ATWS HC LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 25

LOC28-NRC03 Event 5, 6 - Electrical ATWS Instructor Activities Operator Activities Notes us D Directs PCOP to override HPCI D May Direct PCOM to stop and prevent injection with Feedwater and maintain Water level -60" to -11 O" D Directs PCOM to maintain RPV pressure 800 to 1050 psig with Bypass Valves D May direct PCOP to bypass MSIV and CIG interlocks D May direct PCOP to maximize CRD Instructor Note Actions for the fuel failure and high MSL radiation levels are in the next event. Actions for the A TWS in E0-000-113 are dependent upon when all the control rods are inserted with ARI. All of these steps start with 'If directed" or "May direct." LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 26

LOC28-NRC03 Event 7 - Fuel Failure/ MSIV closure Instructor Activities Operator Activities Notes Booth Operator Ensure Event Trigger ETLOC28-NRC03-C fires when all inboard MSIVs are closed to terminate the elevated radiation readings If directed to evacuate any portion of the power block, use KEY 6 to sound the local evacuation alarm. Perform OP:-009-004 attachment A for the announcement and order for the alarm. {Key[6]} SCN exam\LOCAL_EVAC_ALARM PCOM Role Play D Performs AR-106-F03, Offgas Hi Hi As WWM contacted for assistance with the fuel Radiation Alarm failure, wait 5 minutes. D Performs AR-103(104)-D01, Main The scram air header Steam Line Hi Hi Radiation vented very slowly. The vent ports are somehow PCOP restricted. The slow D Performs ON-179-001, Increasing control rod drifting caused Offgas/ MSL Rad Levels a number of fuel rods to fail. D Performs AR-SP-002 for X108_Z1 alarm, observes Fire Pumps Start Role Play D Dispatches NPO to investigate RB As NPO dispatched to investigate a fire alarm in the sump area Reactor Building sump room D When directed, closes all MSIVs and area, wait 2 minutes MSL drains Steam was coming from the Reactor Building us sumps. I had to leave the D Enters ON-179-001 for MSL/ Offgas Hi room due to dose rates in the area. Rad conditions D Directs Unit 2 to perform evacuations Role Play of Unit 1 and Unit 2 Turbine Building As Chemistry contacted for D Contacts WWM to assist with elevated sampling d.ue to the fuel failure, wait 5 minutes dose rates Dose rates by the sample D Contacts Chemistry to collect samples stations are preventing us due to the fuel failure from collecting samples. We are working with RP to D Contacts RP to support Chemistry with gain access. the samples D Directs closure of MSIVs and MSL drains when MSL Hi Hi Rad Alarm is received LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 27

LOC28-NRC03 Event 8 - Steam Leaks Instructor Activities Operator Activities Notes Booth Operator Ensure Event Trigger .ETLOC28-NRC03-D fires when the RCIC steam supply valve HV-150-F045 opens to cause a steam leak in the RCIC room. Ensure Event Trigger ETLOC28-NRC03-E fires when the HPCI steam supply valve HV-155-F001 opens to cause an unisolable steam leak in the HPCI room. This trigger may be forced if HPCI is not initiated for water level control. Ensure Event Trigger ETLOC28-NRC03-F fires when HPCI inboard isolation valve HV-155-F002 is stroked to trip its breaker 18237-082. Ensure Event Trigger ETLOC28-NRC03-G fires when HPCI outboa.rd isolation valve HV-155-F003 is stroked to bind the valve in place.

PCO Role Play D Performs AR-108-EOS, RCIC Leak As NPO dispatched to the RCIC room, wait 2 minutes Detection Hi Temp/Hi Diff Temp I can hear a steam leak in D Performs AR-114-EOS, HPCI Leak the RCIC room Detection Hi Temp/Hi Diff Temp Role Play D Performs AR-SP-002 for X108_Z3 As NPO dispatched to the alarm RCIC room after RCIC has D Dispatches NPO to RCIC room to been isolated, wait 2 minutes investigate leak unless already there then report D Dispatches NPO to HPCI room to I do not hear steam in the investigate leak RC/Croom D Isolates RCIC by closing the steam Role Play valves As NPO dispatched to the D Attempts to isolate HPIC by closing the HPCI room, wait 2 minutes steam isolation valves I can hear steam in the HPClroom D Dispatches NPO to HPCI IB valve breaker 18237-082 Role Play D Dispatches NPO to HPCI OB valve to As NPO dispatched to 18237-082, HPCI IB lso manually close HV-155-F003 valve breaker, wait 2 minutes D Starts an ESW pump in each loop 18237 breaker 82 is tripped on magnetics Role Play As NPO dispatched to HPCI OB isolation valve F003, wait 2 minutes HV-155-F003 HPCI OB valve is about 50% closed LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 28

LOC28-NRC03 Event 8 - Steam Leaks Instructor Activities Operator Activities Notes us Role Play D Enters E0-000-104, Secondary As NPO dispatched to manually close HPCI OB Containment Control valve HV-155~F003, wait 2 D Directs starting ESW minutes D Directs PCO to isolate RCIC The HPCI OB valve F003 will not move manually. D Directs PCO to isolate HPCI D Contacts WWM for assistance with Role Play isolating HPCI As WWM. contacted for assistance with the HPCI IB D Contacts WWM for assistance with valve F002, wait 5 minutes RCIC leak Maintenance believes there is a fault on the HPCI IB valve F002 actuator motor. A Drywell entry will be required to troubleshoot. Role Play As WWM contacted for assistance with the HPCI IB valve F003, acknowledge request. If contacted later, report Engineering and Maintenance are still discussing the issue. Critical Parameter The US should direct a PCO to monitor RCIC and HPCI room temperatures and Radiation levels. These are key to determining if an Emergency Depressurization is required. Instructor Note Event Trigger ETLOC28-NRC03-E will have to be forced if HPCI was not initiated for level control. This will be at the direction of the Chief Evaluator. LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 29

LOC28-NRC03 Event 9 - Emergency Depressurization Instructor Activities Operator Activities Notes Booth Operator Ensure Eve.nt Trigger ETLOC28.-NRC03-H fires when reactor pressure falls below 200 psig to allow the HPCI OB isolation valve F003 to close When directed; Insert KEY 7 to opeh ADS SRVs from the Upper Relay Room. Monitor 1C601 ADS SRV solenoid status and report when complete. {Key(7]} IOR diHS14113G2 d:60 f:OPEN {Key(7]}10RdiHS14113J2 d:66 f:OPEN {Key(7]} IOR diHS14113K2 d:72 f:OPEN {Key[7]} IOR diHS1.4113L2 d:78 f:OPEN {Key[7]} IOR diHS1411.3M2 d:84 f:OPEN {Key[7]} IOR diHS14113N2 d:90 f:OPEN Critical Task Emergency Depressurize the reactor when two Secondary Containment Areas exceed

Max Safe Temperature levels PCO D Prevents injection from RHR pumps not required for adequate core cooling D Prevents injection of Core Spray pumps not required for adequate core cooling D Opens all ADS valves by placing hand switches for the ADS SRVs to open D Restores and maintains RPV level using condensate as reactor pressure lowers D Places RHR is Suppression Pool Cooling IAW OP-149-004 D Places RHRSW in service IAW OP-149-004 LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 30

LOC28-NRC03 Event 9 - Emergency Depressurization Instructor Activities Operator Activities Notes us D Enters E0-000-112, Emergency De pressurization D Enters E0-000-105 for an unisolated primary leak into secondary containment and SGTS not running D Directs PCO to prevent injection from LPCI and Core Spray pumps not required for adequate core cooling D Directs PCO to open all ADS valves D Directs PCO to restore and maintain RPV level using Condensate D Directs PCO to place Suppression Pool Cooling in service Instructor Note E0-000-105 should be entered when the HPCI leak occurs and after the scram. Ventilation has been secured due to the power failure, SGTS is not running, and a primary leak is occuring. This is an unmonitored release. If the crew starts SBGT before the leak, then it will not need to be entered. After the ED, HPCI will isolate and terminate the requirement for entering E0-000-105. Instructor Activity - Termination This scenario may be terminated when RPV water level has been stabilized and actions are being taken to place RHR in Suppression Pool cooling OR at the direction of the Chief Examiner. LOC28-NRC03 Rev 1 Examination Material 4/21/2016. 31

UNIT SUPERVISOR TURNOVER SHEET UNIT 1 "to(dd(yy Date SHIFT 1900 to 0700 SHIFT 0700 to 1900 Start End Start End MODE MODE POWER LEVEL 33 % POWER LEVEL %

                 -------                                                -------

GENERATOR OUTPUT 351 MWe GENERATOR OUTPUT MWe CASK STORAGE GATE INSTALLED: YES/NO CASK STORAGE GATE INSTALLED: YES/NO REMARKS:

1) Reactor power approximately 33 percent, 1 RFP in FCM

2) Shutdown in progress to identify and repair small RCS leak in Drywell. Unidentified leak rate 0.5 gpm. ON-100-005 actions are complete. Leak rate is stable and 12-hour calculations are being performed. AR-106-A 16 & B 16 are locked in for this condition.

3) Perform test of Bypass Valve #3 per S0-182-001 for troubleshooting

4) Insert Control Rod IAW the RMR to 30% APRM power 5) 6)

7 8) 9) 10 11 12 13 14) 15) COMMON:

1) Unit 2 at rated power 2

3) 4) 5 6) 7) 8 9) FORM OP-AD-003-7, Rev. 23, DUPLEX Page 1 of 2 (Electronic Form) Examination Material NRC SCN 3

OFFGOING UNIT SUPERVISOR CHECKLIST: NRC CODE PRIOR TO 0800 FOXTROT DELTA BRAVO OSCAR NRC CODE AFTER 0800 FOXTROT UNIFORM HOTEL ROMEO 1900- 0700-0700 1900

1. Evolutions in progress and items to be completed during next shift, as noted in remarks, have been discussed with oncoming Unit Supervisor (including special evolutions, i.e. SICT/E, OPDRVs, etc.).

2. Problems encountered during past shift and abnormal plant conditions, as noted in remarks, have been discussed with oncoming Unit Supervisor.

3. Information in SOMS Log is complete and discussed with oncoming Unit Supervisor.

4. As applicable, turnover plastic Security Badge cover and CRS Monitor function to oncoming Unit Supervisor.

Offgoing Unit Supervisor ONCOMING UNIT SUPERVISOR CHECKLIST: 0700 1900

 -      -

1. LCO/TRO Log reviewed.

) 2. SOMS Log reviewed for entries made in past 24 hours.

3. Report any changes to license or medical status PER NDAP-QA-0723.

0700-1900 - - - - - - - - - - - Oncoming Qualified Unit Supervisor POST RELIEF 0700 1900

1. Walk down Control Room panels with Unit Responsible PCO.

2. CRC Book reviewed and Reactivity Brief performed with PCO.

3. Completed System Status Operable audit for open PMT this shift.

4. From the OPS Web page, Review OPS Aggregate Index for Challenges, Work Arounds, and Deficiencies Reports for impact on scheduled work activities and compensatory actions. (20l Oncoming Unit Supervisor FORM OP-AD-003-7, Rev. 23, DUPLEX Page 2 of 2 (Electronic Form)

Examination Material NRC SCN 3

SUSQUEHANNA NUCLEAR, LLC OPERATIONS TRAINING PROGRAM SCENARIO EXAMINATION GUIDE EOG SHUTDOWN/ CONTROL ROD DRIFT/ T-20 LOCKOUT/ DRYWELL STEAM LEAK/ RPV FLOODING SCN# LOC28-NRC-04 Revision 1 4/26/2016 Examination Material

LOC28-NRC-04 Lesson Information Title EOG Shutdown/ Failed RPS Reactor Pressure Channel/ Control Rod Drift/ T-20 LockouU Drywell Steam Leak/ RPV Flooding Vision ID Accredited *YES D NO Training ID Revision 11 Date 14/26/2016 Prerequisites Teaching Time 75 minutes Approval CBT Approval 1 N/A Date N/A Preparer Date Review (lnstructor/SME) Date Nuclear Engineering 1 N/A Date N/A Training Supervision Date Line Management Date l If required, otherwise N/A This simulator scenario has been reviewed and satisfies management expectations for inclusion of OE, Department Fundamentals and HuP, error-reduction techniques and safety standards. Specific applications and/or opportunities for reinforcement of management expectations are noted in the scenario guide or Attachment(s) where applicable. Copyrighted by Nuclear Training Group, SUSQUEHANNA NUCLEAR, LLC, 2016. All rights reserved, no part of this training material may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, recording or otherwise, without the prior permission of the Nuclear Training Group. LOC28-NRC-04 Rev 1 Examination Material 4/26/2016. 2

LOC28-NRC-04 Revision History Revision Date Comments 0 6/10/2014 New Scenario Updated to new format. Removed the Pressure transmitter failure Event. Changed the 1 4/26/2016 drifting control rod events from drifting in then out to only drifting in. Removed Event to fail an injection valve for a loop of RHR. Added runaway RRP with Event 2. LOC28-NRC-04 Rev 1 Examination Material 4/26/2016

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LOC28-NRC-04 Table of Contents Scenario Overview................................................................................................................................5 Objectives .............................................................................................................................................6 A. Terminal Objective ................................................................................................................6 B. Generic Performance Objectives ...........................................................................................6 C. Simulator Performance Objectives ........................................................................................7 D. Task List. ...............................................................................................................................9 Scenario Attributes .............................................................................................................................11 A. Critical Tasks ....................................................................................................................... 11 B. Scenario Malfunctions ......................................................................................................... 12 C. Abnormal Events and Major Transients ............................................................................... 12 D. EOP and EOP Contingencies Used .................................................................................... 13 E. Technical Specifications ...................................................................................................... 13 References ..........................................................................................................................................14 Setup Instructions ..............................................................................................................................15 A. Required Materials .............................................................................................................. 15 B. Simulator Initialization ......................................................................................................... 15 C. Simulator Preparation .......................................................................................................... 16 D. Document Training and Performance Feedback ................................................................. 16 E. Scenario Execution ............................................................................................................. 16 F. Simulator Files .................................................................................................................... 17 Event 1 - Secure 'B' EDG ....................................................................................................................20 Event 2 - Raise Reactor Power 5% using Recirc flow ......................................................................21 Event 3 - Control rod drift in ..............................................................................................................22 Event 4 - Startup Transformer 20 lockout ......................................................................................... 23 Event 5 - Small RCS steam leak in the Drywell.. ............................................................................... 24 Event 6 - HPCI fails to automatically initiate .....................................................................................24 Event 7 - RHR F016 Drywell Spray valve failure .........................................................................*.....26 Event 8 - RPV Flooding ......................................................................................................................27 LOC28-NRC-04 Rev 1 Examination Material 4/26/2016. 4

LOC28-NRC-04 Scenario Overview The scenario begins with Unit 1 at 90 percent power in a power ascension following a control rod pattern adjustment. Unit 2 is at rated power. RCIC is out of service due to oil system contamination. The station experienced a less-than-OBE seismic event 6 hours ago due to a magnitude 5.6 earthquake in the Lehigh Valley. The actions of ON-NATPHENOM-001 for the seismic event have been completed. Unit 2 is at rated power. Diesel Generator B is running and synchronized to ESS Bus 1B in accordance with S0-024-001 B, with the 15-minute run at 1000 KW complete. The first action of the crew is to shutdown DG B in accordance with S0-024-001 B. Then, the crew will raise reactor power by 5 percent per G0-100-012 and Reactor Engineering Reactivity Maneuver Request. During the flow change, the 'A' RRP will runaway. The crew will have to lock the scoop tube to stop the flow change. TS 3.4.1 will have to be reviewed for loop mismatch. Once the DG is shutdown and the power ascension is complete, reactor pressure switch PS-B21-1N023C will spike and then fail downscale. The spike high will result in a reactor half-scram, which must be reset. The pressure switch will be inoperable per TS 3.3.1.1. When the half-scram occurs control rod 50-23 will scram in due to a blown fuse to its B RPS solenoid. When the half-scram is reset, control rod 50-23 will begin drifting out of the core due to stuck collet fingers. The crew will respond per ON-CRD-101 and fully insert the control rod. Action will be required to maintain the control rod fully inserted until the CRD can be hydraulically disarmed per the ON and OP-155-001. When the control rod has been hydraulically disarmed, Startup Transformer 20 will experience a lockout. The crew will respond per ON-SUB-001 to restore Recirc Pump cooling and verify ESS Buses transferred to the alternate source. The crew will enter TS 3.8.1 for one offsite AC source inoperable. Once activities associated with the loss of T-20 are complete, a small steam leak will develop in the Drywell. The crew will perform ON-RPR-101 actions and will scram the reactor. The leak will degrade after the scram, resulting in a Plant Aux Load Shed and loss of the Feedwater and the normal heat sink. Condensate Pump discharge valves fail open preventing recovery of Condensate. HPCI will fail to auto-start, requiring the crew to perform a component by component start of the system for injection. The leak size will allow the crew to maintain reactor level during the transient with HPCI. The crew will initiate Suppression Chamber sprays. Once Suppression Chamber pressure exceeds 13 psig, Drywell sprays are required. When Drywell spray is attempted, the first Drywell spray valve opened will experience stem-to-disk separation. The other division of RHR will be placed in Drywell spray. Once Drywell sprays are established, high drywell temperature combined with reduced reactor pressure will result in all reactor level instrumentation becoming erratic and unusable. E0-100-114, RPV Flooding, will be used to depressurize the reactor and flood the RPV to the Main Steam Lines. Neither division of RHR will automatically align in the LPCI mode due to failure of the low reactor pressure permissive logic, but both can be manually aligned. The scenario may be terminated when the crew acknowledges indications of being flooded to the main steam lines OR at the direction of the Chief Examiner. LOC28-NRC-04 Rev 1 Examination Material 4/26/2016. 5

LOC28-NRC-04 Objectives Mastery of the training content shall be demonstrated by individual and/or crew performance evaluation as specified in this training material and the applicable training program description, in accordance with training procedures. A. Terminal Objective Perform all system operations required to maintain the plant operating safely, or place the plant in a safe condition if a plant shutdown is required During the specified mode of plant I system operation Without error and in accordance with site procedures and management expectations B. Generic Performance Objectives

1. For all activities, exhibit use of the Human Performance Tools, demonstrating the ability to:

Use HU tools to effectively control the plant during normal, abnormal, and emergency conditions Use of HU tools will be observable per the standards in HU-AD-003 (SRO) Take every opportunity to coach the team when HU standards are not being met and provide feedback to the team when the HU standards are being met

2. For all activities, exhibit proper use of procedures by:

Applying the correct procedure to operate equipment and respond to abnormalities Ensuring procedures are detailed enough to allow precise control of plant evolutions. Demonstrating the ability to: Apply the correct procedure to the situation Use place keeping for accurate implementation Identify any and all areas for procedure improvement Take ownership of and complete the improvement, whenever an area for procedure improvement is identified

3. Base actions and decisions with a bias toward conservative, safe operation of the plant, demonstrating the ability to:

Assure all plant evolutions and work are assessed for Radiological Safety, Industrial Safety, Nuclear Safety, Environmental Safety, or Corporate Safety Once a risk is determined, take appropriate actions to mitigate or minimize risk Request assistance for any activity which requires additional planning, special precautions, and management oversight to adequately manage the risks (SRO) Champion activities that are biased conservatively LOC28-NRC-04 Rev 1 Examination Material 4/26/2016. 6

LOC28-NRC-04

4. Demonstrate complete understanding of plant design and system interrelationships, demonstrating the ability to:

Work effectively as a team to interpret plant indications and determine an effective response Understand the bases for, and the plant response to, actions being taken

5. Maintain continuous awareness of critical parameters, demonstrating the ability to:

Validate parameters by observing multiple independent indications Relay parameter values with value, units, and trend; and include action being taken for an abnormal value or trend Notify supervision of any change to critical parameters (SRO) Assure critical parameters for operational conditions are understood by the team

6. Operate plant systems and equipment within design and operational limits, maintaining relevant parameters within assigned operating bands, demonstrating the ability to:

Anticipate the impact of component operation prior to its operation, and then verify that the expected effects occur during and following the operation Take manual actions (in accordance with procedure direction) when automatic actions do not occur Take prompt action to adjust system operating controls before assigned operating bands are exceeded Make reactivity and mode changes as directed by detailed operating procedures and approved reactivity plans C. Simulator Performance Objectives

1. Plant Startup/Heatup/Power Maneuvers With the plant operating at off-rated conditions Demonstrate the ability to manipulate console controls to safely operate the facility between shutdown and the designated power level

2. Operational Actions and Annunciator Response Correctly identify plant annunciators and indications and perform appropriate remedial actions

3. System Operation, Controls and Instrumentation Accurately identify plant instrumentation and correctly interpret instrument readings to respond to normal, abnormal, and emergency conditions

4. Facility Design and Operating Characteristics Demonstrate the following:

An understanding of facility operating characteristics LOC28-NRC-04 Rev 1 Examination Material 4/26/2016
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LOC28-NRC-04

The ability to safely control the operating characteristics of the facility within prescribed operating boundaries

5. System Loss and Component Level Malfunctions Perform system control manipulations to obtain desired operating results and demonstrate the ability to correctly respond to malfunction/loss of components and the impact of the malfunction/loss on interfacing plant systems

6. Heat Removal Component Operation Safely operate the plant's heat removal components and demonstrate knowledge of the relationship between the heat removal systems and the operation of facility to prevent exceeding System, Structure, or Component (SSC) design limits which include:

Primary coolant systems
Emergency coolant systems
Decay heat removal systems

7. Auxiliary and Emergency Component Operations Safely operate the plant's auxiliary and emergency components I systems to include the controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment to control release of radioactivity within regulatory limits

8. Reactivity Management Demonstrate knowledge of how reactivity is affected by plant operation and ability to respond to the change in reactivity to protect the safety and integrity of the reactor core

9. Technical Specifications During plant operation with the plant or system in a condition requiring Technical Specification action Identify the deviation and any required actions I notifications

10. Emergency Plan (if required)

During plant operation in an emergency condition Recognize conditions covered by the Emergency Plan (SRO) Demonstrate the ability to:

Identify and Implement the appropriate Emergency Action Level
Use the applicable bases to support an Event Classification on the specified Emergency Action Level LOC28-NRC-04 Rev 1 Examination Material 4/26/2016. 8

LOC28-NRC-04

11. Control Room Duties Demonstrate the knowledge and ability to assume the appropriate responsibilities (for the assigned position) associated with the safe operation of the facility

12. Control Room Team Work Demonstrate the ability to function within the Control Room team to comply with station procedures and limits of facility license and respond to plant events using appropriate human performance tools to support safe operation of the facility D. Task List Task Title ID Licensed Operator Apply Technical Specification (TS) And Technical Requirements Manual (TRM) Requirements S-C00-00-1185 Implement Reactivity Manipulations Standards and Communication Requirements S-C00-00-2784 Implement Appropriate Portions Of Operations Standards For System and Equipment Operation S-C00-00-1081 Implement Operations Standards For Error And Event Prevention S-ADM-00-1091 Implement Standards for Shift Operations S-C00-00-2780 Implement Appropriate Portions of Conduct of Operations S-C00-00-1015 Implement Appropriate Portions of Secondary Containment Integrity Control S-C00-00-1020 Implement EOP Cautions S-C00-00-2566 Implement Operations Directives S-C00-00-3130 Ensure Plant Operates IAW the Operating License, Technical Specifications (TS), and Technical S-C00-00-1183 Requirements Manual (TRM)

Implement HUMAN PERFORMANCE (HuP) - Standards for Error and Event Prevention S-EPP-00-3068 Reactor Operator Perform the Monthly Diesel Generator Operability Test S-264001-01-013 Implement Reactor Power Maneuvering Envelope for Normal Daily Power Operations (ICS) S-C00-01-4764 Direct the Actions for Loss of Startup Bus 20 S-262001-01-017 Perform Manual HPCI System Startup to Maintain Reactor Water Level S-206000-01-005 Perform the Required Actions for a Rod Drift or Rod Scram S-201001-01-021 Initiate Drywell Sprays S-203000-01-089 Initiate Suppression Chamber Sprays S-203000-01-088 Operate the RHR System in the Suppression Pool Cooling Mode S-203000-01-093 Perform a Manual Initiation of the Automatic Depressurization System S-218000-01-002 Direct ESW System Manual Startup S-276001-01-002 Perform a Manual Startup of the RHR System in LPCI Mode with the System Filled S-203000-01-073 LOC28-NRC-04 Rev 1 Examination Material 4/26/2016. 9

LOC28-NRC-04 Task Title ID Senior Reactor Operator Direct and Coordinate Implementation of RPV Control 000000-02-1125 Direct and Coordinate Implementation of Primary Containment Control 000000-02-1126 Direct and Coordinate Implementation of RPV Flooding 000000-02-1131 Implement Reactor Power Maneuvering Envelope for Normal Daily Power Operations (ICS) 000000-02-4 764 Direct Entry into Loss of Startup Bus 20 S-262001-02-007 Direct Entry into CONTROL ROD PROBLEMS S-201001-02-001 LOC28-NRC-04 Rev 1 Examination Material 4/26/2016

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LOC28-NRC-04 Scenario Attributes A. Critical Tasks

1. Spray the Drywell when Suppression Chamber pressure exceeds 13 psig.

Safety Significance Maintenance of primary containment integrity. Consequences for Failure Potential failure of primary containment. to Perform Task Indications/Cues for Event Multiple control board and control room indications of suppression Requiring Critical Task chamber and drywell pressures. Start an operable RHR loop. Perform a valve alignment to provide a Performance Criteria flowpath for spray. RHR pump, valve and system flow indications are available. Multiple Performance Feedback indications of Drywell pressure dropping.

2. Performs RPV Flooding when RPV water level becomes indeterminate by establishing RPV Flooded to Steamlines.

Safety Significance Adequate core cooling may be challenged if core submergence cannot be verified. Consequences for Failure Failure to take the EOP actions may result in uncovering the core and to Perform Task breach of the fuel clad due to overheating. Indications/Cues for Event RPV water level indication is believed to be erroneous or unbelievable due to failure of all reactor water level indications upscale with no Requiring Critical Task injection and a reactor coolant leak into the Drywell in progress. Recognize failure of RPV level indication, initiate emergency depressurization by opening ADS Valves, and then increasing RPV Performance Criteria injection until RPV flooded to Main Steam Lines as indicated by a combination of conditions as shown in FLOODED TO STEAMLINES TABLE. Initiating an emergency depressurization causes Reactor pressure to lower to the shutoff head of the low pressure injection systems allowing RPV water level to rise to the point that it reaches the main steam lines and returns to the suppression pool via the SRVs. No single indication can be relied upon in all events to determine conclusively that the RPV has been flooded to the main steam lines, therefore, some combination of Performance Feedback the following conditions need to be established to ensure water fills the lines:

SRV tail pipe acoustic monitors cycling .
Tail pipe temperatures of open SRVs decrease to subcooled values .
Increasing RPV pressure .
Suppression Pool Water Level not lowering Verify ADS Valves are open using light red light indication, acoustic monitoring and lowering Reactor pressure.

LOC28-NRC-04 Rev 1 Examination Material 4/26/2016

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LOC28-NRC-04 B. Scenario Malfunctions Event Malfunction Operator Action in Response 1 N/A Secure 'B' EOG (S0-024-001 B) 2 Various Raise Reactor Power 5% using Recirc flow, 'A' RRP runs away 3 mfR015500850230055023 Control rod drift in (TS 3.1.3) 4 mfDS003008 Startup Transformer 20 lockout (TS 3.8.1) 5 mfMS183007 Small RCS steam leak in the Orywell 6 Multiple HPCI fails to automatically initiate on high Orywell pressure, all other high-pressure injection lost 7 mfRH149011A(B) Stem-to-disk separation of RHR F016 Orywell Spray valve 8 Multiple Loss of reactor level indication - RPV Flooding (E0-000-114) C. Abnormal Events and Major Transients Malfunction Description R Raise Reactor Power 5% using Recirc flow, 'A' RRP Runaway N Secure 'B' EOG (S0-024-001 B) AE1 Control rod drift in/out AE2 Startup Transformer 20 lockout MT1 Small RCS steam leak in the Orywell MT2 Loss of reactor level indication - RPV Flooding (E0-000-114) HPCI fails to automatically initiate on high Orywell pressure, all other high-pressure MAE1 injection lost MAE2 Stem-to-disk separation of RHR F016 Orywell Spray valve TS1 RRP flow mismatch (TS 3.4.1) TS2 Control rod drift in/out (TS 3.1.3) TS3 Startup Transformer 20 lockout (TS 3.8.1) LOC28-NRC-04 Rev 1 Examination Material 4/26/2016

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LOC28-NRC-04 D. EOP and EOP Contingencies Used EOPs EOP Contingencies 1Z1 E0-000-102, RPV Control D E0-000-102, Alternate Level Control IZI E0-000-103, Primary Containment Control D E0-000-102, Steam Cooling D E0-000-104, Secondary Containment Control D E0-000-112, Emergency Depressurization D E0-000-105, Radioactivity Release Control D E0-000-113, Power/Level Control 1Z1 E0-000-114, RPV Flooding E. Technical Specifications

1. TS 3.1.3 Control Rod Operability

2. TS 3.9.5 Control Rod Operability - Refueling

3. TS 3.8.1 Electrical Power Systems AC Sources Operating

4. TS 3.4.1 Recirc Loop Flow Mismatch LOC28-NRC-04 Rev 1 Examination Material 4/26/2016

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LOC28-NRC-04 References

1. OP-AD-055 Operations Procedure Program

2. OP-AD-300 Administration of Operations

3. OP-AD-338 Reactivity Manipulations Standards and Communication Requirements

4. OP-054-001 Emergency Service Water System

5. OP-155-001 Control Rod Drive Hydraulic System

6. OP-158-001 RPS System

7. G0-100-012 Power Maneuvers

8. S0-024-001 B Monthly Diesel Generator B Operability Test

9. ON-NATPHENOM-001 Severe Weather Natural Phenomena

10. ON-SUB-001 Loss of Startup Bus 10 or 20

11. ON-SCRAM-101 Reactor Scram

12. ON-CRD-101 Control Rod Malfunctions

13. ON-4KV-101 Loss of 4KV Bus

14. ON-RPS-101 Loss of RPS

15. E0-000-102 RPV Control

16. E0-000-103 Primary Containment Control

17. E0-000-104 Secondary Containment Control

18. E0-000-105 Radioactivity Release Control

19. E0-000-112 Emergency Rapid Depressurization

20. E0-000-114 RPV Flooding

21. EP-RM-004 EAL Classification Bases

22. EP-PS-100 Emergency Director Control Room

23. AR-103-A01 RPS Channel A1/A2 Auto Scram

24. AR-103-B02 RX Vessel Hi Press Trip

25. AR-104-H05 Rod Drift

26. AR-109-C05 LOCA ISO Switch LOOP A Manual Override

27. TS 3.1.3 Control Rod Operability

28. TS 3.9.5 Control Rod Operability- Refueling

29. TS 3.8.1 Electrical Power Systems AC Sources Operating

30. TS 3.4.1 Recirc Loop Flow Mismatch LOC28-NRC-04 Rev 1 Examination Material 4/26/2016. 14

LOC28-NRC-04 Setup Instructions A. Required Materials

1. US Turnover Sheet

a. Unit 1

1) Unit 1 is at -90% power following a rod pattern adjustment

2) RCIC is OOS due to contamination of the lube oil system. Estimated RTS is 4 days

3) LCO 3.5.3 entered. Day 2 of the 14 day LCO.

4) Shutdown 'B' EOG IAW S0-024-001 B

5) Raise Reactor Power 5% IAW RMR

b. Common and Unit 2

1) Unit 2 at rated power.

2) SSES experienced a less-than-QBE seismic event 6 hours ago due to expected blasting activities by neighboring industrial facilities.

3) Actions IAW ON-NATPHENOM-001 have been completed

2. Supporting Documents

a. S0-024-001 B

b. RMR (2 copies)

8. Simulator Initialization

1. Reset to exam specific IC, Otherwise perform the following

a. Reset to IC-20

b. Place the simulator in RUN

c. Lower power to 90% with flow

d. Set Xe to fast time to burn Xe until power returns to 90% and starts rising

e. Set Xe to normal time

f. Start the 'B' EOG and sync to 1B ESS bus IAW S0-024-001 B

g. Load the 'B' EOG to 800KW

h. Close HV-149-FOO? & FOOS to isolate RCIC

i. Depressurize RCIC using LV-149-F054

j. Run SCN file exam\RCB_RCICOOS

k. Place the simulator in FREEZE LOC28-NRC-04 Rev 1 Examination Material 4/26/2016

15

LOC28-NRC-04

2. Run SCN file exam\LOC28-NRC-04.scn

3. Place the simulator in RUN

4. Perform simulator activities

a. Place a status control tags on HV-149-FOO?, F008 & F088

b. Place the protected equipment magnets on HPCI

c. Place the 'surveillance in progress' sign on 'B' EOG

d. Ensure the 'Diesel B Power & Vars' R*Time screen under 'Trends' is displayed by the EDGs with it ranged properly

e. Post Blue reactivity signs

5. Verify the simulator matches the following MF RF OR ET CONDITIONS 18:18 2:2 0:0 4 16

6. Ensure FW Control is selected to LEFM

7. Reset ODAs and all Overhead, R*TIME, HMI and RWM alarms

8. Ensure horns and annunciators are on

9. Ensure Overhead Lights Override is off C. Simulator Preparation

1. Ensure the EOL CRC Book is at the PCO Console D. Document Training and Performance Feedback

1. Record crew position assignments in G:\NTGOPS\LOR\REQUAL\lnfo Tracking\ (LOR)

2. Record crew position assignments per TQ-104 (ILO)

3. Complete an IER 11-3 Operator Fundamentals Simulator Observer Aid

4. Complete simulator checklists E. Scenario Execution

1. Identify performance improvement actions that may be addressed during the scenario

2. Provide turnover to the crew using the US Turnover sheet

3. Direct the crew to walk down the Control Room panels

4. Inform the Shift Manager that the crew has the shift LOC28-NRC-04 Rev 1 Examination Material 4/26/2016

16

LOC28-NRC-04 F. Simulator Files LOC28-NRC-04 IMF cmfRLOl_ElllK67B de Imp SCN rat_mp aet ETLOC28-NRC04-A ; Steam leak degrades on scram aet ETLOC28-NRC04-B ; Allow other division of DW spray insmp lssblpos(68) aet ETLOC28-NRC04-C ; Allow other division of DW spray changemp lssblpos(68) ,,,CONTROL ROD 50-23 POS aet ETLOC28-NRC04-E ; Runaway RRP at 95.5 Mlbm Core Flow insmp aoTRSHB311R601E.CurrValue changemp aoTRSHB311R601E.CurrValue 0,300,DEG F,RECIRC ; Drift Control Rod 50-23 In PP A MTR WDG TEMP {Key[l]} IMF mfRD1550085023 insmp aoTRSHB311R601Q.CurrValue ; Hyd disarm HCU 50-23 changemp aoTRSHB311R601Q.CurrValue 0,300,DEG F,RECIRC {Key[2)} IRF rfRD1550075023 d:120 f:DISARM PP B MTR WDG TEMP {Key[2)} DMF mfRD1550085023 insmp aoFl15120AB.CurrValue ; T-20 lockout changemp aoFl15120AB.CurrValue 0,750,GPM,RHR A SC SPRAY {Key[3)} IMF mfDS003008 FL

                                                               ; Small steam leak in DW insmp aoFl15120BB.CurrValue                                     {Key(4)} IMF mfMS183007 r:600 f:0.02 changemp aoFl15120BB.CurrValue 0,750,GPM,RHR B SC SPRAY FL                                                              ; Raise severity of steam leak

{Key[5)} MMF mfMS183007 r:O f:0.05 insmp aoFl15120AA.CurrValue changemp aoFl15120AA.CurrValue 0,12000,GPM,RHR A DW ; Failure of rx level instr SPRAY FL {Key[6)} SCN exam\LOC28-NRC04-C insmp aoFl15120BA.CurrValue ; Backup ADS changemp aoFl15120BA.CurrValue 0,12000,GPM,RHR B DW {Key[7)} IOR diHS14113G2 d:60 f:OPEN SPRAY FL {Key[7)} IOR diHS14113J2 d:66 f:OPEN {Key[7)} IOR diHS14113K2 d:72 f:OPEN insmp aoTRSB211R614A.CurrValue {Key[7)} IOR diHS14113L2 d:78 f:OPEN changemp aoTRSB211R614A.CurrValue 0,600,DEG F,ADS/SRV G {Key(7)} IOR diHS14113M2 d:84 f:OPEN TAILPIPE TEMP {Key[7)} IOR diHS14113N2 d:90 f:OPEN

B CRM spurious alarm suppressed ; Reset Rad Monitors IMF annAR112G04 f: ALARM_OFF {Key[8)} SCN exam\RMA_DIV2RST
DW spray valves stem-to-disk failure LOC28-NRC04-A IMF mfRH149011A f: O.O ; NR/WR ref leg break IMF mfRH149011B f:O.O ;IMF mfRR180002 f:lOO

                                                               ;IMF mfRR180001 f:lOO

Condensate pump discharge valves fail IMF cmfMV09_HV10502A f: lOO ;RCIC/HPCI L8 trip IMF cmfMV09_HV10502B f:lOO IMF cmfRL02_E411Kll IMF cmfMV09_HV10502C f:lOO IMF cmfRLOl_E411K4 IMF cmfMV09_HV10502D f:lOO IMF cmfRL02_E511K58 IMF cmfRLOl_ElllK79B
H PCI auto-start fa ii u re IMF cmfRLOl_ElllK80B IMF mfHP152002 IMF mfRC150001 IMF cmfMV06_HV155F001 IMF cmfMV06_HV155F006 ;ADS L3 confirmatory IMF cmfMV06_HV156F059 IMF cmfRLOl_B21ClK12A IMF cmfPM04_1P213 IMF cmfRLOl_B21ClK12B
LPCI injection valves fail ;NR N004 IMF cmfRLOl_ElllK66A ;IMF cmfTR02 PDTC321N004A f: 60 IMF cmfRLOl_ElllK66B IMF cmfTD03_PDTC321N004A f:60 IMF cmfRLOl_ElllK67A IMF mfRR164022A f:61.2 LOC28-NRC-04 Rev 1 Examination Material 4/26/2016

17

LOC28-NRC-04

IMF cmfTR02_PDTC321N004B f: 60 IMF cmfTR02_LT14201A f:60 IMF cmfTD03_PDTC321N004B f:60 IMF cmfTR02_LT14201B f:60 IMF mfRR164022B f:61.2
IMF cmfTR02_PDTC321N004C f: 60 ;dwclg IMF cmfTD03_PDTC321N004C f:60 IMF cmfNBOl_LIS14221C IMF mfRR164022C f:61.2 IOR aoLIS14221C_Q f:60 IMF cmfNBOl_LIS14221D
NR N042 IOR aoLIS14221D_Q f: 60 IMF cmfNBOl_LISB211N042A IOR aoLISB211N042A_Q f:60 ; ER IMF cmfNBOl_LISB211N042B IMF cmfTR02_LT14203A f:180 IOR aoLISB211N042B_Q f:60 IMF cmfTR02_LT14203B f:180
NR N024 ; UR IMF cmfNBOl_LISB211N024Al ;IMF cmfTR02_PDTC321N017 f: 180 IOR aoLISB211N024A_Q f:60 IMF cmfTD03_PDTC321N017 f:180 IMF cmfNBOl_LISB211N024Bl IOR aoLISB211N024B_Q f:60 ; S/D IMF cmfNBOl_LISB211N024Cl IMF cmfTR02_LTB211N027 f:SOO IOR aoLISB211N024C_Q f:60 IMF cmfNBOl_LISB211N024Dl ; fuel zone IOR aoLISB211N024D_Q f:60 IMF cmfTR02_LT14202A f:-110 IMF cmfTR02_LT14202B f:-110
WR N031 IMF cmfNBOl_LISB211N031Al IMF cmfNBOl_LISB211N031A2 LOC28-NRC04-B IOR aoLISB211N031A_Q f: +60 ; NR/WR ref leg break IMF cmfNBOl_LISB211N031Bl ;DMF mfRR180002 f:lOO IMF cmfNBOl_LISB211N031B2 ;DMF mfRR180001 f:lOO IOR aoLISB211N031B_Q f:+60 IMF cmfNBOl_LISB211N031Cl ;RCIC/HPCI LS trip IMF cmfNBOl_LISB211N031C2 DMF cmfRL02_E411Kll IOR aoLISB211N031C_Q f:+60 DMF cmfRLOl_E411K4 IMF cmfNBOl_LISB211N031Dl DMF cmfRL02_E511K58 IMF cmfNBOl_LISB211N031D2 DMF cmfRLOl_ElllK79B IOR aoLISB211N031D_Q f:+60 DMF cmfRLOl_ElllK80B DMF mfRC150001
WR N025 IMF cmfNBOl_LISB211N025A ;ADS L3 confirmatory IOR aoLISB211N025A_Q f: +60 DMF cmfRLOl_B21ClK12A IMF cmfNBOl_LISB211N025B DMF cmfRLOl_B21ClK12B IOR aoLISB211N025B_Q f:+60 IMF cmfNBOl_LISB211N025C ;NR N004 IOR aoLISB211N025C_Q f:+60 ;DMF cmfTR02 PDTC321N004A IMF cmfNBOl_LISB211N025D DMF cmfTD03_PDTC321N004A IOR aoLISB211N025D_Q f:+60 DMF mfRR164022A

                                           ;DMF cmfTR02_PDTC321N004B

WR n026 DMF cmfTD03_PDTC321N004B IMF cmfNBOl_LISB211N026Al DMF mfRR164022B IMF cmfNBOl_LISB211N026A2 ;DMF cmfTR02_PDTC321N004C IMF cmfTR02_LITSB211N026A f: 60 DMF cmfTD03_PDTC321N004C IMF cmfNBOl_LISB211N026Bl DMF mfRR164022C IMF cmfNBOl_LISB211N026B2 IMF cmfTR02_LITSB211N026B f:60 ;NR N042 IMF cmfNBOl_LISB211N026Cl DMF cmfNBOl_LISB211N042A IMF cmfNBOl_LISB211N026C2 DOR aoLISB211N042A_Q IMF cmfTR02_LITSB211N026C f:60 DMF cmfNBOl_LISB211N042B IMF cmfNBOl_LISB211N026Dl DOR aoLISB211N042B_Q IMF cmfNBOl_LISB211N026D2 IMF cmfTR02_LITSB211N026D f:60 ;NR N024 DMF cmfNBOl_LISB211N024Al
other wr DOR aoLISB211N024A_Q LOC28-NRC-04 Rev 1 Examination Material 4/26/2016. 18

LOC28-NRC-04 DMF emfNBOl_LISB211N024Bl DOR aoLISB211N024B_Q ; S/D DMF emfNBOl_LISB211N024Cl DMF emffR02_LTB211N027 DOR aoLISB211N024C_Q DMF emfNBOl_LISB211N024Dl ; fuel zone DOR aoLISB211N024D_Q DMF emffR02_LT14202A DMF emffR02_LT14202B

WR N031 DMF emfNBOl_LISB211N031Al DMF emfNBOl_LISB211N031A2 LOC28-NRC04-C DOR aoLISB211N031A_Q sen exam\LOC28-NRC04-A DMF emfNBOl_LISB211N031Bl +5 sen exam\LOC28-NRC04-B DMF emfNBOl_LISB211N031B2 +30 sen exam\LOC28-NRC04-A DOR aoLISB211N031B_Q +3 sen exam\LOC28-NRC04-B DMF emfNBOl_LISB211N031Cl +30 sen exam\LOC28-NRC04-A DMF emfNBOl_LISB211N031C2 DOR aoLISB211N031C_Q DMF emfNBOl_LISB211N031Dl LOC28-NRC04-D DMF emfNBOl_LISB211N031D2 ;Revision/Date: 1/09/18/2016 DOR aoLISB211N031D_Q ;Deseription:Recirc A speed failure High
WR N025 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N025A +l set fx1A_MAN_MODE_B200D.BI01=1 DOR aoLISB211N025A_Q +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF emfNBOl_LISB211N025B +l set fx1A_MAN_MODE_B200D.BI01=1 DOR aoLISB211N025B_Q +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF emfNBOl_LISB211N025C +1 set fx1A_MAN_MODE_B200D.BI01=1 DOR aoLISB211N025C_Q +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF emfNBOl_LISB211N025D +1 set fx1A_MAN_MODE_B200D.BI01=1 DOR aoLISB211N025D_Q + 1 set fx1A_MAN_MODE_B200D.BI01=1

                                      +1 set fx1A_MAN_MODE_B200D.BI01=1

WR n026 +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026Al +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026A2 +l set fx1A_MAN_MODE_B200D.BI01=1 DMF cmffR02_LITSB211N026A +l set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026Bl +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026B2 +1 set fxlA_MAN_MODE_B200D.BIOl=l DMF cmffR02_LITSB211N026B + 1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026Cl +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026C2 +l set fx1A_MAN_MODE_B200D.BI01=1 DMF cmffR02_LITSB211N026C +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026Dl +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026D2 +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmffR02_LITSB211N026D
other wr RCB_RCICOOS DMF cmffR02_LT14201A IMF mfRC150011 DMF cmffR02_LT14201B IRF rfDC188073 f: OPEN IRF rfDB106383 f:OPEN
dwclg IMF cmfAOl_HV149F088 DMF cmfNBOl_LIS14221C DOR aoLIS14221C_Q DMF emfNBOl_LIS14221D ETLOC28-NRC04-A DOR aoLIS14221D_Q ;SWITCH: MODE SWITCH diHSC72AlS01.CurrValue != #OR.diHSC72AlS01.RUN
ER MMF mfMS183007 r: 300 i:0.5 f:2 DMF cmffR02_LT14203A IMF mfDS103010 d:lO DMF cmffR02_LT14203B
UR
DMF cmffR02_PDTC321N017 DMF cmffD03_PDTC321N017 LOC28-NRC-04 Rev 1 Examination Material 4/26/2016

19

LOC28-NRC-04 ETLOC28-N RC04-B

SWITCH: DRYWELL SPRAY OB ISO HV-1F016A (E11A-S9A) ETLOC28-N RC04-E diHS15116A.CurrValue != #OR.diHS15116A.CLOSE ;A RRP runaway at 95.5 Mlbm DMF mfRH149011B aoXR14301F.CurrValue>95.5 cet ETLOC28-NRC04-C SCN exam\LOC28-NRC04-D aet ETLOC28-NRC04-D ETLOC28-NRC04-C
SWITCH: DRYWELL SPRAY OB ISO HV-1F016B (EllA-S9B) diHS15116B.CurrValue != #OR.diHS15116B.CLOSE DMF mfRH149011A cet ETLOC28-NRC04-B ETLOC28-NRC04-D
A RRP failure stops with scoop tube lock diHSB311503A.CurrValue=#OR.diHSB311S03A.TRIP abort exam\LOC28-NRC04-D set fx1A_MAN_MODE_B200D.BI01=0 LOC28-NRC-04 Rev 1 Examination Material 4/26/2016. 20

LOC28-NRC-04 Event 1 - Shutdown the '8' EOG Instructor Activities Operator Activities Notes Booth Operator No additional activities are required PCOM Role Play D Monitor diverse plant indications As NPO at the 'B' EOG, acknowledge requests and PCOP report actions complete when D Adjusts EOG KW to the proper setting the 'B' EOG is secured (-5 with HS-000548, Speed governor minutes) D Adjusts EOG Kvars - 0 with HS-000538, Voltage Adjust D Opens 1A20204 to divorce from the EOG D Adjusts voltage to 4250V using HS-000538 for 5 minute unloaded run D Depresses HS-000528, DG 8 Stop pushbutton D Directs NPO to perform field actions us D Directs PCOP to secure the '8' EOG IAW S0-024-0018 Instructor Note There is a 5 minute unloaded cooldown time in the SO. No actions are taken during that time period. Time compression is allowed for that section of the procedure if authorized by the Chief Examiner. LOC28-NRC-04 Rev 1 Examination Material 4/26/2016. 21

LOC28-NRC-04 Event 2 - Raise .Reactor Power 5% with RRPs, 'A' RRP Runaway Instructor Activities Operator Activities Notes Booth Oper~tor After the stop p4shbutton has been depressed for the 'B' EOG and the crew is not proceeding to raise power, perform the first role play. Ensure Event Trigger ETLOC28-NRC04-E fires when Core Flow reaches 95.5 Mlbm .. This should occur the third time 'A' RRP flow is adjusted, The Event Trigger will cause the 'A' RRP to run away and activate ETLOC28-NRC04~D. Ensure Event Trigger E;TLOC28-NRC04-D fires when the scoop tube is locked to stop the scenario and the RRP malfunction. PCOM Role Play D Raises Reactor Power with RRPs IAW As Shift Manager contact the control room provided RMR and OP-AD-338 If we have depressed the D Plots power on the power/flow map stop pushbutton for the 'B' prior to the power change and Diesel,. you have my permission to continue following the power change with the 5% power D Depresses the single or double up ascension while the stop chevron to raise reactor power. (A 2% timers and field actions are proceeding. change in speed on both RRPs equates to - 1% change in reactor power) D Monitors diverse indications of reactor power D Reports 'A' RRP speed is raising D May attempt to lower flow by depressing the up chevron D Locks 'A' RRP MG Scoop Tube. PCOP D Peer checks the PCOM during the power maneuver D As required, adjusts manual voltage to zero manual and auto voltage regulators D Performs ON-RECIRC-101 LOC28-NRC-04 Rev 1 Examination Material 4/26/2016

22

LOC28-NRC-04 Event 2 - Raise Reactor Power 5% with RRPs, 'A' RRP Runaway Instructor Activities Operator Activities Notes us D Obtains permission from the SM to perform the reactivity manipulation D Directs PCOM to raise reactor power using RRPs IAW the RMR and OP-AD-338 D Directs PCOP to peer check the PCOM D May conduct update after the reactivity maneuver D Enters ON-RECIRC-101 on runaway RRP D Evaluates entering TS 3.4.1.B for loop flows not matched. Instructor Note When the crew locks the Scoop Tube, speed may continue to raise. This is because the RRP will match speed to the location of the scoop tube. If speed was lower than the position of the scoop tube, it will continue to rise until it reaches that position and then stop moving. The crew may discuss tripping the 'A' RRP if they do not notice that the scoop tube position is not moving. LOC28-NRC-04 Rev 1 Examination Material 412612016

23

LOC28-NRC-04 Event 3 - Control rod scram Instructor Activities Operator Activities Notes Booth Operator When the power change has been completed, Insert KEY 1 to scram control rod 50-23 due to blown fuses. {Key[1]} IMF mfRD1550085023 Drift Control rod 50-23 In If directed, Insert KEY 2 to disarm co.ntrol rod 50-23. Report when the actions are complete, {Key[2]} IRF rfR01550075023 d:120 f:DISARM Disarms Control rod 50-23 {Key[2]} DMF mfRD1550085023 Removes the drift in malfunction PCOM Role Play D Reports RPV power, pressure, and As NPO dispatched to HCU 50-23, wait 2 minutes water level after the plant stabilizes Scram inlet and outlet D Reports control rod 50-23 is at position valves on HCU 50-23 are 00 open. D Plots position on the Power/Flow Map Role Play PCOP As WWM contacted for D Performs ON-CRD-101 condition D assistance with control rod 50-23, wait 5 minutes D Verifies position of control rod 50-23 l&C discovered a blown D Resets rod drift alarm fuse on the 'B' RPS D Informs US to address LCO 3.1.3 and solenoid for the scram pilot solenoid valve for HCU 50- 3.9.5

23. They are still us troubleshooting. D Enters ON-CRD-101 condition D Role Play D Enters ON-PWR-101 for power change As NPO dispatched to 1C007 D Enters TS 3.1.3.C for a control rod for high temperatures, wait 2 inoperable fully inserted minutes Control rod 50-23 has elevated temperature on 1C007.

LOC28-NRC-04 Rev 1 Examination Material 4/26/2016. 24

LOC28-NRC-04 Event 4 - T-20 Lockout Instructor Activities Operator Activities Notes Booth Operator When the US has reviewed TS for the drifted control rod, Insert KEY 3 to initiate a lockout of Start Up Transformer 20 (T-20). {Key[3]} IMF mfDS003008. T-20 lockout If requested to reset Div 2 rad monitors for the loss of RPS, Wait 1 minute, Insert KEY 8 and report when complete {Key[8]} SCN exam\RMA_DIV2RST Reset Rad monitors PCOM Role Play D Reports RPV Power, Pressure, and As NPO dispatched to T-20, wait 2 minutes Water Level There is nothing abnormal PCOP at the T-20 transformer. D Reports loss of Startup Bus 20 Role Play D Dispatches NPO to Startup Bus 20 As WWM contacted for D Dispatches NPO to Startup assistance with T-20 lockout, Transformer 20 wait 5 minutes Electrical Maintenance D Performs ON-SUB-001 reports the backup D Performs ON-4KV-101 transformer lockouts were D Performs ON-RPS-101 tripped on T-20. It looks like a bad lockout relay and D Restores cooling to the RRPs we are getting a package to us replace it. D Enters ON-SUB-001, Loss of Startup Role Play Bus 10 or 20 As NPO dispatched to SUB- D Enters TS 3.8.1.A, Actions A.1 & A.3 20, wait 2 minutes D Enters TRO 3.4.1 The backup lockout relay for T-20 is tripped on Startup Bus 20. Role Play As NPO dispatched to verify the position of the 'E' EOG OATS, wait 3 minutes The 'E' diesel OATS is on SUB-10. LOC28-NRC-04 Rev 1 Examination Material 4/26/2016. 25

LOC28-NRC-04 Event 5, 6 - Small Steam Leak/ Manual Scram/ HPCI failure Instructor Activities Operator Activities Notes Booth Operator When RRP cooling has been restored, Insert KEY 4 to initiate a small steam leak in the Drywell {Key[4]} IMF mfMS183007 r:600 f:0.02 Small steam leak When the crew recognized the steam leak, Insert KEY 5 when desired to raise the severity of the steam leak and proceed to reactor scram. {Key[5]} MMF mfMS183007 r:9 f:0.05 Raise severity of the leak Ensure EventTrigger ETLOC28-NRC04-A fires when the Mode Switch is placed to SHUTDOWN to raise the severity of the steam leak AND cause a Plant Aux Load Shed PCOM Role Play D If directed, Inserts a LIM #2 on RRPs As NPO dispatched to investigate Condensate D When directed, Places Mode Switch in Pump discharge valves, wait SHUTDOWN to Scram the reactor 2 minutes D Performs Scram Report IAW OP-AD-The Condensate Pump discharge valves all 300 indicate full open. The D Inserts IRMS and SRMS breakers are closed and reset. D Reports trip of all RFPs D If observed, Reports failure of Role Play condensate discharge valves to close As WWM contacted for PCOP assistance with the Drywell steam leak, wait 5 minutes D Reports rising Drywell Pressure I have activated the forced D Verifies Isolations, Initiations, and EOG outage response team at starts the direction of the Duty Manager. D Reports an Aux Bus Load Shed happened Role Play D Reports failure of HPCI to auto start As WWM contacted for assistance with Condensate D Performs Component by component Pump discharge valves, startup of HPCI IAW OP-152-001 acknowledge the request, if asked* about status Engineering and maintenance are still investigating. Instructor Note The initial steam leak is very small in severity and takes -5 minutes to be readily detected LOC28-NRC-04 Rev 1 Examination Material 4/26/2016

26

LOC28-NRC-04 Event 5, 6 - Small Steam Leak/ Manual Scram/ HPCI failure Instructor Activities Operator Activities Notes us D Performs ON-RPR-101 D Directs PCOM to scram the plant D Enters E0-000-102, RPV Control D Enters E0-000-103, PC Control Directs PCOP to maintain RPV water level with HPCI and RCIC Critical Parameter Once Drywell pressure is noticed to be rising, it would be expected that the US gives a Critical Parameter to the PCOP on Drywell pressure and an action to place the Mode Switch to SHUTDOWN when it is reached. LOC28-NRC-04 Rev 1 Examination Material 4/26/2016

27

LOC28-NRC-04 Event 7 - Containment Cooling Instructor Activities Operator Activities Notes Booth Op~rator Ensur~ Event Trigger ETLOC28-NRC04-B(C) fires when the first RHR F016A(B) valve is opened to clear the stem-to-disk malfunction on the other division. Critical Task

Spray the Drywell when Suppression Chamber pressure exceeds 13 psig.

Role Play As NPO dispatched to RHR PCO D When directed, initiates suppression chamber sprays IAW OP-149-004 F016A(B), wait 2 minutes The RHR Drywe/I spray OB D Aligns RHRSW to the RHR heat valve HV-151-F016A(B) exchanger IAW OP-149-004 indicates full open. I do NOT hear any flow. D When directed, initiates Drywell Sprays IAW OP-149-004 Role Play D Requests plant status IAW the DSIL As WWM contacted for curve before spraying the Drywell assistance with RHR F016A(B), acknowledge D Reports failure to achieve flow through request, if contacted about the RHR F016A(B) and moves to the status Engineering and other RHR Loop for Drywell sprays Maintenance are still D Dispatches NPO to investigate RHR troubleshooting. F016A(B) us D Directs PCO to initiate Suppression Chamber Sprays D Directs PCO to line-up for Drywell Sprays D Verifies plant conditions are in the

                                   'Safe to Spray' region of the DISL curve before directing PCO to spray the Drywell LOC28-NRC-04 Rev 1                               Examination Material                         4/26/2016

28

LOC28-NRC-04 Event 8 - RPV Flooding Instructor Activities Operator Activities Notes Booth Operator When the crew has established Drywell Spray and Drywell pressure is trending down, Insert KEY 6 to initiate reactor level notching and subsequent failure of all reactor level indications upscale. {Key[6]} SCN examlLOC28-NRC04-C If directed, Insert KEY 7 to back up ADS with the keylock switches from the relay room. When complete, report to the control room. {Key[7]} IOR d.iHS14113G2 d:60 f:OPEN {Key[7]} IOR diHS14113J2 d:66 f:OPEN {Key[7]} IOR diHS14113K2 d:72 f:OPEN {Key[7]} IOR diHS14113L2 d:78 f:OPEN {Key[7]} IOR diHS14113M2 d:84 f:OPEN {Key[7]} IOR diHS14113N2 d:90 f:OPEN Monitor 'E0114' on R*Time and 'Vesvoid' on the Simulator in the booth and inform the Lead Evaluator when the simulator is Flooded to the Main Steam Lines (MSL) Critical Task

Performs RPV Flooding when RPV water level becomes indeterminate by establishing RPV Flooded to Steamlines.

PCO Role Play D Reports erratic and unusable level As NPO dispatched to Instrument racks C004/C005, instrumentation wait 2 minutes D Verifies ALL level indications are All reactor level indicators erratic at the 4 and 5 racks show full upscale. D When directed, Opens the 6 ADS SRVs on 1 C601 Role Play D May, dispatch NPO to backup ADS As WWM contacted for with the keylocks in the relay room assistance with Reactor level indications, acknowledge D Verify ADS SRVs are open by request and if contacted temperature recorders, acoustic about status Engineering and monitors, and reactor pressure Maintenance are lowering developing a plan to go D Closes all MSIVs and MSL drains troubleshoot. D Aligns RHR to LPCI mode IAW OP-149-004 LOC28-NRC-04 Rev 1 Examination Material 4/26/2016

29

LOC28-NRC-04 Event 8 - RPV Flooding Instructor Activities Operator Activities Notes PCO D Isolates HPCI and RCIC when the supply valves close on low pressure D May bring up on R*Time page E0114 to aid in monitoring for filling to the MSL us D Enters E0-000-114, RPV Flooding D Directs opening all ADS SRVs D Directs isolating all MSIVs and MSL drains D Directs aligning RHR for LPCI injection D Directs maximizing RPV injection to flood the RPV to the MSL Critical Parameter (~; When flooding to the MSL, the US may give a critical parameter to inform the US when flooded conditions are met. Instructor Activity - Termination The scenario may be terminated when the crew acknowledges indications of being flooded to the main steam lines OR at the direction of the Chief Examiner. LOC28-NRC-04 Rev 1 Examination Material 4/26/2016. 30

UNIT SUPERVISOR TURNOVER SHEET UNIT 1 t"o(dd(yy Date SHIFT 1900 to 0700 SHIFT 0700 to 1900 Start End Start End MODE MODE POWER LEVEL 90 % POWER LEVEL %

                  -  ------                                                -------

GENERATOR OUTPUT 1206 MWe GENERATOR OUTPUT MWe CASK STORAGE GATE INSTALLED: YES/NO CASK STORAGE GATE INSTALLED: YES/NO REMARKS:

1) Power ascension from control rod pattern adjustment in progress, 90 percent power

2) RCIC is out-of-service due to contamination of lube oil system. Estimated RTS is 4 days

3) LCO 3.5.3 Entered. Day 2 of the 14 day LCO

4) Shutdown Diesel Generator B per S0-024-001 B

5) Raise power 5 percent per Reactor Engineering RMR to 94% APRM power

6) Perform all briefings prior to taking the shift 7

8 9) 10 11 12 13 14 15) COMMON:

1) Unit 2 is at rated power

2) SSES experienced a less-than-OBE seismic event 6 hours ago due to expected blasting activities by neighboring industrial facilities

3) Actions of ON-000-002 for a seismic event have been completed 4

5) 6 7 8) 9) FORM OP-AD-003-7, DUPLEX Page 1 of 2 (Electronic Form) Examination Material NRC SCN 4

OFFGOING UNIT SUPERVISOR CHECKLIST: NRC CODE PRIOR TO 0800 FOXTROT DELTA BRAVO OSCAR NRC CODE AFTER 0800 FOXTROT UNIFORM HOTEL ROMEO 1900- 0700-0700 1900

1. Evolutions in progress and items to be completed during next shift, as noted in remarks, have been discussed with oncoming Unit Supervisor (including special evolutions, i.e. SICT/E, OPDRVs, etc.).

2. Problems encountered during past shift and abnormal plant conditions, as noted in remarks, have been discussed with oncoming Unit Supervisor.

3. Information in SOMS Log is complete and discussed with oncoming Unit Supervisor.

4. As applicable, turnover plastic Security Badge cover and CRS Monitor function to oncoming Unit Supervisor.

1900-0700 - - - - - - - - - - - 0700 - 1900 - - - - - - - - - - - Offgoing Unit Supervisor ONCOMING UNIT SUPERVISOR CHECKLIST: 0700 1900

   -      -

1. LCOfTRO Log reviewed.

c) 2. SOMS Log reviewed for entries made in past 24 hours.

3. Report any changes to license or medical status PER NDAP-QA-0723.

0700 - 1900 - - - - - - - - - - - - 1900-0700 - - - - - - - - - - - Oncoming Qualified Unit Supervisor POST RELIEF 0700 1900

1. Walk down Control Room panels with Unit Responsible PCO.

2. CRC Book reviewed and Reactivity Brief performed with PCO.

3. Completed System Status Operable audit for open PMT this shift.

4. From the OPS Web page, Review OPS Aggregate Index for Challenges, Work Arounds, and Deficiencies Reports for impact on scheduled work activities and compensatory actions. (2o) 0700-1900 - - - - - - - - - - -

1900 - 0700 - - - - - - - - - - - - Oncoming Unit Supervisor FORM OP-AD-003-7, DUPLEX Page 2 of 2 (Electronic Form) Examination Material NRCSCN4}}

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-{{#Wiki_filter:SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: __ c ...... o ...... m....,p.....,1
+{{#Wiki_filter:SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: __c. . o. ......m.. .,p. . .,1.....
-..... et ...... e_A_b.._o
+et......e_A_b.._o.....rt.....e_d_E_v_o......lu=t"""'io;...;..n"'""L""'"o'"""g.___ _ _ _ _ _ _ _ _ _ _ __
-..... rt ..... e_d_E_v_o
+JPM#: OO.AD.21017.001                                                                    Revision:_o;;;....____ Date: 09/23/2016 Applicability: ~ RO ~ SRO Setting:    Classroom NUREG-1123 E/APE I Sys                                       Generic                             KIA Number                    2.1.20   KIA Importance  2.1.20 Alternate Path: D YES ~                                NO                    Time Critical DYES ~ NO Validation Time (min): _ _2..._5__
-...... lu=t"""'io;...;..n"'""L""'"o'"""g.__
+Examinee Name:
-____________
+                       --                       ----------------
-_ JPM#: OO.AD.21017.001 Revision:_o;;;...._
+Last, First Ml                                                                                          Employee Number Exam Date:                                                                                                      Exam Duration (Min): _ _ _ _ _ _ _ __
-___ Date: 09/23/2016 Applicability: RO SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic KIA Number 2.1.20 KIA Importance 2.1.20 Alternate Path: D YES NO Time Critical DYES NO Validation Time (min): __ 2..._5 __ Examinee Name: ------------------
+             ---------
-Last, First Ml Employee Number Exam Date: ---------Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+Evaluation Result:                   D          Satisfactory                        D            Unsatisfactory Evaluator: _ _ _ _ _ _ _ _ _ __
-__________
+Name                                                                                                           Signature Comments:
-_ Name Signature Comments:
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.21017.001 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.21017.001 I. SAFETY CONSIDERATIONS A.       All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+B.       All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+C.       If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
-II. REFERENCES OP-133-001 Chemical Addition to Turbine Building Chilled Water System (Rev. 37) marked up to step 2.5.10 (2.5.10 only circled, not slashed) OP-AD-002 Standards for Shift Operation (Rev. 63) Blank Aborted Evolution Control Log (AECL) OP-AD-002-3 Attachment B Ill. TASK CONDITIONS Unit 1 is in Mode 1 All Plant Equipment required for Mode 1 is in operation Turbine Building Chilled Water System in Service The Turbine building NPO is performing a Chemical Addition to Turbine Building Chilled Water System IAW OP-133-001 Section 2.5. During step 2.5.10 TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened. Maintenance will not be available until dayshift tomorrow to support opening the 188003 valve. You are the Unit 1 PCOM IV. INITIATING CUE Your Supervisor directs you complete the necessary administrative documentation to turn this information over to the on-coming shift. V. TASK STANDARD Aborted Evolution Control Log identifies TB Chilled Wtr Chem Add Tank Out In valve 188003 could not be opened. Unit 1 turbine bldg. NPO, and Control Room Supervisor notified to make turnover sheet entries referencing the Aborted evolution.
+D.       Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
-Plant operator turnover sheet entry referencing the Aborted evolution is made.
+II. REFERENCES OP-133-001 Chemical Addition to Turbine Building Chilled Water System (Rev. 37) marked up to step 2.5.10 (2.5.10 only circled, not slashed)
-INFORMATION FOR EVALUATOR
+OP-AD-002 Standards for Shift Operation (Rev. 63)
-* Marking a step as UNSAT requires written comments on respective step . TQ-106-Lr.:>
+Blank Aborted Evolution Control Log (AECL) OP-AD-002-3 Attachment B Ill. TASK CONDITIONS Unit 1 is in Mode 1 All Plant Equipment required for Mode 1 is in operation Turbine Building Chilled Water System in Service The Turbine building NPO is performing a Chemical Addition to Turbine Building Chilled Water System IAW OP-133-001 Section 2.5.
-Revision 1 Page 3 of 9
+During step 2.5.10 TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened.
+Maintenance will not be available until dayshift tomorrow to support opening the 188003 valve.
+You are the Unit 1 PCOM IV. INITIATING CUE Your Supervisor directs you complete the necessary administrative documentation to turn this information over to the on-coming shift.
+V. TASK STANDARD Aborted Evolution Control Log identifies TB Chilled Wtr Chem Add Tank Out In valve 188003 could not be opened. Unit 1 turbine bldg. NPO, and Control Room Supervisor notified to make turnover sheet entries referencing the Aborted evolution. Plant operator turnover sheet entry referencing the Aborted evolution is made.
+TQ-106-Lr.:> 10 Revision 1 Page 3 of 9 INFORMATION FOR EVALUATOR
+* Marking a step as UNSAT requires written comments on respective step .
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
 * The time clock starts when the candidate acknowledges the Initiating Cue .
 * This JPM can be performed in the simulator, classroom or other similar environment.
 * Mark-up a copy of OP-133-001 filled out up to step 2.5.10 (2.5.10 only circled, not slashed) .
-* Replacement pages for JPM: Section 5. 7 of OP-AD-002 and blank Aborted Evolution Control Log (AECL) OP-AD-002-3 Attachment B EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OP-AD-002, S/U controlled copy. Standards for shift operations.
+* Replacement pages for JPM: Section 5. 7 of OP-AD-002 and blank Aborted Evolution Control Log (AECL) OP-AD-002-3 Attachment B EVALUATOR CUE Record JPM start time:
-Selects the correct procedure section to perform. Performs OP-AD-002 section 5. 7, Aborted S/U OP-AD-002 Section 5. 7 Evolution Control Log (AECL) 3 Completes OP-AD-002 Attachment B Completes OP-AD-002 Attachment B when : S/U
+Step  Action                                                Standard                                           Eva I  Comments 1  Identifies governing procedure and obtain             Obtains controlled copy of OP-AD-002,               S/U controlled copy.                                      Standards for shift operations.
+Selects the correct procedure section to perform. Performs OP-AD-002 section 5. 7, Aborted            S/U OP-AD-002 Section 5. 7                                Evolution Control Log (AECL) 3  Completes OP-AD-002 Attachment B                      Completes OP-AD-002 Attachment B when :             S/U
 * An evolution is aborted prior to completion and will not be resumed prior to shift turnover.
-* Equipment is left in an abnormal lineup and additional information is essential to the oncoming shift. *4 Completes OP-AD-002 Attachment B Completes Attachment B as follows: S/U
+* Equipment is left in an abnormal lineup and additional information is essential to the oncoming shift.
+   *4  Completes OP-AD-002 Attachment B                      Completes Attachment B as follows:                  S/U
 * Line 1; Date, Time, and name .
-* Line 2; System number 133 and system name Turbine Building Chilled Water System * *Line 3; Procedure number OP-133-001, Revision 37, step 2.5.10 * *Line 4; TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened EVALUATOR NOTE TQ-106-lJ;:)
+* Line 2; System number 133 and system name Turbine Building Chilled Water System
-Revision 1 Page 4 of 9 Due to the nature of this JPM, the information provided by the candidate in the next 2 steps may vary from the information scripted in the STANDARD column. Evaluator judgment may need to be applied to information provided by the candidate.
+                                                             * *Line 3; Procedure number OP-133-001, Revision 37, step 2.5.10
-Completes OP-AD-002 Att B cont'd
+                                                              *  *Line  4; TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened
-* Line 5, NONE S/U
+TQ-106-lJ;:) 10 Revision 1 Page 4 of 9 EVALUATOR NOTE Due to the nature of this JPM, the information provided by the candidate in the next 2 steps may vary from the information scripted in the STANDARD column. Evaluator judgment may need to be applied to information provided by the candidate.
+   Completes OP-AD-002 Att B cont'd
+* Line 5, NONE                               S/U
 * Line 6, notes to resume procedure OP-133-001 beginning at step 2.5.10
-* Line 7, Left Blank *6 Documents and communicates AECL data
+* Line 7, Left Blank
-* Each AECL activity shall be referenced S/U on the Turnover Sheet of the Operator performing the evolution and be reviewed as part of the Turnover process until such time as the AECL is no longer required, or in control * *Informs Turbine building NPO of Administrative requirements for the aborted evolution.
+  *6    Documents and communicates AECL data
-Reference the aborted evolution IAW the AECL form And 0 Review the AECL as part of the turnover to the oncoming shift EVALUATOR CUE Role-play as Turbine building NPO acknowledge the report *7 Notifies Unit Supervisor Informs Unit Supervisor to:
+* Each AECL activity shall be referenced      S/U on the Turnover Sheet of the Operator performing the evolution and be reviewed as part of the Turnover process until such time as the AECL is no longer required, or in control
+                                                               *   *Informs Turbine building NPO of Administrative requirements for the aborted evolution.
+   Reference the aborted evolution IAW the AECL form And 0   Review the AECL as part of the turnover to the oncoming shift EVALUATOR CUE Role-play as Turbine building NPO acknowledge the report
+  *7    Notifies Unit Supervisor                               Informs Unit Supervisor to:
 * Reference the aborted evolution IAW the AECL form S/U AND
-* Review the AECL as part of the turnover to the oncoming shift EVALUATOR CUE Role-play as Turbine building NPO acknowledge the report 8 Identifies requirement to log the equipment failure Informs Unit 1 Control room Supervisor to: in the shift log and initiate a Condition Report.
+* Review the AECL as part of the turnover to the oncoming shift EVALUATOR CUE Role-play as Turbine building NPO acknowledge the report
-* a Narrative Log entry must be made a Condition Report must be initiated EVALUATOR NOTE I CUE Role-play as Unit Supervisor acknowledge the report EVALUATOR CUE Record JPM stop time: EVALUATOR CUE That completes the JPM. EVALUATOR NOTE Do you have ALL your JPM exam materials?
-Task Cue Sheets? Procedures?
+TQ-106-D-;j 10 Revision 1 Page 5 of 9 8      Identifies requirement to log the equipment failure Informs Unit 1 Control room Supervisor to:
-S/U TQ-106-D-;j 10 Revision 1 Page 5 of 9 REVISION
+in the shift log and initiate a Condition Report.
+* a Narrative Log entry must be made       S/U a Condition Report must be initiated EVALUATOR NOTE I CUE Role-play as Unit Supervisor acknowledge the report EVALUATOR CUE Record JPM stop time:
+EVALUATOR CUE That completes the JPM.
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 7 of 9 REVISION
 ==SUMMARY==
-* JOB PERFORMANCE MEASURE OO.AD.21017.001 Revision Description/Purpose of Revision 0 New JPM, Replaced OO.AD.038.001 TQ-106-0310 Revision 1 Page 7 of 9 EVALUATOR COPY: TASK CONDITIONS Unit 1 is in Mode 1 All Plant Equipment required for Mode 1 is in operation Turbine Building Chilled Water System in Service Page 8 of 9 The Turbine building NPO is performing a Chemical Addition to Turbine Building Chilled Water System IAW OP-133-001 Section 2.5. During step 2.5.10 TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened. Maintenance will not be available until dayshift tomorrow to support opening the 188003 valve. You are the Unit 1 PCOM INITIATING CUE Your Supervisor directs you complete the necessary administrative documentation to turn this information over to the on-coming shift.
+* JOB PERFORMANCE MEASURE OO.AD.21017.001 Revision                    Description/Purpose of Revision 0    New JPM, Replaced OO.AD.038.001
-EXAMINEE COPY: TASK CONDITIONS Unit 1 is in Mode 1 All Plant Equipment required for Mode 1 is in operation Turbine Building Chilled Water System in Service Page 9 of 9 The Turbine building NPO is performing a Chemical Addition to Turbine Building Chilled Water System IAW OP-133-001 Section 2.5. During step 2.5.10 TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened. Maintenance will not be available until dayshift tomorrow to support opening the 188003 valve. You are the Unit 1 PCOM INITIATING CUE Your Supervisor directs you complete the necessary administrative documentation to turn this information over to the on-coming shift.
-SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Perform Validation of Heat Balance at 90% Power JPM#: OO.AD.20927.101 Revision:
+Page 8 of 9 EVALUATOR COPY:
-O Date: 9/25/2016
+TASK CONDITIONS Unit 1 is in Mode 1 All Plant Equipment required for Mode 1 is in operation Turbine Building Chilled Water System in Service The Turbine building NPO is performing a Chemical Addition to Turbine Building Chilled Water System IAW OP-133-001 Section 2.5.
------Applicability:
+During step 2.5.10 TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened. Maintenance will not be available until dayshift tomorrow to support opening the 188003 valve.
-Setting: Classroom NUREG-1123 E/APE I Sys_G-=-----
+You are the Unit 1 PCOM INITIATING CUE Your Supervisor directs you complete the necessary administrative documentation to turn this information over to the on-coming shift.
-KIA Number_2_._1_.7
-___ K/A Importance
+Page 9 of 9 EXAMINEE COPY:
-_4..;..;'.;...7
+TASK CONDITIONS Unit 1 is in Mode 1 All Plant Equipment required for Mode 1 is in operation Turbine Building Chilled Water System in Service The Turbine building NPO is performing a Chemical Addition to Turbine Building Chilled Water System IAW OP-133-001 Section 2.5.
-__ _ Alternate Path: DYES NO Time Critical DYES NO Validation Time (min):__..;;;2=5
+During step 2.5.10 TB Chilled Wtr Chem Add Tank In valve 188003 could not be opened. Maintenance will not be available until dayshift tomorrow to support opening the 188003 valve.
-__ q(l?(/J 1 /z_(, bl, / 'f /J=.f / It Approval:
+You are the Unit 1 PCOM INITIATING CUE Your Supervisor directs you complete the necessary administrative documentation to turn this information over to the on-coming shift.
-__ ru ___ l .....
-.............
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Perform Validation of Heat Balance at 90% Power JPM#: OO.AD.20927.101                            Revision:   O            Date:    9/25/2016
-----Date: Cf* l7* lb Nuclear Training Supervisor Examinee Name:
+                                                            -----
-Last, First Ml Employee Number Exam Date: ________ _ Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+Applicability: ~SRO Setting: Classroom NUREG-1123 E/APE I Sys_G-=----- KIA Number_2_._1_.7_ _ _K/A Importance _4..;..;'.;...7_ __
-__________
+Alternate Path:  DYES    ~ NO                 Time Critical DYES   ~ NO       Validation Time (min):__..;;;2=5_ _
-_ Name Signature Comments:
+q(l?(/J 1 /z_(, bl,
+                                                                             /
+                                                                 'f /J=.f / It Approval: _ _   ru
+___l.....;j"""'--~
+                                . . . . . . .- - - - Date:
+Nuclear Training Supervisor Cf* l7* lb Examinee Name:
+                  ~-----------------
+Last, First Ml                                                       Employee Number Exam Date: _ _ _ _ _ _ _ __                               Exam Duration (Min): _ _ _ _ _ _ _ __
+Evaluation Result:   D   Satisfactory            D  Unsatisfactory Evaluator: _ _ _ _ _ _ _ _ _ __
+Name                                                Signature Comments:
 REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.20927.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
 C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
 D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
-II. REFERENCES A. RE-1 TP-026, VALIDA TI ON OF CORE THERMAL POWER HEAT BALANCE (REV 12) III. TASK CONDITIONS
+II. REFERENCES A. RE-1 TP-026, VALIDATION OF CORE THERMAL POWER HEAT BALANCE (REV 12)
-: 1. A plant startup is in progress on Unit 1. 2. APRMs indicate as follows: #1 -89.9%, #2 -90.1%, #3 -92.2%, and #4 -90.3%. 3. % Core Thermal Power (OD-3) is 90%. 4. LPRM arithmetic average from Pl is 46.5. 5. All LPRMs used in the arithmetic average are valid. 6. HPTE pressure at entrance of the A Moisture Seperator (TEP02) is 187 psig. 7. HPTE pressure at entrance of the B Moisture Seperator (TEP03) is 188 psig. 8. Computer Point NBA14 is 93.026 %PWR. 9. Computer Point NBA 15 is 93.329 %PWR. 10. Computer Point NBA16 is 94.7 %PWR. 11. Computer Point NBA17 is 93.16. 12. Computer Point NFA50 is 15.5011 MLBS/H. IV. INITIATING CUE Perform RE-1TP-026, Validation of Heat Balance. Determine what action, if any, is required.
+III. TASK CONDITIONS
-Document conclusions, as necessary, on this cue sheet. V. TASK STANDARD Completes RE-1TP-026, determines the Heat Balance cannot be validated, and contacts STA and Reactor Engineering to perform RE-1TP-026 Attachment C.
+: 1. A plant startup is in progress on Unit 1.
-INFORMATION FOR EVALUATOR
+: 2. APRMs indicate as follows: #1 - 89.9%, #2 - 90.1%, #3 - 92.2%, and #4 - 90.3%.
-* Marking a step as UNSAT requires written comments on respective step. TQ-106-us1 o Revision 1 Page 3 of 10
+: 3.     % Core Thermal Power (OD-3) is 90%.
+: 4. LPRM arithmetic average from Pl is 46.5.
+: 5. All LPRMs used in the arithmetic average are valid.
+: 6. HPTE pressure at entrance of the A Moisture Seperator (TEP02) is 187 psig.
+: 7. HPTE pressure at entrance of the B Moisture Seperator (TEP03) is 188 psig.
+: 8. Computer Point NBA14 is 93.026 %PWR.
+: 9. Computer Point NBA 15 is 93.329 %PWR.
+: 10. Computer Point NBA16 is 94.7 %PWR.
+: 11. Computer Point NBA17 is 93.16.
+: 12. Computer Point NFA50 is 15.5011 MLBS/H.
+IV. INITIATING CUE Perform RE-1TP-026, Validation of Heat Balance. Determine what action, if any, is required.
+Document conclusions, as necessary, on this cue sheet.
+V. TASK STANDARD Completes RE-1TP-026, determines the Heat Balance cannot be validated, and contacts STA and Reactor Engineering to perform RE-1TP-026 Attachment C.
+TQ-106-us1 o Revision 1 Page 3 of 10 INFORMATION FOR EVALUATOR
+* Marking a step as UNSAT requires written comments on respective step.
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
 * The time clock starts when the candidate acknowledges the initiating cue.
-* Ensure the following material is available to support this JPM; RE-1TP-026 and a calculator . EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Obtain a controlled copy of RE-1 TP-026 Controlled copy obtained from evaluator sru 2 Selects correct procedure section(s).
+* Ensure the following material is available to support this JPM; RE-1TP-026 and a calculator.
-Determines section 4.2 and Attachment B S/U applies 3* Record the % CTP as determined by Heat Balance Records the % CTP on Attachment B step (i.e., OD-3) on Attachment B. 4.2.1 as 90 S/U 4 Validate % CTP based on HPTE pressure to the A Records the HPTE pressure at entrance of Moisture Separator.
+EVALUATOR CUE Record JPM start time:
-the A moisture separator (Computer Point TEP02) on Attachment B step 4.2.2.a as 187 SIU Record the HPTE pressure at entrance of the A moisture separator (Computer Point TEP02) on Attachment B. 5 Plot Computer Point TEP02 and % CTP (Step Plots Computer Point TEP02 and % CTP 4.2.1) on Attachment G "High Pressure Turbine (Step 4.2.1) on Attachment G "High S/U Exhaust vs. Heat Balance % Power." Pressure Turbine Exhaust vs. Heat Balance % Power." 6 Record Computer Point NBA 14 (Alternate
+Step   Action                                                 Standard                                          Eva I  Comments 1   Obtain a controlled copy of RE-1 TP-026                Controlled copy obtained from evaluator           sru 2   Selects correct procedure section(s).                  Determines section 4.2 and Attachment B S/U applies 3*   Record the % CTP as determined by Heat Balance         Records the % CTP on Attachment B step 4.2.1 as 90                                       S/U (i.e., OD-3) on Attachment B.
-% CTP) Records Computer Point NBA14 (Alternate on Attachment B. % CTP) on Attachment B step 4.2.2.c as SIU 93.026.
+  Validate % CTP based on HPTE pressure to the A         Records the HPTE pressure at entrance of Moisture Separator.                                    the A moisture separator (Computer Point TEP02) on Attachment B step 4.2.2.a as 187                                               SIU Record the HPTE pressure at entrance of the A moisture separator (Computer Point TEP02) on Attachment B.
-* Confirm that the plotted point is within the valid region OR % CTP is within +/- 2% of the Computer Point NBA14 Attachment B. 8 Validate % CTP based on HPTE pressure to the B Moisture Separator.
+  Plot Computer Point TEP02 and % CTP (Step              Plots Computer Point TEP02 and % CTP 4.2.1) on Attachment G "High Pressure Turbine          (Step 4.2.1) on Attachment G "High S/U Exhaust vs. Heat Balance % Power."                     Pressure Turbine Exhaust vs. Heat Balance
-Record the HPTE pressure at entrance of the B moisture separator (Computer Point TEP03) on Attachment B. 9 Plot Computer Point TEP03 and % CTP (Step 4.2.1) on Attachment G "High Pressure Turbine Exhaust vs. Heat Balance % Power. 10 Record Computer Point NBA 15 (Alternate
+                                                               % Power."
-% CTP) on Attachment B. 11* Confirm that the plotted point is within the valid region OR % CTP is within +/- 2% of the Computer Point NBA 15. Record on Attachment B. Determines that the plotted point for HPTE pressure to the A Moisture Separator is NOT within valid region. Determines that % CTP is NOT within +/- 2% of Computer Point NBA14. Records the HPTE pressure at entrance of the B moisture separator (Computer Point TEP03) on Attachment B step 4.2.3.a as 188. Plots Computer Point TEP03 and % CTP (Step 4.2.1) on Attachment G "High Pressure Turbine Exhaust vs. Heat Balance % Power. Records Computer Point NBA 15 (Alternate
+  Record Computer Point NBA 14 (Alternate % CTP)         Records Computer Point NBA14 (Alternate on Attachment B.                                       % CTP) on Attachment B step 4.2.2.c as            SIU 93.026.
-% CTP) on Attachment B step 4.2.3.c as 93.329. Determines that the plotted point for HPTE pressure to the B Moisture Separator is NOT within valid region. Determines that % CTP is NOT within +/- 2% of Computer Point NBA 15. S/U S/U S/U S/U S/U TQ-106-us1 o Revision 1 Page 4of10 12 Validate % CTP based on LPRM average. Indicates need to obtain LPRM current readings, identify non-valid LPRMs, and Obtain a printout of the current LPRM readings calculate arithmetic average of the valid LPRMs SIU (OD-8). Identify non-valid LPRMs. EVALUATOR NOTE If the candidate indicates the need to obtain printout of LPRM readings and calculate the arithmetic average of the valid LPRMs, tell her I him to use the value obtained from the Pl program. 13 Record arithmetic average of the valid LPRM values Records arithmetic average of the valid (Pl program may be used to obtain the LPRM LPRM values (Pl program is not available)
-S/U average) on Attachment B. on Attachment B step 4.2.4.c as 46.5. 14 Plot the LPRM arithmetic average and % CTP (Step Plots the LPRM arithmetic average and % 4.2.1) on Attachment F "LPRM Average vs. % CTP (Step 4.2.1) on Attachment F "LPRM S/U Power (Heat Balance)." Average vs.% Power (Heat Balance)." 15 Record Computer Point NBA17 (Alternate%
+TQ-106-us1 o Revision 1 Page 4of10 7* Confirm that the plotted point is within the valid Determines that the plotted point for HPTE region OR % CTP is within +/- 2% of the Computer     pressure to the A Moisture Separator is NOT Point NBA14 Attachment B.                          within valid region.
-CTP) Records Computer Point NBA 17 (Alternate on Attachment B. % CTP) on Attachment B step 4.2.4.e as S/U 93.16. 16* Confirm that the plotted point is within the valid Determines that the plotted point for LPRM region OR % CTP is within +/- 2% of the Computer arithmetic average is NOT within valid Point NBA17. Record on Attachment B region. S/U Determines that % CTP is NOT within +/- 2% of Computer Point NBA17. 17 Attach copy of LPRM readings to Attachment B Indicates need to attach copy of LPRM S/U readings to Attachment B EVALUATOR NOTE If the candidate indicates the need to obtain printout of LPRM readings and attach to Attachment B, tell her I him that another operator will attach the LPRM readings once the Attachment B is complete.
+S/U Determines that % CTP is NOT within +/- 2%
-TQ-106-lJ,j 10 Revision 1 Page 5 of 10 18 Validate % CTP based on Feedwater Flows. Records Feedwater Flow (Computer Point NFA50) on Attachment B step 4.2.5.a as 15.5011. Record Feedwater Flow (Computer Point NFA50) on Attachment B. 19 Plot Computer Point NFA50 and% CTP (Step Plots Computer Point NFA50 and% CTP 4.2.1) on Attachment H "Feedwater Flow vs. % (Step 4.2.1) on Attachment H "Feedwater Power (Heat Balance)." Flow vs.% Power (Heat Balance)." 20 Record Computer Point NBA16 (Alternate%
+of Computer Point NBA14.
-CTP) Records Computer Point NBA 16 (Alternate on Attachment B. % CTP) on Attachment B step 4.2.5.c as 94.7. 21* Confirm that the plotted point is within the valid Determines that the plotted point for FW region OR % CTP is within +/- 2% of the Computer Flow is NOT within valid region. Point NBA16. Record on Attachment B. Determines that % CTP is NOT within +/- 2% of Computer Point NBA 16. 22* Confirm that the Heat Balance is within the valid Determines that the Heat Balance is NOT regions of any one of the previous four methods (+/- valid for any of the four methods. 2% CTP from OD-3). Record on Attachment B. 23* IF the Heat Balance cannot be validated, Contact Indicates need to contact Reactor Reactor Engineering and the STA to perform Engineering and/or STA to perform Attachment C. Attachment C. EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials?
+Validate % CTP based on HPTE pressure to the B     Records the HPTE pressure at entrance of Moisture Separator.                                the B moisture separator (Computer Point TEP03) on Attachment B step 4.2.3.a as 188.                                        S/U Record the HPTE pressure at entrance of the B moisture separator (Computer Point TEP03) on Attachment B.
-Task Cue Sheets? Procedures?
+Plot Computer Point TEP03 and % CTP (Step          Plots Computer Point TEP03 and % CTP 4.2.1) on Attachment G "High Pressure Turbine      (Step 4.2.1) on Attachment G "High S/U Exhaust vs. Heat Balance % Power.                  Pressure Turbine Exhaust vs. Heat Balance
-S/U S/U S/U S/U S/U S/U Revision 1 Page 6of10 REVISION
+                                                       % Power.
+Record Computer Point NBA 15 (Alternate % CTP)     Records Computer Point NBA 15 (Alternate on Attachment B.                                   % CTP) on Attachment B step 4.2.3.c as      S/U 93.329.
+* Confirm that the plotted point is within the valid Determines that the plotted point for HPTE region OR % CTP is within +/- 2% of the Computer     pressure to the B Moisture Separator is NOT Point NBA 15. Record on Attachment B.              within valid region.
+S/U Determines that % CTP is NOT within +/- 2%
+of Computer Point NBA 15.
+TQ-106-lJ,j 10 Revision 1 Page 5 of 10 12   Validate % CTP based on LPRM average.                 Indicates need to obtain LPRM current readings, identify non-valid LPRMs, and calculate arithmetic average of the valid Obtain a printout of the current LPRM readings        LPRMs                                           SIU (OD-8).
+Identify non-valid LPRMs.
+EVALUATOR NOTE If the candidate indicates the need to obtain printout of LPRM readings and calculate the arithmetic average of the valid LPRMs, tell her I him to use the value obtained from the Pl program.
+  Record arithmetic average of the valid LPRM values    Records arithmetic average of the valid (Pl program may be used to obtain the LPRM            LPRM values (Pl program is not available)        S/U average) on Attachment B.                             on Attachment B step 4.2.4.c as 46.5.
+  Plot the LPRM arithmetic average and % CTP (Step      Plots the LPRM arithmetic average and %
+.2.1) on Attachment F "LPRM Average vs. %            CTP (Step 4.2.1) on Attachment F "LPRM           S/U Power (Heat Balance)."                                Average vs.% Power (Heat Balance)."
+  Record Computer Point NBA17 (Alternate% CTP)          Records Computer Point NBA 17 (Alternate on Attachment B.                                      % CTP) on Attachment B step 4.2.4.e as           S/U 93.16.
+*   Confirm that the plotted point is within the valid    Determines that the plotted point for LPRM region OR % CTP is within +/- 2% of the Computer        arithmetic average is NOT within valid Point NBA17. Record on Attachment B                   region.
+S/U Determines that % CTP is NOT within +/- 2%
+of Computer Point NBA17.
+  Attach copy of LPRM readings to Attachment B           Indicates need to attach copy of LPRM S/U readings to Attachment B EVALUATOR NOTE If the candidate indicates the need to obtain printout of LPRM readings and attach to Attachment B, tell her I him that another operator will attach the LPRM readings once the Attachment B is complete.
+TQ-106-tJ~10 Revision 1 Page 6of10 18   Validate % CTP based on Feedwater Flows.           Records Feedwater Flow (Computer Point NFA50) on Attachment B step 4.2.5.a as 15.5011.                                 S/U Record Feedwater Flow (Computer Point NFA50) on Attachment B.
+  Plot Computer Point NFA50 and% CTP (Step           Plots Computer Point NFA50 and% CTP 4.2.1) on Attachment H "Feedwater Flow vs. %       (Step 4.2.1) on Attachment H "Feedwater  S/U Power (Heat Balance)."                             Flow vs.% Power (Heat Balance)."
+  Record Computer Point NBA16 (Alternate% CTP)       Records Computer Point NBA 16 (Alternate on Attachment B.                                   % CTP) on Attachment B step 4.2.5.c as   S/U 94.7.
+*   Confirm that the plotted point is within the valid Determines that the plotted point for FW region OR % CTP is within +/- 2% of the Computer     Flow is NOT within valid region.
+Point NBA16. Record on Attachment B.                                                        S/U Determines that % CTP is NOT within +/- 2%
+of Computer Point NBA 16.
+*   Confirm that the Heat Balance is within the valid  Determines that the Heat Balance is NOT regions of any one of the previous four methods (+/- valid for any of the four methods.       S/U 2% CTP from OD-3). Record on Attachment B.
+*   IF the Heat Balance cannot be validated, Contact   Indicates need to contact Reactor Reactor Engineering and the STA to perform         Engineering and/or STA to perform        S/U Attachment C.                                      Attachment C.
+EVALUATOR NOTE I CUE That completes the JPM.
+EVALUATOR CUE Record JPM stop time:
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 8of10 REVISION
 ==SUMMARY==
-JOB PERFORMANCE MEASURE OO.AD.20927.101 Revision Description/Purpose of Revision 0 New JPM, from OO.AD.3658.101 TQ-106-0310 Revision 1 Page 8of10 Page 9 of 10 EVALUATOR COPY: TASK CONDITIONS
-: 1. A plant startup is in progress on Unit I. 2. APRMs indicate as follows: #1 -89.9%, #2 -90.l %, #3 -92.2%, and #4 -90.3%. 3. % Core Thermal Power (OD-3) is 90%. 4. LPRM arithmetic average from Pl is 46.5. 5. All LPRMs used in the arithmetic average are valid. 6. HPTE pressure at entrance of the A Moisture Seperator (TEP02) is 187 psig. 7. HPTE pressure at entrance of the B Moisture Seperator (TEP03) is 188 psig. 8. Computer Point NBA14 is 93.026 %PWR. 9. Computer Point NBA15 is 93.329 %PWR. 10. Computer Point NBA16 is 94.7 %PWR. 11. Computer Point NBAl 7 is 93.16. 12. Computer Point NF A50 is 15.5011 MLBS/H. INITIATING CUE Perform RE-1 TP-026, Validation of Heat Balance. Determine what action, if any, is required.
+JOB PERFORMANCE MEASURE OO.AD.20927.101 Revision                    Description/Purpose of Revision 0    New JPM, from OO.AD.3658.101
+Page 9 of 10 EVALUATOR COPY:
+TASK CONDITIONS
+: 1. A plant startup is in progress on Unit I.
+: 2. APRMs indicate as follows: #1 - 89.9%, #2 - 90.l %, #3 - 92.2%, and #4 - 90.3%.
+: 3.     % Core Thermal Power (OD-3) is 90%.
+: 4. LPRM arithmetic average from Pl is 46.5.
+: 5. All LPRMs used in the arithmetic average are valid.
+: 6. HPTE pressure at entrance of the A Moisture Seperator (TEP02) is 187 psig.
+: 7. HPTE pressure at entrance of the B Moisture Seperator (TEP03) is 188 psig.
+: 8. Computer Point NBA14 is 93.026 %PWR.
+: 9. Computer Point NBA15 is 93.329 %PWR.
+: 10. Computer Point NBA16 is 94.7 %PWR.
+: 11. Computer Point NBAl 7 is 93.16.
+: 12. Computer Point NF A50 is 15.5011 MLBS/H.
+INITIATING CUE Perform RE-1 TP-026, Validation of Heat Balance. Determine what action, if any, is required.
 Document conclusions, as necessary, on this cue sheet.
-Page 10of10 EXAMINEE COPY: TASK CONDITIONS
-: 1. A plant startup is in progress on Unit 1. 2. APRMs indicate as follows: #1 -89.9%, #2 -90.1 %, #3 -92.2%, and #4 -90.3%. 3. % Core Thermal Power (OD-3) is 90%. 4. LPRM arithmetic average from PI is 46.5. 5. All LPRMs used in the arithmetic average are valid. 6. HPTE pressure at entrance of the A Moisture Seperator (TEP02) is 187 psig. 7. HPTE pressure at entrance of the B Moisture Seperator (TEP03) is 188 psig. 8. Computer Point NBA14 is 93.026 %PWR. 9. Computer Point NBA15 is 93.329 %PWR. 10. Computer Point NBAl 6 is 94. 7 %PWR. 11. Computer Point NBAl 7 is 93.16. 12. Computer Point NF A50 is 15.5011 MLBS/H. INITIATING CUE Perform RE-1 TP-026, Validation of Heat Balance. Determine what action, if any, is required.
+Page 10of10 EXAMINEE COPY:
+TASK CONDITIONS
+: 1. A plant startup is in progress on Unit 1.
+: 2. APRMs indicate as follows: #1 - 89.9%, #2 - 90.1 %, #3 - 92.2%, and #4 - 90.3%.
+: 3.     % Core Thermal Power (OD-3) is 90%.
+: 4. LPRM arithmetic average from PI is 46.5.
+: 5. All LPRMs used in the arithmetic average are valid.
+: 6. HPTE pressure at entrance of the A Moisture Seperator (TEP02) is 187 psig.
+: 7. HPTE pressure at entrance of the B Moisture Seperator (TEP03) is 188 psig.
+: 8. Computer Point NBA14 is 93.026 %PWR.
+: 9. Computer Point NBA15 is 93.329 %PWR.
+: 10. Computer Point NBAl 6 is 94. 7 %PWR.
+: 11. Computer Point NBAl 7 is 93.16.
+: 12. Computer Point NFA50 is 15.5011 MLBS/H.
+INITIATING CUE Perform RE-1 TP-026, Validation of Heat Balance. Determine what action, if any, is required.
 Document conclusions, as necessary, on this cue sheet.
-SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Perform LPRM Upscale Alarm Operability Tracking & Determine Required Actions JPM#: OO.AD.20958.101 Revision:
-Date: 09/26/2016
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title:   Perform LPRM Upscale Alarm Operability Tracking & Determine Required Actions JPM#: OO.AD.20958.101                  Revision: 0
---------Applicability:
+                                                -------- Date:    09/26/2016 Applicability: [8] RO [8] SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic KIA Number_2_._2._14          _ _ _ K/A Importance 3.9/4.3 Alternate Path:    0 YES [8] NO        Time Critical DYES [8] NO Validation Time (min):_4'"""'5"---_
-[8] RO [8] SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic KIA Number_2_._2._14
+Date:   crb-1L1t Operations   Re~:            _/                     Date:   z/c~ !_,~,_
-___ K/A Importance 3.9/4.3 Alternate Path: 0 YES [8] NO Time Critical DYES [8] NO Validation Time (min):_4'"""'5"---_
+validated:     .,!CJ_Cf~                             Date: &deg;t/%(/t Approval:       lV\ Lr::J ~                         Date:   &deg;J-:L&deg;f*l&-
-Date: crb-1L1t Operations
+Nuclear TraininQUPervisor Last, First Ml                                        Employee Number Exam Date:                                         Exam Duration (Min): ________________
-_ / validated:
+             ---------------
-.,!CJ_Cf Date:
+Evaluation Result:     D Satisfactory     D Unsatisfactory Evaluator:
-Date: &deg;t/%(/t Approval:
+           ------------------
-lV\ Lr::J Nuclear TraininQUPervisor Date: &deg;J-:L&deg;f*l&-
+Name                                        Signature Comments:
-Last, First Ml Employee Number Exam Date: ---------------
-Exam Duration (Min): _______________
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.20958.101 I. SAFETY CONSIDERATIONS A       All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-_ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+B.      All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
-------------------
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
-Name Signature Comments:
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.20958.101 I. SAFETY CONSIDERATIONS A All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+C.      If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+D.      Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+II. REFERENCES A       01-078-001, LPRM Status Control Rev. 18 B. S0-100-008, Weekly Surveillance Operating Log Rev. 33 C.      Technical Specification 3.3.1.1 Rev. 3 Ill. TASK CONDITIONS Unit 1 is in MODE 1 at 80 percent power.
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+APRM 2 is INOP and bypassed.
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+APRM Gain Calibration was last performed 5 days ago.
-II. REFERENCES A 01-078-001, LPRM Status Control Rev. 18 B. S0-100-008, Weekly Surveillance Operating Log Rev. 33 C. Technical Specification 3.3.1.1 Rev. 3 Ill. TASK CONDITIONS Unit 1 is in MODE 1 at 80 percent power. APRM 2 is INOP and bypassed.
+LPRM detector 40-57A caused a downscale alarm l&C determined the detector failed. Reactor Engineering requested bypassing the detector.
-APRM Gain Calibration was last performed 5 days ago. LPRM detector 40-57 A caused a downscale alarm l&C determined the detector failed. Reactor Engineering requested bypassing the detector.
+The PCOP has just bypassed LPRM detector 40-57A in the Lower Relay Room.
-The PCOP has just bypassed LPRM detector 40-57 A in the Lower Relay Room. IV. INITIATING CUE Perform LPRM Upscale Alarm operability tracking for LPRM detector 40-57 A in accordance with 01-078-001.
+IV. INITIATING CUE Perform LPRM Upscale Alarm operability tracking for LPRM detector 40-57A in accordance with 01-078-001.
 SRO Only Determine the required action(s) based on your findings V. TASK STANDARD For RO and SRO: Zone 8 is identified as having LESS THAN 50% upscale alarms operable.
-APRM Channel 1 determined to be INOPERABLE based on < 3 operable LPRM inputs to the "A" Level. For SROs only: Determine that LCO 3.3.3.1 IS NOT MET for APRM required channels, and TS action A.1 is required; place channel in trip within 12.
+APRM Channel 1 determined to be INOPERABLE based on < 3 operable LPRM inputs to the "A" Level.
-INFORMATION FOR EVALUATOR
+For SROs only: Determine that LCO 3.3.3.1 IS NOT MET for APRM required channels, and TS action A.1 is required; place channel in trip within 12.
+TQ-106-u~10 Revision 1 Page 3 of 12 INFORMATION FOR EVALUATOR
 * Marking a step as UNSAT requires written comments on respective step.
-Revision 1 Page 3 of 12
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
 * The time clock starts when the candidate acknowledges the initiating cue.
 * This JPM can be performed in the classroom.
-* Provide a clean copy of 01-078-001.
+* Provide a clean copy of 01-078-001. Additionally, markup copies of Attachments A, B and C with LPRM status. Have a clean copy and SO-100-008.
-Additionally, markup copies of Attachments A, B and C with LPRM status. Have a clean copy and SO-100-008. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OI-078-001, S/U controlled copy. Section 4. 2 Determine current LPRM status Refers to the previously completed copy of S/U Attachments A and B 3 Complete new Attachment A Performs the following
+EVALUATOR CUE Record JPM start time:
-* Enters 1 for Unit S/U
+Step   Action                                                Standard                                           Eva I  Comments 1   Identifies governing procedure and obtain             Obtains controlled copy of OI-078-001, S/U controlled copy.                                      Section 4.
-* Transfers the previous LPRM data to the new Attachment A *4 Enter a check ('1) in column (2) for LPRM alarms Places a checkmark in column 2 adjacent to determined inoperable or bypassed for all other LPRM detector 40-57A in Zone 8 S/U reasons. EVALUATOR NOTE All LPRM Upscale Alarms with a check in column (1) or (2) of Attachment A are inoperable.
+  Determine current LPRM status                         Refers to the previously completed copy of S/U Attachments A and B 3   Complete new Attachment A                             Performs the following
-*5 Determine ofLPRM Upscale alarms in each zone are operable and circle YES or NO as applicable 6 Notify Reactor Engineering of all LPRM upscale alarms determined inoperable 7 Evaluate the need to place placard to 1 C651 indicating
+* Enters 1 for Unit                                S/U
-< required # of LPRM Upscale Alarms. (requires completion of Attachments C & D, which appears in Step 11, below.) *8 Complete an LPRM vs. APRM Status Control Log (Attachment B) each time LPRM operability status is changed. Performs the following
+* Transfers the previous LPRM data to the new Attachment A
-* Circles YES for zone 1, 2, 3, 4, 5, 6, 7, and9
+   *4   Enter a check ('1) in column (2) for LPRM alarms      Places a checkmark in column 2 adjacent to determined inoperable or bypassed for all other       LPRM detector 40-57A in Zone 8                     S/U reasons.
-* Determines that there are LESS THAN 50% operable LPRMs in zone 8, AND circles NO for zone 8. Identifies Reactor Engineering previously informed ofLPRM 40-57A status as stated in JPM task conditions.
+EVALUATOR NOTE All LPRM Upscale Alarms with a check in column (1) or (2) of Attachment A are inoperable.
-Determines that placard is required.
-Performs the following
+TQ-106-Q;y10 Revision 1 Page 4of12
-* Transfer the previous LPRM data to the new Attachment B
+*5 Determine if~50% ofLPRM Upscale alarms in        Performs the following each zone are operable and circle YES or NO as
-* Circle LPRM detector 40-57 A for APRM 1, under the column 'A' Level, and enter today's date S/U SIU S/U SIU TQ-106-Q;y10 Revision 1 Page 4of12
+* Circles YES for zone 1, 2, 3, 4, 5, 6, 7, applicable                                           and9 S/U
-*9 Refer to weekly surveillance S0-100-008 to confirm APRM operability requirements maintained
+* Determines that there are LESS THAN 50% operable LPRMs in zone 8, AND circles NO for zone 8.
--*10 Track operability of OPRM cells. Compare the following criteria to current APRM/LPRM operability status: * < 20 total operable LPRMs per APRM channel * <3 LPRM inputs per level (A, B, C, or D) * :S 9 LPRMs inop since last APRM gain calibration (after date in task conditions)
+Notify Reactor Engineering of all LPRM upscale   Identifies Reactor Engineering previously alarms determined inoperable                     informed ofLPRM 40-57A status as stated     SIU in JPM task conditions.
-* *Determine that APRM channel 1 does NOT meet operability requirements due to LESS THAN 3 operable level "A" LPRMs. (The only operable Level A LPRMs in APRM 1 are 40-17 A and 08-49A) Performs the following
+Evaluate the need to place placard to 1C651      Determines that placard is required.
+indicating < required # of LPRM Upscale Alarms.
+S/U (requires completion of Attachments C & D, which appears in Step 11, below.)
+*8 Complete an LPRM vs. APRM Status Control Log     Performs the following (Attachment B) each time LPRM operability status
+* Transfer the previous LPRM data to the is changed.                                          new Attachment B SIU
+* Circle LPRM detector 40-57 A for APRM 1, under the column 'A' Level, and enter today's date
+TQ-106-lJ;j 10 Revision 1 Page 5 of 12
+  *9 Refer to weekly surveillance S0-100-008 to       Compare the following criteria to current confirm APRM operability requirements maintained APRM/LPRM operability status:
+                                                     * < 20 total operable LPRMs per APRM channel
+                                                     * <3 LPRM inputs per level (A, B, C, or D)
+* 9 LPRMs inop since last APRM gain
+:S calibration (after date provide~ in task S/U conditions)
+                                                     * *Determine that APRM channel 1 does
+                                        -               NOT meet operability requirements due to LESS THAN 3 operable level "A" LPRMs. (The only operable Level A LPRMs in APRM 1 are 40-17A and 08-49A)
+*10 Track operability of OPRM cells.                 Performs the following
 * Transfers the previous LPRM data to the new Attachment C and circles "A LEVEL" for LPRM 40-57.
 * Determines it inputs to APRMl Cell 03 .
-* Transfers the previous LPRM data to the new Attachment D and circles LPRM 40-57 A in the Cell 03 row, in the LPRM#2 column.
+* Transfers the previous LPRM data to the new Attachment D and circles LPRM S/U 40-57A in the Cell 03 row, in the LPRM#2 column.
 * Determines OPRM cell is INOPERABLE due fewer than two operable LPRMs.
-* Determines OPRM is OPERABLE due to having 22 or more OPERABLE cells S/U S/U TQ-106-lJ;j 10 Revision 1 Page 5 of 12 EVALUATOR CUE For RO examinees, this completes the JPM EVALUATOR CUE For SRO examinee, provide the SRO examinee sheet that addresses determining required actions *11 Identifies Tech Spec 3.3.1.1 for RPS Performs the following:
+* Determines OPRM is OPERABLE due to having 22 or more OPERABLE cells
-Instrumentation and TR 3.1.3 for Control Rod Block * *Refer to Tech Spec 3.3.1.1 and Instrumentation is not met. determine that a minimum of 3 operable APRM channels are required in MODE 1 per table 3 .3 .1.1-1, therefore action A. l is required; place channel in trip within 12 hours. * *Refer to TRM 3 .1.3 and determine that a minimum of 3 operable APRM channels are required in MODE 1 per table 3.1.3-1, therefore action B.2 is required; place 1 channel in tripped condition within 7 days.
-* Refer to TRM 3.3.9 and determine that a placard will have to be posted at 1 C651 indicating less than required number of LPRM upscale alarms, if OPRMs are subsequently declared INOPERABLE EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials?
+TQ-106-lM10 Revision 1 Page 6 of 12 EVALUATOR CUE For RO examinees, this completes the JPM EVALUATOR CUE For SRO examinee, provide the SRO examinee sheet that addresses determining required actions
-Task Cue Sheets? Procedures?
+ *11   Identifies Tech Spec 3.3.1.1 for RPS               Performs the following:
-S/U TQ-106-lM10 Revision 1 Page 6 of 12 REVISION
+Instrumentation and TR 3.1.3 for Control Rod Block * *Refer to Tech Spec 3.3.1.1 and Instrumentation is not met.                            determine that a minimum of 3 operable APRM channels are required in MODE 1 per table 3 .3 .1.1-1, therefore action A. l is required; place channel in trip within 12 hours.
+                                                          * *Refer to TRM 3 .1.3 and determine that a minimum of 3 operable APRM S/U channels are required in MODE 1 per table 3.1.3-1, therefore action B.2 is required; place 1 channel in tripped condition within 7 days.
+* Refer to TRM 3.3.9 and determine that a placard will have to be posted at 1C651 indicating less than required number of LPRM upscale alarms, if OPRMs are subsequently declared INOPERABLE EVALUATOR NOTE I CUE That completes the JPM.
+EVALUATOR CUE Record JPM stop time:
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 8of12 REVISION
 ==SUMMARY==
-Revision 0 1 JOB PERFORMANCE MEASURE OO.AD.20958.101 Description/Purpose of Revision New JPM, Revised from Loe 26 TQ-106-0310 Revision 1 Page 8of12 EVALUATOR COPY: TASK CONDITIONS Unit 1 is in MODE 1 at 80 percent power. APRM 2 is INOP and bypassed.
-APRM Gain Calibration was last performed 5 days ago. LPRM detector 40-57 A caused a downscale alarm Page 9 of 12 l&C determined the detector failed. Reactor Engineering requested bypassing the detector.
+JOB PERFORMANCE MEASURE OO.AD.20958.101 Revision                     Description/Purpose of Revision 0    New JPM, Revised from Loe 26 1
-The PCOP has just bypassed LPRM detector 40-57 A in the Lower Relay Room. INITIATING CUE Perform LPRM Upscale Alarm operability tracking for LPRM detector 40-57 A in accordance with 01-078-001 EXAMINEE COPY: TASK CONDITIONS Unit 1 is in MODE 1 at 80 percent power. APRM 2 is INOP and bypassed.
-APRM Gain Calibration was last performed 5 days ago. LPRM detector 40-57 A caused a downscale alarm Page 10of12 l&C determined the detector failed. Reactor Engineering requested bypassing the detector.
+Page 9 of 12 EVALUATOR COPY:
-The PCOP has just bypassed LPRM detector 40-57 A in the Lower Relay Room. INITIATING CUE Perform LPRM Upscale Alarm operability tracking for LPRM detector 40-57 A in accordance with 01-078-001 Page 11 of 12 SRO EVALUATOR COPY: INITIATING CUE Determine the required action(s) based on your findings Page 12of12 SRO EXAMINEE COPY: INITIATING CUE Determine the required action(s) based on your findings SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Perform Jet Pump Operability Check JPM#: OO.S0.20992.101 Revision:Q Date:08/08/2016 Applicability:
+TASK CONDITIONS Unit 1 is in MODE 1 at 80 percent power.
-IZI RO IZI SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic KIA Number 2.2.12 KIA Importance 3.7/4.1, Alternate Path: DYES IZI NO Time Critical DYES IZI NO Validation Time (min):25 Testing Method: D Simulate Date: 08/08/2016
+APRM 2 is INOP and bypassed.
-...... Date:
+APRM Gain Calibration was last performed 5 days ago.
-I' , Validated:
+LPRM detector 40-57A caused a downscale alarm l&C determined the detector failed. Reactor Engineering requested bypassing the detector.
-_'-'--"....._
+The PCOP has just bypassed LPRM detector 40-57A in the Lower Relay Room.
-..............
+INITIATING CUE Perform LPRM Upscale Alarm operability tracking for LPRM detector 40-57A in accordance with 01-078-001
-Date: C[(fJ.b / lb Approval:
-____ Date: CJ '2 9 -/ft,. 'NUCfear &#xa5;raining Supervisor Last, First Ml Employee Number Exam Date: ________ _ Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+Page 10of12 EXAMINEE COPY:
------------
+TASK CONDITIONS Unit 1 is in MODE 1 at 80 percent power.
-Name Signature Comments:
+APRM 2 is INOP and bypassed.
+APRM Gain Calibration was last performed 5 days ago.
+LPRM detector 40-57A caused a downscale alarm l&C determined the detector failed. Reactor Engineering requested bypassing the detector.
+The PCOP has just bypassed LPRM detector 40-57A in the Lower Relay Room.
+INITIATING CUE Perform LPRM Upscale Alarm operability tracking for LPRM detector 40-57A in accordance with 01-078-001
+Page 11 of 12 SRO EVALUATOR COPY:
+INITIATING CUE Determine the required action(s) based on your findings
+Page 12of12 SRO EXAMINEE COPY:
+INITIATING CUE Determine the required action(s) based on your findings
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Perform Jet Pump Operability Check JPM#: OO.S0.20992.101                                  Revision:Q           Date:08/08/2016 Applicability: IZI RO  IZI SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic                 KIA Number 2.2.12         KIA Importance 3.7/4.1, Alternate Path:    DYES IZI NO              Time Critical DYES IZI NO Validation Time (min):25 Testing Method:     D Simulate Date: 08/08/2016
+                      ~--=~'=!:=.::::::::::===...... Date: c;/zi/u~
+I'    ,
+Validated: _'-'--"....._..............~..-'+----- Date: C[(fJ.b / lb Approval: _*_1fA____..._f~0""""'--Le    ____ Date: CJ '2 9 -/ft,.
+                'NUCfear &#xa5;raining Supervisor Last, First Ml                                               Employee Number Exam Date: _ _ _ _ _ _ _ __                             Exam Duration (Min): _ _ _ _ _ _ _ __
+Evaluation Result:     D Satisfactory          D Unsatisfactory Evaluator:
+           -----------
+Name                                               Signature Comments:
 REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.S0.20992.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
-: 2. Whenever entering any plant area where specific safety as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+: 2.        Whenever entering any plant area where specific safety equipment~such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+C.      If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
-: 11. REFERENCES A. S0-100-007, DAILY SURVEILLANCE LOG, REV 75 Ill. TASK CONDITIONS A. Unit 1 is operating at 100% power. B. Both Reactor Recirc pumps and loops are in operation.
+D.      Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
-C. The necessary data to perform the daily surveillance for Recirc pump and jet pump operability has been taken and recorded on Attachment C, PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG. D. No Tech Spec LCO action statements are in effect. IV. INITIATING CUE Using the data provided on Attachment C, Performance Data Sheet Recirculation System Dual Loop, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG:
+: 11. REFERENCES A. S0-100-007, DAILY SURVEILLANCE LOG, REV 75 Ill. TASK CONDITIONS A. Unit 1 is operating at 100% power.
-* Complete the remaining items in Attachment C. V. TASK STANDARD Recirculation pumps declared OPERABLE; Jet pumps declared OPERABLE INFORMATION FOR EVALUATOR
+B. Both Reactor Recirc pumps and loops are in operation.
---* Marking a step as UNSAT requires written comments on respective step . TQ-106-lJ.j10 Revision 1 Page 3 of 16
+C. The necessary data to perform the daily surveillance for Recirc pump and jet pump operability has been taken and recorded on Attachment C, PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG.
+D. No Tech Spec LCO action statements are in effect.
+IV. INITIATING CUE Using the data provided on Attachment C, Performance Data Sheet Recirculation System Dual Loop, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG:
+* Complete the remaining items in Attachment C.
+V. TASK STANDARD Recirculation pumps declared OPERABLE; Jet pumps declared OPERABLE
+TQ-106-lJ.j10 Revision 1 Page 3 of 16 INFORMATION FOR EVALUATOR                                         --
+* Marking a step as UNSAT requires written comments on respective step .
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
 * The time clock starts when the candidate acknowledges the initiating cue.
 * This JPM should be performed in the classroom.
-* Provide a partially completed S0-100-007 attachment C (Page 1, a-i) * "Candidate's Data Sheet #2" (1 page) is not given to the candidate until they identify the need to evaluate jet pump delta Ps. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Obtain a controlled copy of S0-100-007.
+* Provide a partially completed S0-100-007 attachment C (Page 1, a-i)
-Controlled copy obtained from evaluator.
+* "Candidate's Data Sheet #2" (1 page) is not given to the candidate until they identify the need to evaluate jet pump delta Ps.
-S/U 2 Selects correct procedure section. Selects Item 1. S/U 3 To determine Recirc Pumps/Jet Pumps and Flow Selects Attachment C Biased Simulated Thermal Power Upscale (RPS) OPERABLE, Complete APPLICABLE Attachments:
+EVALUATOR CUE Record JPM start time:
-S/U IF in Dual Loop Operation, Complete Attachment C. For Recirc Pumps and Jet Pumps 4* Recirc pumps operable if loop jet pump flow mismatch maintained within a or b: Enter N/A for item that does not apply. a. 5 Mlbm/hr with core flow ;::: 75 Mlbm/hr b. 10 Mlbm/hr with core flow < 75 Mlbm/hr On Attachment C PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP: Compares line g to h. Determines that the mismatch between Loop A and Loop B is 2 Mlbm/hr. Records: 2 Mlbm/hr on SR 3.4.1.1 line a. Records: N/A on SR 3.4.1.1 line b. Determines Recirc Pumps are operable.
+Step   Action                                                Standard                                           Eva I  Comments 1   Obtain a controlled copy of S0-100-007.               Controlled copy obtained from evaluator.           S/U 2   Selects correct procedure section.                    Selects Item 1.                                    S/U 3   To determine Recirc Pumps/Jet Pumps and Flow          Selects Attachment C Biased Simulated Thermal Power Upscale (RPS)
-Circles YES and places his/her initials under Confirm column on SR 3.4.1.1 line . Records: SAT on Recirc Pumps line of item 1 of S0-100-007 Daily Surveillance Log Attachment A SIU TQ-106-l.1010 Revision 1 Page 4 of 16 5* When recirc pumps operating with flow within limits of a or b above, jet pumps operable if no two (2) following conditions exist simultaneously:
+OPERABLE, Complete APPLICABLE Attachments:
-Recirculation loop drive flow versus recirculation generator speed differs > 10% from established patterns. (Plot applicable performance data on figures 1 and 2 of this attachment)
+S/U IF in Dual Loop Operation, Complete Attachment C.
-On Figure 1 RECIRC PUMP A FLOW VS. SPEED TWO LOOP OPERATION of ATTACHMENT C: Plots a point corresponding to: RECIRC GENERATOR A SPEED (SI 14032A) of 87% AND RECIRC PUMP A FLOW (KGPM) of 38 KGPM On Figure 2 RECIRC PUMP B FLOW VS. SPEED TWO LOOP OPERATION of ATTACHMENT C: Plots a point corresponding to: RECIRC GENERATOR B SPEED (SI 140328) of 88% AND RECIRC PUMP B FLOW (KGPM) of 33 KGPM Circles YES and places his/her initials under Confirm column SR 3.4.2.1 line a. S/U Revision 1 Page 5 of 16 6* Recirculation loop drive flow versus total core flow differs > 10% from established patterns. (Plot applicable performance data on Figures 3 and 4 of this attachment)
+For Recirc Pumps and Jet Pumps
-On Figure 3 TOTAL CORE FLOW VS. RECIRC PUMP A FLOW TWO LOOP OPERATION of ATTACHMENT C: Plots a point corresponding to: RECIRC PUMP A FLOW (KGPM) (FR-831-1 R614) of 38 KGPM AND TOTAL CORE FLOW ML8/HR of 92 ML8/HR On Figure 4 TOTAL CORE FLOW VS. RECIRC PUMP 8 FLOW TWO LOOP OPERATION of ATTACHMENT C Plots a point corresponding to: RECIRC PUMP A FLOW (KGPM) (FR-831-1R614) of 33 KGPM AND TOTAL CORE FLOW ML8/HR of 92 ML8/HR Circles NO and places his/her initials under Confirm column SR 3.4.2.1 line b. S/U TQ-106-us10 Revision 1 Page 6 of 16 7 Notifies Reactor Engineering directly that Contacts Reactor Engineering directly and surveillance parameters differ from established notifies that surveillance parameters differ values by more than 5% or notifies SRO to contact from established values by more than 5%. Reactor Engineering.
-OR Notifies SRO to contact Reactor Engineering.
+TQ-106-l.1010 Revision 1 Page 4 of 16 4* Recirc pumps operable if loop jet pump flow      On Attachment C PERFORMANCE DATA mismatch maintained within a or b: Enter N/A for SHEET RECIRCULATION SYSTEM DUAL item that does not apply.                        LOOP:
-OR Contacts Operator to get additional Jet Pump data. EVALUATOR CUE Role-play Reactor Engineering, SRO, or Operator and acknowledge the report. EVALUATOR CUE Provide the candidate with the Candidate Data Sheet #2 (1 page) (Jet pump delta Ps). S/U TQ-106-u-;::, 10 Revision 1 Page 7 of 16 8 1 Calculates LOOP A JET PUMP PERCENT DEVIATION FROM THE AVERAGE to be used in Plotting applicable performance data on figure 1 of attachment I. EVALUATOR NOTE The candidate may round these numbers to the nearest tenth. Records the following data on Attachment C LOOP A JET PUMP PERCENT DEVIATION FROM THE AVERAGE: 1. JP11_34_[(JP11
+: a.      5 Mlbm/hr with core flow ;::: 75 Mlbm/hr Compares line g to h.
--A) +A] X 100 = _-.87 _ 2. JP12_35_[(JP12 -A)+ A] X 100= _2.04_ 3. JP13_34_[(JP13
+: b.      10 Mlbm/hr with core flow < 75 Mlbm/hr   Determines that the mismatch between Loop A and Loop B is 2 Mlbm/hr.
--A) +A] X 100= _-.87 _ 4. JP14_35_[(JP14 -A)+ A] X 100 = _2.04_ 5. JP15_35_[(JP15
+Records: 2 Mlbm/hr on SR 3.4.1.1 line a.
--A) +A] X 100 = _2.04_ 6. JP16_35_[(JP16 -A)+ A] X 100 = _2.04_ 7. JP17 _34_[(JP17 -A)+ A] x 100 = _-.87 _ I s I u 8. JP18_34_[(JP18
+Records: N/A on SR 3.4.1.1 line b.
--A) +A] X 100 = _-.87 _ 9. JP19_35_[(JP19
+SIU Determines Recirc Pumps are operable.
--A) +A] X 100 = _2.04_ 10. JP20_32_[(JP20
+Circles YES and places his/her initials under Confirm column on SR 3.4.1.1 line .
--A)+ A] X 100 = _-6.71 A= _343 X 0.1 = _34.3_ (Sum of JP11 thru 20 Revision 1 Page 8 of 16 9 1 Calculates LOOP B JET PUMP LiP PERCENT DEVIATION FROM THE AVERAGE to be used in Plotting applicable performance data on figure 2 of attachment I. EVALUATOR NOTE The candidate may round these numbers to the nearest tenth. Records the following data on Attachment C LOOP B JET PUMP LiP PERCENT DEVIATION FROM THE AVERAGE: 1. JP1_39_[(JP1
+Records: SAT on Recirc Pumps line of item 1 of S0-100-007 Daily Surveillance Log Attachment A
--A) +A] X 100 = _3.17 _ 2. JP2_39_[(JP2 -A)+ A] X 100 = _3.17 _ 3. JP3_37_[(JP3-A)
-+A] X 100 = _-2.12_ 4. JP4_39_[(JP4
+TQ-106-0~10 Revision 1 Page 5 of 16 5* When recirc pumps operating with flow within limits On Figure 1 RECIRC PUMP A FLOW VS.
--A)+ A] X 100 =_3.17 _ 5. JP5_39_[(JP5
+of a or b above, jet pumps operable if no two (2)   SPEED TWO LOOP OPERATION of following conditions exist simultaneously:          ATTACHMENT C:
--A) +A] X 100 = _3.17 _ 6. JP6_39_[(JP6
+Recirculation loop drive flow versus recirculation  Plots a point corresponding to:
--A) +A] X 100 = _3.17 _ 7. JP7 _30_[(JP7
+generator speed differs > 10% from established      RECIRC GENERATOR A SPEED (SI patterns. (Plot applicable performance data on      14032A) of 87%
--A)+ A] X 100 = _-20.63_ 8. JP8_39_[(JP8
+figures 1 and 2 of this attachment)
--A) +A] X 100 = _3.17 _ 9. JP9_39_[(JP9
+AND RECIRC PUMP A FLOW (KGPM) of 38 KGPM On Figure 2 RECIRC PUMP B FLOW VS.
--A) +A] X 100 = _3.17 _ 10. JP10_38_[(JP10
+S/U SPEED TWO LOOP OPERATION of ATTACHMENT C:
--A) +A] X 100 = _.53_ A =_378 X 0.1 = _37.8_ (Sum of LiP%) JP1 thru 10 S/U 10 Revision 1 Page 9 of 16 10* Each jet pump to lower plenum differential pressure differs by > 20% from the established patterns, (Plot applicable performance data on figures 1 and 2 of attachment I. EVALUATOR NOTE Plotting of points is not critical in this step. On Figure 1 TWO LOOP JET PUMP DISTRIBUTION LOOP A of ATT I Plots the following points: JP11 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP12 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP13 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP14 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP15 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP16 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP17 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP18 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP19 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP20 and -6.71 % DEVIATION FROM THE MEAN DELTA P VALUE Determines that all points are within _:t20% from the established patterns.
+Plots a point corresponding to:
-* S/U TQ-106-b-;)10 Revision 1 Page 10of16 10* (con) Each jet pump to lower plenum differential pressure differs by > 20% from the established patterns, (Plot applicable performance data on figures 1 and 2 of attachment I. EVALUATOR NOTE Plotting of points is not critical in this step. On Figure 2 TWO LOOP JET PUMP DISTRIBUTION LOOP B of ATT I Plots the following points: JP1and3.17
+RECIRC GENERATOR B SPEED (SI 140328) of 88%
-% DEVIATION FROM THE MEAN DELTA P VALUE JP2 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP3 and -2.12 % DEVIATION FROM THE MEAN DELTA P VALUE JP4 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JPS and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JPG and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP7 and-20.63
+AND RECIRC PUMP B FLOW (KGPM) of 33 KGPM Circles YES and places his/her initials under Confirm column SR 3.4.2.1 line a.
-% DEVIATION FROM THE MEAN DEL TAP VALUE JPS and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP9 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP10 and .53 % DEVIATION FROM THE MEAN DELTA PVALUE Circles NO and places his/her initials under Confirm column SR 3.4.2.1 line c.
-* 10 Revision 1 Page 11 of 16 11* When recirc pumps operating with flow within limits Determines Jet pumps are operable based of a or b above, jet pumps operable if no two (2) on two (2) of the conditions under SR following conditions exist simultaneously:
+TQ-106-us10 Revision 1 Page 6 of 16 6* Recirculation loop drive flow versus total core flow On Figure 3 TOTAL CORE FLOW VS.
-.4.2.1 being met simultaneously.
+differs > 10% from established patterns. (Plot       RECIRC PUMP A FLOW TWO LOOP applicable performance data on Figures 3 and 4 of    OPERATION of ATTACHMENT C:
-Circles YES and places his/her initials under Confirm column SR 3.4.2.1. Records: SAT on Jet Pumps line of item 1 of S0-100-007 Daily Surveillance Log Attachment A. EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials?
+this attachment)
-Task Cue Sheets? Procedures?
+Plots a point corresponding to:
-S/U TQ-106-tr;)
+RECIRC PUMP A FLOW (KGPM) (FR-831-1R614) of 38 KGPM AND TOTAL CORE FLOW ML8/HR of 92 ML8/HR On Figure 4 TOTAL CORE FLOW VS.
-Revision 1 Page 12 of 16 REVISION
+S/U RECIRC PUMP 8 FLOW TWO LOOP OPERATION of ATTACHMENT C Plots a point corresponding to:
+RECIRC PUMP A FLOW (KGPM) (FR-831-1R614) of 33 KGPM AND TOTAL CORE FLOW ML8/HR of 92 ML8/HR Circles NO and places his/her initials under Confirm column SR 3.4.2.1 line b.
+TQ-106-u-;::, 10 Revision 1 Page 7 of 16 7   Notifies Reactor Engineering directly that           Contacts Reactor Engineering directly and surveillance parameters differ from established      notifies that surveillance parameters differ values by more than 5% or notifies SRO to contact    from established values by more than 5%.
+Reactor Engineering.                                 OR Notifies SRO to contact Reactor              S/U Engineering.
+OR Contacts Operator to get additional Jet Pump data.
+EVALUATOR CUE Role-play Reactor Engineering, SRO, or Operator and acknowledge the report.
+EVALUATOR CUE Provide the candidate with the Candidate Data Sheet #2 (1 page) (Jet pump delta Ps).
+TQ-106-u~10 Revision 1 Page 8 of 16 8 1 Calculates LOOP A JET PUMP ~p PERCENT                Records the following data on Attachment C DEVIATION FROM THE AVERAGE to be used in             LOOP A JET PUMP ~p PERCENT Plotting applicable performance data on figure 1 of  DEVIATION FROM THE AVERAGE:
+attachment I.                                        1. JP11_34_[(JP11 - A) +A]  X 100 =_-.87_
+: 2. JP12_35_[(JP12 -A)+ A]   X 100=_2.04_
+: 3. JP13_34_[(JP13 - A) +A]  X 100=_-.87_
+: 4. JP14_35_[(JP14 -A)+ A]   X 100 =_2.04_
+: 5. JP15_35_[(JP15 - A) +A]  X 100 =_2.04_
+: 6. JP16_35_[(JP16 -A)+ A] X 100 =_2.04_
+: 7. JP17_34_[(JP17 -A)+ A] x 100 =_-.87 _   IsI u
+: 8. JP18_34_[(JP18 - A) +A] X 100 =_-.87_
+: 9. JP19_35_[(JP19 - A) +A] X 100 =_2.04_
+: 10. JP20_32_[(JP20 - A)+ A] X 100 =_-
+.71 A=_343 X 0.1 = _34.3_
+(Sum of ~P%)
+JP11 thru 20 EVALUATOR NOTE The candidate may round these numbers to the nearest tenth.
+TQ-106-b~ 10 Revision 1 Page 9 of 16 9 1 Calculates LOOP B JET PUMP LiP PERCENT               Records the following data on Attachment C DEVIATION FROM THE AVERAGE to be used in             LOOP B JET PUMP LiP PERCENT Plotting applicable performance data on figure 2 of  DEVIATION FROM THE AVERAGE:
+attachment I.                                        1. JP1_39_[(JP1 - A) +A] X 100 =_3.17_
+: 2. JP2_39_[(JP2 -A)+ A] X 100 =_3.17 _
+: 3. JP3_37_[(JP3-A) +A] X 100 =_-2.12_
+: 4. JP4_39_[(JP4 - A)+ A] X 100 =_3.17_
+: 5. JP5_39_[(JP5 - A) +A] X 100 =_3.17_
+: 6. JP6_39_[(JP6 - A) +A] X 100 =_3.17 _
+: 7. JP7_30_[(JP7 - A)+ A] X 100 =_-20.63_   S/U
+: 8. JP8_39_[(JP8 - A) +A] X 100 =_3.17_
+: 9. JP9_39_[(JP9 - A) +A] X 100 =_3.17_
+: 10. JP10_38_[(JP10 - A) +A] X 100 =_.53_
+A =_378 X 0.1 = _37.8_
+(Sum of LiP%)
+JP1 thru 10 EVALUATOR NOTE The candidate may round these numbers to the nearest tenth.
+TQ-106-b-;)10 Revision 1 Page 10of16 10*    Each jet pump to lower plenum differential pressure   On Figure 1 TWO LOOP JET PUMP differs by > 20% from the established patterns, (Plot DISTRIBUTION LOOP A of ATT I applicable performance data on figures 1 and 2 of     Plots the following points:
+attachment I.
+JP11 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP12 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP13 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP14 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP15 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE S/U JP16 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP17 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP18 and -.87 % DEVIATION FROM THE MEAN DELTA P VALUE JP19 and 2.04 % DEVIATION FROM THE MEAN DELTA P VALUE JP20 and -6.71 % DEVIATION FROM THE MEAN DELTA P VALUE Determines that all points are within _:t20%
+from the established patterns.
+* EVALUATOR NOTE Plotting of points is not critical in this step.
+TQ-106-lJ~ 10 Revision 1 Page 11 of 16 10*   Each jet pump to lower plenum differential pressure   On Figure 2 TWO LOOP JET PUMP (con)   differs by > 20% from the established patterns, (Plot DISTRIBUTION LOOP B of ATT I applicable performance data on figures 1 and 2 of     Plots the following points:
+attachment I.                                         JP1and3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP2 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP3 and -2.12 % DEVIATION FROM THE MEAN DELTA P VALUE JP4 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JPS and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JPG and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP7 and-20.63 % DEVIATION FROM THE MEAN DELTAP VALUE JPS and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP9 and 3.17 % DEVIATION FROM THE MEAN DELTA P VALUE JP10 and .53 % DEVIATION FROM THE MEAN DELTA PVALUE Circles NO and places his/her initials under Confirm column SR 3.4.2.1 line c.
+* EVALUATOR NOTE Plotting of points is not critical in this step.
+TQ-106-tr;) 10 Revision 1 Page 12 of 16 11*   When recirc pumps operating with flow within limits Determines Jet pumps are operable based of a or b above, jet pumps operable if no two (2)   on two (2) of the conditions under SR following conditions exist simultaneously:          3.4.2.1 being met simultaneously.
+Circles YES and places his/her initials under S/U Confirm column SR 3.4.2.1.
+Records: SAT on Jet Pumps line of item 1 of S0-100-007 Daily Surveillance Log Attachment A.
+EVALUATOR NOTE I CUE That completes the JPM.
+EVALUATOR CUE Record JPM stop time:
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 0 Page 14 of 16 REVISION
 ==SUMMARY==
-JOB PERFORMANCE MEASURE OO.S0.20992.101 Revision Description/Purpose of Revision 0 New JPM, From OO.S0.003.051 TQ-106-0310 Revision 0 Page 14 of 16 Page 15 of 16 EVALUATOR COPY: TASK CONDITIONS A. Unit 1 is operating at 100% power. B. Both Reactor Recirc pumps and loops are in operation.
-C. The necessary data to perform the daily surveillance for Recirc pump and jet pump operability has been taken and recorded on Attachment C, PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG. D. No Tech Spec LCO action statements are in effect. INITIATING CUE Using the data provided on Attachment C, Performance Data Sheet Recirculation System Dual Loop, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG:
+JOB PERFORMANCE MEASURE OO.S0.20992.101 Revision                   Description/Purpose of Revision 0    New JPM, From OO.S0.003.051
+Page 15 of 16 EVALUATOR COPY:
+TASK CONDITIONS A. Unit 1 is operating at 100% power.
+B. Both Reactor Recirc pumps and loops are in operation.
+C. The necessary data to perform the daily surveillance for Recirc pump and jet pump operability has been taken and recorded on Attachment C, PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG.
+D. No Tech Spec LCO action statements are in effect.
+INITIATING CUE Using the data provided on Attachment C, Performance Data Sheet Recirculation System Dual Loop, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG:
 * Complete the remaining items in Attachment C.
-Page 16 of 16 EXAMINEE COPY: TASK CONDITIONS A. Unit 1 is operating at 100% power. B. Both Reactor Recirc pumps and loops are in operation.
-C. The necessary data to perform the daily surveillance for Recirc pump and jet pump operability has been taken and recorded on Attachment C, PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG. D. No Tech Spec LCO action statements are in effect. INITIATING CUE Using the data provided on Attachment C, Performance Data Sheet Recirculation System Dual Loop, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG:
+Page 16 of 16 EXAMINEE COPY:
+TASK CONDITIONS A. Unit 1 is operating at 100% power.
+B. Both Reactor Recirc pumps and loops are in operation.
+C. The necessary data to perform the daily surveillance for Recirc pump and jet pump operability has been taken and recorded on Attachment C, PERFORMANCE DATA SHEET RECIRCULATION SYSTEM DUAL LOOP, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG.
+D. No Tech Spec LCO action statements are in effect.
+INITIATING CUE Using the data provided on Attachment C, Performance Data Sheet Recirculation System Dual Loop, of S0-100-007, DAILY SURVEILLANCE OPERATING LOG:
 * Complete the remaining items in Attachment C.
-SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: ___ _..D:;...;e;;..;;te=r;..;;.;m;.;;..;;i..;.;;.n..;;;..e....;;;;O"'"'p=e.;..;;ra=b--il=it;.&#xa3;..y....;;;;o;.;;...f
-=M=S;.;;...IV;;.......;;..;;ls=o=la=f=10...;;.;;n;...;.A"""'c;;..;;t=ua=t=io=n=---------
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: _ _ __..D:;.. ;e;;..;;te=r;..;;.;m;.;;..;;i. ;.;;.n. ;;;..e. . ;;;;O"'"'p=e.;. ;;ra=b--il=it;.&#xa3;. y. . ;;;;o;.;;.. f=M=S;.;;...IV;;.......;;..;;ls=o=la=f=10...;;.;;n;...;.A"""'c;;..;;t=ua=t=io=n=---------
-JPM#: OO.AD.20933.101 Revision:-'2"'--
+JPM#: OO.AD.20933.101                                              Revision:-'2"'--___ Date: 09/23/2016 Applicability: iZI RO iZ1 SRO Setting:    Classroom NUREG-1123 E/APE I Sys                                 Generic                                           KIA Number                                 2.2.22              KIA Importance                    4.7 Alternate Path: DYES                iZI     NO                                   Time Critical DYES                                            IZI NO             Validation Time (min):_---.45..___
-___ Date: 09/23/2016 Applicability:
+Testing Method: D Simulate                                           IZI Perform Author::   *     !ta lthf Operations Review:
-iZI RO iZ1 SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic KIA Number 2.2.22 KIA Importance 4.7 Alternate Path: DYES iZI NO Time Critical DYES IZI NO Validation Time (min):_---.45..___
+validated:        J?o M                                          1/                                                     Date:
-Testing Method: D Simulate IZI Perform Author:: * !ta lthf 1/ Operations Review: M validated:
+Date:
-J?o Approval:
+Date:
-__ 1V\_ .........
+/:26 (_; b
-_\ .....
+                                                                                                                                             ~./l~!ty or/2tllt Approval: __1V\_    ........._\. . .~'-"""'.... L. . . . . ...______ Date: &deg;l'"-7*/(&#xa3;_                                                        ' '
-.... L ...........
+                "NUCiear Traillil19SUPervisor Examinee Name:
-..__ ___ _ "NUCiear Traillil19SUPervisor Examinee Name: Date: Date: Date: Date: 1 /:26 (_; b or/2tllt ' ' &deg;l'"-7*/(&#xa3;_
+                    --            ----------------
-------------------
+Last, First Ml                                                                                                                                            Employee Number Exam Date: _ _ _ _ _ _ _ __                                                                                                    Exam Duration (Min): _ _ _ _ _ _ _ __
-Last, First Ml Employee Number Exam Date: ________ _ Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+Evaluation Result:          D Satisfactory                                                    D          Unsatisfactory Evaluator:
------------
+           -----------
-Name Signature Comments:
+Name                                                                                                                            Signature Comments:
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.20933.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.20933.101 I. SAFETY CONSIDERATIONS A.      All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required arid/or posted as being necessary.
+B.      All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required arid/or posted as being necessary.
-II. REFERENCES A. Sl-183-312, Quarterly Calibration of Main Steam Line Pressure Channels PSL-B21-1N015A, B, C, D Rev 18 B. NDAP-QA-0312, Control of LCOs, TROs and Safety Function Determination Program Rev 20 C. NDAP-QA-0722, Surveillance Test Program Rev 26 D. Technical Specification 3.3.6.1 Ill. TASK CONDITIONS Unit 1 is operating at 80 percent power. l&C is performing Sl-183-312, Quarterly Calibration of Main Steam Line Pressure Channels PSL-B21-1N015A, B, C, D. l&C notifies you that Pressure Switch PSL-B21-1N015C tripped at 838 psig. They were unable to adjust the setting, and it has failed their surveillance.
+C.      If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
-IV. INITIATING CUE Determine system operability and take appropriate actions. V. TASK STANDARD Examinee determines that LCO 3.3.6.1 is NOT met for MSIV Isolation Actuation Surveillance.
+D.       Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+II. REFERENCES A. Sl-183-312, Quarterly Calibration of Main Steam Line Pressure Channels PSL-B21-1N015A, B, C, D Rev 18 B. NDAP-QA-0312, Control of LCOs, TROs and Safety Function Determination Program Rev 20 C. NDAP-QA-0722, Surveillance Test Program Rev 26 D. Technical Specification 3.3.6.1 Ill. TASK CONDITIONS Unit 1 is operating at 80 percent power.
+l&C is performing Sl-183-312, Quarterly Calibration of Main Steam Line Pressure Channels PSL-B21-1N015A, B, C, D.
+l&C notifies you that Pressure Switch PSL-B21-1N015C tripped at 838 psig. They were unable to adjust the setting, and it has failed their surveillance.
+IV. INITIATING CUE Determine system operability and take appropriate actions.
+V. TASK STANDARD Examinee determines that LCO 3.3.6.1 is NOT met for MSIV Isolation Actuation Surveillance.
 Declares channel INOPERABLE, makes notifications and documents LCO entry per NDAP-QA-0312. Performs LOSF, determines no loss of safety function exists.
-INFORMATION FOR EVALUATOR
-* Marking a step as UNSAT requires written comments on respective step . TQ-106-0';)
+TQ-106-0';) 'I 0 Revision 1 Page 3of11 INFORMATION FOR EVALUATOR
-'I 0 Revision 1 Page 3of11
+* Marking a step as UNSAT requires written comments on respective step .
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
 * The time clock starts when the candidate acknowledges the Initiating Cue.
 * This JPM can be performed in the classroom setting.
 * Mark-up a copy of Sl-183-312.
-EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of TS 3.3.6.1-1.
+EVALUATOR CUE Record JPM start time:
-S/U controlled copy. *2 Evaluate the condition and identify appropriate Using Tech Specs, compare test results with S/U LCO allowable value in Table 3.3.6.1-1
+Step   Action                                                Standard                                           Eva I  Comments 1   Identifies governing procedure and obtain             Obtains controlled copy of TS 3.3.6.1-1.            S/U controlled copy.
-*3 Determine the actions required to be taken Performs the following:
+   *2   Evaluate the condition and identify appropriate       Using Tech Specs, compare test results with         S/U LCO                                                   allowable value in Table 3.3.6.1-1
-S/U
+   *3   Determine the actions required to be taken            Performs the following:                             S/U
-* Declare the channel INOPERABLE in accordance with TS 3.3.6.1 Condition A Recognize that the TRIP SYSTEM must be placed in the TRIP condition within 24 hours in accordance with TS 3.3.6.1 Required Action A.1 4 Identifies need to initiate a Condition Report to Directs l&C to generate a Condition Report. S/U document the condition EVALUATOR CUE Acknowledge direction to initiate a CR 5 Notifies Management and support personnel In accordance with OP-AD-002 performs the S/U following:
+* Declare the channel INOPERABLE in accordance with TS 3.3.6.1 Condition A Recognize that the TRIP SYSTEM must be placed in the TRIP condition within 24 hours in accordance with TS 3.3.6.1 Required Action A.1 4   Identifies need to initiate a Condition Report to     Directs l&C to generate a Condition Report.         S/U document the condition EVALUATOR CUE Acknowledge direction to initiate a CR 5   Notifies Management and support personnel             In accordance with OP-AD-002 performs the           S/U following:
-* Notify Duty Manager Notify appropriate support personnel EVALUATOR CUE Acknowledge communications.
+* Notify Duty Manager Notify appropriate support personnel
-Determines that LCO/TRO Log entry is required EVALUATOR CUE States requirement to make an entry into SOMs LCO module. SIU TQ-106-l.i-;J 10 Revision 1 Page 4of11 SOMs LCO module is unavailable.
-Per NDAP-QA-0312 document the information required to complete a LCOTR when SOMs is restored on the Answer Sheet. Answer any questions about what information is expected on each line of the Answer Sheet. EVALUATOR NOTE Date/time of entry is not critical.
+TQ-106-l.i-;J 10 Revision 1 Page 4of11 EVALUATOR CUE Acknowledge communications.
-Required action date/time is critical based on date/time of entry recorded by examinee.
+Determines that LCO/TRO Log entry is required             States requirement to make an entry into         SIU SOMs LCO module.
-*7 Records applicable TS/TRM, Condition, and Performs the following:
+EVALUATOR CUE SOMs LCO module is unavailable. Per NDAP-QA-0312 document the information required to complete a LCOTR when SOMs is restored on the Answer Sheet. Answer any questions about what information is expected on each line of the Answer Sheet.
-S/U Required Action and required action time Completes Answer Sheet with information listed on Answer Key at a minimum *8 Determines no loss of safety function exists Performs the following:
+EVALUATOR NOTE Date/time of entry is not critical. Required action date/time is critical based on date/time of entry recorded by examinee.
-S/U
+    *7   Records applicable TS/TRM, Condition, and                Performs the following:                          S/U Required Action and required action time                 Completes Answer Sheet with information listed on Answer Key at a minimum
+    *8   Determines no loss of safety function exists             Performs the following:                          S/U
 * Determines TS 3.6.1.3 MSIV and MSL drain NSSS isolation is the supported system
 * Determines that all MSIVs and MSL drains are operable in both inboard and outboard NSSSS Determines no loss of safety function exists in TS 3.6.1.3 EVALUATOR CUE If the examinee does not proceed to document the safety function determination on Attachment E, but did mark Y for application of TS 3.0.6 on the Answer Sheet, ask the examinee what the result of applying LOSF.
-Documents a Loss of Safety Function Completes Attachment E of NDAP-QA-0312 Determination per NDAP-QA-0312 as follows:
+TQ-106-lr~10 Revision 1 Page 5 of 11 9   Documents a Loss of Safety Function             Completes Attachment E of NDAP-QA-0312    S/U Determination per NDAP-QA-0312                  as follows:
 * Records TS 3.6.1.3 MSIVs and MSL drains (or similar) as Supported Component or System
 * Records status of supported system as OPERABLE
-* Records status of opposite division of the supported system as OPERABLE (Optional)
+* Records status of opposite division of the supported system as OPERABLE (Optional) Records TS 3.6.1.3 as the LCO where a loss of safety function was evaluated EVALUATOR CUE Record JPM stop time:
-Records TS 3.6.1.3 as the LCO where a loss of safety function was evaluated EVALUATOR CUE Record JPM stop time: EVALUATOR CUE That completes the JPM. EVALUATOR NOTE Do you have ALL your JPM exam materials?
+EVALUATOR CUE That completes the JPM.
-Task Cue Sheets? Procedures?
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
-S/U Revision 1 Page 5 of 11 REVISION
+TQ-106-0310 Revision 1 Page 7of11 REVISION
 ==SUMMARY==
-Revision 0 1 NewJPM JOB PERFORMANCE MEASURE OO.AD.20933.101 Description/Purpose of Revision Revise for TQ procedures, minor editorial corrections TQ-106-0310 Revision 1 Page 7of11 Page 8of11 EVALUATOR COPY: TASK CONDITIONS Unit 1 is operating at 80 percent power l&C is performing Sl-183-312, Quarterly Calibration of Main Steam Line Pressure Channels PSL-821-1 N015A, B, C, D. l&C notifies you that Pressure Switch PSL-B21-1N015C tripped at 838 psig. They were unable to adjust the setting, and it has failed their surveillance INITIATING CUE Determine system operability and take appropriate actions, including completing the required documentation Page 9of11 EXAMINEE COPY: TASK CONDITIONS Unit 1 is operating at 80 percent power l&C is performing Sl-183-312, Quarterly Calibration of Main Steam Line Pressure Channels PSL-821-1 N015A, B, C, D. l&C notifies you that Pressure Switch PSL-B21-1N015C tripped at 838 psig. They were unable to adjust the setting, and it has failed their surveillance INITIATING CUE Determine system operability and take appropriate actions, including completing the required documentation Page 10 of 11 ANSWER KEY Initiating Condition:
-PSL-821-1 N015C Inoperable Unit 1 TSrrR Number(s)
+JOB PERFORMANCE MEASURE OO.AD.20933.101 Revision                      Description/Purpose of Revision 0    NewJPM 1    Revise for TQ procedures, minor editorial corrections
-TS 3.3.6.1 Condition(s)
-A Condition Description(s)
+Page 8of11 EVALUATOR COPY:
-One or more required channels inoperable Entry Daterrime Today I now Action Statement A.1 Number(s)
+TASK CONDITIONS Unit 1 is operating at 80 percent power l&C is performing Sl-183-312, Quarterly Calibration of Main Steam Line Pressure Channels PSL-821-1 N015A, B, C, D.
-Required Action(s)
+l&C notifies you that Pressure Switch PSL-B21-1N015C tripped at 838 psig. They were unable to adjust the setting, and it has failed their surveillance INITIATING CUE Determine system operability and take appropriate actions, including completing the required documentation
-Place channel in trip TSrrR Completion Time 24 hours Entry Daterrime Today I now Action Daterrime Tomorrow I now Chem/HP Sample Log Y/N Required Support System Invoking TS 3.0.6 LOSF YIN Determination?
+Page 9of11 EXAMINEE COPY:
+TASK CONDITIONS Unit 1 is operating at 80 percent power l&C is performing Sl-183-312, Quarterly Calibration of Main Steam Line Pressure Channels PSL-821-1 N015A, B, C, D.
+l&C notifies you that Pressure Switch PSL-B21-1N015C tripped at 838 psig. They were unable to adjust the setting, and it has failed their surveillance INITIATING CUE Determine system operability and take appropriate actions, including completing the required documentation
+Page 10 of 11 ANSWER KEY Initiating Condition:    PSL-821-1 N015C Inoperable Unit                     1 TSrrR Number(s)          TS 3.3.6.1 Condition(s)             A Condition Description(s) One or more required channels inoperable Entry Daterrime          Today I now Action Statement         A.1 Number(s)
+Required Action(s)       Place channel in trip TSrrR Completion Time    24 hours Entry Daterrime          Today I now Action Daterrime         Tomorrow I now Chem/HP Sample Log Y/N Required Support System Invoking TS 3.0.6 LOSF            YIN Determination?
 Page 11 of 11 ANSWER SHEET Initiating Condition:
 Unit TS/TR Number(s)
@@ Line 303: / Line 540: @@
 Entry Date/Time Action Statement Number(s)
 Required Action(s)
-TS/TR Completion Time Entry Date/Time Action Date/Time Chem/HP Sample Log YIN Required Support System Invoking TS 3.0.6 LOSF YIN Determination?
+TS/TR Completion Time Entry Date/Time Action Date/Time Chem/HP Sample Log YIN Required Support System Invoking TS 3.0.6 LOSF            YIN Determination?
-SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: ___
-________ _ JPM#: 00.AD.21022.101 Revision:
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: _ _ _....:.A...;.;:c=t~iv=at=e'-'t=h=e-=-F...;.;:ir--=-e-=B=r~igl,;:;;a=d=e_ _ _ _ _ _ _ __
-Date: 09/23/2016
+JPM#: 00.AD.21022.101                           Revision: 0                                         09/23/2016
--------Applicability: RO SRO Setting: Simulator NUREG-1123 E/APE I Sys Generic KIA Number 2.4.27 KIA Importance 3.4/4.9 Alternate Path: DYES NO Time Critical DYES NO Validation Time (min):_---"-1
+                                                                       ------- Date:
-__ 0 __ Testing Method: D Simulate Perform Author::
+Applicability: ~ RO ~ SRO Setting:    Simulator NUREG-1123 E/APE I Sys                    Generic                         KIA Number              2.4.27     KIA Importance  3.4/4.9 Alternate Path: DYES ~ NO                                Time Critical DYES ~ NO Validation Time (min):_---"-1__                   0 __
-/ Operations Review:
+Testing Method: D Simulate                       ~ Perform Author::       ~C<_ju,J. /                                                             Date:   Cf/~~ Llt Operations Review:   -~~==::::,4J~1======-                                            Date:   z)~/l,Y Validated:     s(lcr kft-!-                                                             Date: 1/:J'1/Jh Approval:      1'1    k.'.) L                                                          Date:   '7*17*/~
-Validated:
+Nuclear Training Supervisor Examinee Name:
-s(lcr kft-!-Approval:
+                  --      ----------------
-'1 k.'.) L Nuclear Training Supervisor Examinee Name: Date:
+Last, First Ml                                                                               Employee Number Exam Date:                                                                             Exam Duration (Min): _ _ _ _ _ _ _ __
-Llt Date:
+             ---------
-Date: 1/:J'1/Jh Date:
+Evaluation Result:    D Satisfactory                              D Unsatisfactory Evaluator:
-------------------
+           -----------
-Last, First Ml Employee Number Exam Date: ---------Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+Name                                                                             Signature Comments:
------------
-Name Signature Comments:
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.21022.101 1
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.AD.21022.101 1 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+I. SAFETY CONSIDERATIONS A.      All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+B.      All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+C.      If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
-II. REFERENCES A. ON-013-001 Response To Fire, (rev. 45) B. FP-013-132 Common Refueling Floor, (rev. 4) C. AR-SP-002 pages 57, 70, (rev. 33) D. OP-099-004, Station Alarm System (rev. 7) Ill. TASK CONDITIONS Unit 1 is in MODE 1 at 80% Power. SIMPLEX fire alarms have been acknowledged in accordance with OP-013-002.
+D.      Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+II. REFERENCES A.       ON-013-001 Response To Fire, (rev. 45)
+B.       FP-013-132 Common Refueling Floor, (rev. 4)
+C.      AR-SP-002 pages 57, 70, (rev. 33)
+D.       OP-099-004, Station Alarm System (rev. 7)
+Ill. TASK CONDITIONS Unit 1 is in MODE 1 at 80% Power.
+SIMPLEX fire alarms have been acknowledged in accordance with OP-013-002.
 The following VALID SIMPLEX data print out is available:
-FIRE DET X112_Z5 ALM 12:14 MON 06-DEC-10 818 U1 REFUEL FLOOR FIRE DET X114_Z2 ALM 12:16 MON 06-DEC-10 818 U1 REFUEL FLOOR An NPO confirms that a fire exists on Unit 1 Reactor Building 818'. IV. INITIATING CUE Activate the Fire Brigade and select the appropriate Pre-Fire Plan. V. TASK STANDARD Fire brigade activated in accordance with ON-013-001, "Response to Fire", and Pre-Fire Plan FP-013-132 selected.
+FIRE DET X112_Z5 ALM 12:14       MON 06-DEC-10 818     U1 REFUEL FLOOR FIRE DET X114_Z2 ALM 12:16       MON 06-DEC-10 818      U1 REFUEL FLOOR An NPO confirms that a fire exists on Unit 1 Reactor Building 818'.
-INFORMATION FOR EVALUATOR
+IV. INITIATING CUE Activate the Fire Brigade and select the appropriate Pre-Fire Plan.
-* Marking a step as UNSAT requires written comments on respective step . TQ-106-(r;j10 Revision 1 Page 3of9
+V. TASK STANDARD Fire brigade activated in accordance with ON-013-001, "Response to Fire", and Pre-Fire Plan FP-013-132 selected.
+TQ-106-(r;j10 Revision 1 Page 3of9 INFORMATION FOR EVALUATOR
+* Marking a step as UNSAT requires written comments on respective step .
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
 * The time clock starts when the candidate acknowledges the Initiating Cue.
-* This JPM must be performed in the simulator.
+* This JPM must be performed in the simulator. Any IC can be used for simulator setup.
-Any IC can be used for simulator setup. BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of AR-SP-002.
+BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN.
-S/U controlled copy. EVALUATOR NOTE: The alarm response procedure identifies the Pre-Fire Plan FP-013-132 2 Identifies appropriate alarm response Selects AR-SP-002, Fire Det X112_Z5 S/U ALM,818 U1 Refuel Floor and Fire Det X114_Z2 ALM 818 U1 Refuel Floor 3 Enters Off Normal Procedure Obtains a copy of ON-013-001, Response to S/U Fire and performs Attachment L, Fire Brigade Normal Response *4 Dispatch Fire Brigade Leader Contact the Field Unit Supervisor as Fire S/U Brigade Leader using the plant page or radio. AND Inform the Fire Brigade Leader a fire is confirmed in Unit 1 Reactor Building 818'
+EVALUATOR CUE Record JPM start time:
-*5 Activate Fire Brigade Pagers *6 Sound Fire Alarm for -10 seconds. *7 Make plant page announcement EVALUATOR CUE Activate the Fire Brigade pagers using the central desk phone set by pressing blue button and lifting the handset for at least 45 seconds.
+Step   Action                                                Standard                                           Eva I  Comments 1   Identifies governing procedure and obtain             Obtains controlled copy of AR-SP-002.               S/U controlled copy.
-* Pull Out the Pistol Grip EVACUATION ALARM switch
+EVALUATOR NOTE:
+The alarm response procedure identifies the Pre-Fire Plan FP-013-132 2   Identifies appropriate alarm response                 Selects AR-SP-002, Fire Det X112_Z5                 S/U ALM,818 U1 Refuel Floor and Fire Det X114_Z2 ALM 818 U1 Refuel Floor 3   Enters Off Normal Procedure                           Obtains a copy of ON-013-001, Response to           S/U Fire and performs Attachment L, Fire Brigade Normal Response
+   *4   Dispatch Fire Brigade Leader                          Contact the Field Unit Supervisor as Fire           S/U Brigade Leader using the plant page or radio.
+AND Inform the Fire Brigade Leader a fire is confirmed in Unit 1 Reactor Building 818'
+TQ-106-0~:n 0 Revision 1 Page 4 of 9
+  *5   Activate Fire Brigade Pagers                             Activate the Fire Brigade pagers using the     S/U central desk phone set by pressing blue button and lifting the handset for at least 45 seconds.
+  *6   Sound Fire Alarm for -10 seconds.
+* Pull Out the Pistol Grip EVACUATION       S/U ALARM switch
 * Turn the Pistol Grip EVACUATION ALARM switch to PLANT ALARM
 * Place the SIREN TONE GENERATOR switch to FIRE (SIREN)
@@ Line 341: / Line 595: @@
 * Pull Out the Pistol Grip EVACUATION ALARM switch to stop the alarm
 * Turn the Pistol Grip EVACUATION ALARM switch to the OFF position
-* Push In the Pistol Grip EVACUATION ALARM switch Key the plant page and announce: "ATTENTION ALL PERSONNEL:
+* Push In the Pistol Grip EVACUATION ALARM switch
-THERE IS A FIRE ON THE REFUEL FLOOR, REACTOR BUILDING ELEVATION 818'. STATION FIRE BRIGADE HAS BEEN ACTIVATED; STAY CLEAR OF AFFECTED AREAS." S/U S/U S/U 0 Revision 1 Page 4 of 9 Announcement should be repeated.
+  *7    Make plant page announcement                            Key the plant page and announce:               S/U  Announcement should be "ATTENTION ALL PERSONNEL: THERE                   repeated.
-Role-play as fire brigade leader. Inform the candidate you will be setting up the command post at Fire Brigade Shed #2 -Unit 2.Tool Room 676', and radio OPS Channel 1 will be used.
+IS A FIRE ON THE REFUEL FLOOR, REACTOR BUILDING ELEVATION 818'.
--*8 Directs a Fire Brigade Member to take Pre-Fire Designate one fire brigade member to take plan for the applicable building to the Command RB Pre-Fire Plan (FP-013-132) to the Post command post at Fire Brigade Shed #2 -Unit 2 Tool Room 676" 9 Inform Security of fire and OPS radio channel Contacts Security at extension 3114 or 3115 being used and inform them of the fire and the radio channel being used. EVALUATOR CUE Record JPM stop time: EVALUATOR CUE That completes the JPM. EVALUATOR NOTE Do you have ALL your JPM exam materials?
+STATION FIRE BRIGADE HAS BEEN ACTIVATED; STAY CLEAR OF AFFECTED AREAS."
-Task Cue Sheets? Procedures?
+EVALUATOR CUE Role-play as fire brigade leader. Inform the candidate you will be setting up the command post at Fire Brigade Shed #2 - Unit 2.Tool Room 676', and radio OPS Channel 1 will be used.
-S/U S/U TQ-106-0010 Revision 1 Page 5 of 9 REVISION
+TQ-106-0010 Revision 1 Page 5 of 9
+  -
+   *8  Directs a Fire Brigade Member to take Pre-Fire  Designate one fire brigade member to take   S/U plan for the applicable building to the Command RB Pre-Fire Plan (FP-013-132) to the Post                                            command post at Fire Brigade Shed #2 -
+Unit 2 Tool Room 676" 9 Inform Security of fire and OPS radio channel    Contacts Security at extension 3114 or 3115 S/U being used                                      and inform them of the fire and the radio channel being used.
+EVALUATOR CUE Record JPM stop time:
+EVALUATOR CUE That completes the JPM.
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 7 of 9 REVISION
 ==SUMMARY==
-JOB PERFORMANCE MEASURE 00.AD.21022.101 Revision Description/Purpose of Revision 0 New JPM From LOC 26 JPM EPP-RO TQ-106-0310 Revision 1 Page 7 of 9 Page 8 of 9 EVALUATOR COPY: TASK CONDITIONS Unit 1 is in MODE 1 SIMPLEX fire alarms have been acknowledged in accordance with OP-013-002.
+JOB PERFORMANCE MEASURE 00.AD.21022.101 Revision                   Description/Purpose of Revision 0    New JPM From LOC 26 JPM EPP-RO
+Page 8 of 9 EVALUATOR COPY:
+TASK CONDITIONS Unit 1 is in MODE 1 SIMPLEX fire alarms have been acknowledged in accordance with OP-013-002.
 The following VALID SIMPLEX data print out is available:
-FIRE DET X112_Z5ALM 12:14 MON 06-DEC-10 818 U1 REFUEL FLOOR FIRE DET X114_Z2ALM 12:16 MON 06-DEC-10 818 U1 REFUEL FLOOR An NPO confirms that a fire exists on Unit 1 Reactor Building 818'. INITIATING CUE Activate the Fire Brigade and select the appropriate Pre-Fire Plan.
+FIRE DET X112_Z5ALM 12:14      MON 06-DEC-10 818 U1 REFUEL FLOOR FIRE DET X114_Z2ALM 12:16      MON 06-DEC-10 818 U1 REFUEL FLOOR An NPO confirms that a fire exists on Unit 1 Reactor Building 818'.
-Page 9 of 9 EXAMINEE COPY: TASK CONDITIONS Unit 1 is in MODE 1 SIMPLEX fire alarms have been acknowledged in accordance with OP-013-002.
+INITIATING CUE Activate the Fire Brigade and select the appropriate Pre-Fire Plan.
+Page 9 of 9 EXAMINEE COPY:
+TASK CONDITIONS Unit 1 is in MODE 1 SIMPLEX fire alarms have been acknowledged in accordance with OP-013-002.
 The following VALID SIMPLEX data print out is available:
-FIRE DET X112_Z5ALM 12:14 MON 06-DEC-10 818 U1 REFUEL FLOOR FIRE DET X114_Z2 ALM 12:16 MON 06-DEC-10 818 U1 REFUEL FLOOR An NPO confirms that a fire exists on Unit 1 Reactor Building 818'. INITIATING CUE Activate the Fire Brigade and select the appropriate Pre-Fire Plan.
+FIRE DET X112_Z5ALM 12:14      MON 06-DEC-10 818 U1 REFUEL FLOOR FIRE DET X114_Z2 ALM 12:16      MON 06-DEC-10 818 U1 REFUEL FLOOR An NPO confirms that a fire exists on Unit 1 Reactor Building 818'.
-SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Classify an Emergency Condition and Complete Emergency Notification Report JPM#: OO.EP.1132.180 Revision:
+INITIATING CUE Activate the Fire Brigade and select the appropriate Pre-Fire Plan.
-Date: 09/23/2016
-----Applica.bility:
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Classify an Emergency Condition and Complete Emergency Notification Report JPM#: OO.EP.1132.180                            Revision: 2
-IZI RO IZI SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic KIA Number 2.4.41
+                                                           - - - - Date:        09/23/2016 Applica.bility: IZI RO IZI SRO Setting:     Classroom NUREG-1123 E/APE I Sys                         Generic        KIA Number       2.4.41
-* KIA Importance 2.4.41 Alternate Path: IZI YES D NO Time Critical DYES IZI NO Validation Time Date: r/;;G (/ k Date: (/z<r --............
+* KIA Importance  2.4.41 Alternate Path:    IZI YES D               NO           Time Critical  DYES IZI NO Validation Time (min):_----'-1~5-
-...............
+         --r7~~....,..--,.q--- Date: r/;;G(/ k Date: (/z<r ~
----.....,....__
+             --...........................---.....,....___ _ Date: er /~j /It Approval:       Jv\ Lo:J ~                                           Date:   &deg;t
-__ Date: er /It Date: &deg;t
+* 7- 7 ' l 4 Nuclear Training Supervisor Examinee Name:
-* 7-7 ' l 4 Approval:
+                      ---------------------------
-Jv\ Lo:J Nuclear Training Supervisor Examinee Name: ---------------------------
+Last, First Ml                                                           Employee Number Exam Date:                                                          Exam Duration (Min): _ _ _ _ _ _ _ __
-Last, First Ml Employee Number Exam Date: ---------Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+               ---------
-Name Signature Comments:
+Evaluation Result:        D Satisfactory                   D Unsatisfactory Evaluator:
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.EP.1132.180 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+            ~-------------
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+Name                                                        Signature Comments:
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE OO.EP.1132.180 I. SAFETY CONSIDERATIONS A.       All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+B.      All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
-II. REFERENCES A. EP-PS-100, CR Emergency Director (revision
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
-: 34) B. EP-RM-004, EAL CLASSIFICATION BASES (Revision
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
-: 9) C. EP-PS-001, EMERGENCY PLANNING FORMS AND SUPPLEMENTARY INSTRUCTIONS (Revision
+C.       If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
-: 11) Ill. TASK CONDITIONS Each examinee evaluated in the SRO position for a scenario will be required to classify the event once the scenario concludes.
+D.       Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
-Task Conditions for each scenario are provided on the cue sheet. IV. INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan. V. TASK STANDARD Classify the event at the appropriate level on the correct EAL and complete the Emergency Notification Report.
+II. REFERENCES A.       EP-PS-100, CR Emergency Director (revision 34)
-INFORMATION FOR EVALUATOR
+B.       EP-RM-004, EAL CLASSIFICATION BASES (Revision 9)
-* Marking a step as UNSAT requires written comments on respective step . TQ-106-0;:n 0 Revision 1 Page 3 of 16
+C.       EP-PS-001, EMERGENCY PLANNING FORMS AND SUPPLEMENTARY INSTRUCTIONS (Revision 11)
+Ill. TASK CONDITIONS Each examinee evaluated in the SRO position for a scenario will be required to classify the event once the scenario concludes. Task Conditions for each scenario are provided on the cue sheet.
+IV. INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.
+V. TASK STANDARD Classify the event at the appropriate level on the correct EAL and complete the Emergency Notification Report.
+TQ-106-0;:n 0 Revision 1 Page 3 of 16 INFORMATION FOR EVALUATOR
+* Marking a step as UNSAT requires written comments on respective step .
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
 * The time clock starts when the candidate acknowledges the Initiating Cue .
-* Ensure that a copy of EP-RM-004, EP-PS-100 and blank ENR and PAR forms are available . EVALUATOR NOTE This is a TIME CRITICAL JPM. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Obtains copy of EP-PS-100, Emergency Director, Obtains copy of EP-PS-100, Emergency SIU Control Room and EP-RM-004, EAL Classification Director, Control Room and EP-RM-004, Bases. EAL Classification Bases. 2 Refers to classification matrix. Selects the correct Table. SIU *3 Chooses appropriate emergency action level. Declares the correct event level per the JPM SIU key for the scenario within 15 minutes of start time. 4 Determines appropdate procedure section. Identifies the appropriate procedure SIU attachment for the event classification of EP-PS-100. *5 Documents and communicates the Emergency Announces the following:
+* Ensure that a copy of EP-RM-004, EP-PS-100 and blank ENR and PAR forms are available .
-SIU Classification.
+EVALUATOR NOTE This is a TIME CRITICAL JPM.
-* I am assuming duties of the Emergency Director * [Event] declared based on [EAL summary]
+EVALUATOR CUE Record JPM start time:
-* Time and Date of Classification 6 If not performed earlier appoints an Emergency Appoints an Emergency Plan Communicator SIU Plan Communicator.
+Step   Action                                               Standard                                           Eva I  Comments 1   Obtains copy of EP-PS-100, Emergency Director,       Obtains copy of EP-PS-100, Emergency                SIU Control Room and EP-RM-004, EAL Classification       Director, Control Room and EP-RM-004, Bases.                                               EAL Classification Bases.
-and instructs communicator to immediately perform EP-PS-126, E-Plan Communicator.
+  Refers to classification matrix.                     Selects the correct Table.                          SIU
-If not performed earlier, appoints an NRC communicator.
+   *3   Chooses appropriate emergency action level.          Declares the correct event level per the JPM        SIU key for the scenario within 15 minutes of start time.
-*8 Initiates an ENR form. EVALUATOR NOTE Appoints an NRC Communicator and instructs communicator to perform EP-PS-135, NRC Communicator.
+  Determines appropdate procedure section.             Identifies the appropriate procedure                SIU attachment for the event classification of EP-PS-100.
-Performs the following:
+   *5   Documents and communicates the Emergency             Announces the following:                            SIU Classification.
+* I am assuming duties of the Emergency Director
+                                                             *  [Event]  declared based on [EAL summary]
+* Time and Date of Classification 6    If not performed earlier appoints an Emergency      Appoints an Emergency Plan Communicator             SIU Plan Communicator.                                  and instructs communicator to immediately perform EP-PS-126, E-Plan Communicator.
+TQ-106-Q;yfQ Revision 1 Page 4.of 16 7  If not performed earlier, appoints an NRC             Appoints an NRC Communicator and               SIU communicator.                                         instructs communicator to perform EP-PS-135, NRC Communicator.
+    *8  Initiates an ENR form.                                Performs the following:                        SIU
 * Refers to ENR Form under Att J and IF necessary EP-PS-001-4 for instructions on filling out the form
 * Records*cR-1 as the control#*
-* Line 1, places checkmark in THIS IS A DRILL box SIU SIU TQ-106-Q;yfQ Revision 1 Page 4.of 16 The time recorded on Line 3 of the ENR form is compared to the start time recorded at the beginning of the JPM to determine if the examinee is successful in meeting the 15 minute event declaration requirement of the JPM. *9 Completes Line 3 of the ENR Performs the following:
+* Line 1, places checkmark in THIS IS A DRILL box EVALUATOR NOTE The time recorded on Line 3 of the ENR form is compared to the start time recorded at the beginning of the JPM to determine if the examinee is successful in meeting the 15 minute event declaration requirement of the JPM.
-SIU
+    *9  Completes Line 3 of the ENR                            Performs the following:                       SIU
 * Places checkmark in the correct event box
 * Places checkmark in the correct unit box
 * Records declaration time and date
-* Places checkmark in INITIAL DECLARATION box 10 Completes Line 4 of the ENR Performs the following:
+* Places checkmark in INITIAL DECLARATION box 10  Completes Line 4 of the ENR                            Performs the following:                       SIU
-SIU
 * Records EAL in Classification Description
 * Records a brief non-technical description of EAL or applies appropriate sticker marked-up to reflect actual event
-*11 Completes Line 5 of the ENR Performs the following:
+TQ-106-0.,-10 Revision 1 Page 5of16
+  *11   Completes Line 5 of the ENR                     Performs the following:                      S/U
 * Refers to EP-PS-001-48 Att. QQ for guidance in determining if there is a radiological release in progress due to the event
 * Places checkmark in release box as appropriate
-*12 Completes Lines 6 and 7 of the ENR Performs the following:
+ *12   Completes Lines 6 and 7 of the ENR              Performs the following:                      S/U
 * Records wind direction, wind speed .
-* Places checkmark in THIS IS A DRILL box *13 Approves the ENR. Signs the ENR and records the current date and time. 14 Provides the ENR to the Emergency Plan Performs the following:
+* Places checkmark in THIS IS A DRILL box
-Communicator.
+ *13   Approves the ENR.                               Signs the ENR and records the current date   S/U and time.
+  Provides the ENR to the Emergency Plan          Performs the following:                      S/U Communicator.
 * Provides the approved ENR to the Emergency Plan Communicator.
 * Reviews the ENR with the Communicator
-* Directs the Communicator to complete '* the notification within 15 minutes of the event declaration time EVALUATOR CUE Record JPM stop time: EVALUATOR CUE That completes the JPM. EVALUATOR NOTE Do you have ALL your JPM exam materials?
+                                              '*
-Task Cue Sheets? Procedures?
+* Directs the Communicator to complete the notification within 15 minutes of the event declaration time EVALUATOR CUE Record JPM stop time:
-S/U S/U S/U S/U TQ-106-0.,-10 Revision 1 Page 5of16 TQ-106-0310 Revision 1 Page 7 of 16 REVISION
+EVALUATOR CUE That completes the JPM.
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 7 of 16 REVISION
 ==SUMMARY==
-Revision 0 1 2 NewJPM JOB PERFORMANCE MEASURE OO.EP.1132.180 Description/Purpose of Revision Minor editorial changes Updated references and individual scenario task conditions to accommodate the LOC 28 NRC exam.
-EVALUATOR
+JOB PERFORMANCE MEASURE OO.EP.1132.180 Revision                       Description/Purpose of Revision 0    NewJPM 1    Minor editorial changes Updated references and individual scenario task conditions to accommodate 2
--SCENARIO 1 TASK CONDITIONS Unit 1 was at 95% power Unit 1 was manually scrammed resulting in an A TWS. Unit 1 experienced the following conditions:
+the LOC 28 NRC exam.
+Page 8of16 EVALUATOR - SCENARIO 1 TASK CONDITIONS Unit 1 was at 95% power Unit 1 was manually scrammed resulting in an A TWS.
+Unit 1 experienced the following conditions:
 * E0-000-113 actions are being performed
-* Standby Liquid Control is injecting Page 8of16
+* Standby Liquid Control is injecting
 * ES-158-002 has been dispatched, rods are being inserted manually INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.
-EXAMINEE -SCENARIO 1 TASK CONDITIONS Unit 1 was at 95% power Unit 1 was manually scrammed resulting in an A TWS. Unit 1 experienced the following conditions:
+Page 9of16 EXAMINEE - SCENARIO 1 TASK CONDITIONS Unit 1 was at 95% power Unit 1 was manually scrammed resulting in an A TWS.
+Unit 1 experienced the following conditions:
 * E0-000-113 actions are being performed
-* Standby Liquid Control is injecting Page 9of16
+* Standby Liquid Control is injecting
 * ES-158-002 has been dispatched, rods are being inserted manually INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.
-EVALUATOR-SCENARIO 2 TASK CONDITIONS Unit 1 Reactor Power was approximately 80% during a startup A manual scram is inserted due to a low level condition Unit 1 experienced the following conditions:
+Page 10of16 EVALUATOR-SCENARIO 2 TASK CONDITIONS Unit 1 Reactor Power was approximately 80% during a startup A manual scram is inserted due to a low level condition Unit 1 experienced the following conditions:
 * Loss of Offsite Power
 * RPV pressure and level are being maintained by SRVs and RCIC.
@@ Line 430: / Line 723: @@
 * RPV level goes below TAF
 * ADS fails to initiate
-* Emergency Depressurization is performed Page 10of16
+* Emergency Depressurization is performed
 * Manual initiation of ECCS systems required due to a failure to auto initiate INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.
-EXAMINEE -SCENARIO 2 TASK CONDITIONS Unit 1 Reactor Power was approximately 80% during a startup A manual scram is inserted due to a low level condition Unit 1 experienced the following conditions:
+Page 11 of 16 EXAMINEE - SCENARIO 2 TASK CONDITIONS Unit 1 Reactor Power was approximately 80% during a startup A manual scram is inserted due to a low level condition Unit 1 experienced the following conditions:
 * Loss of Offsite Power
 * RPV pressure and level are being maintained by SRVs and RCIC.
@@ Line 438: / Line 732: @@
 * RPV level goes below TAF
 * ADS fails to initiate
-* Emergency Depressurization is performed Page 11 of 16
+* Emergency Depressurization is performed
 * Manual initiation of ECCS systems required due to a failure to auto initiate INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.
-EVALUATOR
--SCENARIO 3 TASK CONDITIONS Unit 1 Reactor Power was approximately 33%. A shutdown was in progress for an unplanned maintenance outage Unit 1 experienced the following conditions:
+Page 12of16 EVALUATOR - SCENARIO 3 TASK CONDITIONS Unit 1 Reactor Power was approximately 33%.
-* A loss of ESS Bus 1 C occurred Page 12of16
+A shutdown was in progress for an unplanned maintenance outage Unit 1 experienced the following conditions:
+* A loss of ESS Bus 1C occurred
 * A manual scram is inserted due to a leak in the drywell resulting in an ATWS
 * ARI is initiated, drifting rods in.
@@ Line 448: / Line 743: @@
 * Rad levels in the CRD HCU area and RCIC room rad levels exceed Max Safe levels
 * Emergency depressurization is conducted INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.
-EXAMINEE -SCENARIO 3 TASK CONDITIONS Unit 1 Reactor Power was approximately 33%. A shutdown was in progress for an unplanned maintenance outage Unit 1 experienced the following conditions:
-* A loss of ESS Bus 1 C occurred Page 13of16
+Page 13of16 EXAMINEE - SCENARIO 3 TASK CONDITIONS Unit 1 Reactor Power was approximately 33%.
+A shutdown was in progress for an unplanned maintenance outage Unit 1 experienced the following conditions:
+* A loss of ESS Bus 1C occurred
 * A manual scram is inserted due to a leak in the drywell resulting in an A TWS
 * ARI is initiated, drifting rods in.
@@ Line 455: / Line 752: @@
 * Rad levels in the CRD HCU area and RCIC room rad levels exceed Max Safe levels
 * Emergency depressurization is conducted INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.
-EVALUATOR-SCENARIO 4 TASK CONDITIONS Unit 1 Reactor Power was approximately 90% A small steam leak developed in the drywell Unit 1 experienced the following conditions:
+Page 14of16 EVALUATOR- SCENARIO 4 TASK CONDITIONS Unit 1 Reactor Power was approximately 90%
+A small steam leak developed in the drywell Unit 1 experienced the following conditions:
 * A manual scram is inserted
 * Plant Aux load shed occurs
@@ Line 461: / Line 760: @@
 * Suppression chamber and Drywell sprays are in service
 * RPV flooding is required due to erratic pressure instruments
-* Level is steady at +30" prior to the loss of level indication INITIATING CUE Page 14of16 Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.
+* Level is steady at +30" prior to the loss of level indication INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.
-* EXAMINEE -SCENARIO 4 TASK CONDITIONS Unit 1 Reactor Power was approximately 90% A small steam leak developed in the drywell Unit 1 experienced the following conditions:
+Page 15of16
+* EXAMINEE - SCENARIO 4 TASK CONDITIONS Unit 1 Reactor Power was approximately 90%
+A small steam leak developed in the drywell Unit 1 experienced the following conditions:
 * A manual scram is inserted
 * Plant Aux load shed occurs
@@ Line 468: / Line 770: @@
 * Suppression chamber and Drywell sprays are in service
 * RPV flooding is required due to erratic pressure instruments
-* Level is steady at +30" prior to the loss of level indication INITIATING CUE Page 15of16 Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.
+* Level is steady at +30" prior to the loss of level indication INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.
-Page 16of16 JPM KEY Scenario Classification EAL Release 1 SAE MS3 No 2 SAE FS1 No 3 SAE FS1 Yes 4 Alert FA1 No SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Determine LCO Applicability to Bypass Secondary Containment Zone 2 Isolation JPM#: 34.0P.21505.201 Revision:____.O'-----
-Date: 09/26/2016 Applicability:
+Page 16of16 JPM KEY Scenario Classification        EAL     Release 1         SAE               MS3       No 2         SAE               FS1       No 3         SAE               FS1      Yes 4         Alert             FA1       No
-] SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic KIA Number _2=*--.3.;;..;.1_,,3
-___ K/A Importance
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Determine LCO Applicability to Bypass Secondary Containment Zone 2 Isolation JPM#: 34.0P.21505.201                   Revision:____.O'----- Date: 09/26/2016 Applicability: 12] SRO Setting: Classroom NUREG-1123 E/APE I Sys Generic KIA Number _2=*--.3.;;..;.1_,,3_ _ _ K/A Importance _3............
-_3 ............
+__
-__ Alternate Path: DYES 12] NO Time Critical DYES 12] NO Validation Time (min):_2=5"'--_
+Alternate Path: DYES 12] NO            Time Critical DYES 12] NO Validation Time (min):_2=5"'--_
-] Perform Author:: J/ Operations Review: L----Validated: , &#xa3;a ,J.A..&#xb5; (/ Date: -------Date:
+] Perform Author::                            J/              Date:
-Jfo Date: &deg;f /:Lt// b Approval:
+                                                          -------
-___ Date: &deg;J ' Z &deg;t
+Operations Review:                 L----            Date:       7._~ Jfo Validated:       , &#xa3;a ,J.A..&#xb5; (/                    Date:  &deg;f /:Lt//b Approval:  _fu~~___;W~;.__:~=;r:--.::::;_____ Date:         &deg;J ' Z&deg;t
-* lk NUCiear Last, First Ml Employee Number Exam Date: ________ _ Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+* lk NUCiear Traini~rvisor Last, First Ml                                           Employee Number Exam Date: _ _ _ _ _ _ _ __                        Exam Duration (Min): _ _ _ _ _ _ _ __
-__________
+Evaluation Result:    D Satisfactory      D Unsatisfactory Evaluator: _ _ _ _ _ _ _ _ _ __
-_ Name Signature Comments:
+Name                                          Signature Comments:
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 34.0P.21505.201 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 34.0P.21505.201 I. SAFETY CONSIDERATIONS A.      All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+B.      All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
-: 11. REFERENCES A. OP-234-002, Reactor Building HVAC Zones 2 and 3 (Rev. 15) B. NDAP-QA-0321, Secondary Containment Integrity Control (Rev. 13) 1 111. TASK CONDITIONS A. Unit 2 is shutdown.
+C.      If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
-B. All rods were inserted 4 hours ago. C. Plant cool down and equipment shutdown are in progress in preparation for start of a refueling outage. D. C RHR Pump is in service in Shutdown Cooling. E. A and B ESW pumps and 2A RHRSW Pump is in service providing cooling to the RHR system. R. Reactor coolant temperature is 194 &deg;F and lowering.
+D.      Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
-G. Cask Storage Gates are removed. H. All other equipment is operable.
+: 11. REFERENCES A.       OP-234-002, Reactor Building HVAC Zones 2 and 3 (Rev. 15)
-I. I & C has requested the Secondary Containment Zone 2 Isolation bypassed to support work. IV. INITIATING CUE Determine the ability to bypass the Secondary Containment Zone 2 Isolation.
+B.      NDAP-QA-0321, Secondary Containment Integrity Control (Rev. 13) 1 111. TASK CONDITIONS A. Unit 2 is shutdown.
-Record your findings, including any applicable references.
+B. All rods were inserted 4 hours ago.
-Document your approval I disapproval of the request. Specify actions required for bypass. V. TASK STANDARD Candidate determines Unit 2 Tech Spec 3.6.4.1 is Not Applicable to Mode 4, and may continue with Bypass of Secondary Containment Isolation signal for Zone 2. Candidate authorizes bypassing the Zone 2 Isolation IAW OP-234-002 and NDAP-QA-0321.
+C. Plant cool down and equipment shutdown are in progress in preparation for start of a refueling outage.
-INFORMATION FOR EVALUATOR
+D. C RHR Pump is in service in Shutdown Cooling.
+E. A and B ESW pumps and 2A RHRSW Pump is in service providing cooling to the RHR system.
+R. Reactor coolant temperature is 194 &deg;F and lowering.
+G. Cask Storage Gates are removed.
+H. All other equipment is operable.
+I. I & C has requested the Secondary Containment Zone 2 Isolation bypassed to support work.
+IV. INITIATING CUE Determine the ability to bypass the Secondary Containment Zone 2 Isolation. Record your findings, including any applicable references. Document your approval I disapproval of the request. Specify actions required for bypass.
+V. TASK STANDARD Candidate determines Unit 2 Tech Spec 3.6.4.1 is Not Applicable to Mode 4, and may continue with Bypass of Secondary Containment Isolation signal for Zone 2. Candidate authorizes bypassing the Zone 2 Isolation IAW OP-234-002 and NDAP-QA-0321.
+TQ-106-u~ 10 Revision 1 Page 3 of 9 INFORMATION FOR EVALUATOR
 * Marking a step as UNSAT requires written comments on respective step.
-Revision 1 Page 3 of 9
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
 * The time clock starts when the candidate acknowledges the initiating cue.
 * This JPM may be performed in the classroom.
-* Ensure the following material is available; OP-234-002, NDAP-QA-0321, and Tech Specs EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Obtain a controlled copy of the procedure Obtains a controlled copy of the applicable S/U procedure(s).
+* Ensure the following material is available; OP-234-002, NDAP-QA-0321, and Tech Specs EVALUATOR CUE Record JPM start time:
-Selects the correct section to perform Selects:
+Step   Action                                                Standard                                           Eva I  Comments 1   Obtain a controlled copy of the procedure             Obtains a controlled copy of the applicable S/U procedure(s).
+  Selects the correct section to perform                Selects:
 * OP-234-002 section 2.12 and/or
-* NDAP-QA-0321 section 6.4 S/U and/or
+* NDAP-QA-0321 section 6.4                     S/U and/or
-* Technical Specification 3.6.4.1/3.6.4.2.
+* Technical   Specification 3.6.4.1/3.6.4.2.
-Review NDAP-QA-0321 section 6.4 Determines nothing in NDAP-QA-0321 prohibits bypassing the Secondary Containment Zone 2 Isolation.
+  Review NDAP-QA-0321 section 6.4                       Determines nothing in NDAP-QA-0321 prohibits bypassing the Secondary Containment Zone 2 Isolation.
 S/U Determines OP-234-002 and Technical Specifications should be referenced.
-Review OP-234-002 section 2.12 Determines must evaluate Technical S/U Specifications 3.6.4.1 and 3.6.4.2. EVALUATOR NOTE Candidate may refer to TRO 3. 7 .10 which addresses cross-tying the Fuel Pools. Candidate may also initially refer to G0-200-006 regarding the precautions for SC Integrity.
+  Review OP-234-002 section 2.12                        Determines must evaluate Technical S/U Specifications 3.6.4.1 and 3.6.4.2.
-*5 I Evaluate Unit 2 Tech Spec 3.6.4.1. EVALUATOR NOTE I CUE Determines plant is currently in Mode 4. Review Technical Specification 3.6.4.1 and determines operability of Secondary Containment is NOT required in Mode 4. Determines irradiated fuel movement and I S I U OPDRVs are not in progress based on initial conditions.
+EVALUATOR NOTE Candidate may refer to TRO 3. 7 .10 which addresses cross-tying the Fuel Pools.
+Candidate may also initially refer to G0-200-006 regarding the precautions for SC Integrity.
+TQ-106-u-,,-10 Revision 1 Page 4 of 9
+    *5 I Evaluate Unit 2 Tech Spec 3.6.4.1.                    Determines plant is currently in Mode 4.
+Review Technical Specification 3.6.4.1 and determines operability of Secondary Containment is NOT required in Mode 4.
+Determines irradiated fuel movement and        I SI U OPDRVs are not in progress based on initial conditions.
 Determines Technical Specification 3.6.4.1 allows bypassing of Secondary Containment Zone 2 Isolation in present plant conditions.
-If asked about irradiated fuel movement, inform candidate that no irradiated fuel movement is in progress.
+EVALUATOR NOTE I CUE If asked about irradiated fuel movement, inform candidate that no irradiated fuel movement is in progress.
 EVALUATOR NOTE I CUE If asked about OPDRVs, inform candidate that no OPDRVs are in progress.
-*6 I Evaluate Unit 2 Tech Spec 3.6.4.2. EVALUATOR CUE Determines plant is in currently in Mode 4. Determines Secondary Containment Isolation Valve operability is NOT required in Mode 4. Determines irradiated fuel movement and I S I U OPDRVs are not in progress based on initial conditions.
+    *6 I Evaluate Unit 2 Tech Spec 3.6.4.2.                    Determines plant is in currently in Mode 4.
-Determines Technical Specification 3.6.4.2 allows bypassing of Secondary Containment Zone 2 Isolation in present plant conditions If a,sked about irradiated fuel movement, inform candidate that no irradiated fuel movement is in progress.
+Determines Secondary Containment Isolation Valve operability is NOT required in Mode 4.
-TQ-106-u-,,-10 Revision 1 Page 4 of 9 EVALUATOR CUE If asked about OPDRVs, inform candidate that no OPDRVs are in progress.
+Determines irradiated fuel movement and        I SI U OPDRVs are not in progress based on initial conditions.
-EVALUATOR CUE If asked about release paperwork (OP-234-002 Att J), inform candidate that OP-234-002 Attachment J has been completed and is being maintained by the Operations Outage Manager (QOM). *7 Complete OP-234-002 Attachment F Indicates need to fill out OP-234-002 Attachment F and indicates they would direct an operator to complete it. S/U Indicates that after this form is completed, they would authorize isolation bypass. EVALUATOR NOTE Provide a blank copy of OP-234-002 Attachment F upon request. EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials?
+Determines Technical Specification 3.6.4.2 allows bypassing of Secondary Containment Zone 2 Isolation in present plant conditions EVALUATOR CUE If a,sked about irradiated fuel movement, inform candidate that no irradiated fuel movement is in progress.
-Task Cue Sheets? Procedures?
-Revision 1 Page 5 of 9 REVISION
+TQ-106-u~ 10 Revision 1 Page 5 of 9 EVALUATOR CUE If asked about OPDRVs, inform candidate that no OPDRVs are in progress.
+EVALUATOR CUE If asked about release paperwork (OP-234-002 Att J), inform candidate that OP-234-002 Attachment J has been completed and is being maintained by the Operations Outage Manager (QOM).
+    *7  Complete OP-234-002 Attachment F                     Indicates need to fill out OP-234-002 Attachment F and indicates they would direct an operator to complete it.
+S/U Indicates that after this form is completed, they would authorize isolation bypass.
+EVALUATOR NOTE Provide a blank copy of OP-234-002 Attachment F upon request.
+EVALUATOR NOTE I CUE That completes the JPM.
+EVALUATOR CUE Record JPM stop time:
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 7of9 REVISION
 ==SUMMARY==
-Revision 0 1 JOB PERFORMANCE MEASURE 34.0P.21505.201 Description/Purpose of Revision New JPM, Revised from 34.0P.2683.201 TQ-106-0310 Revision 1 Page 7of9 Page 8 of 9 EVALUATOR COPY: TASK CONDITIONS A. Unit 2 is shutdown.
-B. All rods were inserted 4 hours ago. C. Plant cool down and equipment shutdown are in progress in preparation for start of a refueling outage. D. C RHR Pump is in service in Shutdown Cooling. E. A and B ESW pumps and 2A RHRSW Pump is in service providing cooling to the RHR system. R. Reactor coolant temperature is 194 &deg;F and lowering.
+JOB PERFORMANCE MEASURE 34.0P.21505.201 Revision                     Description/Purpose of Revision 0    New JPM, Revised from 34.0P.2683.201 1
-G. Cask Storage Gates are removed. H. All other equipment is operable.
-I. I & C has requested the Secondary Containment Zone 2 Isolation bypassed to support work. INITIATING CUE Determine the ability to bypass the Secondary Containment Zone 2 Isolation.
+Page 8 of 9 EVALUATOR COPY:
-Record your findings, including any applicable references.
+TASK CONDITIONS A. Unit 2 is shutdown.
-Document your approval I disapproval of the request. Specify actions required for bypass.
+B. All rods were inserted 4 hours ago.
-Page 9of9 EXAMINEE COPY: TASK CONDITIONS A. Unit 2 is shutdown.
+C. Plant cool down and equipment shutdown are in progress in preparation for start of a refueling outage.
-B. All rods were inserted 4 hours ago. C. Plant cool down and equipment shutdown are in progress in preparation for start of a refueling outage. D. C RHR Pump is in service in Shutdown Cooling. E. A and B ESW pumps and 2A RHRSW Pump is in service providing cooling to the RHR system. R. Reactor coolant temperature is 194&deg;F and lowering.
+D. C RHR Pump is in service in Shutdown Cooling.
-G. Cask Storage Gates are removed. H. All other equipment is operable.
+E. A and B ESW pumps and 2A RHRSW Pump is in service providing cooling to the RHR system.
-I. I & C has requested the Secondary Containment Zone 2 Isolation bypassed to support work. INITIATING CUE Determine the ability to bypass the Secondary Containment Zone 2 Isolation.
+R. Reactor coolant temperature is 194&deg;F and lowering.
-Record your findings, including any applicable references.
+G. Cask Storage Gates are removed.
-Document your approval I disapproval of the request. Specify actions required for bypass.
+H. All other equipment is operable.
-SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Reset Recirculation Pump Limiter #2 Run back, RRP B Runout JPM#: 64.0N.67049.101 Revision:Q Date:07/07/2016 Applicability:
+I. I & C has requested the Secondary Containment Zone 2 Isolation bypassed to support work.
-ll?J RO ll?l SRO Setting: Simulator NUREG-1123 E/APE I Sys 202002 KIA Number A2.05 KIA Importance 3.8/4.0 Alternate Path: DYES ll?J NO Time Critical DYES ll?l NO Validation Time (min):20 Testing Method: D Simulate ll?l Perform Author::Greg van den c / Date: 07/07/2016 Operations Review:
+INITIATING CUE Determine the ability to bypass the Secondary Containment Zone 2 Isolation. Record your findings, including any applicable references. Document your approval I disapproval of the request. Specify actions required for bypass.
-Date: 7 /t[
-Validated:
+Page 9of9 EXAMINEE COPY:
-{1cr_..&#xa3;tAd Date: q/#/,/1/, Approval:
+TASK CONDITIONS A. Unit 2 is shutdown.
-___ Date: 1*:l1
+B. All rods were inserted 4 hours ago.
-* I l Nuclear Training Supervisor Last, First Ml Employee Number Exam Date: ---------Exam Duration (Min .... : ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+C. Plant cool down and equipment shutdown are in progress in preparation for start of a refueling outage.
------------
+D. C RHR Pump is in service in Shutdown Cooling.
-Name Signature Comments:
+E. A and B ESW pumps and 2A RHRSW Pump is in service providing cooling to the RHR system.
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 64.0N.67049.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+R. Reactor coolant temperature is 194&deg;F and lowering.
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+G. Cask Storage Gates are removed.
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+H. All other equipment is operable.
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+I. I & C has requested the Secondary Containment Zone 2 Isolation bypassed to support work.
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+INITIATING CUE Determine the ability to bypass the Secondary Containment Zone 2 Isolation. Record your findings, including any applicable references. Document your approval I disapproval of the request. Specify actions required for bypass.
-II. REFERENCES A. 'ON-RECIRC-101, Reactor Recirculation Malfunction (Rev. 1) B. AOP-164-001, Reactor Recirculation Abnormal Operating Procedure (Rev. 0) Ill. TASK CONDITIONS Unit 1 is in Mode 1. A trip of Condensate Pump 1 D has caused a Reactor Recirculation runback to occur. ON-RECIRC-101, Reactor Recirculation Malfunction, has been completed up to step C.18.d. A Critical Brief has been performed 1 D Condensate Pump has been restored.
-IV. INITIATING CUE Reset the Recirculation Pump limiter #2 run back for both Recirculation Pumps in accordance with AOP-164-001, Attachment B. V. TASK STANDARD Recirc,LIM2 runback is reset for Reactor Recirc Pump IA and lB.
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Reset Recirculation Pump Limiter #2 Run back, RRP B Runout JPM#: 64.0N.67049.101                                              Revision:Q              Date:07/07/2016 Applicability:    ll?J RO ll?l SRO Setting: Simulator NUREG-1123 E/APE I Sys 202002 KIA Number A2.05 KIA Importance 3.8/4.0 Alternate Path: DYES               ll?J NO              Time Critical DYES     ll?l NO  Validation Time (min):20 Testing Method:
-NOTE: SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 64.0N.67049.101 It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
+Author::Greg van den Operations Review:
+c~&--~~
+D Simulate
+                                              /    ll?l Perform Date: 07/07/2016 Date:    7  /t[ /1~<o Validated:       {1cr_..&#xa3;tAd                                          Date:  q/#/,/1/,
+Approval:  _,_1V\__._---=-f;"""""~""'""""--fbp___.___*_ _ _ Date: 1*:l1 *I l Nuclear Training Supervisor Last, First Ml                                                        Employee Number Exam Date:                                                          Exam Duration (Min....:_ _ _ _ _ _ _ __
+               ---------
+Evaluation Result:            D    Satisfactory            D  Unsatisfactory Evaluator:
+          -----------
+Name                                                          Signature Comments:
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 64.0N.67049.101 I. SAFETY CONSIDERATIONS A.       All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+B.      All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+C.       If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+D.       Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+II. REFERENCES A.      'ON-RECIRC-101, Reactor Recirculation Malfunction (Rev. 1)
+B.       AOP-164-001, Reactor Recirculation Abnormal Operating Procedure (Rev. 0)
+Ill. TASK CONDITIONS Unit 1 is in Mode 1.
+A trip of Condensate Pump 1D has caused a Reactor Recirculation runback to occur.
+ON-RECIRC-101, Reactor Recirculation Malfunction, has been completed up to step C.18.d.
+A Critical Brief has been performed 1D Condensate Pump has been restored.
+IV. INITIATING CUE Reset the Recirculation Pump limiter #2 run back for both Recirculation Pumps in accordance with AOP-164-001, Attachment B.
+V. TASK STANDARD Recirc,LIM2 runback is reset for Reactor Recirc Pump IA and lB.
+SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 64.0N.67049.101 NOTE:     It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
 * Reset the simulator to an exam-specific IC if prepared.
-* Configure an exam-specific IC as follows: o Reset to IC-18 o Perform the following expert command to trip Condensate Pump D: !OR diHS10510D f:STOP
+* Configure an exam-specific IC as follows:
+o Reset to IC-18 o Perform the following expert command to trip Condensate Pump D:
+               !OR diHS10510D f:STOP
 * Place the simulator in RUN.
 * Allow plant conditions to stabilize.
 * Perform actions of ON-RECIRC-101 through step C.14
-* Perform the following expert command to delete the Condensate Pump D trip malfunction:
+* Perform the following expert command to delete the Condensate Pump D trip malfunction: DOR diHS10510D f:START
-DOR diHS10510D f:START
 * Restart Condensate Pump lD
-* Perform the following expert command to load RRP A(B) speed as a Monitored Parameter i nsmp rrnlp40la insmp rrnlp401b INFORMATION FOR EVALUATOR
+* Perform the following expert command to load RRP A(B) speed as a Monitored Parameter i nsmp rrnlp40la insmp rrnlp401b
-* Marking a step as UNSAT requires written comments on respective step . TQ-106-lM 10 Revision 1 Page 4of12
+TQ-106-lM 10 Revision 1 Page 4of12 INFORMATION FOR EVALUATOR
+* Marking a step as UNSAT requires written comments on respective step .
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
 * The time clock starts when the candidate acknowledges the initiating cue.
 * This JPM must be performed in the simulator.
-* Configure the Simulator per the Simulator Setup Instructions . BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Verifies AOP-164-001 Att. B is the controlling Controlled copy of AOP-164-001 obtained, S/U document.
+* Configure the Simulator per the Simulator Setup Instructions .
-select Att. B. 2 Verifies Condenser Pressure is <5 .5'' HgA. Verifies Condenser Pressure is <5 .5'' HgA at S/U panel 1 C668B 3 Determines RFP(s) indicated flow.
+BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN.
+EVALUATOR CUE Record JPM start time:
+Step   Action                                                Standard                                            Eva I Comments 1 Verifies AOP-164-001 Att. B is the controlling          Controlled copy of AOP-164-001 obtained, S/U document.                                             select Att. B.
+  Verifies Condenser Pressure is <5 .5'' HgA.           Verifies Condenser Pressure is <5 .5'' HgA at S/U panel 1C668B 3   Determines RFP(s) indicated flow.
 * Observe Feedwater flow on the Feedwater Flow Overview.
 S/U
-* Determines that RFP discharge flows are all <0.9Mlbm/hr
+* Determines that RFP discharge flows are all <0.9Mlbm/hr (> 16.4%).
-(> 16.4%). 4 Ensures associated IND RFP FLOW< 16.4%
+  Ensures associated IND RFP FLOW< 16.4%
-* On the RRP A HMI screen, determines Limiter# 2 Input(s) to Rx Recirc Runback Circuit is IND FLOW <16.4% is ENABLED. S/U ENABLED.
+* On the RRP A HMI screen, determines Limiter# 2 Input(s) to Rx Recirc Runback Circuit is       IND FLOW <16.4% is ENABLED.
-* On the RRP B HMI screen, determines IND FLOW <16.4% is ENABLED. EVALUATOR NOTE The Limiter #2 RESET buttons will not become active until Controller Output indication is 27.10% and initiating condition has cleared (with the exception of CWP Trip/High Condenser Pressure and/or Condensate Pump trips). 5 Ensure a Critical Brief has been conducted Verifies initial conditions state that the S/U Critical Brief has been conducted.
+S/U ENABLED.
-* I RESET Limiter #2 Runback on 'A' Reactor Recirculation Pump EVALUATOR NOTE Performs the following:
+* On the RRP B HMI screen, determines IND FLOW <16.4% is ENABLED.
-* VERIFY SY-B31-1R621A
+EVALUATOR NOTE The Limiter #2 RESET buttons will not become active until Controller Output indication is    ~ 27.10% and initiating condition has cleared (with the exception of CWP Trip/High Condenser Pressure and/or Condensate Pump trips).
-% Controller Output Signal is approximately 27.10%. * *TOUCH DEC button RECIRC PUMP lA SPEED SY-B31-1R621A Controller
+  Ensure a Critical Brief has been conducted                Verifies initial conditions state that the S/U Critical Brief has been conducted.
+TQ-106-l,;;,10 Revision 1 Page 5 of 12 6* I RESET Limiter #2 Runback on 'A' Reactor              Performs the following:
+Recirculation Pump
+* VERIFY SY-B31-1R621A % Controller Output Signal is approximately 27.10%.
+                                                            *   *TOUCH DEC button RECIRC PUMP lA SPEED SY-B31-1R621A Controller
 * Observes a change in the following:
-o Lowering of Gen 1A Speed or on SI 14032A (TRA036) o Lowering of Gen 1A Demand, on I SIU XI 14032A (TRA040) o Lowering of Scoop Tube 1 A Position (TRA044) o Lowering of Loop 1A Drive Flow (APMF01)
+o   Lowering of Gen 1A Speed or on SI 14032A (TRA036) o   Lowering of Gen 1A Demand, on  I SIU XI 14032A (TRA040) o   Lowering of Scoop Tube 1A Position (TRA044) o   Lowering of Loop 1A Drive Flow (APMF01)
-* OBSERVE HS-B31-1S12A RX RECIRC LIMITER #2 (48%) RUNBACK RESET button is ACTIVE One minute time delay allows for Scoop Tube Positioner to make the final (0.111 %) position adjustment 7* I Depress the RX RECIRC LIMITER #2 (48%) RUNBACK RESET button. 8 I Monitor Recirc Pump A speed. *TOUCH HS-B31-1S12A RX RECIRC LIMITER #2 (48%) RUNBACK RESET button AND *TOUCH RESET LIMITER #2 button Observe GEN lA SPEED SI-14032A remains steady. S/U TQ-106-l,;;,10 Revision 1 Page 5 of 12 9 Observes Recirc Pump A LIM2 runback resets. Observe the following:
+* OBSERVE HS-B31-1S12A RX RECIRC LIMITER #2 (48%)
-* # 2 LIMITER INITIATED status block background changes from RED to GRAY
+RUNBACK RESET button is ACTIVE EVALUATOR NOTE One minute time delay allows for Scoop Tube Positioner to make the final (0.111 %) position adjustment 7* I Depress the RX RECIRC LIMITER #2 (48%)               *TOUCH HS-B31-1S12A RX RECIRC RUNBACK RESET button.                                LIMITER #2 (48%) RUNBACK RESET button S/U AND
-* AR-102-CO 1 annunciator clears 1 O* RESET Limiter #2 Runback on 'B' Reactor Performs the following:
+                                                            *TOUCH RESET LIMITER #2 button 8 I Monitor Recirc Pump A speed.                         Observe GEN lA SPEED SI-14032A remains steady.
+TQ-106-u~ 10 '
+Revision 1 Page 6of12 9  Observes Recirc Pump A LIM2 runback resets.           Observe the following:
+                                                            * # 2 LIMITER INITIATED status block background changes from RED to         S/U GRAY
+* AR-102-CO 1 annunciator clears 1O*  RESET Limiter #2 Runback on 'B' Reactor               Performs the following:
 Recirculation Pump
-* VERIFY SY-B31-1R621B
+* VERIFY SY-B31-1R621B % Controller Output Signal is approximately 26.90%.
-% Controller Output Signal is approximately 26.90%. * *TOUCH DEC button RECIRC PUMP lA SPEED SY-B31-1R621B Controller
+                                                            *   *TOUCH DEC button RECIRC PUMP lA SPEED SY-B31-1R621B Controller
 * Observes a change in the following:
-Lowering of Gen 1 A Speed or on -SI 14032A {TRA037) 0 Lowering of Gen 1A Demand, on XI 14032A (TRA041) 0 Lowering of Scoop Tube 1A Position {TRA045) 0 Lowering of Loop 1A Drive Flow (APMF02) OBSERVE HS-B31-1S12B RX RECIRC LIMITER #2 ( 48%) RUNBACK RESET button is ACTIVE EVALUATOR NOTE One minute time delay allows for Scoop Tube Positioner to make the final (0.111 %) position adjustment S/U S/U 10 ' Revision 1 Page 6of12 11* Depress the RX RECIRC LIMITER #2 (48%) RUN8ACK RESET button. 12 Monitor Recirc Pump B speed. 13 Observes Recirc Pump B LIM2 runback resets. *TOUCH HS-831-1S128 RX RECIRC LIMITER #2 (48%) RUN8ACK RESET button AND *TOUCH RESET LIMITER #2 button Observe GEN lB SPEED SI-14032B is raising. Observe the following:
+  Lowering of Gen 1A Speed or on
-* # 2 LIMITER INITIATED status block background changes from RED to GRAY
+                         -
-* AR-102-C04 annunciator clears S/U SIU TQ-106-tJ-;j 10 Revision 1 Page 7 of 12 14* RESET Limiter #2 Runback on 'B' Reactor Performs the following:
+SI 14032A {TRA037) 0   Lowering of Gen 1A Demand, on  S/U XI 14032A (TRA041) 0   Lowering of Scoop Tube 1A Position {TRA045) 0   Lowering of Loop 1A Drive Flow (APMF02)
+OBSERVE HS-B31-1S12B RX RECIRC LIMITER #2 (48%) RUNBACK RESET button is ACTIVE EVALUATOR NOTE One minute time delay allows for Scoop Tube Positioner to make the final (0.111 %) position adjustment
+TQ-106-tJ-;j 10 Revision 1 Page 7 of 12 11* Depress the RX RECIRC LIMITER #2 (48%)      *TOUCH HS-831-1S128 RX RECIRC RUN8ACK RESET button.                       LIMITER #2 (48%) RUN8ACK RESET button S/U AND
+                                                *TOUCH RESET LIMITER #2 button 12 Monitor Recirc Pump B speed.                Observe GEN lB SPEED SI-14032B is raising.                             SIU 13 Observes Recirc Pump B LIM2 runback resets. Observe the following:
+                                                * # 2 LIMITER INITIATED status block background changes from RED to GRAY
+* AR-102-C04 annunciator clears
+TQ-106-lJ~ 10 Revision 1 Page 8 of 12 14*   RESET Limiter #2 Runback on 'B' Reactor         Performs the following:
 Recirculation Pump
-* VERIFY SY-B31-1R621B
+* VERIFY SY-B31-1R621B % Controller Output Signal is approximately 26.90%.
-% Controller Output Signal is approximately 26.90%. * *TOUCH DEC button RECIRC PUMP IA SPEED SY-B31-1R621B Controller
+                                                       *  *TOUCH DEC button RECIRC PUMP IA SPEED SY-B31-1R621B Controller
 * Observes a change in the following:
-Lowering of Gen 1A Speed or on SI 14032A (TRA037) 0 Lowering of Gen 1A Demand, on XI 14032A (TRA041) 0 Lowering of Scoop Tube 1A Position (TRA045) 0 Lowering of Loop 1A Drive Flow (APMF02)
+  Lowering of Gen 1A Speed or on SI 14032A (TRA037) 0   Lowering of Gen 1A Demand, on XI 14032A (TRA041) 0   Lowering of Scoop Tube 1A Position (TRA045) 0   Lowering of Loop 1A Drive Flow (APMF02)
-* OBSERVE HS-B31-1S12B RX RECIRC LIMITER #2 ( 48%) RUNBACK RESET button is ACTIVE EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials?
+* OBSERVE HS-B31-1S12B RX RECIRC LIMITER #2 (48%)
-Task Cue Sheets? Procedures?
+RUNBACK RESET button is ACTIVE EVALUATOR NOTE I CUE That completes the JPM.
-Revision 1 Page 8 of 12 REVISION
+EVALUATOR CUE Record JPM stop time:
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 10 of 12 REVISION
 ==SUMMARY==
-Revision 0 1 NewJPM JOB PERFORMANCE MEASURE 64.0N.67049.101 Description/Purpose of Revision This JPM was created by modifying 64.0N.2131.151.
-TQ-106-0310 Revision 1 Page 10 of 12 Page 11 of 12 EVALUATOR COPY: TASK CONDITIONS Unit 1 is in Mode 1. A trip of Condensate Pump 1 D has caused a Reactor Recirculation runback to occur. ON-RECIRC-101, Reactor Recirculation Malfunction, has been completed up to step C.18.d. A Critical Brief has been performed 1 D Condensate Pump has been restored INITIATING CUE Reset the Recirculation Pump limiter #2 runback for both Recirculation Pumps in accordance with AOP-164-001, Attachment B.
+JOB PERFORMANCE MEASURE 64.0N.67049.101 Revision                     Description/Purpose of Revision 0    NewJPM 1    This JPM was created by modifying 64.0N.2131.151.
-Page 12of12 EXAMINEE COPY: TASK CONDITIONS Unit 1 is in Mode 1. A trip of Condensate Pump 1 D has caused a Reactor Recirculation runback to occur. ON-RECIRC-101, Reactor Recirculation Malfunction, has been completed up to step C.18.d. A Critical Brief has been performed 1 D Condensate Pump has been restored INITIATING CUE Reset the Recirculation Pump limiter #2 runback for bofh Recirculation Pumps in accordance with AOP-164-001, Attachment B.
-SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Implement RFP Post Scram Recovery JPM#: 45.0P.21388.102 Revision:
+Page 11 of 12 EVALUATOR COPY:
-Date: 7/27/2016
+TASK CONDITIONS Unit 1 is in Mode 1.
--------Applicability: RO SRO Setting: __ ..;;;S=im=u=l--a
+A trip of Condensate Pump 1D has caused a Reactor Recirculation runback to occur.
-..... to .... r _______________
+ON-RECIRC-101, Reactor Recirculation Malfunction, has been completed up to step C.18.d.
-_ NUREG-1123 E/APE I Sys 259001 KIA Number _A_3_.0_7
+A Critical Brief has been performed 1D Condensate Pump has been restored INITIATING CUE Reset the Recirculation Pump limiter #2 runback for both Recirculation Pumps in accordance with AOP-164-001, Attachment B.
-____ K/A Importance 3.2 I 3.2 Alternate Path: DYES NO Time Critical DYES NO Validation Time (min):__..;;;2=0
-__ Date:
+Page 12of12 EXAMINEE COPY:
-Date: CJk0 b }c ' . Date:
+TASK CONDITIONS Unit 1 is in Mode 1.
-I Approval:
+A trip of Condensate Pump 1D has caused a Reactor Recirculation runback to occur.
-____.11/\_....__0--=-*
+ON-RECIRC-101, Reactor Recirculation Malfunction, has been completed up to step C.18.d.
-___ _ Nuclear TralniifgSupervisor Date:
+A Critical Brief has been performed 1D Condensate Pump has been restored INITIATING CUE Reset the Recirculation Pump limiter #2 runback for bofh Recirculation Pumps in accordance with AOP-164-001, Attachment B.
-Examinee Name: ------------------
-Last, First Ml Employee Number Exam Date: ---------Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Implement RFP Post Scram Recovery JPM#: 45.0P.21388.102                                  Revision:
------------
+                                                                  -------
-Name Signature Comments:
+        Date: 7/27/2016 Applicability: ~ RO ~ SRO Setting: _ _..;;;S=im=u=l--a.....
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 45.0P.21388.102 I. SAFETY CONSIDERATIONS A All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+to....r _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+NUREG-1123 E/APE I Sys 259001                            KIA Number _A_3_.0_7_ _ _ _K/A Importance 3.2 I 3.2 Alternate Path:   DYES ~             NO             Time Critical DYES ~       NO Validation Time (min):__..;;;2=0_ _
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+Date:   TJP-~L1&.
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+Date:
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+                                                                        'CJk0
-II. REFERENCES A OP-145-001, RFP AND RFP LUBE OIL SYSTEM (Rev. 84) Ill. TASK CONDITIONS Unit 1 scrammed from approximately 70 percent power. All 3 RFPs tripped on a spurious high RPV level signal following the scram. RPV level is being maintained at approximately
+                                                                          .     ~
--5" using RCIC and CRD IV. INITIATING CUE Restart a RFP and maintain RPV level -40" to -50". V. TASK STANDARD Places a RFP in-service in Discharge Pressure Mode and establishes a rising RPV level trend by injection through the HV-10641 SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 45.0P.21388.102 NOTE: It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
+b}c Date:  Cff~1,Ll6 I
+Approval:  ____.11/\_....__0--=-*--~-+...;;;;.....__ _ __        Date:   &deg;1 1 21*!~
+Nuclear TralniifgSupervisor Examinee Name:
+                     --           ----------------
+Last, First Ml                                                      Employee Number Exam Date:                                                      Exam Duration (Min): _ _ _ _ _ _ _ __
+              ---------
+Evaluation Result:        D Satisfactory               D Unsatisfactory Evaluator:
+           -----------
+Name                                                        Signature Comments:
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 45.0P.21388.102 I. SAFETY CONSIDERATIONS A       All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+B.      All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+C.      If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+D.      Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+II. REFERENCES A       OP-145-001, RFP AND RFP LUBE OIL SYSTEM (Rev. 84)
+Ill. TASK CONDITIONS Unit 1 scrammed from approximately 70 percent power.
+All 3 RFPs tripped on a spurious high RPV level signal following the scram.
+RPV level is being maintained at approximately -5" using RCIC and CRD IV. INITIATING CUE Restart a RFP and maintain RPV level -40" to -50".
+V. TASK STANDARD Places a RFP in-service in Discharge Pressure Mode and establishes a rising RPV level trend by injection through the HV-10641
+SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 45.0P.21388.102 NOTE:     It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
 : 1. Configure an exam-specific IC as follows
 * Reset to IC-20
@@ Line 625: / Line 1,025: @@
 * Insert Ni's
 * Verify RCIC initiates (or initiate and return collar to not armed)
-* Stabilizes RPV level at approximately
+* Stabilizes RPV level at approximately -45"
--45"
 * Trip 2 Condensate Pumps (to prevent condensate pump damage)
 * Reset Generator Lockouts
-* Override AR-108-E02 INFORMATION FOR EVALUATOR
+* Override AR-108-E02
-* Marking a step as UNSAT requires written comments on respective step. TQ-106-u-.:>
-Revision 1 Page 4of11
+TQ-106-u-.:> 10 Revision 1 Page 4of11 INFORMATION FOR EVALUATOR
+* Marking a step as UNSAT requires written comments on respective step.
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
 * The time clock starts when the candidate acknowledges the Initiating Cue.
-* This JPM must be performed in the simulator.
+* This JPM must be performed in the simulator. Reset to exam-specific IC, or configure the simulator per the Simulator Setup Instructions.
-Reset to exam-specific IC, or configure the simulator per the Simulator Setup Instructions.
+EVALUATOR CUE Record JPM start time:
-EVALUATOR CUE Record JPM start time: BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN. BOOTH OPERATOR CUE Adjust the RCIC flow controller setpoint to maintain RPV water level -60" to -50" during performance of the JPM. Step Action Standard Eva I Comments 1 Verifies OP-145-001 Attachment Bis governing Controlled copy of OP-145-001 obtained, S/U procedure and obtains controlled copy. select Attachment B. EVALUATOR NOTE The following step is critical only if more than two Condensate Pumps are running. This 'step is not required to be performed for successful completion of the JPM if only two Condensate Pumps are running in the simulator IC. 2* Stops 2 Condensate Pumps. Depress 1P102A(B)(C)(D), CONDENSATE PUMP, STOP PB as necessary to leave 2 S/U Condensate Pumps running. 2 Ensures all HV-10603A(B)(C)
+BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN.
-RFP A(B)(C) Observe HV-10603A(B)(C)
+BOOTH OPERATOR CUE Adjust the RCIC flow controller setpoint to maintain RPV water level -60" to -50" during performance of the JPM.
-RFP A(B)(C) S/U Discharge lso Viv closed. DISCHARGE ISO VLV indicate full closed. 3 Ensures all HV-10651A(B)(C)
+Step   Action                                                  Standard                                         Eva I  Comments 1   Verifies OP-145-001 Attachment Bis governing            Controlled copy of OP-145-001 obtained, S/U procedure and obtains controlled copy.                 select Attachment B.
-RFP A(B)(C) Startup Observe HV-10651A(B)(C)
+EVALUATOR NOTE The following step is critical only if more than two Condensate Pumps are running. This 'step is not required to be performed for successful completion of the JPM if only two Condensate Pumps are running in the simulator IC.
-RFP A(B)(C) S/U lso Viv closed. STARTUP ISO VLV indicate full closed.
+*   Stops 2 Condensate Pumps.                               Depress 1P102A(B)(C)(D), CONDENSATE PUMP, STOP PB as necessary to leave 2            S/U Condensate Pumps running.
-Ensures controller LIC-C32-1 R602, FW Lo Load On controller LIC-C32-1R602, FW LO Demand Signal to LV-10641, in MANUAL and 0 LOAD DEMAND SIGNAL TO LV-10641, percent output. perform the following:
+  Ensures all HV-10603A(B)(C) RFP A(B)(C)                 Observe HV-10603A(B)(C) RFP A(B)(C)
-* Depress MAN PB
+S/U Discharge lso Viv closed.                               DISCHARGE ISO VLV indicate full closed.
-* Depress single-or double-DEC PB until % CONTROLLER OUTPUT indicates 0 percent 5 Ensures 2 NR RPV level instruments indicate <54" Observe any 2 of NAR RNG A(B)(C) on FW HMI. indicate less <54". 6* Open RFPT A(B)(C) steam supply isolation valves. At 1 C668, depress RFPT A(B)(C) LP ISO HV-12709A(B)(C)
+  Ensures all HV-10651A(B)(C) RFP A(B)(C) Startup         Observe HV-10651A(B)(C) RFP A(B)(C)
-OPEN PB. EVALUATOR NOTE The RESET A(B)(C) RFPT TRIP PB must be depressed for approximately 5 seconds to reset the RFPT. 7* Reset RFPT A(B)(C) trip. Perform the following:
+S/U lso Viv closed.                                         STARTUP ISO VLV indicate full closed.
-* Select RFP _A(B)(C) screen
+TQ-106-(J;:>-10 Revision 1 Page 5of11 4 Ensures controller LIC-C32-1 R602, FW Lo Load    On controller LIC-C32-1R602, FW LO Demand Signal to LV-10641, in MANUAL and 0       LOAD DEMAND SIGNAL TO LV-10641, percent output.                                  perform the following:
+* Depress MAN PB                         SIU
+* Depress single- or double-DEC PB until
+                                                          % CONTROLLER OUTPUT indicates 0 percent 5 Ensures 2 NR RPV level instruments indicate <54" Observe any 2 of NAR RNG A(B)(C)
+S/U on FW HMI.                                       indicate less <54".
+*  Open RFPT A(B)(C) steam supply isolation valves. At 1C668, depress RFPT A(B)(C) LP ISO S/U HV-12709A(B)(C) OPEN PB.
+EVALUATOR NOTE The RESET A(B)(C) RFPT TRIP PB must be depressed for approximately 5 seconds to reset the RFPT.
+*  Reset RFPT A(B)(C) trip.                         Perform the following:
+* Select RFP_A(B)(C) screen               I
 * Depress A(B)(C) RFPT TRIPPED PB
-* On overlay HS-12745A2(82)(C2), RFPT A(B)(C) TRIP RESET SWITCH, depress RESET PB
+* On overlay HS-12745A2(82)(C2), RFPT A(B)(C) TRIP RESET SWITCH, depress S/U RESET PB
 * Depress ENABLE RESET PB
-* Depress and hold RESET A(B)(C) RFPT TRIP PB until RFP A(B)(C) icon indicates Reset 8* Places RFPT A(B)(C) valve control in AUTO Depress the A(B)(C) RFPT AUTO VLV CTL ,PB and observes it backlit YELLOW. SIU S/U S/U I S/U S/U TQ-106-(J;:>-10 Revision 1 Page 5of11
+* Depress and hold RESET A(B)(C) RFPT TRIP PB until RFP A(B)(C) icon indicates Reset 8* Places RFPT A(B)(C) valve control in AUTO        Depress the A(B)(C) RFPT AUTO VLV CTL S/U
-*9 Places RFPT A(B)(C) in Idle mode. 10* Stops RFP A turning gear when RFPT A speed is > 100 rpm and then returns to AUTO. 11* Places RFPT A(B)(C) in Discharge Pressure Mode. Perform the following:
+                                                       ,PB and observes it backlit YELLOW.
-* Observe controller FIC-10604A(B)(C)
-RX FEED PUMP A(B)(C) RECIRC FLOW in AUTO * *Depress A(B)(C) IDLE MODE PB and then depress I OLE MODE PB
+TQ-106-0siO Revision 1 Page 6of11
-* On controller FIC-10604A(B)(C), RX FEED PUMP A RECIRC FLOW, depress the MAN PB and then the single-and double-chevron I NC PB as necessary to raise RFP flow as indicated on Fl-10604A, RFP FLOW, > 600 gpm * *When RFP A(B)(C) recirc flow indicates
+  *9 Places RFPT A(B)(C) in Idle mode.               Perform the following:
-> 600 gpm, depress 1,000 RPMS PB
+* Observe controller FIC-10604A(B)(C) RX FEED PUMP A(B)(C) RECIRC FLOW in AUTO
-* On controller FIC-10604A(B)(C), RX FEED PUMP A RECIRC FLOW, depress the AUTO PB Observe RFPT A turning gear is OFF and in AUTO. Perform the following:
+                                                    * *Depress A(B)(C) IDLE MODE PB and then depress I OLE MODE PB
-* Selects RFP _A(B)(C) screen * *Depress the A(B)(C) RFPT DSCH PRESS MODE PB AND then depresses the INITIATE DSH PRSS MODE PB
+* On controller FIC-10604A(B)(C), RX FEED PUMP A RECIRC FLOW, depress the MAN PB and then the single- and     S/U double-chevron INC PB as necessary to raise RFP flow as indicated on Fl-10604A, RFP FLOW, > 600 gpm
-* After 30 seconds, observe A(B)(C) RFPT DSCH PRESS MODE PB YELLOW
+                                                    * *When RFP A(B)(C) recirc flow indicates
+                                                      > 600 gpm, depress 1,000 RPMS PB
+* On controller FIC-10604A(B)(C), RX FEED PUMP A RECIRC FLOW, depress the AUTO PB 10* Stops RFP A turning gear when RFPT A speed is   Observe RFPT A turning gear is OFF and in S/U
+    > 100 rpm and then returns to AUTO.             AUTO.
+* Places RFPT A(B)(C) in Discharge Pressure Mode. Perform the following:
+* Selects RFP_A(B)(C) screen
+                                                    * *Depress the A(B)(C) RFPT DSCH PRESS MODE PB AND then depresses the INITIATE DSH PRSS MODE PB
+* After 30 seconds, observe A(B)(C) RFPT SIU DSCH PRESS MODE PB YELLOW
 * Observe HV-10651A(B)(C) stroke FULL OPEN
 * Observe RFP A(B)(C) pressure rise approximately 120 psig above reactor pressure.
-S/U S/U SIU TQ-106-0siO Revision 1 Page 6of11 EVALUATOR CUE TQ-106-CJ;;;
-I 0 Revision 1 Page 7of11 It is required to raise RFP A discharge pressure for DPM per Step 17 of the hard card. (Only needed for time compression, if cue not given skip step 13) 12* Establishes RFPT A(B)(C) discharge pressure for On controller SIC-C32-1 R601A(B)(C)
+TQ-106-CJ;;; I 0 Revision 1 Page 7of11 EVALUATOR CUE It is required to raise RFP A discharge pressure for DPM per Step 17 of the hard card. (Only needed for time compression, if cue not given skip step 13) 12*   Establishes RFPT A(B)(C) discharge pressure for      On controller SIC-C32-1 R601A(B)(C) RFP DPM.                                                 A(B)(C) SPD CTL/DEMAND SIGNAL perform the following:
-RFP DPM. A(B)(C) SPD CTL/DEMAND SIGNAL perform the following:
+* Depress MAN PB                               S/U
-* Depress MAN PB S/U
+* Depress single- and/or double-chevron INC and DEC PB as necessary to obtain approximately 55% on SPD DMD (STPT)
-* Depress single-and/or double-chevron INC and DEC PB as necessary to obtain approximately 55% on SPD DMD (STPT)
+* Depress AUTO PB 13*   Adjusts LV-10641 FW LO LOAD VALVE                    Perform the following on controller LIC-C32-1 R602 controller to slowly raise reactor    LIC-C32-1R602 FW LO LOAD VALVE water level.
-* Depress AUTO PB 13* Adjusts LV-10641 FW LO LOAD VALVE Perform the following on controller LIC-C32-1 R602 controller to slowly raise reactor LIC-C32-1R602 FW LO LOAD VALVE water level.
+* Depress single- and double-chevron INC       S/U PB as necessary to raise controller output to desired level EVALUATOR CUE When flow is indicated from RFP A, inform the examinee RCIC has been secured and that the examinee            S/U has control of RPV level.
-* Depress single-and double-chevron INC S/U PB as necessary to raise controller output to desired level EVALUATOR CUE When flow is indicated from RFP A, inform the examinee RCIC has been secured and that the examinee S/U has control of RPV level. BOOTH OPERATOR CUE S/U When flow is indicated from RFP A, place the RCIC flow controller to manual at O percent output. EVALUATOR NOTE I CUE That completes the JPM. -EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials?
+BOOTH OPERATOR CUE S/U When flow is indicated from RFP A, place the RCIC flow controller to manual at O percent output.
-Task Cue Sheets? Procedures?
+EVALUATOR NOTE I CUE That completes the JPM.
+EVALUATOR CUE
+                      -
+Record JPM stop time:
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
 TQ-106-0310 Revision 1 Page 9of11 REVISION
 ==SUMMARY==
-Revision 0 1 NewJPM JOB PERFORMANCE MEASURE 45.0P.21388.102 Description/Purpose of Revision Revised to modify faulted JPM 45.0P.4677.152.
-This revision eliminates the faulted aspect of the JPM. A JPM without a fault could not be found for this task, therefore this is a modified JPM.
+JOB PERFORMANCE MEASURE 45.0P.21388.102 Revision                        Description/Purpose of Revision 0      NewJPM Revised to modify faulted JPM 45.0P.4677.152. This revision eliminates 1      the faulted aspect of the JPM. A JPM without a fault could not be found for this task, therefore this is a modified JPM.
-Page 10of11 EVALUATOR COPY: TASK CONDITIONS Unit 1 scrammed from approximately 70 percent power. All 3 RFPs tripped on a spurious high RPV level signal following the scram. RPV level is being maintained at approximately
--50" using RCIC and CRD INITIATING CUE Restart a RFP and restore RPV level -40" to -50".
+Page 10of11 EVALUATOR COPY:
-Page 11 of 11 EXAMINEE COPY: TASK CONDITIONS Unit 1 scrammed from approximately 70 percent power. All 3 RFPs tripped on a spurious high RPV level signal following the scram. RPV level is being maintained at approximately-50" using RCIC and CRD INITIATING CUE Restart a RFP and restore RPV level -40" to -50". (
+TASK CONDITIONS Unit 1 scrammed from approximately 70 percent power.
-SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Open MSIVs During Reactor Startup (All Rods In) JPM#: 84.0P.24667.151 Revision:!
+All 3 RFPs tripped on a spurious high RPV level signal following the scram.
-Date:07/07/2016 Applicability: RO SRO Setting: Simulator NUREG-1123 E/APE I Sys239001 KJA Number A4.01 KJA Importance 4.2 Alternate Path:
+RPV level is being maintained at approximately -50" using RCIC and CRD INITIATING CUE Restart a RFP and restore RPV level -40" to -50".
-NO Time Critical DYES NO Validation Time (min):25 Testing Method: D Simulate Date: 07/07/2016 Date: cJ/z(,,,/((yz Validated:
-____ Date: 1b "i (/t Approval:
+Page 11 of 11 EXAMINEE COPY:
-___
+TASK CONDITIONS Unit 1 scrammed from approximately 70 percent power.
-...... 11,..._, ....,..lA.....,)......._J2
+All 3 RFPs tripped on a spurious high RPV level signal following the scram.
-.....
+RPV level is being maintained at approximately-50" using RCIC and CRD INITIATING CUE Restart a RFP and restore RPV level -40" to -50".
-Date: 7'
+(
-* Z. 'J' 16 Nuclear Training Supervisor Last, First Ml Employee Number Exam Date: ________ _ Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
------------
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Open MSIVs During Reactor Startup (All Rods In)
-Name Signature Comments:
+JPM#: 84.0P.24667.151                                                 Revision:!              Date:07/07/2016 Applicability: ~ RO ~ SRO Setting: Simulator NUREG-1123 E/APE I Sys239001 KJA Number A4.01 KJA Importance 4.2 Alternate Path: ~YES                 0        NO           Time Critical DYES ~ NO Validation Time (min):25 Testing Method: D Simulate Date: 07/07/2016 Date:  cJ/z(,,,/((yz Validated:  --;~.=.;:;~~__:::::;.....__                   ____          Date:  1b "i (/t Approval: ___!_~k......                            .....~.._.---- Date:
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 84.0P.24667.151 I. SAFETY CONSIDERATIONS A All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+,..._,....,..lA.....,)......._J2                         7'
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+* Z. 'J' 16 Nuclear Training Supervisor Last, First Ml                                                             Employee Number Exam Date: _ _ _ _ _ _ _ __                                            Exam Duration (Min): _ _ _ _ _ _ _ __
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+Evaluation Result:         D         Satisfactory             D  Unsatisfactory Evaluator:
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+           -----------
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+Name                                                              Signature Comments:
-II. REFERENCES A. G0-100-002, Plant Startup, Heatup and Power Operations (Rev 105) B. OP-184-001, Main Steam System (Rev 37) C. ON-193-001, Turbine EHC System Malfunction (Rev 24) Ill. TASK CONDITIONS Unit 1 startup is in progress in accordance with G0-100-002.
-The reactor is at the POAH. Reactor startup will continue after the MSIV s are open. Reactor pressure is 10 psig and reactor coolant temperature is 240 &deg;F. The operator will perform all control room actions. IV. INITIATING CUE Open the MSIVs per OP-184-001 Section 2.3. V. TASK STANDARD Open MSIVs for reactor startup. Close the MSIV's when the turbine bypass valves fail open.
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 84.0P.24667.151 I. SAFETY CONSIDERATIONS A       All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 84.0P.24667.151 NOTE: It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
+B.      All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
-: 1. Reset the simulator to a hot startup IC at POAH. Scram the reactor and then reset the scram. Establish reactor pressure and stabilize no higher than 10 psig. 2. Run scenario file EVAL840P24667151.scn
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
-;Overides alarm horns on oc653 and lc668 IOR do0C653HRN1 f:OFF IOR do0C653HRN2 f:OFF IOR do1C668HRN f:OFF ;Fails A EHC PT to 1000 psig ;Cause all the BPVs to open {Key[l]} IMF mfTC193002A f:1000 3. Other Adjust RWCU blowdown flow if necessary to stabilize reactor level at approximately 35" and place the RWCU blowdown flow controller back to AUTO.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
-INFORMATION FOR EVALUATOR
+C.      If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
-* Marking a step as UNSAT requires written comments on respective step . T0,106-0;:,*10 Revision 1 Page 4of12
+D.      Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+II. REFERENCES A. G0-100-002, Plant Startup, Heatup and Power Operations (Rev 105)
+B. OP-184-001, Main Steam System (Rev 37)
+C. ON-193-001, Turbine EHC System Malfunction (Rev 24)
+Ill. TASK CONDITIONS Unit 1 startup is in progress in accordance with G0-100-002.
+The reactor is at the POAH.
+Reactor startup will continue after the MSIV s are open.
+Reactor pressure is 10 psig and reactor coolant temperature is 240 &deg;F.
+The operator will perform all control room actions.
+IV. INITIATING CUE Open the MSIVs per OP-184-001 Section 2.3.
+V. TASK STANDARD Open MSIVs for reactor startup. Close the MSIV's when the turbine bypass valves fail open.
+SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 84.0P.24667.151 NOTE:      It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
+: 1. Reset the simulator to a hot startup IC at POAH. Scram the reactor and then reset the scram.
+Establish reactor pressure and stabilize no higher than 10 psig.
+: 2. Run scenario file EVAL840P24667151.scn
+   ;Overides alarm horns on oc653 and lc668 IOR do0C653HRN1 f:OFF IOR do0C653HRN2 f:OFF IOR do1C668HRN f:OFF
+   ;Fails A EHC PT to 1000 psig
+   ;Cause all the BPVs to open
+{Key[l]} IMF mfTC193002A f:1000
+: 3. Other Adjust RWCU blowdown flow if necessary to stabilize reactor level at approximately 35" and place the RWCU blowdown flow controller back to AUTO.
+T0,106-0;:,*10 Revision 1 Page 4of12 INFORMATION FOR EVALUATOR
+* Marking a step as UNSAT requires written comments on respective step .
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
 * The time clock starts when the candidate acknowledges the initiating cue.
-* This JPM must be performed in the simulator.
+* This JPM must be performed in the simulator. Reset to exam-specific IC, or configure the simulator per the Simulator Setup Instructions.
-Reset to exam-specific IC, or configure the simulator per the Simulator Setup Instructions.
+EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.
-EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Refers to OP-184-001 Section 2.3. Obtains controlled copy. controlled copy of OP-184-001 and selects S/U section 2.3. *2 Reset Main Steam Line Isolation logic Performs the following
+BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN.
+EVALUATOR CUE Record JPM start time:
+Step   Action                                                Standard                                           Eva I  Comments 1 Identifies governing procedure and obtain               Refers to OP-184-001 Section 2.3. Obtains controlled copy.                                      controlled copy of OP-184-001 and selects          S/U section 2.3.
+   *2   Reset Main Steam Line Isolation logic                 Performs the following
 * Ensure All MSIV control switches in CLOSE position
-* Reset Main Steam Line Isolation by Depressing Mn Stm Line Div 1 Iso Reset S/U HS B21 1S32 push button.
+* Reset Main Steam Line Isolation by Depressing Mn Stm Line Div 1 Iso Reset         S/U HS B21 1S32 push button.
-* Reset Main Steam Line Isolation by Depressing Mn Stm Line Div 2 Iso Reset HS B21 1S33 push button. 3 Enters TRO 3.8.2.1 Informs Unit Supervisor to take TRO S/U 3.8.2.1. EVALUATOR CUE TRO 3.8.2.1 taken.
+* Reset Main Steam Line Isolation by Depressing Mn Stm Line Div 2 Iso Reset HS B21 1S33 push button.
-Place MOY overloads in service. *5 Open outboard MSIV s 6 Open Main Steam Line Drains Performs the following:
+Enters TRO 3.8.2.1                                      Informs Unit Supervisor to take TRO S/U 3.8.2.1.
-* Place AC MOY OL BYPS HS-B21-1S37A Keyswitch to TEST Position.
+EVALUATOR CUE TRO 3.8.2.1 taken.
+TQ-106-0;n 0 Revision 1 Page 5 of 12 4 Place MOY overloads in service. Performs the following:
+* Place AC MOY OL BYPS HS-B21-1S37A Keyswitch to TEST Position.                            S/U
 * Place DC MOY OL BYPS HS-B21-1S37B Keyswitch to TEST Position.
-Performs the following:
+*5 Open outboard MSIV s            Performs the following:
 * Place Mn Stm Line A OB Iso HV-141-F028A control switch to AUTO.
 * Place Mn Stm Line B, OB Iso HV-141-F028B, control switch to AUTO.
 * Place Mn Stm Line C, OB Iso HV-141-F028C, control switch to AUTO.
-* Place Mn Stm Line D, OB Iso HV-141-F028D, control switch to AUTO.
+* Place Mn Stm Line D, OB Iso          S/U HV-141-F028D, control switch to AUTO.
 * Check Outboard MSIV OPENS by observing Red indicating light ILLUMINATED.
-HV-141-F028A OPEN 0 HV-141-F028B OPEN 0 HV-141-F028C OPEN 0 HV-141-F028D OPEN Open following Main Steam Line Drain Valves:
+  HV-141-F028A OPEN 0   HV-141-F028B OPEN 0   HV-141-F028C OPEN 0   HV-141-F028D OPEN 6 Open Main Steam Line Drains     Open following Main Steam Line Drain Valves:
+S/U
 * Mn Stm Line IB Drain HV-141-F016
-* Main Stm Line OB Drain HV-141-F019 S/U S/U S/U TQ-106-0;n 0 Revision 1 Page 5 of 12 7 Bypass MOV overloads 8 Drain Main Steam lines *9 Open Inboard MSIV s WAIT 2 minutes, THEN:
+* Main Stm Line OB Drain HV-141-F019
-* Place AC MOV OL BYPS HS-B21-1S37A Keyswitch to NORM position
-* Place DC MOV OL BYPS HS-B21-1S37B Keyswitch to NORM position Performs the following:
+TQ-106-0.:> I 0 Revision 1 Page 6of12 7 Bypass MOV overloads   WAIT 2 minutes, THEN:
+* Place AC MOV OL BYPS HS-B21-1S37A Keyswitch to NORM position       S/U
+* Place  DC MOV OL BYPS HS-B21-1S37B Keyswitch to NORM position 8 Drain Main Steam lines Performs the following:
 * Jog Open Mn Stm Line Drain To Cdsr HV-141-F021.
-* AFTER 1 minute, Close Mn Stm Line Drain To Cdsr HV-141-F021.
+* AFTER 1 minute, Close Mn Stm Line        S/U Drain To Cdsr HV-141-F021.
-* Open Mn Steam Line Warm up HV-141F020.
+* Open Mn Steam Line Warmup HV-141F020.
-Performs the following
+*9 Open Inboard MSIV s    Performs the following
-* Place in MANUAL L V-10641 FW STARTUP CONTROL VLV. * *Open Inboard MSIV by Placing Mn Stm Line A IB Iso HV-141-F022A control switch to AUTO.
+* Place in MANUAL LV-10641 FW STARTUP CONTROL VLV.
-* WHEN power, pressure, level stabilizes THEN Open Inboard MSIV's as follows: 0 *Place Mn Stm Line B, IB Iso HV -141-F022B, control switch to AUTO. 0 *Place Mn Stm Line C, IB Iso HV -141-F022C, control switch to AUTO. 0 *Place Mn Stm Line D, IB Iso HV-141-F022D, control switch to AUTO. Check each Inboard MSIV OPENS by observing Red indicating light ILLUMINATED.
+                          * *Open Inboard MSIV by Placing Mn Stm Line A IB Iso HV-141-F022A control switch to AUTO.
-S/U S/U S/U TQ-106-0.:>
+* WHEN power, pressure, level stabilizes THEN Open Inboard MSIV's as follows:
-I 0 Revision 1 Page 6of12 FAULT STATEMENT TQ-106-0.:>-IO Revision 1 Page 7 of 12 AFTER THE LAST INBOARD MSIV HAS BEEN OPENED, THE "A" EHC PRESSURE TRANSMITTER OUTPUT WILL FAIL TO 1000 PSIG WHICH WILL CAUSE ALL THE TURBINE BYPASS VALVES TO OPEN AND DEPRESSURIZE THE REACTOR. BOOTH OPERATOR CUE After the last inboard MSIV has been opened, depress Key 1 to initiate bypass valves opening due to failure of the 'A' EHC pressure transmitter.
+*Place Mn Stm Line B, IB Iso HV -   S/U 141-F022B, control switch to AUTO.
-Recognize EHC malfunction Observes the following:
+*Place Mn Stm Line C, IB Iso HV -
-* Alarm -MAIN TURBINE BYPASS VALVES OPEN (AR 105 106) SIU
+-F022C, control switch to AUTO.
+*Place Mn Stm Line D, IB Iso HV-141-F022D, control switch to AUTO.
+Check each Inboard MSIV OPENS by observing Red indicating light ILLUMINATED.
+TQ-106-0.:>-IO Revision 1 Page 7 of 12 FAULT STATEMENT AFTER THE LAST INBOARD MSIV HAS BEEN OPENED, THE "A" EHC PRESSURE TRANSMITTER OUTPUT WILL FAIL TO 1000 PSIG WHICH WILL CAUSE ALL THE TURBINE BYPASS VALVES TO OPEN AND DEPRESSURIZE THE REACTOR.
+BOOTH OPERATOR CUE After the last inboard MSIV has been opened, depress Key 1 to initiate bypass valves opening due to failure of the 'A' EHC pressure transmitter.
+  Recognize EHC malfunction                               Observes the following:
+* Alarm - MAIN TURBINE BYPASS VALVES OPEN (AR 105 106)                SIU
 * All turbine bypass valves open
-* Reactor pressure lowering EVALUATOR NOTE Due to the failure of the EHC system to automatically control reactor pressure, the operators are authorized to close MSIV s without a procedure reference in order to mitigate the effects of the failure. ON-193-00lstep 3.7 provides procedural direction to close MSIVs and scram the reactor if the reactor is startup and <861 psig. 11 Scram the Reactor Places the Mode Switch to Shutdown S/U
+* Reactor pressure lowering EVALUATOR NOTE Due to the failure of the EHC system to automatically control reactor pressure, the operators are authorized to close MSIV s without a procedure reference in order to mitigate the effects of the failure. ON-193-00lstep 3.7 provides procedural direction to close MSIVs and scram the reactor if the reactor is startup and <861 psig.
-*12 Close MSIV's. Prior to reactor pressure going below 0 psig, close MSIV' s and drains by performing the following:
+  Scram the Reactor                                       Places the Mode Switch to Shutdown              S/U
+TQ-106-0.:> I 0 Revision 1 Page 8of12
+  *12   Close MSIV's.                                  Prior to reactor pressure going below 0 psig, close MSIV' s and drains by performing the following:
 * Place MN STM Line A, OB ISO HV 141 F028A, Control Switch to CLOSE.
 * Place MN STM Line BOB ISO HV 141 F028B Control Switch to CLOSE.
 * Place MN STM Line C, OB ISO HV 141 F028C, Control Switch to CLOSE.
 * Place MN STM Line D OB ISO HV 141 F028D, Control Switch to CLOSE.
+SIU
 * Place MN STM Line A IB ISO HV 141 F022A Control Switch to CLOSE.
-* Place MN STM Line BIB ISO HV 141 ' F022B Control Switch to CLOSE. *, Place MN STM Line C IB ISO HV 141 F022C Control Switch to CLOSE.
+* Place MN STM Line BIB ISO HV 141
+                                      '                     F022B Control Switch to CLOSE.
+                                                        *, Place MN STM Line C IB ISO HV 141 F022C Control Switch to CLOSE.
 * Place MN STM Line D IB ISO HV 141 F022D Control Switch to CLOSE.
 * Check Inboard MSIV Opens by Observing Red Indicating Light ILLUMINATED.
-EVALUATOR NOTE I CUE That completes the JPM. -EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials?
+EVALUATOR NOTE I CUE That completes the JPM.                                                                   -
-Task Cue Sheets? Procedures?
+EVALUATOR CUE Record JPM stop time:
-SIU TQ-106-0.:>
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
-I 0 Revision 1 Page 8of12 TQ-106-0310 Revision 1 Page 10of12 REVISION
+TQ-106-0310 Revision 1 Page 10of12 REVISION
 ==SUMMARY==
-Revision 0 1 New JP,M I JOB PERFORMANCE MEASURE 84.0P.24667.151 Description/Purpose of Revision JPM revised to incorporated referenced document revisions.
-Also, revised to put JPM in the new format.
+JOB PERFORMANCE MEASURE 84.0P.24667.151 Revision                       Description/Purpose of Revision 0    New JP,M I
-EVALUATOR COPY: TASK CONDITIONS Unit 1 startup is in progress in accordance with G0-100-002.
+JPM revised to incorporated referenced document revisions. Also, revised to 1
-The reactor is at the POAH. Reactor startup will continue after the MSIV s are open. Reactor pressure is 10 psig and reactor coolant temperature is 240 &deg;F. The operator will perform all control room actions. INITIATING CUE Open the MSIVs per OP-184-001 Section 2.3. Page 11of12 EXAMINEE COPY: TASK CONDITIONS Unit 1 startup is in progress in accordance with G0-100-002.
+put JPM in the new format.
-The reactor is at the POAH. Reactor startup will continue after the MSIV s are open. Reactor pressure is 10 psig and reactor coolant temperature is 240 &deg;F. The operator will perform all control room actions. INITIATING CUE Open the MSIVs per OP-184-001 Section 2.3. Page 12of12 SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Shutdown Cooling Temperature Control JPM#: 49.0N.20294.151 Revision:3 Date:07/07/2016 Applicability: RO SRO Setting: Simulator NUREG-1123 E/APE I Sys223002 KIA Number K1.08 KIA Importance 3.4/3.5 Alternate Path: YES 0 NO Time Critical DYES NO Validation Time (min):25 Testing Method: D Simulate Author::Greg van den Berg Date: 07/07/2016 Operations Review:
-........._
+Page 11of12 EVALUATOR COPY:
-Date: r/u Validated:
+TASK CONDITIONS Unit 1 startup is in progress in accordance with G0-100-002.
-...... Mf ____ / ________ Date:
+The reactor is at the POAH.
-I It Approval: l .fLe Date: '7 ""l C7
+Reactor startup will continue after the MSIV s are open.
-* IC, Nuclear Training Supervisor Last, First Ml Employee Number Exam Date: ---------Exam Duration Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+Reactor pressure is 10 psig and reactor coolant temperature is 240 &deg;F.
-"'-------------
+The operator will perform all control room actions.
-Name Signature Comments:
+INITIATING CUE Open the MSIVs per OP-184-001 Section 2.3.
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 49.0N.20294.151 1 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+Page 12of12 EXAMINEE COPY:
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+TASK CONDITIONS Unit 1 startup is in progress in accordance with G0-100-002.
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+The reactor is at the POAH.
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+Reactor startup will continue after the MSIV s are open.
-: 11. REFERENCES A. ON-SDC-101, Loss of Shutdown Cooling (Rev. 1) B. OP-149-002, RHR Shutdown Cooling (Rev. 72) C. AOP-149-001, RHR Abnormal Operating Procedure (Rev 0) Ill. TASK CONDITIONS Unit 1 is in MODE 4, 2 days into an outage. Reactor coolant temperature is 170 &deg;P. Time to 200 &deg;P is approximately 45 minutes. Section 2.22 (Operation of SDC in Mode 4 or 5) of OP-149-002 has NOT been performed.
+Reactor pressure is 10 psig and reactor coolant temperature is 240 &deg;F.
-TRO 3.8.2.1 has been entered for SDC temperature control. An operator has been assigned to perform a S0-100-011 during the cooldown.
+The operator will perform all control room actions.
-IV. INITIATING CUE Lower reactor coolant temperature to 140&deg;P in accordance with OP-149-002, Attachment E, step 6. V. TASK STANDARD Manipulate RHR to lower reactor coolant temperature.
+INITIATING CUE Open the MSIVs per OP-184-001 Section 2.3.
-Restore SDC following SOC isolation.
-SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 49.0N.20294.151 NOTE: It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Shutdown Cooling Temperature Control JPM#: 49.0N.20294.151                              Revision:3              Date:07/07/2016 Applicability: ~ RO ~ SRO Setting: Simulator NUREG-1123 E/APE I Sys223002 KIA Number K1.08 KIA Importance 3.4/3.5 Alternate Path: ~ YES      0  NO     Time Critical DYES ~ NO Validation Time (min):25 Testing Method: D Simulate        ~ ~erform Author::Greg van den Berg       ~                     Date: 07/07/2016 Operations Review:      C..~                . . ._  Date:    r/u b~
+Validated:  -..-~-C-~--. .Mf
+                          . ____/________ Date: cr1~~I It Approval:     ~ l ~ .fLe                            Date:    '7 ""lC7
+* IC, Nuclear Training Supervisor Last, First Ml                                                Employee Number Exam Date:                                          Exam Duration (Min~=---------
+             ---------
+Evaluation Result:   D Satisfactory     D Unsatisfactory Evaluator:
+          "'-------------
+Name                                           Signature Comments:
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 49.0N.20294.151 1
+I. SAFETY CONSIDERATIONS A.      All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+B.      All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+C.      If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+D.      Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+: 11. REFERENCES A. ON-SDC-101, Loss of Shutdown Cooling (Rev. 1)
+B. OP-149-002, RHR Shutdown Cooling (Rev. 72)
+C. AOP-149-001, RHR Abnormal Operating Procedure (Rev 0)
+Ill. TASK CONDITIONS Unit 1 is in MODE 4, 2 days into an outage.
+Reactor coolant temperature is 170 &deg;P.
+Time to 200 &deg;P is approximately 45 minutes.
+Section 2.22 (Operation of SDC in Mode 4 or 5) of OP-149-002 has NOT been performed.
+TRO 3.8.2.1 has been entered for SDC temperature control.
+An operator has been assigned to perform a S0-100-011 during the cooldown.
+IV. INITIATING CUE Lower reactor coolant temperature to 140&deg;P in accordance with OP-149-002, Attachment E, step 6.
+V. TASK STANDARD Manipulate RHR to lower reactor coolant temperature. Restore SDC following SOC isolation.
+SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 49.0N.20294.151 NOTE:       It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
 : 1. Reset the simulator to IC 272 'B' Loop of RHR in Shutdown Cooling
 * Place the simulator in RUN.
 * Open RHR F048B
-* Adjust RHR flow to 10,000 gpm and RHRSW flow to 9000 gpm. 2. Run scenario file EVAL490N20294151 IC SETUP.SCN to lower ESW temperature.
+* Adjust RHR flow to 10,000 gpm and RHRSW flow to 9000 gpm.
-The scenario will take 5 min to complete.
+: 2. Run scenario file EVAL490N20294151 IC SETUP.SCN to lower ESW temperature. The scenario will take 5 min to complete.
-:00:00 IRF r fE N009002 f:45 00:00:01 IRF rfEN100005 f:45 00:00:02 set ypxfstctwbasin=100 00:00:03 set ypxfsttsprpond=100 00:05:02 set ypxfstctwbasin=l 00:05:03 set ypxfsttsprpond=l
+:00:00      IRF  r fE N009002 f:45 00:00:01      IRF  rfEN100005 f:45 00:00:02      set  ypxfstctwbasin=100 00:00:03      set  ypxfsttsprpond=100 00:05:02      set  ypxfstctwbasin=l 00:05:03      set  ypxfsttsprpond=l
 : 3. Run scenario file EVAL490N20294151.SCN IMF cmfMV01_HV151F007A
-{Key[l]} IMF cmfMV05_HV151F009 c:20 INFORMATION FOR EVALUATOR
+{Key[l]} IMF cmfMV05_HV151F009 c:20
+TQ-106-u~ 10 Revision 1 Page 4of11 INFORMATION FOR EVALUATOR
 * Marking a step as UNSAT requires written comments on respective step .
-Revision 1 Page 4of11
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
 * The time clock starts when the candidate acknowledges the initiating cue.
-* This JPM must be performed in the simulator.
+* This JPM must be performed in the simulator. Reset to exam-specific IC, or configure the simulator per the Simulator Setup Instructions.
-Reset to exam-specific IC, or configure the simulator per the Simulator Setup Instructions.
+EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.
-EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OP-149-002 S/U controlled copy. Att. E, SDC Temperature Control. 2 Ensure TRO 3.8.2.1 is entered. Confirms TRO 3.8.2.1 is entered per initial S/U conditions 3 Places HS-Ell-1S62B RHR LOOP B MOV OL Place keyswitch to TEST S/U BYPS keyswitch to TEST EVALUATOR NOTE Due to RHR conditions (F003B and F047B open and RHRSW and RHR at maximum flow), the only option for 'lowering temperature is to throttle closed F048B) *4 Operates RHR B to lower reactor coolant Throttle Closed on HV-151-F048B RHR HX S/U temperature B SHELL SIDE BYPS 5 AFTER 2 minutes, Place HS-El l-1S62B RHR AFTER 2 minutes, place keyswitch to S/U LOOP A MOV OL BYPS keyswitch to OPERATE NORM FAULT STATEMENT TQ-106-CJ..110 Revision 1 Page 5 of 11 HV-151-F009, SDC SUCTION OB ISOLATION VAL VE SPURIOUS CLOSURE OCCURS WHILE LOWERING REACTOR COOLANT TEMPERATURE BOOTH OPERATOR CUE After reactor coolant temperature begins to lower (indicated by RHR HX Inlet temperature) or when directed by the evaluator, depress Key 1 to initiate spurious isolation of F009 and cause a loss of SDC. EVALUATOR NOTE Examinee will investigate isolation ofHV-151-F009 6 Enters and obtains a copy of ON-SDC-101 for Loss Enters ON-SDC-101 based on isolation of S/U of Shutdown Cooling for automatic isolation of HV-HV-151-F009 and loss of SDC flow. 151-F009.
+BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN.
+EVALUATOR CUE Record JPM start time:
+Step    Action                                                Standard                                           Eva I  Comments 1 Identifies governing procedure and obtain                Obtains controlled copy of OP-149-002 S/U controlled copy.                                      Att. E, SDC Temperature Control.
+   Ensure TRO 3.8.2.1 is entered.                        Confirms TRO 3.8.2.1 is entered per initial S/U conditions 3 Places HS-Ell-1S62B RHR LOOP B MOV OL                    Place keyswitch to TEST S/U BYPS keyswitch to TEST EVALUATOR NOTE Due to RHR conditions (F003B and F047B open and RHRSW and RHR at maximum flow), the only option for 'lowering temperature is to throttle closed F048B)
+   *4    Operates RHR B to lower reactor coolant               Throttle Closed on HV-151-F048B RHR HX S/U temperature                                           B SHELL SIDE BYPS 5 AFTER 2 minutes, Place HS-El l-1S62B RHR                 AFTER 2 minutes, place keyswitch to S/U LOOP A MOV OL BYPS keyswitch to OPERATE               NORM
+TQ-106-CJ..110 Revision 1 Page 5 of 11 FAULT STATEMENT HV-151-F009, SDC SUCTION OB ISOLATION VAL VE SPURIOUS CLOSURE OCCURS WHILE LOWERING REACTOR COOLANT TEMPERATURE BOOTH OPERATOR CUE After reactor coolant temperature begins to lower (indicated by RHR HX Inlet temperature) or when directed by the evaluator, depress Key 1 to initiate spurious isolation of F009 and cause a loss of SDC.
+EVALUATOR NOTE Examinee will investigate isolation ofHV-151-F009 6   Enters and obtains a copy of ON-SDC-101 for Loss      Enters ON-SDC-101 based on isolation of      S/U of Shutdown Cooling for automatic isolation of HV-    HV-151-F009 and loss of SDC flow.
+-F009.
 EVALUATOR CUE If the applicant does not recognize to enter ON-SDC-101, ask, "What procedure will the SRO direct you to enter in this condition?" Then direct Entry for ON-SDC-101.
-EVALUATOR CUE Once the examinee has determined that HV -151-F009 is closed, provide report as the US that "Electrical maintenance has determined that F009 experienced a spurious closure. The cause of the spurious closure has been found and corrected." If the examinee does not recognize that a quick recovery can be performed due to the F009 being closed, as the US direct the examinee to "Restore shutdown cooling in accordance with ON-SDC-101." 7 Determines cause for the loss of RHR was due to Performs the following spurious isolation of HV -151-F009.
+EVALUATOR CUE Once the examinee has determined that HV -151-F009 is closed, provide report as the US that "Electrical maintenance has determined that F009 experienced a spurious closure. The cause of the spurious closure has been found and corrected." If the examinee does not recognize that a quick recovery can be performed due to the F009 being closed, as the US direct the examinee to "Restore shutdown cooling in accordance with ON-SDC-101."
-* Recognizes that Condition B of ON-S/U SDC-101 is applicable to restore RHR Loop B to shutdown cooling. EVALUATOR CUE If candidate begins to perform the surveillance, S0-100-011 in the next step, provide a cue that another operator will perform the surveillance.
+Determines cause for the loss of RHR was due to         Performs the following spurious isolation of HV -151-F009.
-Perform S0-100-011 Determines another operator is performing S0-100-011.
+* Recognizes that Condition B of ON-         S/U SDC-101 is applicable to restore RHR Loop B to shutdown cooling.
-Comply with Tech Specs Notifies US to comply with Mode 4 LCO 3.4.9 EVALUATOR CUE If candidate begins to perform Attachment B in the next step, provide a cue that another operator will perform the attachment to determine time to 200&deg;F. 10 Determines time to 200&deg;F Determines another operator will perform attachment B. EVALUATOR CUE If candidate begins to determine if reactor coolant circulation is established in the next step, provide a cue that another operator will maintain reactor coolant circulation.
+EVALUATOR CUE If candidate begins to perform the surveillance, S0-100-011 in the next step, provide a cue that another operator will perform the surveillance.
-Establish reactor coolant circulation Determines another operator will maintain reactor coolant circulation EVALUATOR CUE Once the examinee has determined that a quick recovery can be performed due to the F009 being closed, as the US direct the examinee to "Restore shutdown cooling in accordance with AOP-149-001, Att A." 12 Restore previously in-service loop ofRHR to SDC Determines AOP-149-001, Att A will govern a quick recovery of the previously in-service SDC loop I 0 Revision 1 Page 6 of 11 13 Verify valve alignment prepared for SDC
-* Ensure HV-151-F015B CLOSED . restoration.
+TQ-106-0~ I 0 Revision 1 Page 6 of 11 8 Perform S0-100-011                                        Determines another operator is performing S0-100-011.
+Comply with Tech Specs                                   Notifies US to comply with Mode 4 LCO 3.4.9 EVALUATOR CUE If candidate begins to perform Attachment B in the next step, provide a cue that another operator will perform the attachment to determine time to 200&deg;F.
+Determines time to 200&deg;F                                 Determines another operator will perform attachment B.
+EVALUATOR CUE If candidate begins to determine if reactor coolant circulation is established in the next step, provide a cue that another operator will maintain reactor coolant circulation.
+Establish reactor coolant circulation                     Determines another operator will maintain reactor coolant circulation EVALUATOR CUE Once the examinee has determined that a quick recovery can be performed due to the F009 being closed, as the US direct the examinee to "Restore shutdown cooling in accordance with AOP-149-001, Att A."
+Restore previously in-service loop ofRHR to SDC            Determines AOP-149-001, Att A will govern a quick recovery of the previously in-service SDC loop
+TQ-106-0~ I 0 Revision 1 Page 7 of 11 13   Verify valve alignment prepared for SDC
+* Ensure HV-151-F015B CLOSED .
+restoration.
 * Ensure HV-151-F049 Radwaste OB Isolation CLOSED.
-* Ensure HV -151-F040 Radwaste IB , Isolation CLOSED.
+                        ,
-* Ensure HV-151-F007B RHR PUMPS B&D DISCHARGE MIN FLOW VL V TO SUPP POOL is CLOSED and DEACTIVATED.
+* Ensure HV -151-F040 Radwaste IB Isolation CLOSED.                S/U
-Determines that loop voiding is not suspected Marks step 7 as N/ A *15 Opens shutdown cooling suction isolation valve
+* Ensure HV-151-F007B RHR PUMPS B&D DISCHARGE MIN FLOW VLV TO SUPP POOL is CLOSED and DEACTIVATED.
-* Ensure Open HV-151-F008 OPEN F009. SHUTDOWN CLG SUCT OB ISO.
+Determines that loop voiding is not suspected     Marks step 7 as N/A                  S/U
-* Ensure Open HV-151-F009 SHUTDOWN CLG SUCT IB ISO. *16 Lines up RHR injection valves for pump start.
+ *15   Opens shutdown cooling suction isolation valve
-* Close HV-151-F017B RHR INJ FLOW CTL.
+* Ensure Open HV-151-F008 OPEN F009.                                               SHUTDOWN CLG SUCT OB ISO.
-* OpenHV-151-F015B RHRINJ OB ISO . *17 Starts an RHR pump Starts RHR PUMP 1P202B or D. *18 Establishes approximately 5000 GPM ofRHR Throttle OPEN HV-151-F017B RHR INJ flow. FLOW CTL to promptly establish flow approximately 5,000 gpm. EVALUATOR NOTE I CUE I That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials?
+S/U
-Task Cue Sheets? Procedures?
+* Ensure Open HV-151-F009 SHUTDOWN CLG SUCT IB ISO.
-S/U S/U S/U S/U S/U S/U I 0 Revision 1 Page 7 of 11 REVISION
+ *16   Lines up RHR injection valves for pump start.
+* Close HV-151-F017B RHR INJ FLOW CTL.                             S/U
+* OpenHV-151-F015B RHRINJ OB ISO .
+ *17   Starts an RHR pump                              Starts RHR PUMP 1P202B or D.         S/U
+ *18   Establishes approximately 5000 GPM ofRHR        Throttle OPEN HV-151-F017B RHR INJ flow.                                           FLOW CTL to promptly establish flow  S/U approximately 5,000 gpm.
+EVALUATOR NOTE I CUE                                     I That completes the JPM.
+EVALUATOR CUE Record JPM stop time:
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 9of11 REVISION
 ==SUMMARY==
-Revision 0 NewJPM JOB PERFORMANCE MEASURE 49.0N.20294.151 Description/Purpose of Revision TQ-106-0310 Revision 1 Page 9of11 3 Updated to match new format of ON-SDC-101 and AOP-149-001.
-EVALUATOR COPY: TASK CONDITIONS Unit 1 is in MODE 4, 2 days into an outage. Reactor coolant temperature is 170 &deg;F. Time to 200 &deg;F is approximately 45 minutes. Page 10of11 Section 2.22 (Operation of SOC in Mode 4 or 5) of OP-149-002 has NOT been performed.
+JOB PERFORMANCE MEASURE 49.0N.20294.151 Revision                     Description/Purpose of Revision 0    NewJPM 3    Updated to match new format of ON-SDC-101 and AOP-149-001.
-TRO 3.8.2.1 has been entered for SOC temperature control. An operator has been assigned to perform a S0-100-011 during the cooldown.
+Page 10of11 EVALUATOR COPY:
+TASK CONDITIONS Unit 1 is in MODE 4, 2 days into an outage.
+Reactor coolant temperature is 170 &deg;F.
+Time to 200 &deg;F is approximately 45 minutes.
+Section 2.22 (Operation of SOC in Mode 4 or 5) of OP-149-002 has NOT been performed.
+TRO 3.8.2.1 has been entered for SOC temperature control.
+An operator has been assigned to perform a S0-100-011 during the cooldown.
 INITIATING CUE Lower reactor coolant temperature to 140&deg;F in accordance with OP-149-002, Attachment E, step 6.
-EXAMINEE COPY: TASK CONDITIONS Unit 1 is in MODE 4, 2 days into an outage. Reactor coolant temperature is 170 &deg;F. Time to 200 &deg;F is approximately 45 minutes. Page 11 of 11 Section 2.22 (Operation of SOC in Mode 4 or 5) of OP-149-002 has NOT been performed.
-TRO 3.8.2.1 has been entered for SOC temperature control. An operator has been assigned to perform a S0-100-011 during the cooldown.
+Page 11 of 11 EXAMINEE COPY:
+TASK CONDITIONS Unit 1 is in MODE 4, 2 days into an outage.
+Reactor coolant temperature is 170 &deg;F.
+Time to 200 &deg;F is approximately 45 minutes.
+Section 2.22 (Operation of SOC in Mode 4 or 5) of OP-149-002 has NOT been performed.
+TRO 3.8.2.1 has been entered for SOC temperature control.
+An operator has been assigned to perform a S0-100-011 during the cooldown.
 INITIATING CUE Lower reactor coolant temperature to 140&deg;F in accordance with OP-149-002, Attachment E, step 6.
-RB HVSUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Re-establish RB HVAC IAW ES-134-003 JPM#: 34.E0.20802.151 Revision:&sect; Date:07/06/2016 Applicability: RO SRO Setting: Simulator NUREG-1123 E/APE I Sys295032 KIA Number EA1 .03 KIA Importance 3.7/3.7 Alternate YES D NO Time Critical DYES NO Validation Time (min):20 Testing Method: D Simulate Perform Author::Greg van den Berg j Date: 07/06/2016 Operations Review:
-Date:
+RB HVSUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Re-establish RB HVAC IAW ES-134-003 JPM#: 34.E0.20802.151                               Revision:&sect;             Date:07/06/2016 Applicability: ~ RO ~ SRO Setting: Simulator NUREG-1123 E/APE I Sys295032 KIA Number EA1 .03                       KIA Importance 3.7/3.7 Alternate Path:~ YES     D NO          Time Critical  DYES     ~ NO    Validation Time (min):20 Testing Method:
-y Validated:
+Operations Review:
-fJ{Xfe& Date:
+D Simulate Author::Greg van den Berg       j  ~ Perform
-Approval:
+_L~=:.,**~(}b_=======:::::....
-Date: 9
+Date: 07/06/2016 Date:   ~(.,,J y Validated:      fJ{Xfe&                               Date:   'f/~~(/k Approval:  --~----'W..___-~---.;;;;=:=----
-* Z CJ, fC, Nuclear Training Supervisor Examinee Name: ------------------
+Nuclear Training Supervisor Date: 9
-Last, First Ml Employee Number Exam Date: ---------Exam Duration (Min .... : ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+* Z CJ, fC, Examinee Name:
-Name Signature Comments:
+                  ------------------
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 34.E0.20802.151 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+Last, First Ml                                               Employee Number Exam Date:                                           Exam Duration (Min....:_ _ _ _ _ _ _ __
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+              ---------
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+Evaluation Result:    D Satisfactory       D Unsatisfactory Evaluator:----~~~~~~~~~-
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+Name                                            Signature Comments:
-D. .Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
-II. REFERENCES A. ES-134-003, Re-Establishing Reactor Building HVAC (Revision
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 34.E0.20802.151 I. SAFETY CONSIDERATIONS A.      All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-: 24) Ill. TASK CONDITIONS
+B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+C.      If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+D.     .Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+II. REFERENCES A. ES-134-003, Re-Establishing Reactor Building HVAC (Revision 24)
+Ill. TASK CONDITIONS
 * The Plant has experienced a loss of normal feed and makeup. The Reactor is shut down, with water level at -65", pressure is 900 psig.
 * A primary and secondary containment isolation has occurred due to level being< -38". The isolations are verified to be completed IAW ON-159-002.
-* RPV control is IAW E0-100-102.
+* RPV control is IAW E0-100-102. Primary containment parameters are all normal (i.e.,
-Primary containment parameters are all normal (i.e., pressure, temperature and suppression pool level).
+pressure, temperature and suppression pool level).
 * E0-100-104, Secondary Containment Control, has been entered due to Zone I HVAC not being in service for four hours.
 * HPCI is unavailable, RCIC is being restored and expected to be lined up feeding the vessel in approximately 30 minutes. RCIC had been down for repairs, which are now complete.
@@ Line 836: / Line 1,377: @@
 * A control structure chiller is in service.
 * All Individual room cooler fans are running.
-* Service water is available IV. INITIATING CUE Re-establish Reactor Building HVAC in accordance with ES-134-003, Re-establishing Reactor Building HV AC V. TASK STANDARD Zone 1 ISO SIGNALS LOCKOUT RELAYS re-tripped SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 34.E0.20802.151 NOTE: It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
+* Service water is available IV. INITIATING CUE Re-establish Reactor Building HVAC in accordance with ES-134-003, Re-establishing Reactor Building HV AC V. TASK STANDARD Zone 1 ISO SIGNALS LOCKOUT RELAYS re-tripped
-: 1. Reset the simulator to any rated-power IC. 2. Setup the simulator as follows: a. Both loops of ESW in service with at least one pump running in both loops b. Take the Mode Switch to SHUTDOWN c. Ensure RB HVAC isolation trip on low level and maintain reactor water level <-50" d. Start all room coolers with a cooling source 3. Insert the following malfunctions
-: a. IMF cmfPM01_1V202A
+SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 34.E0.20802.151 NOTE:      It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
-: b. IMF cmfPM01_ 1V2028 4. Other Zone 1 fans do not start Zone 1 fans do not start INFORMATION FOR EVALUATOR
+: 1. Reset the simulator to any rated-power IC.
+: 2. Setup the simulator as follows:
+: a. Both loops of ESW in service with at least one pump running in both loops
+: b. Take the Mode Switch to SHUTDOWN
+: c. Ensure RB HVAC isolation trip on low level and maintain reactor water level <-50"
+: d. Start all room coolers with a cooling source
+: 3. Insert the following malfunctions
+: a. IMF cmfPM01_1V202A                    Zone 1 fans do not start
+: b. IMF cmfPM01_1V2028                    Zone 1 fans do not start
+: 4. Other
+TQ-106-CJ~ 10 Revision 1 Page 4of12 INFORMATION FOR EVALUATOR
 * Marking a step as UNSAT requires written comments on respective step .
-Revision 1 Page 4of12
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
 * The time clock starts when the candidate acknowledges the initiating cue.
 * This JPM must be performed in simulator.
-* Configure the Simulator per the Simulator Setup Instructions . EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy ofES-134-003.
+* Configure the Simulator per the Simulator Setup Instructions .
-S/U controlled copy. EVALUATOR NOTE It will not be necessary to obtain any of the required equipment in the next step. This JPM deals with the control room actions ONLY. 2 Reviews, required equipment, precautions and Identifies Shift managers office as the S/U limitations location for obtaining the special equipment.
+EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.
+BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN.
+EVALUATOR CUE Record JPM start time:
+Step    Action                                                Standard                                          Eva I  Comments 1 Identifies governing procedure and obtain                Obtains controlled copy ofES-134-003.
+S/U controlled copy.
+EVALUATOR NOTE It will not be necessary to obtain any of the required equipment in the next step. This JPM deals with the control room actions ONLY.
+Reviews, required equipment, precautions and             Identifies Shift managers office as the S/U limitations                                           location for obtaining the special equipment.
 EVALUATOR CUE Inform the student that any required equipment will be SIMULATED.
-Ensure Service Water is available for restoration of Determines from task conditions that Reactor Building chillers prior to bypassing service water is available S/U isolations 4 Ensure following conditions exist:
+Ensure Service Water is available for restoration of      Determines from task conditions that Reactor Building chillers prior to bypassing           service water is available                       S/U isolations
-* Both loops ofESW in operation in accordance with OP-054-001.
-* Control Structure Chiller in operation in accordance with OP-030-001.
+TQ-106-u-310 Revision 1 Page 5of12 4  Ensure following conditions exist:                     Determines from task conditions:
-* All individual room cooler fans that have cooling source in operation in accordance with OP-134-002.
+* Both loops ofESW in operation in accordance with
-EVALUATOR NOTE Determines from task conditions:
+* Both loops ofESW are in operation OP-054-001.
-* Both loops ofESW are in operation
+* Control Structure Chiller in operation in accordance
-* Control structure chiller is in service
+* Control structure chiller is in service SIU with OP-030-001.
-* All individual room coolers are runnmg SIU TQ-106-u-310 Revision 1 Page 5of12 With Reactor Building HVAC isolation signal present, the following will be performed to bypass High Drywell Pressure/Low RPV Water Level HV AC Interlocks.
+* All individual room cooler fans that have cooling
-Confirm automatic actuations per Attachment A 6* On 1 C681 Heat & Ventilation Control Panel, Place ZONE 1 HVAC LOCA ISO BYPASS HS 17551A keylock switch to BYPASS 7 Observe Zone 1 HV AC LOCA ISO BYPASSED annunciator AR-127 D09 alarms 8* On 1 C681 Heat & Ventilation Control Panel, Place Zone 1 HVAC LOCA ISO BYPASS HS-17551B keylock switch to BYPASS Completes Attachment A:
+* All individual room coolers are source in operation in accordance with OP-134-002.
-* RECIRC SYS TO ZONE I SUP SYS DMP HD-l 7657A-OPEN
+runnmg EVALUATOR NOTE With Reactor Building HVAC isolation signal present, the following will be performed to bypass High Drywell Pressure/Low RPV Water Level HVAC Interlocks.
+TQ-106-0s1 0 Revision 1 Page 6of12 5 Confirm automatic actuations per Attachment A    Completes Attachment A:
+* RECIRC SYS TO ZONE I SUP SYS DMP HD-l 7657A- OPEN
 * ZONE I EXH SYS TO RECIRC SYS DMP HD-17602A-OPEN
 * ZONE I FILT EXH TO RECIRC SYS DMP HD-17601A-OPEN
-* ZONE I EXH SYS ISOLATION DMP HD-l 7576A-CLOSED
+* ZONE I EXH SYS ISOLATION DMP HD-l 7576A- CLOSED
 * ZONE I EQUIP COMPT EXH SYS DMP HD-l 7524A-CLOSED
-* ZONE I SUPP SYS ISOLATION DMP HD-l 7586A-CLOSED ". RECIRC SYS TO ZONE I SUP SYS DMP HD-17657B-OPEN
+* ZONE I SUPP SYS ISOLATION DMP HD-l 7586A- CLOSED                S/U RECIRC SYS TO ZONE I SUP SYS DMP
+                                                       ". HD-17657B-OPEN
 * ZONE I EXH SYS TO RECIRC SYS DMP HD-17602B-OPEN
 * ZONE I FILT EXH TO RECIRC SYS DMP HD-17601B-OPEN
 * ZONE I EXH SYS ISOLATION DMP HD-17576B-CLOSED
 * ZONE I EQUIP COMPT EXH SYS DMP HD-17524B-CLOSED
-* ZONE I SUPP SYS ISOLATION DMP HD-17 5 86B -CLOSED Inserts key and Places ZONE 1 HV AC LOCA ISO BYPASS HS 17551A keylock switch to BYPASS Verifies Zone 1 HV AC LOCA ISO BYPASSED annunciator AR-127 D09 alanns Inserts key and Places ZONE 1 HV AC LOCA ISO BYPASS HS 17551B keylock switch to BYPASS S/U SIU SIU S/U TQ-106-0s1 0 Revision 1 Page 6of12 9 Observe Zone 1 HV AC LOCA ISO BYPASSED Verifies Zone 1 HV AC LOCA ISO BYPASSED annunciator AR-128 D09 alarms annunciator AR-128 D09 alarms. 10* Reset Zone 1 ISO SIGNALS LOCKOUT RELAY Turns the lockout relay clockwise UNTIL it XY07551A remains in the vertical position 11
+* ZONE I SUPP SYS ISOLATION DMP HD-17 5 86B - CLOSED 6* On 1C681 Heat & Ventilation Control Panel, Place Inserts key and Places ZONE 1 HVAC ZONE 1 HVAC LOCA ISO BYPASS HS 17551A            LOCA ISO BYPASS HS 17551A keylock         SIU keylock switch to BYPASS                         switch to BYPASS 7 Observe Zone 1 HV AC LOCA ISO BYPASSED           Verifies Zone 1 HVAC LOCA ISO BYPASSED annunciator AR-127 D09 alanns SIU annunciator AR-127 D09 alarms 8* On 1C681 Heat & Ventilation Control Panel, Place Inserts key and Places ZONE 1 HVAC Zone 1 HVAC LOCA ISO BYPASS HS-17551B            LOCA ISO BYPASS HS 17551B keylock         S/U keylock switch to BYPASS                         switch to BYPASS
-* Reset Zone 1 ISO SIGNALS LOCKOUT RELAY Turns the lockout relay clockwise UNTIL it XY07551B remains in the vertical position FAULT STATEMENT THE ZONE I FANS DO NOT RETURN TO NORMAL OPERATION.
-Ensure Reactor Building Ventilation System Verifies RB Zone 1 NO Vent AR-127-C09 is Division I and Division II fans for Zone 1 return to STILL LIT normal operation in accordance with OP-134-002 Contacts the RB NPO to determine the status of the RB Ventilation system EVALUATOR CUE Acknowledge request and report, "Both RB ventilation fans are tripped and neither can be restarted." EVALUATOR NOTE The operator should continue to step 5.1.3.b.7 to restore the line-up. 13* On 1 C681 Heat & Ventilation Control Panel, Place Places ZONE 1 HV AC LOCA ISO ZONE 1 HV AC LOCA ISO BYPASS HS-1755 lA BYPASS HS-17551A keylock switch to keylock switch to NORMAL NORMAL 14 Observe Zone 1 ISO SIGNALS LOCKOUT Verifies Zone 1 ISO SIGNALS LOCKOUT RELAY XY07551A trips RELAY XY07551A-pointing 10 o'clock position with the RED semaphore visible 15 Observe Zone 1 HV AC LOCA ISO BYPASSED Verifies Zone 1 HV AC LOCA ISO BYPASSED alarm AR-127 D09 clears alarm AR-127 D09 -SLOW FLASHING 16* On 1 C681 Heat & Ventilation Control Panel, Place Places ZONE 1 HV AC LOCA ISO Zone 1 HV AC LOCA ISO BYPASS HS-17551B BYPASS HS-17551B keylock switch to keylock switch to NORMAL NORMAL S/U SIU S/U S/U S/U S/U S/U S/U Revision 1 Page 7of12 17 Observe Zone 1 ISO SIGNALS LOCKOUT Verifies Zone 1 ISO SIGNALS LOCKOUT RELAY XY07551B trips RELAY XY07551B -pointing 10 o'clock position with the RED semaphore visible 18 Observe Zone 1 HV AC LOCA ISO BYPASSED Verifies Zone 1 HV AC LOCA ISO BYPASSED alarm AR 128 D09 clears alarm AR-128 D09 -SLOW FLASHING 19 Notify Technical Support Coordinator attempts to Contacts TSC restart RB HV AC have failed and to determine additional actions required to restart HV AC or shed electrical loads to reduce heat load EVALUATOR CUE Role-play the TSC coordinator, and acknowledge the request. 20 Exit this procedure Exits the procedure EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials?
+TQ-106-u~10 Revision 1 Page 7of12 9  Observe Zone 1 HV AC LOCA ISO BYPASSED                    Verifies Zone 1 HVAC LOCA ISO BYPASSED annunciator AR-128 D09 alarms.             S/U annunciator AR-128 D09 alarms 10*   Reset Zone 1 ISO SIGNALS LOCKOUT RELAY                    Turns the lockout relay clockwise UNTIL it SIU XY07551A                                                  remains in the vertical position 11
-Task Cue Sheets? Procedures?
+* Reset Zone 1 ISO SIGNALS LOCKOUT RELAY                     Turns the lockout relay clockwise UNTIL it S/U XY07551B                                                  remains in the vertical position FAULT STATEMENT THE ZONE I FANS DO NOT RETURN TO NORMAL OPERATION.
-S/U SIU S/U SIU TQ-106-lJ310 Revision 1 Page 8 of 12 REVISION
+  Ensure Reactor Building Ventilation System                Verifies RB Zone 1 NO Vent AR-127-C09 is Division I and Division II fans for Zone 1 return to      STILL LIT Contacts the RB NPO to determine the S/U normal operation in accordance with OP-134-002 status of the RB Ventilation system EVALUATOR CUE Acknowledge request and report, "Both RB ventilation fans are tripped and neither can be restarted."
+EVALUATOR NOTE The operator should continue to step 5.1.3.b.7 to restore the line-up.
+*   On 1C681 Heat & Ventilation Control Panel, Place          Places ZONE 1 HV AC LOCA ISO ZONE 1 HVAC LOCA ISO BYPASS HS-1755 lA                    BYPASS HS-17551A keylock switch to         S/U keylock switch to NORMAL                                  NORMAL 14   Observe Zone 1 ISO SIGNALS LOCKOUT                        Verifies Zone 1 ISO SIGNALS LOCKOUT RELAY XY07551A trips                                      RELAY XY07551A-pointing to~ 10 o'clock     S/U position with the RED semaphore visible 15   Observe Zone 1 HV AC LOCA ISO BYPASSED                    Verifies Zone 1 HVAC LOCA ISO BYPASSED alarm AR-127 D09 - SLOW FLASHING           S/U alarm AR-127 D09 clears 16*   On 1C681 Heat & Ventilation Control Panel, Place          Places ZONE 1 HV AC LOCA ISO Zone 1 HV AC LOCA ISO BYPASS HS-17551B                    BYPASS HS-17551B keylock switch to         S/U keylock switch to NORMAL                                  NORMAL
+TQ-106-lJ310 Revision 1 Page 8 of 12 17   Observe Zone 1 ISO SIGNALS LOCKOUT                   Verifies Zone 1 ISO SIGNALS LOCKOUT RELAY XY07551B trips                                 RELAY XY07551B - pointing to~ 10 o'clock S/U position with the RED semaphore visible 18   Observe Zone 1 HVAC LOCA ISO BYPASSED                Verifies Zone 1 HVAC LOCA ISO BYPASSED alarm AR-128 D09 - SLOW FLASHING         SIU alarm AR 128 D09 clears 19   Notify Technical Support Coordinator attempts to     Contacts TSC restart RB HV AC have failed and to determine S/U additional actions required to restart HVAC or shed electrical loads to reduce heat load EVALUATOR CUE Role-play the TSC coordinator, and acknowledge the request.
+  Exit this procedure                                  Exits the procedure                      SIU EVALUATOR NOTE I CUE That completes the JPM.
+EVALUATOR CUE Record JPM stop time:
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 10of12 REVISION
 ==SUMMARY==
-Revision 0 5 NewJPM JOB PERFORMANCE MEASURE 34.E0.20802.151 Description/Purpose of Revision Revised to new JPM format. TQ-106-0310 Revision 1 Page 10of12 Page 11 of 12 EVALUATOR COPY: TASK CONDITIONS
+JOB PERFORMANCE MEASURE 34.E0.20802.151 Revision                     Description/Purpose of Revision 0    NewJPM 5    Revised to new JPM format.
+Page 11 of 12 EVALUATOR COPY:
+TASK CONDITIONS
 * The Plant has experienced a loss of normal feed and makeup. The Reactor is shut down, with water level at-65", pressure is 900 psig.
 * A primary and secondary containment isolation has occurred due to level being< -38". The isolations are verified to be completed IAW ON-159-002.
-* RPV control is IAW E0-100-102.
+* RPV control is IAW E0-100-102. Primary containment parameters are all normal (i.e.,
-Primary containment parameters are all normal (i.e., pressure, temperature and suppression pool level).
+pressure, temperature and suppression pool level).
 * E0-100-104, Secondary Containment Control, has been entered due to Zone I HVAC not being in service for four hours.
 * HPCI is unavailable, RCIC is being restored and expected to be lined up feeding the vessel in approximately 30 minutes. RCIC had been down for repairs, which are now complete.
@@ Line 884: / Line 1,458: @@
 * A control structure chiller is in service.
 * All Individual room cooler fans are running.
-* Service water is available INITIATING CUE Re-establish Reactor Building HVAC in accordance with ES-134-003, Re-establishing Reactor ( Building HVAC Page 12 of 12 EXAMINEE COPY: TASK CONDITIONS
+* Service water is available INITIATING CUE Re-establish Reactor Building HVAC in accordance with ES-134-003, Re-establishing Reactor (
+Building HVAC
+Page 12 of 12 EXAMINEE COPY:
+TASK CONDITIONS
 * The Plant has experienced a loss of normal feed and makeup. The Reactor is shut down, with water level at -65", pressure is 900 psig.
 * A primary and secondary containment isolation has occurred due to level being< -38". The isolations are verified to be completed IAW ON-159-002.
-* RPV control is IAW E0-100-102.
+* RPV control is IAW E0-100-102. Primary containment parameters are all normal (i.e.,
-Primary containment parameters are all normal (i.e., pressure, temperature and suppression pool level).
+pressure, temperature and suppression pool level).
 * E0-100-104, Secondary Containment Control, has been entered due to Zone I HVAC not being in service for four hours.
 * HPCI is unavailable, RCIC is being restored and expected to be lined up feeding the vessel in approximately 30 minutes. RCIC had been down for repairs, which are now complete.
@@ Line 894: / Line 1,472: @@
 * A control structure chiller is in service.
 * All Individual room cooler fans are running.
-* Service water is available INITIATING CUE Re-establish Reactor Building HVAC in accordance with ES-134-003, Re-establishing Reactor Building HVAC \\
+* Service water is available INITIATING CUE Re-establish Reactor Building HVAC in accordance with ES-134-003, Re-establishing Reactor Building HVAC
-SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Energize "Dead" 4KV ESS Bus '20' JPM#: 04.0N.20641.251 Date:07/06/2016 Applicability: RO SRO Setting: Simulator NUREG-1123 E/APE I Sys262001 KIA Number A2.07K/A Importance 3.0/3.2 Alternate YES D NO Time Critical DYES NO Validation Time (min):25 Testing Method: D Simulate f rform Author::Greg van den Operations Re1f: '*Date: Validated:
+                    \\
-//10 .. Date: ' Approval:
-_____ Lr:.:......_.:)
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Energize "Dead" 4KV ESS Bus '20' JPM#: 04.0N.20641.251                              Revision:~ Date:07/06/2016 Applicability: ~ RO ~ SRO Setting: Simulator NUREG-1123 E/APE I Sys262001 KIA Number A2.07K/A Importance 3.0/3.2 Alternate Path:~ YES        D NO        Time Critical DYES    ~ NO    Validation Time (min):25 Testing Method:   D Simulate         ~  f  rform Author::Greg van den     c~G/2016 Operations Re1f:                    *~            '*Date:    z/-v~,dy Validated:     //10 . ~                               Date:  q(j_4//?
-___
+' Approval:  __..~             ___~------ Date:
-Date: NUclearTrainill9s';ervisor Examinee Name:
+_____Lr:.:......_.:)                          q,:z.1~1,h NUclearTrainill9s';ervisor Examinee Name:
-q(j_4//?
+                    ------------------
-------------------
+Last, First Ml                                               Employee Number Exam Date:                                          Exam Duration (Min): _ _ _ _ _ _ _ __
-Last, First Ml Employee Number Exam Date: ---------Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+                ---------
------------
+Evaluation Result:  D Satisfactory          D  Unsatisfactory Evaluator:
-Name Signature Comments:
+             -----------
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 04.0N.20641.251 I. SAFETY CONSIDERATIONS A All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+Name                                           Signature Comments:
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 04.0N.20641.251 I. SAFETY CONSIDERATIONS A      All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
+: 1.       Whenever any electrical panel is opened for inspection during JPM performance.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
 C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
 D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
-II. REFERENCES A. AOP-004-001, Energizing Dead 4KV ESS Bus (Rev. 1) 8. AOP-024-001, Diesel Generator AOP (Rev. 0) C. AR-016-001, DIG D, ESW, RWMU, and Misc Load Center (Rev 61) Ill. TASK CONDITIONS A. Unit 2 is at rated power. 8. An Electrical transient has occurred on the 2D ESS bus. C. DG D failed to auto start. It is now in LOCAL, repaired, and available to be started and loaded. D. No electrical Bus fault is present. E. You are the On-Shift U2 PCOP F. Both loops of ESW are operational IV. INITIATING CUE Implement AOP-004-001 Attachment A to re-energize the 2D ESS bus from the 'D' EOG V. TASK STANDARD ESS Bus 20 is re-energized from DG 'D' IAW AOP-004-001 (Energizing Dead 4KV ESS Bus) recognizing that the DG trips and must be shutdown.
+II. REFERENCES A. AOP-004-001, Energizing Dead 4KV ESS Bus (Rev. 1)
-SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 04.0N.20641.251 NOTE: It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
+: 8. AOP-024-001, Diesel Generator AOP (Rev. 0)
-: 1. Reset the simulator to IC-18 or an IC with Unit 2 SID. 2. Insert the following malfunctions
+C. AR-016-001, DIG D, ESW, RWMU, and Misc Load Center (Rev 61)
-: a. IMF cmfBR05_2A20401
+Ill. TASK CONDITIONS A. Unit 2 is at rated power.
-: b. IMF cmfBR03_2A20408
+: 8. An Electrical transient has occurred on the 2D ESS bus.
-: c. IOR di43CMD_Q f:LOCAL 3. Have the following keys assigned Bkr 01 Fails Asis Bkr 08 Overcurrent Trip 'D' EDG 43CM to LOCAL a. {Key[31]}
+C. DG D failed to auto start. It is now in LOCAL, repaired, and available to be started and loaded.
-IOR di5ESD_Q f:STOP Depress 5ES Pushbutton
+D. No electrical Bus fault is present.
-: b. {Key[32]}
+E. You are the On-Shift U2 PCOP F. Both loops of ESW are operational IV. INITIATING CUE Implement AOP-004-001 Attachment A to re-energize the 2D ESS bus from the 'D' EOG V. TASK STANDARD ESS Bus 20 is re-energized from DG 'D' IAW AOP-004-001 (Energizing Dead 4KV ESS Bus) recognizing that the DG trips and must be shutdown.
-DOR di5ESD_Q f:STOP Depress 5ES reset P/B c. {Key[32]}
-IOR di5ESRD_Q f:RESET Depress 5ES reset P/B -cl. {Key[33]}
+SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 04.0N.20641.251 NOTE:      It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
-IOR diOC521DRST_Q f:RESET c:5 Annunciator reset e. {Key[34]}
+: 1. Reset the simulator to IC-18 or an IC with Unit 2 SID.
-IOR di43GMD_Q f:ISO Switch to iso on EOG f. {Key[35]}
+: 2. Insert the following malfunctions
-IOR di1LD_Q f:START Starts the 'D' EOG 4. Activate the following ET to trip the'D' EOG on overspeed after it starts a. ET-040N1203251
+: a. IMF cmfBR05_2A20401                 Bkr 01 Fails Asis
+: b. IMF cmfBR03_2A20408                 Bkr 08 Overcurrent Trip
+: c. IOR di43CMD_Q f:LOCAL                 'D' EDG 43CM to LOCAL
+: 3. Have the following keys assigned
+: a. {Key[31]} IOR di5ESD_Q f:STOP                         Depress 5ES Pushbutton
+: b. {Key[32]} DOR di5ESD_Q f:STOP                         Depress 5ES reset P/B
+: c. {Key[32]} IOR di5ESRD_Q f:RESET                       Depress 5ES reset P/B
+      -cl. {Key[33]} IOR diOC521DRST_Q f:RESET c:5 Annunciator reset
+: e. {Key[34]} IOR di43GMD_Q f:ISO                         Switch to iso on EOG
+: f. {Key[35]} IOR di1LD_Q f:START                         Starts the 'D' EOG
+: 4. Activate the following ET to trip the'D' EOG on overspeed after it starts
+: a. ET-040N1203251
 : b. di1LD_Q.CurrValue=#OR.di1LD_Q.START
-: c. IMF mfDG024008D d:10 5. Other EVALUATOR INSTRUCTIONS
+: c. IMF mfDG024008D d:10
-* Marking a step as UNSAT requires written comments on respective step . TQ-106-Ui.J I 0 Revision 1 Page 4 of 12
+: 5. Other
+TQ-106-Ui.J I 0 Revision 1 Page 4 of 12 EVALUATOR INSTRUCTIONS
+* Marking a step as UNSAT requires written comments on respective step .
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
 * The time clock starts when the candidate acknowledges the Initiating Cue .
-* This JPM must be performed in the simulator.
+* This JPM must be performed in the simulator. Reset to exam-specific IC or configure the simulator per the Simulator Setup Instructions .
-Reset to exam-specific IC or configure the simulator per the Simulator Setup Instructions .
+* Have a copy of AOP-004-001 .
-* Have a copy of AOP-004-001 . EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. EVALUATOR CUE Record JPM start time: BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN. Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of AOP-004-001.
+EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.                                           -
-S/U controlled copy. 2 Review sections 1-5 Determines that step 5.1 starts with S/U attachment A EVALUATOR NOTE -The following steps prevent inadvertent auto breaker closure by mismatching semaphores.
+EVALUATOR CUE Record JPM start time:
-This is performed on the de-energized 4KV ESS bus only. 3* Place XFMR 101 TO BUS 2D BKR 2A20401 Places 2A20401 switch to CLOSE. Verifies switch to CLOSE Red light OFF, Amber light LIT, Green light SIU LIT. 4* Place XFMR 201 TO BUS 2D BKR 2A20408 Places 2A20408 switch to CLOSE. Verifies switch to CLOSE Red light OFF, Amber light LIT, Green light S/U LIT.
+BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN.
-Check the status oflockout relays on Bus 2D (86A-Directs an NPO to check the status of Bus 204, 86Al-204, and 86A2-204) 2D lockout relays EVALUATOR CUE Acknowledge request and report NO lockout relays are tripped on the 2D ESS Bus. EVALUATOR NOTE SIU TQ-106-L_ ,Q Revision 1 Page 5 of 12 Steps 3, 4, and 5 of Attachment A determine which Attachment of the procedure is required to energize the bus. Step 3 and 5 are not applicable due to no Bus lockouts and the availability of the 'D' EDG. The given sections of the procedure have the applicable Attachments for all three steps so not to cue the operator.
+Step  Action                                                 Standard                                          Eva I  Comments 1 Identifies governing procedure and obtain               Obtains controlled copy of AOP-004-001.
-Determines step 4 is applicable Proceeds to attachment M S/U 7 Determines step 1 is not applicable N/As step 1 SIU 8 Verify XFMR 101 TO BUS 2D BKR 2A20401, Verifies breakers 2A20401, 2A20408, and XFMR 201 TO BUS 2D BKR 2A20408, and Diesel 2A20404 are open by Green flags S/U Generator B(E) Output Breaker 2A20404 are OPEN EVALUATOR NOTE The following step can be verified using R *Time screen or sending an NPO to verify 9 Ensure the following breakers are OPEN: Dispatches an NPO to verify breaker
+S/U controlled copy.
-* 2A20402, RHR Pump 2P202D positions
+Review sections 1-5                                    Determines that step 5.1 starts with S/U attachment A EVALUATOR NOTE The following steps prevent inadvertent auto breaker closure by mismatching semaphores. This is performed on the de-energized 4KV ESS bus only.
-* 2A20403, CRD Wtr Pump 2P132B S/U
+*   Place XFMR 101 TO BUS 2D BKR 2A20401                  Places 2A20401 switch to CLOSE. Verifies switch to CLOSE                                       Red light OFF, Amber light LIT, Green light        SIU LIT.
-* 2A20405, CS Pump 2P206D 2A20409, Turbine Bldg Chiller 2K102B EVALUATOR CUE Acknowledge request and report, "At 2A204, breakers 2, 3, 5, and 9 are open." 10 Determines step 3 is not applicable N/As step 3 S/U 11
+*   Place XFMR 201 TO BUS 2D BKR 2A20408                  Places 2A20408 switch to CLOSE. Verifies switch to CLOSE                                       Red light OFF, Amber light LIT, Green light        S/U LIT.
-* At OC521D, Place DG D Control Mode Select Determines this step has been completed S/U Switch to LOCAL 12* At OCS21D, Depress SES Emergency Stop Directs NPO to depress SES Pushbutton on Pushbutton
-'D'EDG BOOTH OPERATOR CUE When directed by the floor, insert Key 31 EVALUATOR CUE Acknowledge request, Direct booth to insert Key 31, and report SES pushbutton has been depressed 13 At OCS21D, Verify the following:
+TQ-106-L_ ,Q Revision 1 Page 5 of 12 5 Check the status oflockout relays on Bus 2D (86A-       Directs an NPO to check the status of Bus SIU 204, 86Al-204, and 86A2-204)                          2D lockout relays EVALUATOR CUE Acknowledge request and report NO lockout relays are tripped on the 2D ESS Bus.
-Directs NPO to report status of the
+EVALUATOR NOTE Steps 3, 4, and 5 of Attachment A determine which Attachment of the procedure is required to energize the bus. Step 3 and 5 are not applicable due to no Bus lockouts and the availability of the 'D' EDG. The given sections of the procedure have the applicable Attachments for all three steps so not to cue the operator.
-* Remote light NOT illuminated indicating lights
+Determines step 4 is applicable                         Proceeds to attachment M                        S/U 7 Determines step 1 is not applicable                     N/As step 1                                     SIU 8 Verify XFMR 101 TO BUS 2D BKR 2A20401,                  Verifies breakers 2A20401, 2A20408, and XFMR 201 TO BUS 2D BKR 2A20408, and Diesel            2A20404 are open by Green flags                 S/U Generator B(E) Output Breaker 2A20404 are OPEN EVALUATOR NOTE The following step can be verified using R *Time screen or sending an NPO to verify 9 Ensure the following breakers are OPEN:                Dispatches an NPO to verify breaker
-* Local light illuminated DG D Available for emergency light not illuminated EVALUATOR CUE Acknowledge request and report, "The Remote light is NOT illuminated, Local light is illuminated, and DG D Available for emergency light is not illuminated." 14 Determines step 4.b and care not applicable N/As step 4.b and c lS Verifies ESW is available Determines ESW pumps are running 16* At OCS21D, Depress SES Emergency Stop Reset Directs NPO to depress SES Reset pushbutton Pushbutton on 'D' EDG EVALUATOR CUE Acknowledge request, Direct booth to insert Key 32, and report SES reset pushbutton has been depressed BOOTH OPERA TOR CUE When directed by the floor, insert Key 32 17* At OCS21D, Depress Annunciator and System Reset Directs NPO to depress Annunciator and-pushbutton
+* 2A20402, RHR Pump 2P202D                       positions
-' System Reset Pushbutton on 'D' EDG EVALUATOR CUE Acknowledge request, Direct booth to insert Key 3 3, and report Annunciator and System reset pushbutton has been depressed S/U S/U S/U S/U S/U S/U Revision 1 Page 6 of 12 BOOTH OPERA TOR CUE When directed by the floor, insert Key 33 18* At OC521D, Place Governor mode select switch to Directs NPO to Place 'D' EDG Governor S/U ISOCHRONOUS mode select switch to ISOCHRONOUS EVALUATOR CUE Acknowledge request, Direct booth to insert Key 34, and report Governor mode select switch is in ISOCHRONOUS BOOTH OPERATOR CUE When directed by the floor, insert Key 34 FAULT STATEMENT 10 SECONDS AFTER THE DG IS STARTED, THE ENGINE WILL OVERSPEED AND TRIP THE EDG. 19* At OC521D, Depress DG D Engine Directs NPO to Start the 'D' EDG S/U Control START P/B EVALUATOR CUE Acknowledge request, Direct booth to insert Key 35, and report The 'D' diesel has started BOOTH OPERATOR CUE When directed by the floor, insert Key 35 20 Verify 2A20404 DG D(E) TO BUS 2D Verifies that 2A20404 closes and the ESS S/U automatically closes. Bus available light is Illuminated.
+* 2A20403, CRD Wtr Pump 2P132B                                                                   S/U
-EVALUATOR NOTE When the EDG trips the operator may perform actions per AR-016-001 or per AOP-004-001 att M step D.5. The below sequence is from the AR. Continue at step 24 if AOP-004-001 is followed.
+* 2A20405, CS Pump 2P206D 2A20409, Turbine Bldg Chiller 2K102B EVALUATOR CUE Acknowledge request and report, "At 2A204, breakers 2, 3, 5, and 9 are open."
-Ensure automatic actions Verifies 2A20404 DG D(E) TO BUS 2D SIU opens and the EDG stops EVALUATOR CUE Inform the student that another operator will finish the AR and they are to continue with AOP-004-001 10 Revision 1 Page 7of12 22 Enter AOP-024-001 Obtains AOP-024-001 23 Determine attachment D is applicable Reads the procedure to see Attachment D is for the 'D' EDG. 24 Verify 43CM DG D Control mode switch is in Contacts NPO to verify position of 43CM. LOCAL EVALUATOR CUE Acknowledge request and report, "The 'D' DG mode switch is in LOCAL." EVALUATOR NOTE S/U S/U S/U TQ-106-L __ , 0 Revision 1 Page 8 of 12 The operator may or may not depress the SES Stop Pushbutton depending on which procedure they use. Since the ID ESS bus has power, it is not essential that the SES Stop P IB is depressed.
+Determines step 3 is not applicable                     N/As step 3                                     S/U 11
-EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials?
+* At OC521D, Place DG D Control Mode Select              Determines this step has been completed S/U Switch to LOCAL
-Task Cue Sheets? Procedures?
-REVISION
+TQ-106-lJ~10 Revision 1 Page 6 of 12 12*   At OCS21D, Depress SES Emergency Stop                 Directs NPO to depress SES Pushbutton on S/U Pushbutton                                            'D'EDG BOOTH OPERATOR CUE When directed by the floor, insert Key 31 EVALUATOR CUE Acknowledge request, Direct booth to insert Key 31, and report SES pushbutton has been depressed 13   At OCS21D, Verify the following:                      Directs NPO to report status of the
+* Remote light NOT illuminated                    indicating lights S/U
+* Local light illuminated DG D Available for emergency light not illuminated EVALUATOR CUE Acknowledge request and report, "The Remote light is NOT illuminated, Local light is illuminated, and DG D Available for emergency light is not illuminated."
+Determines step 4.b and care not applicable            N/As step 4.b and c                         S/U lS  Verifies ESW is available                             Determines ESW pumps are running            S/U 16*   At OCS21D, Depress SES Emergency Stop Reset           Directs NPO to depress SES Reset S/U pushbutton                                            Pushbutton on 'D' EDG EVALUATOR CUE Acknowledge request, Direct booth to insert Key 32, and report SES reset pushbutton has been depressed BOOTH OPERATOR CUE When directed by the floor, insert Key 32 17*   At OCS21D, Depress Annunciator and System Reset       Directs NPO to depress Annunciator and-S/U pushbutton                                '           System Reset Pushbutton on 'D' EDG EVALUATOR CUE Acknowledge request, Direct booth to insert Key 33, and report Annunciator and System reset pushbutton has been depressed
+TQ-106-u~ 10 Revision 1 Page 7of12 BOOTH OPERATOR CUE When directed by the floor, insert Key 33 18*  At OC521D, Place Governor mode select switch to         Directs NPO to Place 'D' EDG Governor S/U ISOCHRONOUS                                             mode select switch to ISOCHRONOUS EVALUATOR CUE Acknowledge request, Direct booth to insert Key 34, and report Governor mode select switch is in ISOCHRONOUS BOOTH OPERATOR CUE When directed by the floor, insert Key 34 FAULT STATEMENT 10 SECONDS AFTER THE DG IS STARTED, THE ENGINE WILL OVERSPEED AND TRIP THE EDG.
+*  At OC521D, Depress DG D Engine                          Directs NPO to Start the 'D' EDG S/U Control START P/B EVALUATOR CUE Acknowledge request, Direct booth to insert Key 35, and report The 'D' diesel has started BOOTH OPERATOR CUE When directed by the floor, insert Key 35 20  Verify 2A20404 DG D(E) TO BUS 2D                        Verifies that 2A20404 closes and the ESS S/U automatically closes.                                   Bus available light is Illuminated.
+EVALUATOR NOTE When the EDG trips the operator may perform actions per AR-016-001 or per AOP-004-001 att M step D.5.
+The below sequence is from the AR. Continue at step 24 if AOP-004-001 is followed.
+Ensure automatic actions                                Verifies 2A20404 DG D(E) TO BUS 2D SIU opens and the EDG stops EVALUATOR CUE Inform the student that another operator will finish the AR and they are to continue with AOP-004-001
+TQ-106-L __ , 0 Revision 1 Page 8 of 12 22    Enter AOP-024-001                                  Obtains AOP-024-001                          S/U 23    Determine attachment D is applicable               Reads the procedure to see Attachment D is S/U for the 'D' EDG.
+   Verify 43CM DG D Control mode switch is in         Contacts NPO to verify position of 43CM.
+S/U LOCAL EVALUATOR CUE Acknowledge request and report, "The 'D' DG mode switch is in LOCAL."
+EVALUATOR NOTE The operator may or may not depress the SES Stop Pushbutton depending on which procedure they use. Since the ID ESS bus has power, it is not essential that the SES Stop P IB is depressed.
+EVALUATOR NOTE I CUE That completes the JPM.
+EVALUATOR CUE Record JPM stop time:
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 10of12 REVISION
 ==SUMMARY==
-Revision 0 NewJPM JOB PERFORMANCE MEASURE 04.0N.20641.251 Description/Purpose of Revision TQ-106-0310 Revision 1 Page 10of12 2 Updated to new JPM format, revised task number and updated referenced procedures.
-Page 11 of 12 EVALUATOR COPY: TASK CONDITIONS
+JOB PERFORMANCE MEASURE 04.0N.20641.251 Revision                     Description/Purpose of Revision 0    NewJPM Updated to new JPM format, revised task number and updated referenced 2
+procedures.
+Page 11 of 12 EVALUATOR COPY:
+TASK CONDITIONS
 * Unit 2 is at rated power.
 * An Electrical transient has occurred on the 20 ESS bus.
@@ Line 958: / Line 1,576: @@
 * No electrical Bus fault is present.
 * You are the On-Shift U2 PCOP
-* Both loops of ESW are operational INITIATING CUE Implement AOP-004-001 Attachment A to re-energize the 20 ESS bus from the 'D' EDG Page 12of12 EXAMINEE COPY: TASK CONDITIONS
+* Both loops of ESW are operational INITIATING CUE Implement AOP-004-001 Attachment A to re-energize the 20 ESS bus from the 'D' EDG
+Page 12of12 EXAMINEE COPY:
+TASK CONDITIONS
 * Unit 2 is at rated power.
 * An Electrical transient has occurred on the 20 ESS bus.
@@ Line 964: / Line 1,585: @@
 * No electrical Bus fault is present.
 * You are the On-Shift U2 PCOP
-* Both loops of ESW are operational INITIATING CUE Implement AOP-004-001 Attachment A to re-energize the 20 ESS bus from the 'D' EOG SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: APRM Gain Adjustment JPM#: 78.0P.27731.101 Revision:
+* Both loops of ESW are operational INITIATING CUE Implement AOP-004-001 Attachment A to re-energize the 20 ESS bus from the 'D' EOG
-Date: 09/23/2016
---"----
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: APRM Gain Adjustment Revision: 5 JPM#: 78.0P.27731.101
-RO Setting: Simulator NUREG-1123 E/APE I Sys 215005 KIA Number A1 .07 KIA Importance 3.0/3.4 Alternate Path: DYES NO Time Critical NO Validation Time (min): _ _...;;.1.;;;..5_
+                                          --"---- Date:      09/23/2016 Applicability:~ RO ~SRO Setting:    Simulator NUREG-1123 E/APE I Sys        215005      KIA Number      A1 .07     KIA Importance  3.0/3.4 Alternate Path: DYES ~ NO           Time Critical DYES~ NO Validation Time (min): _ _...;;.1.;;;..5_
-Examinee Name:
+cr/2~11~
-J/it-// (,, 'j/;)_'i flt 2; l q, llp ------------------
+J/it-// (,
-Last, First Ml Employee Number Exam Date: ---------Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:.
+                                                       'j/;)_'i flt 2; l q, llp Examinee Name:
-__________
+                  --  ----------------
-_ Name Signature Comments:
+Last, First Ml                                          Employee Number Exam Date:                                      Exam Duration (Min): _ _ _ _ _ _ _ __
+             ---------
+Evaluation Result:  D Satisfactory      D Unsatisfactory Evaluator:. _ _ _ _ _ _ _ _ _ __
+Name                                       Signature Comments:
 REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 78.0P.27731.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
 C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
 D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
-: 11. REFERENCES A. OP-178-002, PRNMS (Revision
+: 11. REFERENCES A. OP-178-002, PRNMS (Revision 9)
-: 9) Ill. TASK CONDITIONS APRM Channel 3 is reading approximately 70%. Core thermal power from the OD-3 heat balance has been verified to be 73% APRM Channel 3 has already been bypassed by the PCO. IV. INITIATING CUE Perform a manual APRM GAF adjustment of APRM 3 IAW OP-178-002 Section 2.2.5. V. TASK STANDARD Successfully perform manual APRM GAF adjustments for APRM 3.
+Ill. TASK CONDITIONS APRM Channel 3 is reading approximately 70%.
+Core thermal power from the OD-3 heat balance has been verified to be 73%
+APRM Channel 3 has already been bypassed by the PCO.
+IV. INITIATING CUE Perform a manual APRM GAF adjustment of APRM 3 IAW OP-178-002 Section 2.2.5.
+V. TASK STANDARD Successfully perform manual APRM GAF adjustments for APRM 3.
 SIMULATOR SETUP INSTRUCTIONS
 : 1. Reset Simulator to any power IC and adjust reactor power to 73%.
-* Adjust APRM 3 GAF to indicate
+* Adjust APRM 3 GAF to indicate ~70%
-* Bypass APRM 3. SIMULATOR SETUP INSTRUCTIONS FOR LOC 28 NRC EXAM 1. Reset the simulator to IC 390. 2. Verify conditions above.
+* Bypass APRM 3.
-INFORMATION FOR EVALUATOR
+SIMULATOR SETUP INSTRUCTIONS FOR LOC 28 NRC EXAM
-* Marking a step as UNSAT requires written comments on respective step . TQ-106-ll;:, 10 Revision 1 Page 4of10
+: 1. Reset the simulator to IC 390.
+: 2. Verify conditions above.
+TQ-106-ll;:, 10 Revision 1 Page 4of10 INFORMATION FOR EVALUATOR
+* Marking a step as UNSAT requires written comments on respective step .
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
 * The time clock starts when the candidate acknowledges the Initiating Cue .
-* This JPM must be performed in the simulator.
+* This JPM must be performed in the simulator. Reset to ~xam-specific IC, or configure the simulator per the Simulator Setup Instructions .
-Reset to IC, or configure the simulator per the Simulator Setup Instructions .
+* A replacement copy of OP-178-002 section 2.2.
-* A replacement copy of OP-178-002 section 2.2. BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OP-178-002, S/U controlled copy. determines section 2.2.5 applies. Verifies prerequisites and precautions are met. EVALUATOR NOTE Role-play as PCO or SRO to avoid using plant page system during the JPM 2 Establish communications with PCO Establishes communications using plant S/U page. EVALUATOR CUE State that all communications will be with examiner role playing as PCO or SRO to avoid using plant page system during the JPM EVALUATOR CUE When operator is confirming BYPASS LED status state, "Channel 13 BYPASSED LEDs for APRM 11, 12, and 14 are lit." 3 Verifies APRM 3 bypassed Confirms all four 2/4 voters, BYPASSED SIU LEDs for bypassed APRM are illuminated
+BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN.
-*4 Adjust the display to the proper screen Press ETC button to display ENTER SET S/U MODE *5 Accept the proper display screen Press ENTER SET MODE key S/U *6 Enter the password Enter password "1234" and press ENT S/U 7 Confirm mode Confirm OPER SET mode indicated on SIU APRM or ODA *8 Setup display for gain adjustment
+EVALUATOR CUE Record JPM start time:
-* Using the cursor keys, highlight the S/U APRM GAIN
+Step   Action                                                 Standard                                         Eva I  Comments 1   Identifies governing procedure and obtain              Obtains controlled copy of OP-178-002,            S/U controlled copy.                                       determines section 2.2.5 applies. Verifies prerequisites and precautions are met.
+EVALUATOR NOTE Role-play as PCO or SRO to avoid using plant page system during the JPM 2   Establish communications with PCO                      Establishes communications using plant            S/U page.
+EVALUATOR CUE State that all communications will be with examiner role playing as PCO or SRO to avoid using plant page system during the JPM EVALUATOR CUE When operator is confirming BYPASS LED status state, "Channel 13 BYPASSED LEDs for APRM 11, 12, and 14 are lit."
+  Verifies APRM 3 bypassed                               Confirms all four 2/4 voters, BYPASSED            SIU LEDs for bypassed APRM are illuminated
+   *4   Adjust the display to the proper screen                Press ETC button to display ENTER SET             S/U MODE
+   *5   Accept the proper display screen                       Press ENTER SET MODE key                          S/U
+   *6   Enter the password                                     Enter password "1234" and press ENT               S/U
+TQ-106-us1 o Revision 1 Page 5of10 7  Confirm mode                                              Confirm OPER SET mode indicated on                SIU APRM or ODA
+  *8  Setup display for gain adjustment
+* Using the cursor keys, highlight the        S/U APRM GAIN
 * Press SET PARAMETERS key Verify APRM indicates SET PARAMETERS:
-APRM GAIN *9 Adjust APRM 3 GAF to the target gain Performs the following IAW section 2.2.5: S/U
+APRM GAIN
-* Adjust the APRM GAIN DESIRED UNTIL PROJECTED FLUX (%) is+/- 2% of calculated CTP using using U i) CURSOR keys to scroll
+  *9  Adjust APRM 3 GAF to the target gain                      Performs the following IAW section 2.2.5:         S/U
-* Press the ACCEPT key 10 Confirm APRM 3 target gain is selected
+* Adjust the APRM GAIN DESIRED UNTIL PROJECTED FLUX (%) is+/- 2%
-* Confirm the APRM GAIN PRESENT S/U changes to equal the APRM GAIN DESIRED Confirm ACTUAL FLUX (%) is +/- 2% of calculated CTP 11 Exit the setup displays
+of calculated CTP using using Ui)
-* Press EXIT key S/U
+CURSOR keys to scroll
-* Press EXIT SET MODE key Press YES key 12 Confirms APRM 3 display indicates OPERA TE Confirms APRM upper display section S/U indicates OPERA TE on top right corner of display 13 Ensures indications are within 2% of APRM Ensure reading on NMSB display and S/U reading APRM ODA reading within 2% of desired APRM reading EVALUATOR NOTE When Applicant either calls the control room or is returning to the control room to verify indications, end the JPM. TQ-106-us1 o Revision 1 Page 5of10 EVALUATOR CUE Record JPM stop time: EVALUATOR CUE That completes the JPM. EVALUATOR NOTE Do you have ALL your JPM exam materials?
+* Press the ACCEPT key 10  Confirm APRM 3 target gain is selected
-Task Cue Sheets? Procedures?
+* Confirm the APRM GAIN PRESENT                S/U changes to equal the APRM GAIN DESIRED Confirm ACTUAL FLUX (%) is +/- 2% of calculated CTP 11  Exit the setup displays
-TQ-106-u-s10 Revision 1 Page 6 of 10 TQ-106-0310 Revision 1 Page 8of10 REVISION
+* Press EXIT key                               S/U
+* Press EXIT SET MODE key Press YES key 12  Confirms APRM 3 display indicates OPERATE                  Confirms APRM upper display section              S/U indicates OPERATE on top right corner of display 13  Ensures indications are within 2% of APRM                  Ensure reading on NMSB display and               S/U reading                                                   APRM ODA reading within 2% of desired APRM reading EVALUATOR NOTE When Applicant either calls the control room or is returning to the control room to verify indications, end the JPM.
+TQ-106-u-s10 Revision 1 Page 6 of 10 EVALUATOR CUE Record JPM stop time:
+EVALUATOR CUE That completes the JPM.
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 8of10 REVISION
 ==SUMMARY==
-Revision 0 1 2 3 4 5 NewJPM JOB PERFORMANCE MEASURE 78.0P.27731.101 Description/Purpose of Revision Revise for TQ procedures, minor editorial corrections NRC revised based on facility comments Revised for format change from NRC format to SSES format Minor editorial changes. Revised power level to accommodate JPM pairing. Updated to new format and updated referenced procedure revisionss Page 9of10 EVALUATOR-SCENARIO 1 , TASK CONDITIONS APRM Channel 3 is reading approximately 70%. Core thermal power from the 00-3 heat balance has been verified to to be 73% APR_M Channel 3 has already been bypassed by the PCO. INITIATING CUE Perform a manual APRM GAF adjustment of APRM 3 IAW OP-178-002 Section 2.2.5.
-Page 10of10 EXAMINEE -SCENARIO 1 TASK CONDITIONS APRM Channel 3 is reading approximately 70%. Core thermal power from the OD-3 heat balance has been verified to to be 73% APRM Channel 3 has already been bypassed by the PCO. INITIATING CUE Perform a manual APRM GAF adjustment of APRM 3 IAW OP-178-002 Section 2.2.5.
+JOB PERFORMANCE MEASURE 78.0P.27731.101 Revision                       Description/Purpose of Revision 0    NewJPM 1    Revise for TQ procedures, minor editorial corrections 2    NRC revised based on facility comments 3    Revised for format change from NRC format to SSES format 4    Minor editorial changes. Revised power level to accommodate JPM pairing.
-SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Implement Placing Alternate TBCCW Pump In Service JPM#: 15.0P.20688.151 Date:07/07/2016 Applicability:
+    Updated to new format and updated referenced procedure revisionss
-:8] RO 1:8] SRO Setting: Simulator NUREG-1123 E/APE I Sys400000 KIA Number A2.01 KIA Importance 3.3/3.4 Alternate Path: 1:8] YES 0 NO Time Critical DYES 1:8] NO Validation Time (min):10 Testing Method: D Simulate 1:8] Perform Date Date: Author::Greg van den Berg '\ Validated:
-Date: q( 2. c;(/? Approval: L;:) Date: '.l-'7, /'2 Nuclear Training Supervisor Last, First Ml Employee Number Exam Date: ---------Exam Duration (Min): ________ _ Evaluation Result: 0 Satisfactory 0 Unsatisfactory Evaluator:
+Page 9of10 EVALUATOR- SCENARIO 1
------------
+  ,
-Name Signature Comments:
+TASK CONDITIONS APRM Channel 3 is reading approximately 70%.
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE I5.0P.20688.I5I I. SAFETY CONSIDERATIONS A All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+Core thermal power from the 00-3 heat balance has been verified to to be 73%
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+APR_M Channel 3 has already been bypassed by the PCO.
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+INITIATING CUE Perform a manual APRM GAF adjustment of APRM 3 IAW OP-178-002 Section 2.2.5.
+Page 10of10 EXAMINEE - SCENARIO 1 TASK CONDITIONS APRM Channel 3 is reading approximately 70%.
+Core thermal power from the OD-3 heat balance has been verified to to be 73%
+APRM Channel 3 has already been bypassed by the PCO.
+INITIATING CUE Perform a manual APRM GAF adjustment of APRM 3 IAW OP-178-002 Section 2.2.5.
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Implement Placing Alternate TBCCW Pump In Service JPM#: 15.0P.20688.151                               Revision:~             Date:07/07/2016 Applicability: 1:8] RO 1:8] SRO Setting: Simulator NUREG-1123 E/APE I Sys400000 KIA Number A2.01 KIA Importance 3.3/3.4 Alternate Path: 1:8] YES  0   NO         Time Critical DYES 1:8] NO Validation Time (min):10 Testing Method:     D Simulate      1:8] Perform Author::Greg van den Berg
+                            '\                         Date ;j71~;
+Date:      L~
+Validated:  -.v.-t-~~~~---- Date: q(2. c;(/?
+Approval:      ~ L;:) ~                               Date:  ~ '.l- '7, /'2 Nuclear Training Supervisor Last, First Ml                                              Employee Number Exam Date:                                           Exam Duration (Min): _ _ _ _ _ _ _ __
+              ---------
+Evaluation Result:     0  Satisfactory      0  Unsatisfactory Evaluator:
+           -----------
+Name                                            Signature Comments:
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE I5.0P.20688.I5I I. SAFETY CONSIDERATIONS A      All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
+: 1.       Whenever any electrical panel is opened for inspection during JPM performance.
+: 2.       Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
 C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
 D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
-: 11. REFERENCES A. OP-I I5-00I, Turbine Building Closed Cooling Water System (Revision
+: 11. REFERENCES A. OP-I I5-00I, Turbine Building Closed Cooling Water System (Revision 26)
-: 26) B. ON-TBCCW-IOI, Loss of Turbine Building Closed Cooling Water (Revision I) C. AR-I23-G02, TBCCW PUMP B MOTOR TRIP (Revision
+B. ON-TBCCW-IOI, Loss of Turbine Building Closed Cooling Water (Revision I)
-: 27) D. AR-I23-G04, TBCCW HEAT EXCHANGER HEADER LO PRESS (Revision
+C. AR-I23-G02, TBCCW PUMP B MOTOR TRIP (Revision 27)
-: 27) 111. TASK CONDITIONS TBCCW Pump IA is in service, TBCCW Pump IB is in standby. TBCCW Pump IA is to be removed from service for planned maintenance.
+D. AR-I23-G04, TBCCW HEAT EXCHANGER HEADER LO PRESS (Revision 27) 111. TASK CONDITIONS TBCCW Pump IA is in service, TBCCW Pump IB is in standby.
+TBCCW Pump IA is to be removed from service for planned maintenance.
 IA TBCCW HTX is in-service.
-Pre-start checks for TBCCW Pump IB are sat. An NPO is stationed in the Unit I TBCCW pump area. IV. INITIATING CUE Place TBCCW Pump IB in service and shutdown TBCCW Pump IA, IAW OP-I I5-00I section 2.2. V. TASK STANDARD TBCCW Pump IA restarted and supplying cooling to TBCCW loads SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 15.0P.20688.151 NOTE: It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
+Pre-start checks for TBCCW Pump IB are sat.
+An NPO is stationed in the Unit I TBCCW pump area.
+IV. INITIATING CUE Place TBCCW Pump IB in service and shutdown TBCCW Pump IA, IAW OP-I I5-00I section 2.2.
+V. TASK STANDARD TBCCW Pump IA restarted and supplying cooling to TBCCW loads
+SIMULATOR SETUP INSTRUCTIONS JOB PERFORMANCE MEASURE 15.0P.20688.151 NOTE:      It is permissible to use a similar IC to the IC listed below, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
 * Reset the simulator to IC-18, or an exam-specific IC 389.
-* Insert the following Event Triggers ETEVAL 150P20688151 tw_lp103a(l)
+* Insert the following Event Triggers ETEVAL 150P20688151 tw_lp103a(l) = 0 & twvp114011 > 0.9 aet ETEVAL150P20688151A ETEVAL 150P20688151A diHS11405A.CurrValue = #OR.diHS11405A.RUN
-= 0 & twvp114011
+  +30 IOR di1C140ACK_Q f:ACK
-> 0.9 aet ETEVAL150P20688151A ETEVAL 150P20688151A diHS11405A.CurrValue
+  +2 MOR dilC140ACK_Q f:NORMAL
-= #OR.diHS11405A.RUN
+  +2 DOR di1C140ACK_Q
-+30 IOR di1C140ACK_Q f:ACK +2 MOR dilC140ACK_Q f:NORMAL +2 DOR di1C140ACK_Q
+  +2 IOR dilC140RST_Q f:RESET
-+2 IOR dilC140RST_Q f:RESET +2 MOR di1Cl40RST_Q f:NORMAL +2 DOR di1C140RST_Q IRF rfIA119003 f:RESET
+  +2 MOR di1Cl40RST_Q f:NORMAL
+  +2 DOR di1C140RST_Q IRF rfIA119003 f:RESET
 * Perform the following expert commands IMF cmf PM04_1P103A
-* Perform the following expert commands to assign keys to perform the required operator actions for the JPM. {Key[26]}
+* Perform the following expert commands to assign keys to perform the required operator actions for the JPM.
-IRF rfTW115001 f:0 ' {Key[27]}
+{Key[26]} IRF rfTW115001 f:0 '
-IRF rfTW115001 f:100 INFORMATION FOR EVALUATOR
+{Key[27]} IRF rfTW115001 f:100
-* Marking a step as UNSAT requires written comments on respective step. TQ-106-lM 10 Revision 1 Page 4 of 10
+TQ-106-lM 10 Revision 1 Page 4 of 10 INFORMATION FOR EVALUATOR
+* Marking a step as UNSAT requires written comments on respective step.
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
 * The time clock starts when the candidate acknowledges the initiating cue.
-* This JPM must be performed in the simulator.
+* This JPM must be performed in the simulator. Reset to exam-specific IC-389, or configure the simulator per the Simulator Setup Instructions.
-Reset to exam-specific IC-389, or configure the simulator per the Simulator Setup Instructions.
+EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.
-EVALUATOR NOTE: For Faulted JPMs The FAULTED step in the JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies OP-115-001 Section 2.2 is governing Obtains controlled copy of OP-115-001 S/U procedure and obtains controlled copy. obtained, selects Section 2.2. 2* Starts TBCCW Pump 1 B Depresses TBCCW PP 1P103B RUN PB S/U 3 Closes TBCCW Pump lA discharge valve Directs NPO to slowly close 114011, S/U TBCCW PUMP A DSCH BOOTH OPERA TOR CUE Depress KEY 26 to close 114011. EVALUATOR CUE 114011 is closed. 4 Checks TBCCW Pump lB discharge pressure 86-Performs the following:
+BOOTH OPERATOR CUE When student is ready to begin the JPM and the evaluator indicates, place the simulator in RUN.
+EVALUATOR CUE Record JPM start time:
+Step   Action                                                Standard                                           Eva I  Comments 1 Identifies OP-115-001 Section 2.2 is governing          Obtains controlled copy of OP-115-001 S/U procedure and obtains controlled copy.                obtained, selects Section 2.2.
+*   Starts TBCCW Pump 1B                                  Depresses TBCCW PP 1P103B RUN PB                   S/U 3   Closes TBCCW Pump lA discharge valve                  Directs NPO to slowly close 114011, S/U TBCCW PUMP A DSCH BOOTH OPERATOR CUE Depress KEY 26 to close 114011.
+EVALUATOR CUE 114011 is closed.
+  Checks TBCCW Pump lB discharge pressure 86-           Performs the following:
 psig.
 * Requests from NPO current indication on PI-11405B, TBCCW PUMP B DSCH S/U PRESS.
 * Confirms value is within 86-100 psig band.
-EVALUATOR CUE PI-I I 405B indicates 98 psig. 5* Stops TBCCW Pump IA. Depresses TBCCW PP IPI03A STOP PB. SIU 6 Checks TBCCW HX IA outlet temperature 92-Performs the following:
+TQ-106-D~10 Revision 1 Page 5 of 10 EVALUATOR CUE PI-I I 405B indicates 98 psig.
+*     Stops TBCCW Pump IA.                                Depresses TBCCW PP IPI03A STOP PB.             SIU 6    Checks TBCCW HX IA outlet temperature 92-            Performs the following:
 &deg;P.
-* Requests from NPO current indication on TI-I I 407 A, TBCCW HX A OUTLET SIU TEMP.
+* Requests from NPO current indication on TI-I I 407 A, TBCCW HX A OUTLET             SIU TEMP.
-* Confirms value is within 92-98 &deg;P band. EVALUATOR CUE TI-I I 407 A indicates 95 &deg;P. 7 Checks TBCCW system pressure stabilizes at Observes PI-I 1409, TB CCW HX OUTLET approximately 64-66 psig. HEADER, indicates approximately 64-SIU 66 psig. EVALUATOR NOTE The following step is a critical step only if the TBCCW Pump IA discharge valve was closed in the preceding steps. FAULT STATEMENT TBCCW PUMP lB TRIPS WHEN TBCCW PUMP lA DISCHARGE VAL VE IS STROKING OPEN. 8* Opens TBCCW Pump IA discharge valve. Performs the following:
+* Confirms value is within 92-98 &deg;P band.
+EVALUATOR CUE TI-I I 407A indicates 95 &deg;P.
+   Checks TBCCW system pressure stabilizes at          Observes PI-I 1409, TB CCW HX OUTLET approximately 64-66 psig.                           HEADER, indicates approximately 64-            SIU 66 psig.
+EVALUATOR NOTE The following step is a critical step only if the TBCCW Pump IA discharge valve was closed in the preceding steps.
+FAULT STATEMENT TBCCW PUMP lB TRIPS WHEN TBCCW PUMP lA DISCHARGE VAL VE IS STROKING OPEN.
+*     Opens TBCCW Pump IA discharge valve.                Performs the following:
 * Directs NPO to open I I 40 I I, TBCCW PUMPADSCH
-* Observes AR-I23-G02, TBCCW PUMP SIU B MOTOR TRIP, in alarm.
+* Observes AR-I23-G02, TBCCW PUMP              SIU B MOTOR TRIP, in alarm.
-* Informs Unit Supervisor of TBCCW Pump IB trip. BOOTH OPERA TOR CUE
+* Informs Unit Supervisor of TBCCW Pump IB trip.
+BOOTH OPERATOR CUE
 * Depress KEY 27 to open I I40I I.
 * Ensure Event Trigger ETEVALI50P20688I5I fires as I I40I 1 strokes open to trip TBCCW Pump IB.
-Revision 1 Page 5 of 10 EVALUATOR CUE As NPO: 114011 is open. As Unit Supervisor:
-Respond per procedure.
+TQ-106-lJ010 Revision 1 Page 6 of 10 EVALUATOR CUE As NPO: 114011 is open.
-As NPO if contacted about TBCCW Pump lB status: TBCCW Pump lB tripped. I don't know why. EVALUATOR NOTE Direction to start TBCCW Pump lA is provided in AR-123-G02, AR-123-G04, or ON-TBCCW-101.
+As Unit Supervisor: Respond per procedure.
-* I Starts TBCCW Pump lA. I Depresses TBCCW PP 1P103A RUN PB. BOOTH OPERATOR CUE SIU TQ-106-lJ010 Revision 1 Page 6 of 10 Ensure Event Trigger ETEVAL150P20668151A fires when TBCCW Pump lA is re-started to reset I/A and S/A compressors.
+As NPO if contacted about TBCCW Pump lB status: TBCCW Pump lB tripped. I don't know why.
-EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials?
+EVALUATOR NOTE Direction to start TBCCW Pump lA is provided in AR-123-G02, AR-123-G04, or ON-TBCCW-101.
-Task Cue Sheets? Procedures?
+*  I Starts TBCCW Pump lA.                          I Depresses TBCCW PP 1P103A RUN PB.       SIU BOOTH OPERATOR CUE Ensure Event Trigger ETEVAL150P20668151A fires when TBCCW Pump lA is re-started to reset I/A and S/A compressors.
+EVALUATOR NOTE I CUE That completes the JPM.
+EVALUATOR CUE Record JPM stop time:
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
 TQ-106-0310 Revision 1 Page 8 of 10 REVISION
 ==SUMMARY==
-Revision 0 2 NewJPM JOB PERFORMANCE MEASURE 15.0P.20688.151 Description/Purpose of Revision Revised for the new template and to update referenced procedures.
-ON-115-001 is now ON-TBCCW-101, Loss of Turbine Building Closed Cooling Water Page 9 of 10 EVALUATOR COPY: TASK CONDITIONS TBCCW Pump 1A is in service, TBCCW Pump 1 B is in standby. TBCCW Pump 1A is to be removed from service for planned maintenance.
+JOB PERFORMANCE MEASURE 15.0P.20688.151 Revision                       Description/Purpose of Revision 0    NewJPM Revised for the new template and to update referenced procedures. ON-2    115-001 is now ON-TBCCW-101, Loss of Turbine Building Closed Cooling Water
+Page 9 of 10 EVALUATOR COPY:
+TASK CONDITIONS TBCCW Pump 1A is in service, TBCCW Pump 1B is in standby.
+TBCCW Pump 1A is to be removed from service for planned maintenance.
 lA TBCCW HTX is in-service.
-Pre-start checks for TBCCW Pump 1 B are sat. An NPO is stationed in the Unit 1 TBCCW pump area. INITIATING CUE Place TBCCW Pump lB in service and shutdown TBCCW Pump lA, IAW OP-115-001 section 2.2.
+Pre-start checks for TBCCW Pump 1B are sat.
-Page 10of10 EXAMINEE COPY: TASK CONDITIONS TBCCW Pump 1A is in service, TBCCW Pump 1 B is in standby. TBCCW Pump 1A is to be removed from service for planned maintenance.
+An NPO is stationed in the Unit 1 TBCCW pump area.
+INITIATING CUE Place TBCCW Pump lB in service and shutdown TBCCW Pump lA, IAW OP-115-001 section 2.2.
+Page 10of10 EXAMINEE COPY:
+TASK CONDITIONS TBCCW Pump 1A is in service, TBCCW Pump 1B is in standby.
+TBCCW Pump 1A is to be removed from service for planned maintenance.
 IA TBCCW HTX is in-service.
-Pre-start checks for TBCCW Pump 1 B are sat. An NPO is stationed in the Unit 1 TBCCW pump area. INITIATING CUE Place TBCCW Pump IB in service and shutdown TBCCW Pump IA, IAW OP-I I5-00I section 2.2.
+Pre-start checks for TBCCW Pump 1B are sat.
-SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Hydraulically Remove a HCU from Service in Accordance With OP-155-001 JPM#: 55.0P.20241.102 Revision:
+An NPO is stationed in the Unit 1 TBCCW pump area.
-Date: 09/23/2016
+INITIATING CUE Place TBCCW Pump IB in service and shutdown TBCCW Pump IA, IAW OP-I I5-00I section 2.2.
---""-----Applicability: RO SRO Setting: Plant NUREG-1123 E/APE I Sys 201001 KIA Number ----"""A-""-1"""".0'""'6
-_____ K/A Importance 3.4/3.4 Alternate Path: DYES NO Time Critical DYES NO Validation Time (min):___,;1;...;;.0
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Hydraulically Remove a HCU from Service in Accordance With OP-155-001 JPM#: 55.0P.20241.102                            Revision: --""-----
-__ Testing Method:
+                      Date: 09/23/2016 Applicability: ~ RO ~ SRO Setting:         Plant NUREG-1123 E/APE I Sys 201001                      KIA Number ----"""A-""-1"""".0'""'6_____K/A Importance 3.4/3.4 Alternate Path:     DYES       ~ NO           Time Critical DYES      ~        NO Validation Time (min):___,;1;...;;.0_ _
-D Perform Author::
+Testing Method: ~Simulate                 D   Perform Author::        ~o.._.IA..J<_f //                           Date:~
-//
+Operations   ~eview:          CM - .,                       Date:~
-Operations CM --.,
+Validated:         (?a ,tcJ1.1
-Validated:
+_......_,,__..__.____-=--'------- Date: CfI               /2?//6     I Approval:      ~21.Ac       L0 k Nuclear Training Supervisor Date:  q ' J_7
-(?a ,tcJ1.1 Date: Cf /2?//6 _......_,,__..__._
+* I (o Examinee Name:
-___ -=--'-------
+                       --      ----------------
-I I Approval:
+Last, First Ml                                                         Employee Number Exam Date:    ______ __              ___..;.
-L0 k Date: q ' J_ 7
+Exam Duration (Min): _ _ _ _ _ _ _ __
-* I (o Nuclear Training Supervisor Examinee Name: ------------------
+Evaluation Result:         D Satisfactory        D Unsatisfactory Evaluator: _ _ _ _ _ _ _ _ _ __
-Last, First Ml Employee Number Exam Date: ______ ___..;. __ Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+Name                                                 Signature Comments:
-__________
-_ Name Signature Comments:
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 55.0P.20241.102 I. SAFETY CONSIDERATIONS A.      All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 55.0P.20241.102 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+B.      All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+C.      If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+D.      Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
-II. REFERENCES A. OP-155-001 Control Rod Drive Hydraulic System (Revision
+II. REFERENCES A.      OP-155-001       Control Rod Drive Hydraulic System (Revision 69)
-: 69) Ill. TASK CONDITIONS A. Unit 1 is in Mode 4; all rods in. B. CRD System is aligned for normal operation.
+Ill. TASK CONDITIONS A.      Unit 1 is in Mode 4; all rods in.
-C. Tech Specs 3.1.3, 3.1.4, and 3.1.5 have been referenced and all appropriate actions are being followed.
+B.      CRD System is aligned for normal operation.
-IV. INITIATING CUE Isolate HCU 30-47 IAW OP-155-001 section 2.17. DO NOT drain OR depressurize the HCU. V. TASK STANDARD HCU 30-47 is Hydraulically isolated.
+C.      Tech Specs 3.1.3, 3.1.4, and 3.1.5 have been referenced and all appropriate actions are being followed.
-INFORMATION FOR EVALUATOR
+IV. INITIATING CUE Isolate HCU 30-47 IAW OP-155-001 section 2.17. DO NOT drain OR depressurize the HCU.
+V. TASK STANDARD HCU 30-47 is Hydraulically isolated.
+TQ-106-lJ~ I 0 Revision 1 Page 3 of 9 INFORMATION FOR EVALUATOR
 * Marking a step as UNSAT requires written comments on respective step .
-I 0 Revision 1 Page 3 of 9
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
 * The time clock starts when the candidate acknowledges the Initiating Cue.
 * This JPM must be performed in the plant. Obtain Shift Manager authorization to proceed. This JPM requires access to the RB.
 * Have a copy of OP-155-001section2.17 .
-* A different HCU may be selected for the JPM prior to the start if in-plant situations require changing it. (High rad, protected area, etc) Prior approval of the supervisor is required and the JPM may be pen and inked to identify the change. EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OP-155-001 S/U controlled copy. section 2.17. 2 Review the prerequisites and precautions Reviews prerequisites and precautions.
+* A different HCU may be selected for the JPM prior to the start if in-plant situations require changing it. (High rad, protected area, etc) Prior approval of the supervisor is required and the JPM may be pen and inked to identify the change.
-S/U EVALUATOR CUE S/U All prerequisites have been met. 3 Comply with following:
+EVALUATOR CUE Record JPM start time:
-Determines all appropriate actions are being followed from the initial conditions.
+Step     Action                                               Standard                                          Eva I   Comments 1  Identifies governing procedure and obtain            Obtains controlled copy of OP-155-001 S/U controlled copy.                                     section 2.17.
-S/U TS 3.1.3, TS 3.1.4, TS 3.1.5. ' EVALUATOR NOTE Following is applicable to all Hydraulic Control Units 1S239. Three (3) digit standard HCU valve numbers are used.(i.e.
+Review the prerequisites and precautions             Reviews prerequisites and precautions.            S/U EVALUATOR CUE S/U All prerequisites have been met.
-instead of 147101-3047 it will say 101) *4 Close 101, CRD Insert lso. Closes 101, CRD Insert lso by turning the S/U handwheel clockwise.
+Comply with following:                               Determines all appropriate actions are being followed from the initial conditions.       S/U TS 3.1.3, TS 3.1.4, TS 3.1.5.                '
-EVALUATOR CUE If turned clockwise, the valve moved and is now closed. S/U If turned counter-clockwise, the valve did not move. *5 Close 102, CRD Withdrawal lso. Closes 102, CRD Withdrawal lso by turning S/U the handwheel clockwise.
+EVALUATOR NOTE Following is applicable to all Hydraulic Control Units 1S239. Three (3) digit standard HCU valve numbers are used.(i.e. instead of 147101-3047 it will say 101)
-EVALUATOR CUE If turned clockwise, the valve moved and is now closed. If turned counter-clockwise, the valve did not move. *6 Close 113, Charging Water lso EVALUATOR CUE If turned clockwise, the valve moved and is now closed. If turned counter-clockwise, the valve did not move. *7 Close 104, Cooling Water lso. EVALUATOR CUE If turned clockwise, the valve moved and is now closed. If turned counter-clockwise, the valve did not move. *8 Close 103, Drive Header lso. EVALUATOR CUE If turned clockwise, the valve moved and is now closed. If turned counter-clockwise, the valve did not move. *9 Close 105, Exhaust Header lso. EVALUATOR CUE If turned clockwise, the valve moved and is now closed. If turned counter-clockwise, the valve did not move. *10 Close 112, Scram Discharge Header lso. Closes 113, Charging Water lso by turning the handwheel clockwise.
+     *4   Close 101, CRD Insert lso.                            Closes 101, CRD Insert lso by turning the S/U handwheel clockwise.
-Closes 104, Cooling Water lso by turning the handwheel clockwise.
+EVALUATOR CUE If turned clockwise, the valve moved and is now closed.                                                          S/U If turned counter-clockwise, the valve did not move.
-Closes 103, Drive Header lso by turning the handwheel clockwise.
+      *5  Close 102, CRD Withdrawal lso.                        Closes 102, CRD Withdrawal lso by turning S/U the handwheel clockwise.
-Closes 105, Exhaust Header lso by turning the handwheel clockwise.
-Closes 112, Scram Discharge Header lso by turning the handwheel clockwise.
+TQ-106-u~ 10 Revision 1 Page 4 of 9 EVALUATOR CUE If turned clockwise, the valve moved and is now closed.                                             S/U If turned counter-clockwise, the valve did not move.
-S/U S/U S/U SIU S/U S/U S/U SIU S/U SIU 10 Revision 1 Page 4 of 9 EVALUATOR CUE If turned clockwise, the valve moved and is now closed. If turned counter-clockwise, the valve did not move. EVALUATOR NOTE I CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials?
+     *6  Close 113, Charging Water lso                  Closes 113, Charging Water lso by turning S/U the handwheel clockwise.
-Task Cue Sheets? Procedures?
+EVALUATOR CUE If turned clockwise, the valve moved and is now closed.                                             S/U If turned counter-clockwise, the valve did not move.
-S/U
+     *7  Close 104, Cooling Water lso.                  Closes 104, Cooling Water lso by turning the handwheel clockwise.                    SIU EVALUATOR CUE If turned clockwise, the valve moved and is now closed.                                             S/U If turned counter-clockwise, the valve did not move.
-*1 0 Revision 1 Page 5 of 9 REVISION
+     *8  Close 103, Drive Header lso.                   Closes 103, Drive Header lso by turning the handwheel clockwise.                        S/U EVALUATOR CUE If turned clockwise, the valve moved and is now closed.                                             S/U If turned counter-clockwise, the valve did not move.
+     *9  Close 105, Exhaust Header lso.                 Closes 105, Exhaust Header lso by turning the handwheel clockwise.                    SIU EVALUATOR CUE If turned clockwise, the valve moved and is now closed.                                             S/U If turned counter-clockwise, the valve did not move.
+   *10   Close 112, Scram Discharge Header lso.         Closes 112, Scram Discharge Header lso by turning the handwheel clockwise.         SIU
+TQ-106-0~ *1 0 Revision 1 Page 5 of 9 EVALUATOR CUE If turned clockwise, the valve moved and is now closed.               S/U If turned counter-clockwise, the valve did not move.
+EVALUATOR NOTE I CUE That completes the JPM.
+EVALUATOR CUE Record JPM stop time:
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 7of9 REVISION
 ==SUMMARY==
-JOB PERFORMANCE MEASURE 55.0P.20241.102 Revision Description/Purpose of Revision 0 New JPM,-Revised from 55.0P.003.102 TQ-106-0310 Revision 1 Page 7of9 Page 8 of 9 EVALUATOR COPY: TASK CONDITIONS A. Unit 1 is in Mode 4; all rods in. B. CRD System is aligned for normal operation.
+JOB PERFORMANCE MEASURE 55.0P.20241.102 Revision                      Description/Purpose of Revision 0    New JPM,- Revised from 55.0P.003.102
+Page 8 of 9 EVALUATOR COPY:
+TASK CONDITIONS A. Unit 1 is in Mode 4; all rods in.
+B. CRD System is aligned for normal operation.
 C. Tech Specs 3.1.3, 3.1.4, and 3.1.5 have been referenced and all appropriate actions are being followed.
-INITIATING CUE Isolate HCU 30-47 IAW OP-155-001section2.17.
+INITIATING CUE Isolate HCU 30-47 IAW OP-155-001section2.17. DO NOT drain OR depressurize the HCU.
-DO NOT drain OR depressurize the HCU.
-Page 9 of 9 EXAMINEE COPY: TASK CONDITIONS A. Unit 1 is in Mode 4; all rods in. B. CRD System is aligned for normal operation.
+Page 9 of 9 EXAMINEE COPY:
+TASK CONDITIONS A. Unit 1 is in Mode 4; all rods in.
+B. CRD System is aligned for normal operation.
 C. Tech Specs 3.1.3, 3.1.4, and 3.1.5 have been referenced and all appropriate actions are being followed.
-INITIATING CUE Isolate HCU 30-47 IAW OP-155-001section2.17.
+INITIATING CUE Isolate HCU 30-47 IAW OP-155-001section2.17. DO NOT drain OR depressurize the HCU.
-DO NOT drain OR depressurize the HCU.
-SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Start RPS MG Set 2S237A(B) from Local Control Panel 2G201A(8)
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title: Start RPS MG Set 2S237A(B) from Local Control Panel 2G201A(8) IAW OP-258-001 JPM#: 58.0P.26824.201                   Revision: 3
-IAW OP-258-001 JPM#: 58.0P.26824.201 Revision:
+                                                 ------- Date:      09/23/2016 Applicability: 1Z! RO IZI SRO Setting: -'P_l.....
-Date: 09/23/2016
+an"""t_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
--------Applicability:
+NUREG-1123 E/APE I Sys             212000        KIA Number       A2.02      KIA Importance  3.7/3.9 Alternate Path:      DYES IZI NO            Time Critical DYES IZI NO Validation Time (min):_--=2.;;;..5_
-Z! RO IZI SRO Setting: -'P_l ..... an"""t __________________
+::~~;::: Met~~~PeITonn Date:~
-_ NUREG-1123 E/APE I Sys 212000 KIA Number A2.02 KIA Importance 3.7/3.9 Alternate Path: DYES IZI NO Time Critical DYES IZI NO Validation Time (min):_--=2.;;;..5
+Operations   RevieW:C~---                                Date:  CJ/z~ O~
-_
+Validated:     (}er ,f,edcJ                               Date: 1/2~ /It Approval:-~-=--\-"....)_&+?_         . . .*____ Date:
-Operations Validated:
+NUclear Training Supervisor Examinee Name:
-(}er ,f,edcJ Date: Date:
+                      --    ----------------
-/It
+Last, First Ml                                             Employee Number Exam Date: _ _ _ _ _ _ _ __                             Exam Duration (Min): _ _ _ _ _ _ _ __
-.... )_&+?_ .....
+Evaluation Result:       D Satisfactory        D Unsatisfactory Evaluator:
-* ____ Date: NUclear Training Supervisor Examinee Name: ------------------
+           -----------
-Last, First Ml Employee Number Exam Date: ________ _ Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+Name                                             Signature Comments:
------------
-Name Signature Comments:
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 58. OP.26824.201 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+: 58. OP.26824.201 I. SAFETY CONSIDERATIONS A.        All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+B.      All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
-* C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+: 2.         Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+* C.        If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
-II. REFERENCES A. OP-258-001, RPS SYSTEM (Rev. 62) Ill. TASK CONDITIONS RPS MG Set 2S237 A(B) has been de-energized for emergent maintenance on the normal supply EPA breakers.
+D.        Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
-The 120V RPS Power Distribution Panel 2Y201A(B) is on Alternate Power. Maintenance has been completed on the RPS A(B) MG Set, and all clearance orders have been removed. All 480V AC and 125V DC power systems are in operation.
+II. REFERENCES A.       OP-258-001, RPS SYSTEM (Rev. 62)
+Ill. TASK CONDITIONS RPS MG Set 2S237A(B) has been de-energized for emergent maintenance on the normal supply EPA breakers.
+The 120V RPS Power Distribution Panel 2Y201A(B) is on Alternate Power.
+Maintenance has been completed on the RPS A(B) MG Set, and all clearance orders have been removed.
+All 480V AC and 125V DC power systems are in operation.
 CL-258-0011 is complete.
 Electrical Maintenance is available to support this evolution.
@@ Line 1,155: / Line 1,884: @@
 * The MG voltmeter and ammeter indicate 0
 * Both EPA breakers (2CBS003A-A and 2CBS003A-C) are open
-* All four red indicating lights on the EPA breakers are extinguished IV. INITIATING CUE Start Unit 2 RPS MG Set A(B) and close the associated EPA breakers IAW OP-258-001 Sections 2.1 and 2.2. V. TASK STANDARD Unit 2 RPS MG Set A(B) started OP-258-001 Section 2.1 and normal supply EPA breakers closed per OP-258-001 Section 2.2.
+* All four red indicating lights on the EPA breakers are extinguished IV. INITIATING CUE Start Unit 2 RPS MG Set A(B) and close the associated EPA breakers IAW OP-258-001 Sections 2.1 and 2.2.
-INFORMATION FOR EVALUATOR
+V. TASK STANDARD Unit 2 RPS MG Set A(B) started p~r OP-258-001 Section 2.1 and normal supply EPA breakers closed per OP-258-001 Section 2.2.
+TQ-106-u~*10 Revision 1 Page 3 of 12 INFORMATION FOR EVALUATOR
 * Marking a step as UNSAT requires written comments on respective step .
-Revision 1 Page 3 of 12
 * Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .
 * The time clock starts when the candidate acknowledges the Initiating Cue .
 * This JPM must be performed in the plant. Obtain Shift Manager authorization to proceed. This JPM requires access to Unit 2 RB RPS MG set
 * This JPM can be performed on either Unit 2 RPS MG set
-* Have a copy of OP-258-001 Section 2.1 and 2.2 . EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OP-258-001 S/U controlled copy. sections 2.1 and 2.2. EVALUATOR NOTE The Operator will require a key for the EPA breakers later. They may choose to obtain a 235, 1235, or 2235 key from Control Room or the FUS. If they ask now, they now have a 2235 key. 2 Unlock AND rotate Voltage Adjust potentiometer to At 2G201A(B), REACTOR PROT SYS M-G S/U full counter-clockwise position.
+* Have a copy of OP-258-001 Section 2.1 and 2.2 .
-SET A(B) GENERA TOR, local control panel performs the following
+EVALUATOR CUE Record JPM start time:
-* Loosens locking device set screw . Rotates the potentiometer to the full counter-clockwise position EVALUATOR CUE Voltage adjust potentiometer unlocked Voltage adjust potentiometer is in the full counter-clockwise position EVALUATOR NOTE Motor has automatic reset of thermal overloads.
+Step    Action                                                Standard                                         Eva I  Comments 1   Identifies governing procedure and obtain             Obtains controlled copy of OP-258-001             S/U controlled copy.                                      sections 2.1 and 2.2.
-If examinee releases PB before MOTOR ON PB cued as ON, such that motor would fail to come up to speed, thermal overloads should be allowed time to reset prior to initiating another start sequence.
+EVALUATOR NOTE The Operator will require a key for the EPA breakers later. They may choose to obtain a 235, 1235, or 2235 key from Control Room or the FUS. If they ask now, they now have a 2235 key.
-*3 Depress AND hold MOTOR ON pushbutton Depresses the MOTOR ON PB and S/U maintains it depressed EVALUATOR CUE Motor On PB is depressed
+  Unlock AND rotate Voltage Adjust potentiometer to     At 2G201A(B), REACTOR PROT SYS M-G                S/U full counter-clockwise position.                      SET A(B) GENERATOR, local control panel performs the following
-*4 Release Motor On PB when Motor On red indicating light Illuminates.
+* Loosens locking device set screw.
-EVALUATOR CUE Motor On red light is lit and when released, the Motor On PB releases 5 Observes MG Set comes up to speed EVALUATOR CUE MG set running at speed EVALUATOR NOTE Observes the MOTOR ON red light is illuminated and releases the MOTOR ON PB Observes MG Set comes up to speed S/U S/U TQ-106-C.r;:>10 Revision 1 Page 4of12 The Motor On pushbutton must be depressed again in order to reset the overvoltage trip. There is no visible indication that it has reset. *6 Resets OV relay Depresses MOTOR ON PB S/U .EVALUATOR CUE Motor On PB depressed and released 7 Verifies RPS MG set voltage at 120V AC Observes RPS MG Set A(B) voltmeter.
+Rotates the potentiometer to the full counter-clockwise position EVALUATOR CUE Voltage adjust potentiometer unlocked Voltage adjust potentiometer is in the full counter-clockwise position EVALUATOR NOTE Motor has automatic reset of thermal overloads. If examinee releases PB before MOTOR ON PB cued as ON, such that motor would fail to come up to speed, thermal overloads should be allowed time to reset prior to initiating another start sequence.
-S/U I EVALUATOR CUE RPS MG set voltmeter indicates 11 OV AC *8 Adjusts voltage output to 120V AC. Turns the VOLTAGE ADJUST S/U potentiometer clockwise until 120V AC EVALUATOR CUE RPS MG set voltmeter indicates 120V AC 9 Locks Voltage Adjust potentiometer.
+    *3   Depress AND hold MOTOR ON pushbutton                  Depresses the MOTOR ON PB and                     S/U maintains it depressed
-* Tightens the locking set screw on the S/U VOLTAGE ADJUST potentiometer.
-*10 Closes MG set generator output breaker Lifts the GENERA TOR OUTPUT breaker S/U operating paddle to the full up position.
+TQ-106-C.r;:>10 Revision 1 Page 4of12 EVALUATOR CUE Motor On PB is depressed
-EVALUATOR CUE ' Generator Output breaker is closed. 11 Observes EPA breaker 2CBS003A-A(B-B).lnput Power Available red light ILLUMINATES EVALUATOR CUE Power In Motor Gen red light is lit. EVALUATOR NOTE Section 2.1 is complete.
+    *4  Release Motor On PB when Motor On red               Observes the MOTOR ON red light is                 S/U indicating light Illuminates.                       illuminated and releases the MOTOR ON PB EVALUATOR CUE Motor On red light is lit and when released, the Motor On PB releases 5  Observes MG Set comes up to speed                   Observes MG Set comes up to speed                  S/U EVALUATOR CUE MG set running at speed EVALUATOR NOTE The Motor On pushbutton must be depressed again in order to reset the overvoltage trip. There is no visible indication that it has reset.
-Remaining steps are in Section 2.2. *12 Obtains 235, 1235, or 2235 key from Control Room. EVALUATOR CUE You have a 2235 key. *13 Inserts key in 2CBS003A-A(B-B), RPS MG Set A(B) EPA Breaker, Oper/Reset switch. EVALUATOR CUE Key inserted.
+    *6  Resets OV relay                                     Depresses MOTOR ON PB                              S/U
-*14 Resets 2CBS003A-A(B-B), RPS MG Set A(B) EPA Breaker. EVALUATOR CUE EPA breaker reset. *15 Place 2CBS003A-A(B-B), RPS MG Set A(B) EPA Breaker, in Operate EVALUATOR CUE Oper/Reset switch is in OPER At 1 CBS003A-A (B-B), RPS MG SET A(B) EPA BREAKER, observes POWER IN MOTOR GEN red light illuminated.
+.EVALUATOR CUE Motor On PB depressed and released 7  Verifies RPS MG set voltage at 120V AC              Observes RPS MG Set A(B) voltmeter.                S/U   I EVALUATOR CUE RPS MG set voltmeter indicates 11 OV AC
-Indicates keys available from Control Room, FUS office. At 2CBS003A-A (B-B), RPS MG SET A(B) EPA BREAKER, inserts key in OPER/RESET switch Momentarily places OPER/RESET Switch to RESET. Places OPER/RESET switch to OPER S/U S/U S/U S/U S/U TQ-106-uv
+    *8  Adjusts voltage output to 120V AC.                  Turns the VOLTAGE ADJUST                           S/U potentiometer clockwise until 120V AC EVALUATOR CUE RPS MG set voltmeter indicates 120V AC 9   Locks Voltage Adjust potentiometer.
-*10 Revision 1 Page 5of12
+* Tightens the locking set screw on the        S/U VOLTAGE ADJUST potentiometer.
-*16 Confirm overvoltage, undervoltage, and Observes OVERVOL TAGE, underfrequency lights are not illuminated UNDERVOL TAGE and UNDERFREQUENCY lights are extinguished.
+   *10   Closes MG set generator output breaker              Lifts the GENERATOR OUTPUT breaker                S/U operating paddle to the full up position.
-EVALUATOR CUE Overvoltage, Undervoltage And Underfrequency lights are out. 17 Removes key from 2CBS003A-A(B-B), RPS MG Removes key from OPER/RESET switch Set A(B) EPA Breaker, Oper/Reset switch. EVALUATOR CUE Key removed. *18 Close 2CBS003A-A(B-B), RPS MG Set A(B) EPA Lifts the 2CBS003A-A(B-B), RPS MG SET Breaker A(B) EPA BKR, operating paddle to the full up position EVALUATOR CUE EPA breaker is closed. 19 Observe EPA breaker 2CBS003A-C(B-D).lnput Observes 2CBS003A-C(B-D), RPS MG Power Available red light ILLUMINATES SET A(B) EPA BKR, POWER IN MOTOR GEN red light illuminated EVALUATOR CUE Power In Motor Gen red light is lit. *20 Inserts key in 2CBS003A-C(B-D), RPS MG Set At 2CBS003A-C(B-D), RPS MG SET A(B) A(B) EPA Breaker, Oper/Reset switch. EPA BREAKER, inserts key in OPER/RESET switch EVALUATOR CUE Key inserted.
-*21 Resets 2CBS003A-C(B-D), RPS MG Set A(B) Momentarily places OPER/RESET Switch EPA Breaker. to RESET. EVALUATOR CUE EPA breaker reset. S/U SIU S/U S/U S/U S/U 10 Revision 1 Page 6 of 12
+TQ-106-uv *10 Revision 1 Page 5of12 EVALUATOR CUE
-*22 Place 2CBS003A-C(B-D), RPS MG Set A(B) EPA Places OPER/RESET switch to OPER Breaker, in Operate Observes OVERVOLTAGE, UNDERVOL TAGE and UNDERFREQUENCY lights are extinguished.
+                                                  '
-EVALUATOR CUE Oper/Reset switch is in OPER *23 Confirm overvoltage, undervoltage, and Observes OVERVOL TAGE, underfrequency lights are not illuminated UNDERVOLTAGE and UNDERFREQUENCY lights are extinguished.
+Generator Output breaker is closed.
-EVALUATOR CUE Overvoltage, Undervoltage And Underfrequency lights are out. *24 Remove key from 2CBS003A-C(B-D), RPS MG Removes key from OPER/RESET switch Set A(B) EPA Breaker, Oper/Reset switch. EVALUATOR CUE Key removed. *25 Closes 2CBS003A-C(B-D), RPS MG Set A(B) Lifts the 2CBS003A-C(B-D), RPS MG SET EPA Breaker A(B) EPA BKR, operating paddle to the full up position EVALUATOR CUE EPA breaker is closed. 26 Verifies Generator A(B) Feed to RPS Bus A(B) Contacts Control Room to observe at white indicating light illuminated at 2C610. 2C610 GENERATOR A (B) FEED TO RPS BUS A(B) white indicating light illuminated.
+  Observes EPA breaker 2CBS003A-A(B-B).lnput            At 1CBS003A-A (B-B), RPS MG SET A(B)  S/U Power Available red light ILLUMINATES                 EPA BREAKER, observes POWER IN MOTOR GEN red light illuminated.
-EVALUATOR CUE Generator A(B) feed to RPS Bus A(B) white light is lit at 2C610. EVALUATOR CUE Record JPM stop time: S/U S/U S/U S/U S/U I TQ-106-0.:>
+EVALUATOR CUE Power In Motor Gen red light is lit.
-.0 Revision 1 Page 7of12 EVALUATOR CUE That completes the JPM. EVALUATOR NOTE Do you have ALL your JPM exam materials?
+EVALUATOR NOTE Section 2.1 is complete. Remaining steps are in Section 2.2.
-Task Cue Sheets? Procedures?
+ *12   Obtains 235, 1235, or 2235 key from Control           Indicates keys available from Control S/U Room.                                                 Room, FUS office.
-I 0 Revision 1 Page 8 of 12 REVISION
+EVALUATOR CUE You have a 2235 key.
+ *13   Inserts key in 2CBS003A-A(B-B), RPS MG Set            At 2CBS003A-A (B-B), RPS MG SET A(B)  S/U A(B) EPA Breaker, Oper/Reset switch.                  EPA BREAKER, inserts key in OPER/RESET switch EVALUATOR CUE Key inserted.
+ *14   Resets 2CBS003A-A(B-B), RPS MG Set A(B)               Momentarily places OPER/RESET Switch  S/U EPA Breaker.                                          to RESET.
+EVALUATOR CUE EPA breaker reset.
+ *15   Place 2CBS003A-A(B-B), RPS MG Set A(B) EPA            Places OPER/RESET switch to OPER      S/U Breaker, in Operate EVALUATOR CUE Oper/Reset switch is in OPER
+TQ-106-u~ 10 Revision 1 Page 6 of 12
+ *16   Confirm overvoltage, undervoltage, and               Observes OVERVOLTAGE,                      S/U underfrequency lights are not illuminated            UNDERVOLTAGE and UNDERFREQUENCY lights are extinguished.
+EVALUATOR CUE Overvoltage, Undervoltage And Underfrequency lights are out.
+   Removes key from 2CBS003A-A(B-B), RPS MG             Removes key from OPER/RESET switch         SIU Set A(B) EPA Breaker, Oper/Reset switch.
+EVALUATOR CUE Key removed.
+ *18   Close 2CBS003A-A(B-B), RPS MG Set A(B) EPA           Lifts the 2CBS003A-A(B-B), RPS MG SET      S/U Breaker                                              A(B) EPA BKR, operating paddle to the full up position EVALUATOR CUE EPA breaker is closed.
+  Observe EPA breaker 2CBS003A-C(B-D).lnput            Observes 2CBS003A-C(B-D), RPS MG           S/U Power Available red light ILLUMINATES                SET A(B) EPA BKR, POWER IN MOTOR GEN red light illuminated EVALUATOR CUE Power In Motor Gen red light is lit.
+ *20   Inserts key in 2CBS003A-C(B-D), RPS MG Set           At 2CBS003A-C(B-D), RPS MG SET A(B)        S/U A(B) EPA Breaker, Oper/Reset switch.                  EPA BREAKER, inserts key in OPER/RESET switch EVALUATOR CUE Key inserted.
+ *21   Resets 2CBS003A-C(B-D), RPS MG Set A(B)               Momentarily places OPER/RESET Switch      S/U EPA Breaker.                                          to RESET.
+EVALUATOR CUE EPA breaker reset.
+TQ-106-0.:> 1.0 Revision 1 Page 7of12
+  *22   Place 2CBS003A-C(B-D), RPS MG Set A(B) EPA             Places OPER/RESET switch to OPER              S/U Breaker, in Operate                                    Observes OVERVOLTAGE, UNDERVOLTAGE and UNDERFREQUENCY lights are extinguished.
+EVALUATOR CUE Oper/Reset switch is in OPER
+ *23   Confirm overvoltage, undervoltage, and                 Observes OVERVOLTAGE,                         S/U underfrequency lights are not illuminated              UNDERVOLTAGE and UNDERFREQUENCY lights are extinguished.
+EVALUATOR CUE Overvoltage, Undervoltage And Underfrequency lights are out.
+I
+ *24   Remove key from 2CBS003A-C(B-D), RPS MG                Removes key from OPER/RESET switch            S/U Set A(B) EPA Breaker, Oper/Reset switch.
+EVALUATOR CUE Key removed.
+ *25   Closes 2CBS003A-C(B-D), RPS MG Set A(B)                Lifts the 2CBS003A-C(B-D), RPS MG SET         S/U EPA Breaker                                            A(B) EPA BKR, operating paddle to the full up position EVALUATOR CUE EPA breaker is closed.
+  Verifies Generator A(B) Feed to RPS Bus A(B)           Contacts Control Room to observe at           S/U white indicating light illuminated at 2C610.           2C610 GENERATOR A (B) FEED TO RPS BUS A(B) white indicating light illuminated.
+EVALUATOR CUE Generator A(B) feed to RPS Bus A(B) white light is lit at 2C610.
+EVALUATOR CUE Record JPM stop time:
+TQ-106-{J~ I 0 Revision 1 Page 8 of 12 EVALUATOR CUE That completes the JPM.
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 10of12 REVISION
 ==SUMMARY==
-Revision 0 1 2 NewJPM JOB PERFORMANCE MEASURE 58.0P.26824.201 Description/Purpose of Revision Revision history unknown Changed to new TQ format Updated procedures to latest revision TQ-106-0310 Revision 1 Page 10of12 Page 11 of 12 EVALUATOR
--SCENARIO 1 TASK CONDITIONS RPS MG Set 2S23 7 A(B) has been de-energized for emergent maintenance on the normal supply EPA breakers.
+JOB PERFORMANCE MEASURE 58.0P.26824.201 Revision                      Description/Purpose of Revision 0    NewJPM 1    Revision history unknown Changed to new TQ format 2
-The 120V RPS Power Distribution Panel 2Y201A(B) is on Alternate Power. Maintenance has been completed on the RPS A(B) MG Set, and all clearance orders have been removed. All 480V AC and 125V DC power systems are in operation.
+Updated procedures to latest revision
+Page 11 of 12 EVALUATOR - SCENARIO 1 TASK CONDITIONS RPS MG Set 2S23 7A(B) has been de-energized for emergent maintenance on the normal supply EPA breakers.
+The 120V RPS Power Distribution Panel 2Y201A(B) is on Alternate Power.
+Maintenance has been completed on the RPS A(B) MG Set, and all clearance orders have been removed.
+All 480V AC and 125V DC power systems are in operation.
 CL-258-0011 is complete.
 Electrical Maintenance is available to support this evolution Initial conditions at the RPS MG set are
@@ Line 1,201: / Line 1,969: @@
 * Both EPA breakers (2CBS003A-A and 2CBS003A-C) are open
 * All four red indicating lights on the EPA breakers are extinguished INITIATING CUE Start Unit 2 RPS MG Set A(B) and close the associated EPA breakers IA W OP-258-001 Sections 2.1 and 2.2.
-Page 12of12 EXAMINEE -SCENARIO 1 TASK CONDITIONS RPS MG Set 2S237 A(B) has been de-energized for emergent maintenance on the normal supply EPA breakers.
-The 120V RPS Power Distribution Panel 2Y201A(B) is on Alternate Power. Maintenance has been completed on the RPS A(B) MG Set, and all clearance orders have been removed. All 480V AC and 125V DC power systems are in operation.
+Page 12of12 EXAMINEE - SCENARIO 1 TASK CONDITIONS RPS MG Set 2S237A(B) has been de-energized for emergent maintenance on the normal supply EPA breakers.
+The 120V RPS Power Distribution Panel 2Y201A(B) is on Alternate Power.
+Maintenance has been completed on the RPS A(B) MG Set, and all clearance orders have been removed.
+All 480V AC and 125V DC power systems are in operation.
 CL-258-0011 is complete.
 Electrical Maintenance is available to support this evolution Initial conditions at the RPS MG set are
@@ Line 1,210: / Line 1,981: @@
 * The MG voltmeter and ammeter indicate 0
 * Both EPA breakers (2CBS003A-A and 2CBS003A-C) are open
-* All four red indicating lights on the EPA breakers are extinguished INITIATING CUE Start Unit 2 RPS MG Set A(B) and close the associated EPA breakers IA W OP-258-001 Sections 2.1 and 2.2.
+* All four red indicating lights on the EPA breakers are extinguished INITIATING CUE Start Unit 2 RPS MG Set A(B) and close the associated EPA breakers IAW OP-258-001 Sections 2.1 and 2.2.
-SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET I Task Title: Place RHR In Suppression Pool Colling at Remote Shutdown Panel JPM#: 49.0P.20301.201 Revision:_"""2'----
-Date: 09/23/2016 Applicability: RO SRO Setting: Plant NUREG-1123 E/APE I Sys 219000 KIA
+SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET I
-____ K/A Importance 3.5/3.7 Alternate Path: 0 YES NO Time Critical DYES NO Validation Time (min):--=2=0
+Task Title:    Place RHR In Suppression Pool Colling at Remote Shutdown Panel JPM#: 49.0P.20301.201                                  Revision:_"""2'---- Date:                     09/23/2016 Applicability: ~ RO ~ SRO Setting:          Plant NUREG-1123 E/APE I Sys 219000                            KIA     Number"""'A~2.;....;.1..;;;..3_ _ _ _ K/A  Importance 3.5/3.7 Alternate Path:    0   YES ~ NO                   Time Critical DYES ~ NO Validation Time (min):--=2=0_ _
-__ Testing Method: D D Perform Author:: tj'a // Operations Re!: 12/L Validated:
+Testing Method: D Si~mulate D Perform Author::     tj'a ~                         //                        Date:           ql~sL1t Operations Re!:           12/L                                       Date:          c;.,lc. ~,/,,re_
-___.,..._0!:_......._Cf_........,]j&}_"----"""''--------
+Validated:  ___.,..._0!:_......._Cf_........,]j&}_"----"""''-------- Date: 1/9-~//t Approval: -~---I_               0:)_~---- Date: &deg;l*17*/~
-Approval:
+Nuclear"Trainifi9Supervisor Last, First Ml                                                                    Employee Number Exam Date:                                                          Exam Duration (Min): _ _ _ _ _ _ _ __
-Nuclear"Trainifi9Supervisor Last, First Ml Date: Date: Date: Date: q c;.,lc.
+              ---------
-Employee Number Exam Date: ---------Exam Duration (Min): ________ _ Evaluation Result: D Satisfactory D Unsatisfactory Evaluator:
+Evaluation Result:        D Satisfactory              D Unsatisfactory Evaluator: _ _ _ _ _ _ _ _ _ __
-__________
+Name                                                                    Signature Comments:
-_ Name Signature Comments:
-REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 49.0P.20301.201 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
+REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE 49.0P.20301.201 I. SAFETY CONSIDERATIONS A.      All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
-B. All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.
+B.      All applicable safety precautions shall be taken in accordance with established Talen Energy safety policies and the Safety Rule Book, for example:
-: 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
+: 1.        Whenever any electrical panel is opened for inspection during JPM performance.
-C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
+: 2.        Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
-D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
+C.      If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
-II. REFERENCES A. ON-200-009, Control Room Evacuation (Rev 37) B. OP-249-005, RHR Operation in Suppression Pol Cooling Mode (Rev 32) Ill. TASK CONDITIONS Unit 2 was operating at rated power when the Control Room was evacuated due to a hazardous atmosphere.
+D.      Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.
-Operators completed all actions in ON-200-009, Control Room Evacuation, before evacuating the Control Room. Unit 2 RSDP transfer switches have been aligned per ON-200-009.
+II. REFERENCES A.       ON-200-009, Control Room Evacuation (Rev 37)
-RPV level control is with RCIC, stable at -40". RPV pressure is being maintained with SRVs 800-1050 psig. RHR was in the normal standby alignment when the Control Room was evacuated.
+B.      OP-249-005, RHR Operation in Suppression Pol Cooling Mode (Rev 32)
+Ill. TASK CONDITIONS Unit 2 was operating at rated power when the Control Room was evacuated due to a hazardous atmosphere.
+Operators completed all actions in ON-200-009, Control Room Evacuation, before evacuating the Control Room.
+Unit 2 RSDP transfer switches have been aligned per ON-200-009.
+RPV level control is with RCIC, stable at -40". RPV pressure is being maintained with SRVs 800-1050 psig.
+RHR was in the normal standby alignment when the Control Room was evacuated.
 ESW is in operation.
 RHRSW is in operation, supplying the 2A RHR heat exchanger.
 Condensate Transfer is in operation.
-IV. INITIATING CUE Place RHR A in Suppression Pool cooling from the Unit 2 RSDP IAW OP-249-005 section 2.4. V. TASK STANDARD RHR A operating in Suppression Pool cooling per OP-249-005 at :510,000 gpm flow, with all flow through the RHR heat exchanger.
+IV. INITIATING CUE Place RHR A in Suppression Pool cooling from the Unit 2 RSDP IAW OP-249-005 section 2.4.
-INFORMATION FOR EVALUATOR
+V. TASK STANDARD RHR A operating in Suppression Pool cooling per OP-249-005 at :510,000 gpm flow, with all flow through the RHR heat exchanger.
+TQ-106-0~10 Revision 1 Page 3of10 INFORMATION FOR EVALUATOR
 * Marking a step as UNSAT requires written comments on respective step .
-Revision 1 Page 3of10
 * Critical .steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a*.
 * The time clock starts when the candidate acknowledges the initiating cue.
 * This JPM must be performed in the plant. Obtain Shift Manager authorization to proceed. This JPM requires access to Unit 2 RB RSDP.
-* Have a copy of OP-249-005 section 2.4 and ON-200-009 . EVALUATOR CUE Record JPM start time: Step Action Standard Eva I Comments 1 Identifies governing procedure and obtain Obtains controlled copy of OP-249-005 S/U controlled copy. section 2.4. 2 Review prerequisites and precautions.
+* Have a copy of OP-249-005 section 2.4 and ON-200-009 .
-Reviews prerequisites and precautions.
+EVALUATOR CUE Record JPM start time:
-S/U 3 Ensure ESW in operation.
+Step   Action                                                 Standard                                           Eva I  Comments 1   Identifies governing procedure and obtain              Obtains controlled copy of OP-249-005 S/U controlled copy.                                       section 2.4.
-Observes ESW in operation is specified in S/U Task Conditions.
+  Review prerequisites and precautions.                  Reviews prerequisites and precautions.             S/U 3   Ensure ESW in operation.                               Observes ESW in operation is specified in S/U Task Conditions.
-Place RHRSW in operation.
+  Place RHRSW in operation.                              Observes RHRSW in operation to the S/U 2A RHR HX is specified in Task Conditions.
-Observes RHRSW in operation to the S/U 2A RHR HX is specified in Task Conditions.
+   *5   Verifies that RHR Pump 1A not running.                 Contacts Unit 1 RSDP to determine RHR S/U Pump 1A status.
-*5 Verifies that RHR Pump 1A not running. Contacts Unit 1 RSDP to determine RHR S/U Pump 1A status. EVALUATOR CUE S/U RHR Pump 1A is in standby. *6 Ensure HV-251-F048A, Hx A Shell Side Byps, is Observes HV-251-F048A, HX A SHELL S/U open. SIDE BYPS, indicates full open. EVALUATOR CUE S/U HV-251-F048A indicates red light ON, amber light OFF. *7 Open HV-251-F028A, Supp Chmbr Spry Test Places HS HV-251-F028A, SUPP CHMBR Shutoff. SPRY TEST SHUTOFF, to the OPEN S/U position EVALUATOR CUE HV-251-F028A indicates red light ON, amber light OFF. *8 Ensure HV-251-FOO?A, RHR PP A/C Min Flow, is Observes HV-251-FOO?A, RHR PP A/C open. MIN FLOW, indicates full open. EVALUATOR CUE HV-251-FOO?A indicates red light ON, amber light OFF. 9 Determines no potential for RHR discharge loop Observes Condensate Transfer in operation voiding. is specified in Task Conditions.
+EVALUATOR CUE S/U RHR Pump 1A is in standby.
-EVALUATOR CUE RHR A was in the normal standby lineup when the Control Room was evacuated.
+   *6   Ensure HV-251-F048A, Hx A Shell Side Byps, is          Observes HV-251-F048A, HX A SHELL S/U open.                                                  SIDE BYPS, indicates full open.
-*10 Ensure RHR A filled and vented. Directs NPO to vent RHR A using 251821, RHR DIV 1 DRYWELL SPRAY VENT VALVE, per OP-249-001 Step 2.4.10. EVALUATOR CUE ' RHR A fill and vent complete.
+EVALUATOR CUE S/U HV-251-F048A indicates red light ON, amber light OFF.
-*11 Start RHR Pump A, 2P202A Places HS RHR PUMP A 2P202A to the ST ART position and observes breaker closed. EVALUATOR CUE RHR Pump A indicates red light ON, amber light OFF. *12 Throttle Open HV-251-F048A HX A SHELL SIDE Performs the following:
+   *7   Open HV-251-F028A, Supp Chmbr Spry Test                Places HS HV-251-F028A, SUPP CHMBR Shutoff.                                               SPRY TEST SHUTOFF, to the OPEN                     S/U position
+TQ-106-u;) 10 Revision 1 Page 4 of 10 EVALUATOR CUE SIU HV-251-F028A indicates red light ON, amber light OFF.
+  *8  Ensure HV-251-FOO?A, RHR PP A/C Min Flow, is        Observes HV-251-FOO?A, RHR PP A/C S/U open.                                               MIN FLOW, indicates full open.
+EVALUATOR CUE S/U HV-251-FOO?A indicates red light ON, amber light OFF.
+Determines no potential for RHR discharge loop      Observes Condensate Transfer in operation S/U voiding.                                            is specified in Task Conditions.
+EVALUATOR CUE S/U RHR A was in the normal standby lineup when the Control Room was evacuated.
+ *10  Ensure RHR A filled and vented.                     Directs NPO to vent RHR A using 251821, RHR DIV 1 DRYWELL SPRAY VENT                S/U VALVE, per OP-249-001 Step 2.4.10.
+EVALUATOR CUE                                               '
+S/U RHR A fill and vent complete.
+ *11  Start RHR Pump A, 2P202A                            Places HS RHR PUMP A 2P202A to the START position and observes breaker         S/U closed.
+EVALUATOR CUE S/U RHR Pump A indicates red light ON, amber light OFF.
+ *12  Throttle Open HV-251- F048A HX A SHELL SIDE         Performs the following:
 BYPS to establish a system flow between 3,000
-* Places HS HV-251-F048A HX A gpm and 3,500 gpm as indicated on RHR SYSTEM SHELL SIDE BYPS, to the OPEN FLOW INDICATOR Fl-25105 position in 500 gpm increments followed by a 20 second pause.
+* Places HS HV-251- F048A HX A gpm and 3,500 gpm as indicated on RHR SYSTEM            SHELL SIDE BYPS, to the OPEN FLOW INDICATOR Fl-25105                                 position in 500 gpm increments followed by a 20 second pause.                   S/U
 * Observes Fl-25105, RHR SYSTEM FLOW, indicates 6000 gpm
-* Releases HS HV-251-F024A, TEST LINE CTL SIU S/U S/U S/U S/U S/U S/U S/U S/U S/U TQ-106-u;)
+                                                                                                            -
-Revision 1 Page 4 of 10 -
+* Releases HS HV-251-F024A, TEST LINE CTL
-EVALUATOR CUE HV-251-F048A indicates red light ON, amber light ON. Fl-25105 indicates 3500 gpm. *13 Throttle Open HV-251-F048A HX A SHELL SIDE BYPS to establish RHR loop flow between 11,000 gpm and 12,000 gpm as indicated on RHR SYSTEM FLOW INDICATOR Fl-25105 *14 Throttle Closed HV-251-F024A TEST LINE CTL to maintain ::::; 10,000 gpm as indicated on RHR SYSTEM FLOW INDICATOR Fl-25105 EVALUATOR CUE HV-251-F024A indicates red light OFF, amber light ON. *15 Fully Open HV-251-F048A HX A SHELL SIDE BYPS EVALUATOR CUE HV-251-F048A indicates red light ON, amber light OFF. Fl-25105 indicates 9700 gpm. *16 Open HV-251-F047A RHR HX A SHELL SIDE INLET Performs the following:
-* Places HS HV-251-F048A HX A . SHELL SIDE BYPS, to the OPEN position and establishes 11, 000 to 12, 000 gpm as indicated on RHR SYSTEM FLOW INDICATOR Fl-25105
+TQ-106-u~10 Revision 1 Page 5 of 10 EVALUATOR CUE HV-251-F048A indicates red light ON, amber light ON.                                                S/U Fl-25105 indicates 3500 gpm.
+ *13  Throttle Open HV-251- F048A HX A SHELL SIDE     Performs the following:
+BYPS to establish RHR loop flow between 11,000
+* Places HS HV-251- F048A HX A .
+gpm and 12,000 gpm as indicated on RHR           SHELL SIDE BYPS, to the OPEN SYSTEM FLOW INDICATOR Fl-25105                   position and establishes 11, 000 to 12, 000 gpm as indicated on RHR SYSTEM SIU FLOW INDICATOR Fl-25105
 * Observes Fl-25105, RHR SYSTEM FLOW, indicates 11,000 gpm
 * Releases HS HV-251-F024A, TEST LINE CTL
-* Places HS HV-251-F024A TEST LINE CTL, to the CLOSED position
+  *14  Throttle Closed HV-251-F024A TEST LINE CTL to
-* Maintains
+* Places HS HV-251-F024A TEST LINE maintain ::::; 10,000 gpm as indicated on RHR     CTL, to the CLOSED position SYSTEM FLOW INDICATOR Fl-25105
-::::; 10,000 gpm as indicated on RHR SYSTEM FLOW INDICATOR Fl-25105 Performs the following:
+* Maintains ::::; 10,000 gpm as indicated on S/U RHR SYSTEM FLOW INDICATOR Fl-25105 EVALUATOR CUE S/U HV-251-F024A indicates red light OFF, amber light ON.
-* Places HS HV-251-F048A HX A SHELL SIDE BYPS, to the OPEN position Performs the following:
+  *15  Fully Open HV-251-F048A HX A SHELL SIDE        Performs the following:
-* Places HS HV-251-F047A RHR HX A SHELL SIDE INLET, to the OPEN position S/U SIU S/U S/U S/U S/U S/U Revision 1 Page 5 of 10 EVALUATOR CUE HV-251-F047A indicates red light ON, amber light OFF. EVALUATOR CUE That completes the JPM. EVALUATOR CUE Record JPM stop time: EVALUATOR NOTE Do you have ALL your JPM exam materials?
+BYPS
-Task Cue Sheets? Procedures?
+* Places HS HV-251- F048A HX A                S/U SHELL SIDE BYPS, to the OPEN position EVALUATOR CUE HV-251-F048A indicates red light ON, amber light OFF.                                               S/U Fl-25105 indicates 9700 gpm.
-Revision 1 Page 6of10 REVISION
+  *16  Open HV-251-F047A RHR HX A SHELL SIDE          Performs the following:
+INLET
+* Places HS HV-251- F047A RHR HX A S/U SHELL SIDE INLET, to the OPEN position
+TQ-106-CJ~iO Revision 1 Page 6of10 EVALUATOR CUE HV-251-F047A indicates red light ON, amber light OFF.
+EVALUATOR CUE That completes the JPM.
+EVALUATOR CUE Record JPM stop time:
+EVALUATOR NOTE Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
+TQ-106-0310 Revision 1 Page 8 of 10 REVISION
 ==SUMMARY==
-Revision 0 1 2 NewJPM JOB PERFORMANCE MEASURE 49.0P.20301.201 Description/Purpose of Revision Changed to new TQ format Updated to latest procedure revisions Updated to latest procedure revisions TQ-106-0310 Revision 1 Page 8 of 10 Page 9of10 EVALUATOR COPY: TASK CONDITIONS Unit 2 was operating at rated power when the Control Room was evacuated due to a hazardous atmosphere.
-Operators completed all actions in ON-200-009, CONTROL ROOM EVACUATION, before evacuating the Control Room. Unit 2 RSDP transfer switches have been aligned per ON-200-009.
+JOB PERFORMANCE MEASURE 49.0P.20301.201 Revision                       Description/Purpose of Revision 0    NewJPM Changed to new TQ format 1
-RPV level control is with RCIC, stable at-40". RPV pressure is being maintained with SRVs 800-1050 psig. ' RHR was in the normal standby alignment when the Control Room was evacuated.
+Updated to latest procedure revisions 2    Updated to latest procedure revisions
+Page 9of10 EVALUATOR COPY:
+TASK CONDITIONS Unit 2 was operating at rated power when the Control Room was evacuated due to a hazardous atmosphere.
+Operators completed all actions in ON-200-009, CONTROL ROOM EVACUATION, before evacuating the Control Room.
+Unit 2 RSDP transfer switches have been aligned per ON-200-009.
+RPV level control is with RCIC, stable at-40". RPV pressure is being maintained with SRVs 800-1050 psig. '
+RHR was in the normal standby alignment when the Control Room was evacuated.
 ESW is in operation.
 RHRSW is in operation, supplying the 2A RHR heat exchanger.
 Condensate Transfer is in operation.
 INITIATING CUE Place RHR A in Suppression Pool cooling from the Unit 2 RSDP IAW OP-249-005 section 2.4.
-Page 10of10 EXAMINEE COPY: TASK CONDITIONS Unit 2 was operating at rated power when the Control Room was evacuated due to a hazardous atmosphere.
-' Operators completed all actions in ON-200-009, CONTROL ROOM EVACUATION, before evacuating the Control Room. Unit 2 RSDP transfer switches have been aligned per ON-200-009.
+Page 10of10 EXAMINEE COPY:
-RPV level control is with RCIC, stable at-40". RPV pressure is being maintained with SRVs 800-1050 psig. RHR was in the normal standby alignment when the Control Room was evacuated.
+TASK CONDITIONS Unit 2 was operating at rated power when the Control Room was evacuated due to a hazardous atmosphere.                    '
+Operators completed all actions in ON-200-009, CONTROL ROOM EVACUATION, before evacuating the Control Room.
+Unit 2 RSDP transfer switches have been aligned per ON-200-009.
+RPV level control is with RCIC, stable at-40". RPV pressure is being maintained with SRVs 800-1050 psig.
+RHR was in the normal standby alignment when the Control Room was evacuated.
 ESW is in operation.
 RHRSW is in operation, supplying the 2A RHR heat exchanger.
 Condensate Transfer is in operation.
 INITIATING CUE Place RHR A in Suppression Pool cooling from the Unit 2 RSDP IAW OP-249-005 section 2.4.
-SUSQUEHANNA NUCLEAR, LLC OPERATIONS TRAINING PROGRAM SCENARIO EXAMINATION GUIDE CONTROL ROD PATTERN ADJUSTMENT/
-RFP LUBE OIL PUMP SWAP/ RFP VIBRATION/
+SUSQUEHANNA NUCLEAR, LLC OPERATIONS TRAINING PROGRAM SCENARIO EXAMINATION GUIDE CONTROL ROD PATTERN ADJUSTMENT/ RFP LUBE OIL PUMP SWAP/ RFP VIBRATION/
-LOSS OF RBCCW/
+LOSS OF RBCCW/ HYDRAULIC-BLOCK ATWS SCN# LOC28-NRC-01 Revision 1 04/14/2016 Examination Material
-BLOCK ATWS SCN# LOC28-NRC-01 Revision 1 04/14/2016 Examination Material LOC28-NRC-01 Lesson Information Title Control Rod Pattern Adjustment/
-RFP lube oil pump swap/ RFP Vibration/
+LOC28-NRC-01 Lesson Information Title                 Control Rod Pattern Adjustment/ RFP lube oil pump swap/ RFP Vibration/ Loss of RBCCW/ Hydraulic-Block A TWS Vision ID                                                        Accredited     *YES           o  NO Training ID           LOC28-NRC-01                    Revision 11                Date  I 04/14/2016 Prerequisites Teaching Time         65 Minutes Approval CBT Approval 1               N/A                                              Date      N/A Preparer                                                                     Date Review (lnstructor/SME)                                                      Date Nuclear Engineering 1       N/A                                              Date      N/A Training Supervision                                                          Date Line Management                                                              Date 1
-Loss of RBCCW/ Hydraulic-Block A TWS Vision ID Accredited
+If required, otherwise N/A This simulator scenario has been reviewed and satisfies management expectations for inclusion of OE, Department Fundamentals and HuP, error-reduction techniques and safety standards. Specific applications and/or opportunities for reinforcement of management expectations are noted in the scenario guide or Attachment(s) where applicable.
-*YES o NO Training ID LOC28-NRC-01 Revision 11 Date I 04/14/2016 Prerequisites Teaching Time 65 Minutes Approval CBT Approval 1 N/A Date N/A Preparer Date Review (lnstructor/SME)
+Copyrighted by Nuclear Training Group, SUSQUEHANNA NUCLEAR, LLC, 2016. All rights reserved, no part of this training material may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, recording or otherwise, without the prior permission of the Nuclear Training Group.
-Date Nuclear Engineering 1 N/A Date N/A Training Supervision Date Line Management Date 1 If required, otherwise N/A This simulator scenario has been reviewed and satisfies management expectations for inclusion of OE, Department Fundamentals and HuP, error-reduction techniques and safety standards.
+LOC28-NRC-01 Rev 1                            Examination Material                              04/14/2016
-Specific applications and/or opportunities for reinforcement of management expectations are noted in the scenario guide or Attachment(s) where applicable.
+* 2
-Copyrighted by Nuclear Training Group, SUSQUEHANNA NUCLEAR, LLC, 2016. All rights reserved, no part of this training material may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, recording or otherwise, without the prior permission of the Nuclear Training Group. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016
-* 2 LOC28-NRC-01 Revision History Revision Date Comments 0 03/17/2014 New exam Revised to new template format. Changed event number 1 to the lube oil pump transfer.
+LOC28-NRC-01 Revision History Revision            Date                                Comments 0            03/17/2014                             New exam Revised to new template format.
-Removed some RWCU malfunctions.
+Changed event number 1 to the lube oil pump transfer.
-Clarified the event going 1 04/14/2016 into the scram. Changed the reports to match procedures and actual guidance.
+Removed some RWCU malfunctions. Clarified the event going 1            04/14/2016 into the scram. Changed the reports to match procedures and actual guidance. Changed the scram from high RRP temperature to a RBCCW rupture. Event 3 is just a setup for Event 4 and actions are removed due to the fast nature of the RFP trip.
-Changed the scram from high RRP temperature to a RBCCW rupture. Event 3 is just a setup for Event 4 and actions are removed due to the fast nature of the RFP trip. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
+LOC28-NRC-01 Rev 1                  Examination Material                            04/14/2016. 3
-LOC28-NRC-01 Table of Contents Scenario Overview ................................................................................................................................
-Objectives
+LOC28-NRC-01 Table of Contents Scenario Overview................................................................................................................................5 Objectives .............................................................................................................................................7 A. Terminal Objective ................................................................................................................7 B. Generic Performance Objectives ...........................................................................................7 C. Simulator Performance Objectives ........................................................................................8 D. Task List. ............................................................................................................................. 1O Scenario Attributes .............................................................................................................................12 A. Critical Tasks ....................................................................................................................... 12 B. Scenario Malfunctions ......................................................................................................... 13 C. Abnormal Events and Major Transients ............................................................................... 14 D. EOP and EOP Contingencies Used .................................................................................... 14 E. Technical Specifications ...................................................................................................... 15 References ..........................................................................................................................................16 Setup Instructions ..............................................................................................................................18 A. Required Materials .............................................................................................................. 18 B. Simulator Initialization ......................................................................................................... 18 C. Simulator Preparation .......................................................................................................... 19 D. Document Training and Performance Feedback ................................................................. 19 E. Scenario Execution ............................................................................................................. 19 F. Simulator Files .................................................................................................................... 19 Event 1 - RFP 'A' Main Lube Oil Pump Swap .................................................................................... 22 Event 2 - Control Rod Pattern Adjustment .......................................................................................23 Event 3 - '8' RFP vibration .................................................................................................................25 Event 4 - 'B' RFP trip ..........................................................................................................................25 Event 5 - RBCCW TCV fails ................................................................................................................28 Event 6 - Complete loss of RBCCW ..................................................................................................30 Event 7 - Hydraulic block ATWS .......................................................................................................32 Event 8 - SLC pump trips ...................................................................................................................32 Event 9 - Wide Range level instrument fails .....................................................................................32 Event 1O - In-service RFP trips ..........................................................................................................37 LOC28-NRC-01 Rev 1                                           Examination Material                                                        04/14/2016
-.............................................................................................................................................
+* 4
-A. Terminal Objective
-................................................................................................................
+LOC28-NRC-01 Scenario Overview The scenario begins with Unit 1 at 95 percent power, 500 days into the operating cycle. Preparations are set for performing a control rod pattern adjustment. HPCI is in day 2 of a planned 4-day system outage window. Diesel Generator E is substituted for DG A for a system outage window. The RFP lube oil conditioner was swapped from the RFP A reservoir to the B reservoir last shift. A severe thunderstorm watch is in effect for Luzerne County for the next 12 hours.
-B. Generic Performance Objectives
+The first task for the crew is to test the RFP A main lube oil pumps, and perform a pump swap in the process, per OP-145-003. NPOs will report the RFP lube oil conditioner is in-service on the RFP B reservoir once the lube oil pump swap is complete.
-...........................................................................................
+When the RFP main lube oil Pump swap is complete the crew will withdraw control rods in accordance with the Reactivity Maneuver Request provided by Reactor Engineering, then proceed to raise power with recirc flow. The pattern adjustment will raise reactor power approximately 3 percent.
-C. Simulator Performance Objectives
+When the reactivity maneuver has been completed, 'B' RFP will experience a rising vibration trend.
-........................................................................................
+Vibration will quickly rise to the alarm setpoint and then to the RFP trip setpoint. The crew is not expected to be able to respond to vibration trip. The crew will respond per off-normal procedures to the RFP trip and recirc LIM2 runback. Control rod insertion may be performed due to margin to the MELLA rod-line. The Recirc loop 'A' drive flow inputs to APRM flow channels 'C' and 'D' (APRMs 2 and 3) will drift high during the runback, resulting in a RBM flow compare control rod withdrawal block. The inoperable flow-biased scram and rod-block functions of the two APRMs will require entry into TS 3.3.1.1 and TRO 3.1.3.
-D. Task List. .............................................................................................................................
+When the crew has lowered power below the MELLA rod-line, the RBCCW TCV will malfunction resulting in a loss of cooling to RBCCW. RBCCW temperature will quickly rise. The RBCCW TCV bypass valve will be stuck closed. The crew will be required to place RBCCW on ESW which bypasses the RBCCW TCVs and will restore cooling to RBCCW loads. Entry into TS 3.7.2 will be required for the loop of ESW made inoperable when aligned to the RBCCW HX.
-O Scenario Attributes
+Once the crew has placed ESW in-service to RBCCW the return valve HV11024A2 will fail closed after approximately 5 minutes, due to its solenoid failing, resulting in a total loss of RBCCW cooling. Recirc Pump A lower motor bearing temperature will rise rapidly on the second loss of cooling, requiring a reactor scram and tripping of the Recirc Pump. If the reactor is not scrammed before the recirc pump is tripped, Region 1 of the power-flow map will be entered and the reactor will automatically scram on OPRMs.
-.............................................................................................................................
+The reactor scram will result in a hydraulic-block A TWS. The crew will trip both Recirc Pumps and reduce level to the A TWS band to lower power. The crew will perform the ES to bypass RPS trips, allowing the scram to be reset to drain the SDV and scram again. The crew will be able to insert control rods using RMCS. The first SLC pump started will trip shortly after starting, requiring the second pump to be started. As reactor level is lowered one channel of Wide Range reactor level will fail, requiring the crew to diagnose the failure and raise FW flow to maintain reactor level within the ATWS band.
-A. Critical Tasks .......................................................................................................................
+The in-service RFP will trip after the scram is reset. RCIC can be used to maintain reactor level as the standby RFP is placed in service.
-B. Scenario Malfunctions
+The first attempt at draining the SDV and re-inserting a scram will result in limited control rod motion.
-.........................................................................................................
+The crew should reset the scram and allow the SDV to drain again while continuing control rod insertion.
-C. Abnormal Events and Major Transients
-...............................................................................
-D. EOP and EOP Contingencies Used ....................................................................................
-E. Technical Specifications
-......................................................................................................
-References
-..........................................................................................................................................
-Setup Instructions
-..............................................................................................................................
-A. Required Materials
-..............................................................................................................
-B. Simulator Initialization
-.........................................................................................................
-C. Simulator Preparation
-..........................................................................................................
-D. Document Training and Performance Feedback .................................................................
-E. Scenario Execution
-.............................................................................................................
-F. Simulator Files ....................................................................................................................
-Event 1 -RFP 'A' Main Lube Oil Pump Swap ....................................................................................
-Event 2 -Control Rod Pattern Adjustment
-.......................................................................................
-Event 3 -'8' RFP vibration
-.................................................................................................................
-Event 4 -'B' RFP trip ..........................................................................................................................
-Event 5 -RBCCW TCV fails ................................................................................................................
-Event 6 -Complete loss of RBCCW ..................................................................................................
-Event 7 -Hydraulic block ATWS .......................................................................................................
-Event 8 -SLC pump trips ...................................................................................................................
-Event 9 -Wide Range level instrument fails .....................................................................................
-Event 1 O -In-service RFP trips ..........................................................................................................
-LOC28-NRC-01 Rev 1 Examination Material 04/14/2016
-* 4 LOC28-NRC-01 Scenario Overview The scenario begins with Unit 1 at 95 percent power, 500 days into the operating cycle. Preparations are set for performing a control rod pattern adjustment.
-HPCI is in day 2 of a planned 4-day system outage window. Diesel Generator E is substituted for DG A for a system outage window. The RFP lube oil conditioner was swapped from the RFP A reservoir to the B reservoir last shift. A severe thunderstorm watch is in effect for Luzerne County for the next 12 hours. The first task for the crew is to test the RFP A main lube oil pumps, and perform a pump swap in the process, per OP-145-003.
-NPOs will report the RFP lube oil conditioner is in-service on the RFP B reservoir once the lube oil pump swap is complete.
-When the RFP main lube oil Pump swap is complete the crew will withdraw control rods in accordance with the Reactivity Maneuver Request provided by Reactor Engineering, then proceed to raise power with recirc flow. The pattern adjustment will raise reactor power approximately 3 percent. When the reactivity maneuver has been completed, 'B' RFP will experience a rising vibration trend. Vibration will quickly rise to the alarm setpoint and then to the RFP trip setpoint.
-The crew is not expected to be able to respond to vibration trip. The crew will respond per off-normal procedures to the RFP trip and recirc LIM2 runback. Control rod insertion may be performed due to margin to the MELLA rod-line.
-The Recirc loop 'A' drive flow inputs to APRM flow channels 'C' and 'D' (APRMs 2 and 3) will drift high during the runback, resulting in a RBM flow compare control rod withdrawal block. The inoperable flow-biased scram and rod-block functions of the two APRMs will require entry into TS 3.3.1.1 and TRO 3.1.3. When the crew has lowered power below the MELLA rod-line, the RBCCW TCV will malfunction resulting in a loss of cooling to RBCCW. RBCCW temperature will quickly rise. The RBCCW TCV bypass valve will be stuck closed. The crew will be required to place RBCCW on ESW which bypasses the RBCCW TCVs and will restore cooling to RBCCW loads. Entry into TS 3.7.2 will be required for the loop of ESW made inoperable when aligned to the RBCCW HX. Once the crew has placed ESW in-service to RBCCW the return valve HV11024A2 will fail closed after approximately 5 minutes, due to its solenoid failing, resulting in a total loss of RBCCW cooling. Recirc Pump A lower motor bearing temperature will rise rapidly on the second loss of cooling, requiring a reactor scram and tripping of the Recirc Pump. If the reactor is not scrammed before the recirc pump is tripped, Region 1 of the power-flow map will be entered and the reactor will automatically scram on OPRMs. The reactor scram will result in a hydraulic-block A TWS. The crew will trip both Recirc Pumps and reduce level to the A TWS band to lower power. The crew will perform the ES to bypass RPS trips, allowing the scram to be reset to drain the SDV and scram again. The crew will be able to insert control rods using RMCS. The first SLC pump started will trip shortly after starting, requiring the second pump to be started. As reactor level is lowered one channel of Wide Range reactor level will fail, requiring the crew to diagnose the failure and raise FW flow to maintain reactor level within the A TWS band. The in-service RFP will trip after the scram is reset. RCIC can be used to maintain reactor level as the standby RFP is placed in service. The first attempt at draining the SDV and re-inserting a scram will result in limited control rod motion. The crew should reset the scram and allow the SDV to drain again while continuing control rod insertion.
 The scenario may be terminated when RPV water level is stable in the ATWS band, the 'A' RFP has tripped, and the Scram has been reset twice OR at the lead evaluator's discretion.
-LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
+LOC28-NRC-01 Rev 1                             Examination Material                               04/14/2016. 5
-LOC28-NRC-01 Objectives Mastery of the training content shall be demonstrated by individual and/or crew performance evaluation as specified in this training material and the applicable training program description, in accordance with training procedures.
+LOC28-NRC-01 Objectives Mastery of the training content shall be demonstrated by individual and/or crew performance evaluation as specified in this training material and the applicable training program description, in accordance with training procedures.
 A. Terminal Objective Perform all system operations required to maintain the plant operating safely, or place the plant in a safe condition if a plant shutdown is required During the specified mode of plant I system operation Without error and in accordance with site procedures and management expectations
 : 8. Generic Performance Objectives
-: 1. For all activities, exhibit use of the Human Performance Tools, demonstrating the ability to: Use HU tools to effectively control the plant during normal, abnormal, and emergency conditions Use of HU tools will be observable per the standards in HU-AD-003 (SRO) Take every opportunity to coach the team when HU standards are not being met and provide feedback to the team when the HU standards are being met 2. For all activities, exhibit proper use of procedures by: Applying the correct procedure to operate equipment and respond to abnormalities Ensuring procedures are detailed enough to allow precise control of plant evolutions.
+: 1. For all activities, exhibit use of the Human Performance Tools, demonstrating the ability to:
-Demonstrating the ability to: Apply the correct procedure to the situation Use place keeping for accurate implementation Identify any and all areas for procedure improvement Take ownership of and complete the improvement, whenever an area for procedure improvement is identified
+Use HU tools to effectively control the plant during normal, abnormal, and emergency conditions Use of HU tools will be observable per the standards in HU-AD-003 (SRO) Take every opportunity to coach the team when HU standards are not being met and provide feedback to the team when the HU standards are being met
-: 3. Base actions and decisions with a bias toward conservative, safe operation of the plant, demonstrating the ability to: Assure all plant evolutions and work are assessed for Radiological Safety, Industrial Safety, Nuclear Safety, Environmental Safety, or Corporate Safety Once a risk is determined, take appropriate actions to mitigate or minimize risk Request assistance for any activity which requires additional planning, special precautions, and management oversight to adequately manage the risks (SRO) Champion activities that are biased conservatively LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
+: 2. For all activities, exhibit proper use of procedures by:
-LOC28-NRC-01
+Applying the correct procedure to operate equipment and respond to abnormalities Ensuring procedures are detailed enough to allow precise control of plant evolutions.
-: 4. Demonstrate complete understanding of plant design and system interrelationships, demonstrating the ability to: Work effectively as a team to interpret plant indications and determine an effective response Understand the bases for, and the plant response to, actions being taken 5. Maintain continuous awareness of critical parameters, demonstrating the ability to: Validate parameters by observing multiple independent indications Relay parameter values with value, units, and trend; and include action being taken for an abnormal value or trend Notify supervision of any change to critical parameters (SRO) Assure critical parameters for operational conditions are understood by the team 6. Operate plant systems and equipment within design and operational limits, maintaining relevant parameters within assigned operating bands, demonstrating the ability to: Anticipate the impact of component operation prior to its operation, and then verify that the expected effects occur during and following the operation Take manual actions (in accordance with procedure direction) when automatic actions do not occur Take prompt action to adjust system operating controls before assigned operating bands are exceeded Make reactivity and mode changes as directed by detailed operating procedures and approved reactivity plans C. Simulator Performance Objectives
+Demonstrating the ability to:
-: 1. Operational Actions and Annunciator Response Correctly identify plant annunciators and indications and perform appropriate remedial actions 2. System Operation, Controls and Instrumentation Accurately identify plant instrumentation and correctly interpret instrument readings to respond to normal, abnormal, and emergency conditions
+Apply the correct procedure to the situation Use place keeping for accurate implementation Identify any and all areas for procedure improvement Take ownership of and complete the improvement, whenever an area for procedure improvement is identified
+: 3. Base actions and decisions with a bias toward conservative, safe operation of the plant, demonstrating the ability to:
+Assure all plant evolutions and work are assessed for Radiological Safety, Industrial Safety, Nuclear Safety, Environmental Safety, or Corporate Safety Once a risk is determined, take appropriate actions to mitigate or minimize risk Request assistance for any activity which requires additional planning, special precautions, and management oversight to adequately manage the risks (SRO) Champion activities that are biased conservatively LOC28-NRC-01 Rev 1                               Examination Material                            04/14/2016. 6
+LOC28-NRC-01
+: 4. Demonstrate complete understanding of plant design and system interrelationships, demonstrating the ability to:
+Work effectively as a team to interpret plant indications and determine an effective response Understand the bases for, and the plant response to, actions being taken
+: 5. Maintain continuous awareness of critical parameters, demonstrating the ability to:
+Validate parameters by observing multiple independent indications Relay parameter values with value, units, and trend; and include action being taken for an abnormal value or trend Notify supervision of any change to critical parameters (SRO) Assure critical parameters for operational conditions are understood by the team
+: 6. Operate plant systems and equipment within design and operational limits, maintaining relevant parameters within assigned operating bands, demonstrating the ability to:
+Anticipate the impact of component operation prior to its operation, and then verify that the expected effects occur during and following the operation Take manual actions (in accordance with procedure direction) when automatic actions do not occur Take prompt action to adjust system operating controls before assigned operating bands are exceeded Make reactivity and mode changes as directed by detailed operating procedures and approved reactivity plans C. Simulator Performance Objectives
+: 1. Operational Actions and Annunciator Response Correctly identify plant annunciators and indications and perform appropriate remedial actions
+: 2. System Operation, Controls and Instrumentation Accurately identify plant instrumentation and correctly interpret instrument readings to respond to normal, abnormal, and emergency conditions
 : 3. Facility Design and Operating Characteristics Demonstrate the following:
 * An understanding of facility operating characteristics
-* The ability to safely control the operating characteristics of the facility within prescribed operating boundaries LOC28-NRC-01 Rev 1 Examination Material 04/14/2016
+* The ability to safely control the operating characteristics of the facility within prescribed operating boundaries LOC28-NRC-01 Rev 1                            Examination Material                                  04/14/2016
-* 7 LOC28-NRC-01
+* 7
-: 4. System Loss and Component Level Malfunctions Perform system control manipulations to obtain desired operating results and demonstrate the ability to correctly respond to malfunction/loss of components and the impact of the malfunction/loss on interfacing plant systems 5. Heat Removal Component Operation Safely operate the plant's heat removal components and demonstrate knowledge of the relationship between the heat removal systems and the operation of facility to prevent exceeding System, Structure, or Component (SSC) design limits which include:
+LOC28-NRC-01
+: 4. System Loss and Component Level Malfunctions Perform system control manipulations to obtain desired operating results and demonstrate the ability to correctly respond to malfunction/loss of components and the impact of the malfunction/loss on interfacing plant systems
+: 5. Heat Removal Component Operation Safely operate the plant's heat removal components and demonstrate knowledge of the relationship between the heat removal systems and the operation of facility to prevent exceeding System, Structure, or Component (SSC) design limits which include:
 * Primary coolant systems
 * Emergency coolant systems
-* Decay heat removal systems 6. Auxiliary and Emergency Component Operations Safely operate the plant's auxiliary and emergency components I systems to include the controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment to control release of radioactivity within regulatory limits 7. Reactivity Management Demonstrate knowledge of how reactivity is affected by plant operation and ability to respond to the change in reactivity to protect the safety and integrity of the reactor core 8. Technical Specifications During plant operation with the plant or system in a condition requiring Technical Specification action Identify the deviation and any required actions I notifications
+* Decay heat removal systems
+: 6. Auxiliary and Emergency Component Operations Safely operate the plant's auxiliary and emergency components I systems to include the controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment to control release of radioactivity within regulatory limits
+: 7. Reactivity Management Demonstrate knowledge of how reactivity is affected by plant operation and ability to respond to the change in reactivity to protect the safety and integrity of the reactor core
+: 8. Technical Specifications During plant operation with the plant or system in a condition requiring Technical Specification action Identify the deviation and any required actions I notifications
 : 9. Emergency Plan (if required)
 During plant operation in an emergency condition Recognize conditions covered by the Emergency Plan (SRO) Demonstrate the ability to:
 * Identify and Implement the appropriate Emergency Action Level
-* Use the applicable bases to support an Event Classification on the specified Emergency Action Level 10. Control Room Duties Demonstrate the knowledge and ability to assume the appropriate responsibilities (for the assigned position) associated with the safe operation of the facility LOC28-NRC-01 Rev 1 Examination Material 04/14/2016
+* Use the applicable bases to support an Event Classification on the specified Emergency Action Level
-* 8 LOC28-NRC-01
+: 10. Control Room Duties Demonstrate the knowledge and ability to assume the appropriate responsibilities (for the assigned position) associated with the safe operation of the facility LOC28-NRC-01 Rev 1                             Examination Material                               04/14/2016
-: 11. Control Room Team Work Demonstrate the ability to function within the Control Room team to comply with station procedures and limits of facility license and respond to plant events using appropriate human performance tools to support safe operation of the facility D. Task List Task Title ID Licensed Operator Apply Technical Specification (TS) And Technical Requirements Manual (TRM) Requirements S-C00-00-1185 Implement Reactivity Manipulations Standards and Communication Requirements S-C00-00-2784 Implement Appropriate Portions Of Operations Standards S-C00-00-1081 For System and Equipment Operation Implement Operations Standards For Error And Event S-ADM-00-1091 Prevention Implement Standards for Shift Operations S-C00-00-2780 Implement Appropriate Portions of Conduct of Operations S-C00-00-1015 Implement Appropriate Portions of Secondary Containment Integrity Control S-C00-00-1020 Implement EOP Cautions S-C00-00-2566 Implement Operations Directives S-C00-00-3130 Ensure Plant Operates IAW the Operating License, Technical Specifications (TS}, and Technical S-C00-00-1183 Requirements Manual (TRM) Implement HUMAN PERFORMANCE (HuP) -Standards for Error and Event Prevention S-EPP-00-3068 Reactor Operator Implement Withdraw Control Rod One Notch Implement Test of Standby Main and Emergency Oil Pumps Operate a Single Reactor Feed Pump in Manual Perform Speed Adjustment of Reactor Recirc Pump During Normal Operation Direct RBCCW Heat Exchanger Manual Transfer Of Service Water And Emergency Service Water Inhibit ADS from actuating Bypass the MSIV and CIG Interlocks Inject Liquid Poison Using Pump 1 P208A(B)/2P208A(B)
+* 8
-Perform the Required Actions to Maximize CRD Flow Start an Individual Reactor Feed Pump Turbine following a Trip Perform a Manual Startup of RCIC Using Turbine Trip and Throttling Valve Perform Actions Required to Override RCIC Injection Perform HPCI System Override Injection Direct the Actions for Unanticipated Reactivity Change Direct Actions for Core Flux Oscillations LOC28-NRC-01 Rev 1 Examination Material S-201002-01-005 S-259001-01-100 S-259001-01-037 S-202001-01-008 S-276000-01-003 S-218000-01-006 S-239001-01-025
-S-211000-01-006
+LOC28-NRC-01
+: 11. Control Room Team Work Demonstrate the ability to function within the Control Room team to comply with station procedures and limits of facility license and respond to plant events using appropriate human performance tools to support safe operation of the facility D.      Task List Task Title                                                                                    ID Licensed Operator Apply Technical Specification (TS) And Technical Requirements Manual (TRM) Requirements       S-C00-00-1185 Implement Reactivity Manipulations Standards and Communication Requirements                   S-C00-00-2784 Implement Appropriate Portions Of Operations Standards                                        S-C00-00-1081 For System and Equipment Operation Implement Operations Standards For Error And Event                                            S-ADM-00-1091 Prevention Implement Standards for Shift Operations                                                      S-C00-00-2780 Implement Appropriate Portions of Conduct of Operations                                       S-C00-00-1015 Implement Appropriate Portions of Secondary Containment Integrity Control                     S-C00-00-1020 Implement EOP Cautions                                                                        S-C00-00-2566 Implement Operations Directives                                                               S-C00-00-3130 Ensure Plant Operates IAW the Operating License, Technical Specifications (TS}, and Technical S-C00-00-1183 Requirements Manual (TRM)
+Implement HUMAN PERFORMANCE (HuP) - Standards for Error and Event Prevention                  S-EPP-00-3068 Reactor Operator Implement Withdraw Control Rod One Notch                                                      S-201002-01-005 Implement Test of Standby Main and Emergency Oil Pumps                                        S-259001-01-100 Operate a Single Reactor Feed Pump in Manual                                                  S-259001-01-037 Perform Speed Adjustment of Reactor Recirc Pump During Normal Operation                       S-202001-01-008 Direct RBCCW Heat Exchanger Manual Transfer Of                                                S-276000-01-003 Service Water And Emergency Service Water Inhibit ADS from actuating                                                                    S-218000-01-006 Bypass the MSIV and CIG Interlocks                                                            S-239001-01-025 Inject Liquid Poison Using Pump 1P208A(B)/2P208A(B)                                           S-211000-01-006 Perform the Required Actions to Maximize CRD Flow                                             S-201001-01-044 Start an Individual Reactor Feed Pump Turbine following a Trip                                S-259001-01-045 Perform a Manual Startup of RCIC Using Turbine Trip and Throttling Valve                      S-217000-01-035 Perform Actions Required to Override RCIC Injection                                           S-217000-01-060 Perform HPCI System Override Injection                                                        S-206000-01-062 Direct the Actions for Unanticipated Reactivity Change                                        S-201002-01-009 Direct Actions for Core Flux Oscillations                                                     S-215005-01-017 LOC28-NRC-01 Rev 1                                   Examination Material                                 04/14/2016. 9
-S-201001-01-044
+LOC28-NRC-01 Task Title                                                                ID Direct Actions for Loss of RBCCW Flow                                     S-208000-01-007 Direct the Actions for RPS and ARI Trip Bypass                            S-212000-01-038 Perform Required Actions for a Reactor Recirculation Pump Runback         S-202002-01-022 Enter EOP RPV Control                                                     S-EOPRR-01-006 Enter Level/Power Control EO Procedure                                    S-EOPRPV-01-004 Confirm Reactor Scram                                                     S-EOPRPV-01-002 Confirm Reactor Shutdown                                                  S-EOPRPV-01-003 Ensure All Isolations and Actuations Occur                                S-EOPRPV-01-005 Enter Primary Containment Control                                         S-EOPPCC-01-002 Scram the Reactor                                                         S-EOPRR-01-005 Senior Reactor Operator Direct Entry into Loss of Reactor Recirculation Flow                      S-202001-02-004 Direct Required Actions for a Trip of Both Reactor Recirculation Pumps    S-202001-02-009 Direct Entry into Unanticipated Reactivity Change                         S-201002-02-001 Direct Entry into Loss of Reactor Building Closed Cooling Water (RBCCW)   S-208000-02-001 Direct and Coordinate Implementation of Level Power Control (ATWS)        000000-02-1154 Direct Performance of RPS and ARI Trip Bypass                             S-212000-02-002 Direct the Operation of a Single Reactor Feed Pump in Manual (ICS)        S-259001-02-024 Direct a Reactor Feed Pump Turbine A(B)(C) Trip                           S-259001-02-035 Direct Speed Adjustment of Reactor Recirc Pump During Normal Operation    S-202001-02-002 Direct Inhibiting the Automatic Depressurization System from Actuating    S-218000-02-001 Direct Performance of the Required Actions to Maximize CRD Flow           S-201001-02-007 Direct Start of an Individual Reactor Feed Pump Turbine Following a Trip  S-259001-02-030 Direct Performance of Overriding RCIC Injection                           S-217000-02-010 LOC28-NRC-01 Rev 1                                   Examination Material            04/14/2016. 10
-S-259001-01-045 S-217000-01-035
+LOC28-NRC-01 Scenario Attributes A. Critical Tasks
+: 1. Inject SLC Early boron injection has the following benefits:
+Safety Significance
+* Stop or prevent large magnitude Limit Cycle Oscillations which can lead to core damage.
+* Limit fuel damage from uneven flux patterns that could result from partial rod inserts.
+Failure to inject Boron can result in Consequences for Failure
+* Cycle Oscillations which can lead to core damage .
+to Perform Task
+* Fuel damage from uneven flux patterns that could result from partial rod inserts.
+Indications/Cues for Event A TWS with initial reactor power level greater than 5% APRM power.
+Requiring Critical Task Inject SLC by inserting key into keylock switch and turning to start Performance Criteria       selected SLC pump, fire the Squib valves and close the Reactor Water Cleanup isolation valve.
+Successful SLC injection would be indicated by a lowering SLC tank level Performance Feedback and a corresponding power level decrease.
+: 2. Lowers RPV level to <-60" and maintains until E0-000-113 directs otherwise Core damage due to unstable operation can be prevented or at least Safety Significance        mitigated by promptly reducing Feedwater flow so that level is lowered below the Feedwater spargers.
+A General Electric Company study (NED0-32047) indicates that the Consequences for Failure   major threat to fuel integrity from ATWS is caused by large-amplitude to Perform Task            power/flow instabilities. The power oscillations can become large enough to cause melting of fuel in high-power bundles.
+Indications/Cues for Event A TWS with initial reactor power level greater than 5% APRM power.
+Requiring Critical Task Lower reactor water level by manually controlling injection rate from Performance Criteria Feedwater, HPCI and/or RCIC.
+Reducing vessel injection will result in Wide Range level indications lowering to -60 to -110 inches and will result in power level lowering as Performance Feedback indicated on the Average Power Range Monitors.
+LOC28-NRC-01 Rev 1                         Examination Material                             04/14/2016
+* 11
-S-217000-01-060 S-206000-01-062 S-201002-01-009 S-215005-01-017 04/14/2016.
+LOC28-NRC-01
-LOC28-NRC-01 Task Title ID Direct Actions for Loss of RBCCW Flow S-208000-01-007 Direct the Actions for RPS and ARI Trip Bypass S-212000-01-038 Perform Required Actions for a Reactor Recirculation Pump Runback S-202002-01-022 Enter EOP RPV Control S-EOPRR-01-006 Enter Level/Power Control EO Procedure S-EOPRPV-01-004 Confirm Reactor Scram S-EOPRPV-01-002 Confirm Reactor Shutdown S-EOPRPV-01-003 Ensure All Isolations and Actuations Occur S-EOPRPV-01-005 Enter Primary Containment Control S-EOPPCC-01-002 Scram the Reactor S-EOPRR-01-005 Senior Reactor Operator Direct Entry into Loss of Reactor Recirculation Flow S-202001-02-004 Direct Required Actions for a Trip of Both Reactor Recirculation Pumps S-202001-02-009 Direct Entry into Unanticipated Reactivity Change S-201002-02-001 Direct Entry into Loss of Reactor Building Closed Cooling Water (RBCCW) S-208000-02-001 Direct and Coordinate Implementation of Level Power Control (ATWS) 000000-02-1154 Direct Performance of RPS and ARI Trip Bypass S-212000-02-002 Direct the Operation of a Single Reactor Feed Pump in Manual (ICS) S-259001-02-024 Direct a Reactor Feed Pump Turbine A(B)(C) Trip S-259001-02-035 Direct Speed Adjustment of Reactor Recirc Pump During Normal Operation S-202001-02-002 Direct Inhibiting the Automatic Depressurization System from Actuating S-218000-02-001 Direct Performance of the Required Actions to Maximize CRD Flow S-201001-02-007 Direct Start of an Individual Reactor Feed Pump Turbine Following a Trip S-259001-02-030 Direct Performance of Overriding RCIC Injection S-217000-02-010 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
+: 3. Insert Control Rods IAW E0-000-113 Safety Significance          Control rod insertion initiates power reduction immediately.
-LOC28-NRC-01 Scenario Attributes A. Critical Tasks 1. Inject SLC Early boron injection has the following benefits:
+Consequences for Failure     Failure to insert control rods allows power to remain elevated with to Perform Task               resultant power oscillations and potential core damage.
-* Stop or prevent large magnitude Limit Cycle Oscillations which can Safety Significance lead to core damage.
+Indications/Cues for Event   Exceeding a RPS scram setting with NO reactor scram signal, or Requiring Critical Task      RPS/ARI fail to fully insert all control rods.
-* Limit fuel damage from uneven flux patterns that could result from partial rod inserts. Failure to inject Boron can result in Consequences for Failure
+Insert Control Rods by one or more of the following methods:
-* Cycle Oscillations which can lead to core damage . to Perform Task
+Performance Criteria
-* Fuel damage from uneven flux patterns that could result from partial rod inserts. Indications/Cues for Event A TWS with initial reactor power level greater than 5% APRM power. Requiring Critical Task Inject SLC by inserting key into keylock switch and turning to start Performance Criteria selected SLC pump, fire the Squib valves and close the Reactor Water Cleanup isolation valve. Performance Feedback Successful SLC injection would be indicated by a lowering SLC tank level and a corresponding power level decrease.
-: 2. Lowers RPV level to <-60" and maintains until E0-000-113 directs otherwise Core damage due to unstable operation can be prevented or at least Safety Significance mitigated by promptly reducing Feedwater flow so that level is lowered below the Feedwater spargers.
-A General Electric Company study (NED0-32047) indicates that the Consequences for Failure major threat to fuel integrity from ATWS is caused by large-amplitude to Perform Task power/flow instabilities.
-The power oscillations can become large enough to cause melting of fuel in high-power bundles. Indications/Cues for Event A TWS with initial reactor power level greater than 5% APRM power. Requiring Critical Task Performance Criteria Lower reactor water level by manually controlling injection rate from Feedwater, HPCI and/or RCIC. Reducing vessel injection will result in Wide Range level indications Performance Feedback lowering to -60 to -110 inches and will result in power level lowering as indicated on the Average Power Range Monitors.
-LOC28-NRC-01 Rev 1 Examination Material 04/14/2016
-* 11 LOC28-NRC-01
-: 3. Insert Control Rods IAW E0-000-113 Safety Significance Control rod insertion initiates power reduction immediately.
-Consequences for Failure Failure to insert control rods allows power to remain elevated with to Perform Task resultant power oscillations and potential core damage. Indications/Cues for Event Exceeding a RPS scram setting with NO reactor scram signal, or Requiring Critical Task RPS/ARI fail to fully insert all control rods. Insert Control Rods by one or more of the following methods: Performance Criteria
 * Drive control rods after bypassing RWM
 * Reset and Scram again by performing ES-158-002 Bypass RPS logic trips Successful insertion of control rods will be indicated by:
 * Rod position full in indication for manual insertion of control rods Performance Feedback
 * Rod position showing control rod insertion after resetting scram, draining scram discharge volume and re-scram
-* Power level lowering as indicated on the Average Power Range Monitors B. Scenario Malfunctions Event Malfunction Operator Action in Response 1 N/A Swap 'A' RFP main lube oil pumps (OP-145-003) 2 N/A Withdraw control rods to raise reactor power 3 percent. (OP-AD-338, G0-100-012) 3 'B' RFPT vibration rises and 'B' RFPT trips on mfFW145 0078 high vibration, Recirc LIM2 runback (ON-164-002) 4 cmITR03_FTB31 APRM 2 and 3 'A' Recirc Loop drive flow fails 1N014C high during LIM2 runback (TS 3.3.1.1) 5 RBCCW TCV fails, ESW placed in-service to cmfAV04_TV11028 restore RBCCW cooling (ON-114-001), ESW loop declared inoperable when aligned to RBCCW (TS 3.7.2) 6 Complete loss of RBCCW, High RRP cmfAV01_HV11024A2 temperatures, Manual Scram 7 Hydraulic-block A TWS mfRD155 017 (E0-100-113, OP-145-005, ES-158-002)
+* Power level lowering as indicated on the Average Power Range Monitors B. Scenario Malfunctions Event                  Malfunction                           Operator Action in Response 1                                               Swap 'A' RFP main lube oil pumps N/A                     (OP-145-003) 2                       N/A                     Withdraw control rods to raise reactor power 3 percent. (OP-AD-338, G0-100-012) 3                                               'B' RFPT vibration rises and 'B' RFPT trips on mfFW145 0078                 high vibration, Recirc LIM2 runback (ON-164-002) 4                 cmITR03_FTB31                 APRM 2 and 3 'A' Recirc Loop drive flow fails 1N014C                    high during LIM2 runback (TS 3.3.1.1) 5                                               RBCCW TCV fails, ESW placed in-service to restore RBCCW cooling (ON-114-001), ESW cmfAV04_TV11028 loop declared inoperable when aligned to RBCCW (TS 3.7.2) 6                                               Complete loss of RBCCW, High RRP cmfAV01_HV11024A2 temperatures, Manual Scram 7                                               Hydraulic-block ATWS mfRD155 017 (E0-100-113, OP-145-005, ES-158-002)
-LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
+LOC28-NRC-01 Rev 1                           Examination Material                                04/14/2016. 12
-LOC28-NRC-01 8 cmfPM03_ 1P208A SLC pump trips after start, standby SLC pump cmfPM03_ 1P208B successfully injects boron (OP-153-001) 9 Wide Range level instrument fails, RFP flow cmfTR01_L T14201A must be raised to maintain reactor level in A TWS band 10 In-service RFPT trips after first scram, RCIC mfFW148002 restored to maintain RPV level while standby RFPT placed in-service C. Abnormal Events and Major Transients Malfunction Description R Withdraw control rods to raise reactor power 3 percent. (OP-AD-338, G0-100-012)
-N Swap 'A' RFP main lube oil pumps (OP-145-003)
+LOC28-NRC-01 8                  cmfPM03_ 1P208A               SLC pump trips after start, standby SLC pump cmfPM03_ 1P208B               successfully injects boron (OP-153-001) 9                                                Wide Range level instrument fails, RFP flow cmfTR01_L T14201A              must be raised to maintain reactor level in A TWS band 10                                               In-service RFPT trips after first scram, RCIC mfFW148002                  restored to maintain RPV level while standby RFPT placed in-service C. Abnormal Events and Major Transients Malfunction                                             Description R         Withdraw control rods to raise reactor power 3 percent. (OP-AD-338, G0-100-012)
-AE1 RBCCW TCV fails, ESW placed in-service to restore RBCCW cooling (ON-114-001)
+N         Swap 'A' RFP main lube oil pumps (OP-145-003)
-AE2 RBCCW ruputure (ON-114-001)
+AE1         RBCCW TCV fails, ESW placed in-service to restore RBCCW cooling (ON-114-001)
-MT1 Hydraulic-block A TWS TS1 APRM 2 and 3 'A' Recirc Loop drive flow fails high during LIM2 run back (TS 3.3.1.1) TS2 ESW loop declared inoperable when aligned to RBCCW (TS 3.7.2) MAE1 SLC pump trips after start, standby SLC pump successfully injects boron (OP-153-001) MAE2 Wide Range level instrument fails, RFP flow must be raised to maintain reactor level in ATWS band MAE3 In-service RFPT trips after first scram, RCIC restored to maintain RPV level while standby RFPT placed in-service D. EOP and EOP Contingencies Used EOPs EOP Contingencies IZI E0-000-102, RPV Control D E0-000-102, Alternate Level Control IZI E0-000-103, Primary Containment Control D E0-000-102, Steam Cooling D E0-000-104, Secondary Containment Control D E0-000-112, Emergency Depressurization D E0-000-105, Radioactivity Release Control IZI E0-000-113, Power/Level Control D E0-000-114, RPV Flooding LOC28-NRC-01 Rev 1 Examination Material 04/14/2016
+AE2         RBCCW ruputure (ON-114-001)
-* 13 LOC28-NRC-01 E. Technical Specifications
+MT1         Hydraulic-block A TWS TS1         APRM 2 and 3 'A' Recirc Loop drive flow fails high during LIM2 run back (TS 3.3.1.1)
-: 1. TS 3.3.1.1, Instrumentation Reactor Protection System (RPS) 2. TS 3.7.2, Plant Systems Emergency Service Water System 3. TRM 3.1.3, Reactivity Control Systems Control Rod Block Instrumentation LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
+TS2         ESW loop declared inoperable when aligned to RBCCW (TS 3.7.2)
-LOC28-NRC-01 References
+SLC pump trips after start, standby SLC pump successfully injects boron (OP-153-MAE1 001)
-: 1. OP-AD-001 Operations Standards for System and Equipment Operation
+Wide Range level instrument fails, RFP flow must be raised to maintain reactor level MAE2 in ATWS band In-service RFPT trips after first scram, RCIC restored to maintain RPV level while MAE3 standby RFPT placed in-service D. EOP and EOP Contingencies Used EOPs                                                   EOP Contingencies IZI E0-000-102, RPV Control                             D E0-000-102, Alternate Level Control IZI E0-000-103, Primary Containment Control             D E0-000-102, Steam Cooling D E0-000-104, Secondary Containment Control             D E0-000-112, Emergency Depressurization D E0-000-105, Radioactivity Release Control             IZI E0-000-113, Power/Level Control D E0-000-114, RPV Flooding LOC28-NRC-01 Rev 1                            Examination Material                                04/14/2016
-: 2. OP-AD-004 Operations Standards for Error and Event Prevention
+* 13
-: 3. OP-AD-300 Administration of Operations
-: 4. OP-AD-338 Reactivity Manipulations Standards and Communication Requirements
+LOC28-NRC-01 E. Technical Specifications
-: 5. OP-111-001 Service Water System 6. OP-145-001 RFP and RFP Lube Oil System 7. OP-145-005 Infrequent Manual RFP System Operations
+: 1. TS 3.3.1.1, Instrumentation Reactor Protection System (RPS)
-: 8. OP-145-006 Feedwater HMI Operations
+: 2. TS 3.7.2, Plant Systems Emergency Service Water System
-: 9. OP-153-001 Standby Liquid Control System 10. OP-156-001 Reactor Manual Control System RMCS 11. OP-183-001 Automatic Depressurization System and Safety Relief Valves 12. OP-184-001 Main Steam System 13. G0-100-012 Power Maneuvers
+: 3. TRM 3.1.3, Reactivity Control Systems Control Rod Block Instrumentation LOC28-NRC-01 Rev 1                          Examination Material                    04/14/2016. 14
-: 14. ON-SCRAM-101 Reactor Scram 15. ON-RBCCW-101 Loss of RBCCW 16. ON-PWR-101 Reactor Power 17. ON-REC I RC-101 Reactor Recirculation Malfunction
-: 18. E0-000-102 RPV Control 19. E0-000-103 Primary Containment Control 20. E0-000-104 Secondary Containment Control 21. E0-000-112 Emergency Rapid Depressurization
+LOC28-NRC-01 References
-: 22. E0-000-113 Power/Level Control 23. AR-101-A01 RWCU Filter Inlet Hi Temp Isa 24. AR-101-A10 RFPT A Trip 25. AR-101-A16 RFPT B Trip 26. AR-102-F03 Recirc Pump A Seal Clg Water Lo Flow 27. AR-103-E06 APRM Flow Reference Off Normal 28. AR-104-H03 Rod Out Block 29. AR-106-C09 Gen Volt Reg Auto To Man Set Point Unbalanced
+: 1. OP-AD-001      Operations Standards for System and Equipment Operation
-: 30. AR-110-A01 ADS Logic A Timer Initiated
+: 2. OP-AD-004      Operations Standards for Error and Event Prevention
-: 31. AR-110-A02 ADS Logic B Timer Initiated LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
+: 3. OP-AD-300      Administration of Operations
+: 4. OP-AD-338      Reactivity Manipulations Standards and Communication Requirements
-: 32. AR-100-A03
+: 5. OP-111-001     Service Water System
-: 33. AR-100-A04
+: 6. OP-145-001     RFP and RFP Lube Oil System
-: 34. AR-123-E05
+: 7. OP-145-005     Infrequent Manual RFP System Operations
-: 35. LA-1295-001
+: 8. OP-145-006     Feedwater HMI Operations
-: 36. EP-PS-100
+: 9. OP-153-001     Standby Liquid Control System
-: 37. EP-RM-004
+: 10. OP-156-001     Reactor Manual Control System RMCS
-: 38. ES-158-002
+: 11. OP-183-001     Automatic Depressurization System and Safety Relief Valves
-: 39. LOC28-NRC-01 Rev 1 LOC28-NRC-01 ADS Logic C Timer Initiated ADS Logic D Timer Initiated RBCCW Header Hi Temp RWCU System Panel 1 C295 Emergency Director Control Room Emergency Plan Position Specific Instruction EAL Classification Bases RPS and ARI Trip Bypass Examination Material 04/14/2016.
+: 12. OP-184-001     Main Steam System
-LOC28-NRC-01 Setup Instructions A. Required Materials
+: 13. G0-100-012     Power Maneuvers
-: 1. US Turnover Sheet a. Unit 1 1) -95% power for control rod pattern adjustment, 500 days on-line 2) HPCI in day 2 of 4-day system outage window for steam side maintenance.
+: 14. ON-SCRAM-101   Reactor Scram
-LCO 3.5.1 condition D has been entered for the outage. 3) 'E' EOG substituted for 'A' EDG for 'A' system outage window 4) RFP lube oil conditioner was swapped from RFP 'A' reservoir to 'B' reservoir last shift 5) Perform control rod pattern adjustment per RMR 6) Test 'A' RFP main lube oil pump 'B' and swap to main lube oil pump 'B' b. Common and Unit 2 1) Unit 2 at rated power. 2) Severe thunderstorm watch is in effect for Luzerne County for the next 12 hours 2. Supporting Documents
+: 15. ON-RBCCW-101   Loss of RBCCW
-: a. RMR (2 copies) b. OP-145-003 (for the Normal Event) B. Simulator Initialization
+: 16. ON-PWR-101     Reactor Power
+: 17. ON-REC IRC-101 Reactor Recirculation Malfunction
+: 18. E0-000-102     RPV Control
+: 19. E0-000-103     Primary Containment Control
+: 20. E0-000-104     Secondary Containment Control
+: 21. E0-000-112     Emergency Rapid Depressurization
+: 22. E0-000-113     Power/Level Control
+: 23. AR-101-A01     RWCU Filter Inlet Hi Temp Isa
+: 24. AR-101-A10     RFPT A Trip
+: 25. AR-101-A16     RFPT B Trip
+: 26. AR-102-F03     Recirc Pump A Seal Clg Water Lo Flow
+: 27. AR-103-E06     APRM Flow Reference Off Normal
+: 28. AR-104-H03     Rod Out Block
+: 29. AR-106-C09     Gen Volt Reg Auto To Man Set Point Unbalanced
+: 30. AR-110-A01     ADS Logic A Timer Initiated
+: 31. AR-110-A02     ADS Logic B Timer Initiated LOC28-NRC-01 Rev 1                    Examination Material                         04/14/2016. 15
+LOC28-NRC-01
+: 32. AR-100-A03  ADS Logic C Timer Initiated
+: 33. AR-100-A04  ADS Logic D Timer Initiated
+: 34. AR-123-E05  RBCCW Header Hi Temp
+: 35. LA-1295-001 RWCU System Panel 1C295
+: 36. EP-PS-100   Emergency Director Control Room Emergency Plan Position Specific Instruction
+: 37. EP-RM-004   EAL Classification Bases
+: 38. ES-158-002  RPS and ARI Trip Bypass 39.
+LOC28-NRC-01 Rev 1                 Examination Material                       04/14/2016. 16
+LOC28-NRC-01 Setup Instructions A. Required Materials
+: 1. US Turnover Sheet
+: a. Unit 1
+: 1)    -95% power for control rod pattern adjustment, 500 days on-line
+: 2)    HPCI in day 2 of 4-day system outage window for steam side maintenance. LCO 3.5.1 condition D has been entered for the outage.
+: 3)    'E' EOG substituted for 'A' EDG for 'A' system outage window
+: 4)    RFP lube oil conditioner was swapped from RFP 'A' reservoir to 'B' reservoir last shift
+: 5)    Perform control rod pattern adjustment per RMR
+: 6)    Test 'A' RFP main lube oil pump 'B' and swap to main lube oil pump 'B'
+: b. Common and Unit 2
+: 1)    Unit 2 at rated power.
+: 2)    Severe thunderstorm watch is in effect for Luzerne County for the next 12 hours
+: 2. Supporting Documents
+: a. RMR (2 copies)
+: b. OP-145-003 (for the Normal Event)
+B. Simulator Initialization
 : 1. Reset to exam specific IC. If not available, setup IAW the following instructions
-: a. Reset to IC-20 b. Place the simulator in RUN c. Reduce core power to 95% using RRPs. Match loop flows. d. Isolate the HPCI steam supply by closing the F002 and F003 isolation valves. e. Depressurize the HPCI steam supply line after F002 and F003 are closed by opening F054 valve. Close the F054 valve once the steam line is depressurized.
+: a. Reset to IC-20
+: b. Place the simulator in RUN
+: c. Reduce core power to 95% using RRPs. Match loop flows.
+: d. Isolate the HPCI steam supply by closing the F002 and F003 isolation valves.
+: e. Depressurize the HPCI steam supply line after F002 and F003 are closed by opening F054 valve. Close the F054 valve once the steam line is depressurized.
 : f. Run SCN file HPB_HPCIOOS.scn to tagout HPCI steam-side
-: g. Place the simulator in FREEZE 2. Run SCN file exam\LOC28-NRC-01.scn
+: g. Place the simulator in FREEZE
-: 3. Place the simulator in RUN LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
+: 2. Run SCN file exam\LOC28-NRC-01.scn
-LOC28-NRC-01
+: 3. Place the simulator in RUN LOC28-NRC-01 Rev 1                             Examination Material                           04/14/2016. 17
+LOC28-NRC-01
 : 4. Perform simulator activities
-: a. Place a status control tag on the HPCI Steam Supply Valves b. Place protected equipment magnets around RCIC c. Place the 'E' for 'A' EOG signs up d. Ensure proper CRMs are inservice
+: a. Place a status control tag on the HPCI Steam Supply Valves
-: e. Post the blue reactivity signs 5. Verify the simulator matches the following
+: b. Place protected equipment magnets around RCIC
-: a. 3 RFs and 1 MF is in the list due to performing the HPCI setup MF RF OR ET CONDITIONS 7:7 4:4 0:0 8 15 6. Ensure FW Control is selected to LEFM 7. Reset ODAs and all Overhead, PICSY, HMI and RWM alarms 8. Ensure horns and annunciators are on 9. Ensure Overhead Lights Override is off C. Simulator Preparation
+: c. Place the 'E' for 'A' EOG signs up
-: 1. Ensure the EOL CRC Book is at the PCO Console D. Document Training and Performance Feedback 1. Record crew position assignments in G:\NTGOPS\LOR\REQUAL\lnfo Tracking\ (LOR) 2. Record crew position assignments per TQ-104 (ILO) 3. Complete simulator exam checklist E. Scenario Execution
+: d. Ensure proper CRMs are inservice
-: 1. Identify performance improvement actions that may be addressed during the scenario 2. Provide turnover to the crew using the US Turnover sheet 3. Direct the crew to walk down the Control Room panels 4. Inform the Shift Manager that the crew has the shift F. Simulator Files LOC28-NRC-01 de Imp SCN rat_mp insmp ycpxftv03 changemp ycpxftv03 0,10,mils,RFP B VIBR insmp fx10FWCTRL_B21.0UT LOC28-NRC-01 Rev 1 changemp fx10FWCTRL_B21.0UT
+: e. Post the blue reactivity signs
-,,%,FW MASTER LVL CTRL OUTPUT insmp fxlBRFP _BllS.OUT changemp fxlBRFP _BllS.OUT
+: 5. Verify the simulator matches the following
-,,%,RFP B DEMAND insmp fxlBB_SM_Bl.OUT changemp fxlBB_SM_Bl.OUT
+: a. 3 RFs and 1MF is in the list due to performing the HPCI setup MF                 RF                OR                    ET           CONDITIONS 7:7                4:4               0:0                    8                 15
-,,RPM,RFPT B SPEED insmp fxlBRFP _BllS.MA Examination Material 04/14/2016
+: 6. Ensure FW Control is selected to LEFM
-* 18 LOC28-N RC-01 change mp fxlBRFP _BUS.MA ,,bool,RFPT B AUTO/MAN insmp rwttll305 change mp rwttll305
+: 7. Reset ODAs and all Overhead, PICSY, HMI and RWM alarms
-,,,RBCCW HX OUTLET TEMP insmp swvsptv11028 changemp swvsptv11028
+: 8. Ensure horns and annunciators are on
-,,,RBCCW HX TCV POS insmp aoTRSHB311R601D.CurrValue changemp aoTRSHB311R601D.CurrValue 0,300,DEG F,RRP A LO GUIDE BRG TEMP(PT4) insmp aoTRSHB311R6011.CurrValue changemp aoTRSHB311R6011.CurrValue 0,300,DEG F,RRPA #1 SEAL CAV TEMP insmp cuteg331n019 changemp cuteg331n019
+: 9. Ensure Overhead Lights Override is off C. Simulator Preparation
-,,DEG F,RWCU NRHX INLET ;0-G alarms suppressed SDR IMF annAR106F15 f:ALARM_OFF IMF annAR131A04 f:ALARM_OFF
+: 1. Ensure the EOL CRC Book is at the PCO Console D. Document Training and Performance Feedback
-;E DG subst for A IRF rfDG024001 f:A ;Recirc loop A xmitter offset initialization IMF cmfTR03_FTB311N014C f:O IMF cmfTR03_FTB311N014D f:O ;Hyd-block ATWS IMF mfRD155017
+: 1. Record crew position assignments in G:\NTGOPS\LOR\REQUAL\lnfo Tracking\ (LOR)
-;CRD PCV binding IMF cmfMV07 _PV146F003 f:Asls ;Recirc loop A channel D flow xmitter malfunctions aet ETLOC28-NRC01-B
+: 2. Record crew position assignments per TQ-104 (ILO)
-;activate NRHX iso alarm on high temp aet ETLOC28-NRC01-C
+: 3. Complete simulator exam checklist E. Scenario Execution
-;align ESW to RBCCW HX aet ETLOC28-NRC01-D
+: 1. Identify performance improvement actions that may be addressed during the scenario
-;Activates ETLOC28-NRC01-J aet ETLOC28-NRC01-E
+: 2. Provide turnover to the crew using the US Turnover sheet
-;1st SLC pump trips aet ETLOC28-NRC01-F aet ETLOC28-NRC01-G
+: 3. Direct the crew to walk down the Control Room panels
-;Trips breaker for PV-146-F003 when operated aet ETLOC28-NRC01-H
+: 4. Inform the Shift Manager that the crew has the shift F. Simulator Files LOC28-NRC-01                                                 changemp fx10FWCTRL_B21.0UT ,,%,FW MASTER LVL CTRL OUTPUT de Imp SCN rat_mp                                                   insmp fxlBRFP _BllS.OUT changemp fxlBRFP _BllS.OUT ,,%,RFP B DEMAND insmp ycpxftv03 changemp ycpxftv03 0,10,mils,RFP B VIBR                      insmp fxlBB_SM_Bl.OUT changemp fxlBB_SM_Bl.OUT ,,RPM,RFPT B SPEED insmp fx10FWCTRL_B21.0UT insmp fxlBRFP _BllS.MA LOC28-NRC-01 Rev 1                              Examination Material                                   04/14/2016
-;WR level A fails as-is aet ETLOC28-NRC01-I
+* 18
+LOC28-N RC-01 change mp fxlBRFP _BUS.MA ,,bool,RFPT B AUTO/MAN                ; RBCCW HX TCV fails
+{Key[3]} IMF cmfAV04_TV11028 r:lO f:O insmp rwttll305 change mp rwttll305 ,,,RBCCW HX OUTLET TEMP                     ; Adjust RBCCW cooling
+{Key[4]} IMF cmfAV04_TV11028 d:lS r:30 f:5 insmp swvsptv11028 changemp swvsptv11028 ,,,RBCCW HX TCV POS                       ; RBCCW discharge header rupture
+{Key[S]} IMF mfRW114001 f:20 insmp aoTRSHB311R601D.CurrValue changemp aoTRSHB311R601D.CurrValue 0,300,DEG F,RRP A LO         ; Byp CRD pump suet filter GUIDE BRG TEMP(PT4)                                             {Key[6]} IRF rfRD155028 d:120 f:lOO insmp aoTRSHB311R6011.CurrValue                                 ; Close CRD chrg wtr isol F034 changemp aoTRSHB311R6011.CurrValue 0,300,DEG F,RRPA #1          {Key[7]} IRF rfRD155017 d:120 f:O SEAL CAV TEMP
+                                                                ; ES-158-002 - ARI insmp cuteg331n019                                              {Key[8]} IRF rfDC102129 f:OPEN d:120 changemp cuteg331n019 ,,DEG F,RWCU NRHX INLET                   {Key[8]} IRF rfDC102103 f:OPEN d:120
+;0-G alarms suppressed SDR                                      ; ES-158-002 - Div 1 RPS IMF annAR106F15 f:ALARM_OFF                                     {Key[9]} IRF rfRP158039 f:BYPASS d:120 IMF annAR131A04 f:ALARM_OFF                                     {Key[9]} IRF rfRP158040 f:BYPASS d:120
+;E DG subst for A                                               ; ES-158-002 - Div 2 RPS IRF rfDG024001 f:A                                              {Key[lO]} IRF rfRP158041 f:BYPASS d:120
+{Key[lO]} IRF rfRP158042 f:BYPASS d:120
+;Recirc loop A xmitter offset initialization IMF cmfTR03_FTB311N014C f:O                                     ; Re-open CRD chrg wtr isol F034 IMF cmfTR03_FTB311N014D f:O                                     {Key[ll]} IRF rfRD155017 d:120 f:lOO
+;Hyd-block ATWS                                                 ; X-Tie CIG and I/A IMF mfRD155017                                                  {Key[l2]} IRF rfPC125001 f:OPEN
+;CRD PCV binding                                                ; HPCI OOSVC - isolate and depress steam-side first IMF cmfMV07 _PV146F003 f:Asls                                   {Key[40]} SCN exam\HPB_HPCIOOS
+;Recirc loop A channel D flow xmitter malfunctions aet ETLOC28-NRC01-B                                             HPB.HPCIOOS
+                                                                ;# HV-F002 BRKR OPEN (IB)
+;activate NRHX iso alarm on high temp                           IRF rfDB106236 f:OPEN aet ETLOC28-NRC01-C                                             ;# HV-F003 BRKR OPEN (OB)
+IRF rfDC188113 f:OPEN
+;align ESW to RBCCW HX                                          ;# HPCI AOP BRK OPEN aet ETLOC28-NRC01-D                                             IRF rfDC188128 f:OPEN
+                                                                ;#LOSS OF PWR TO HV-FlOO SOLENOID
+;Activates ETLOC28-NRC01-J                                      IMF cmfAVOl_HVlSSFlOO aet ETLOC28-NRC01-E
+;1st SLC pump trips                                             ETLOC28-NRC01-B aet ETLOC28-NRC01-F                                             fx1B_LIMITERS_B432.B001 = 1 aet ETLOC28-NRC01-G                                             MMF cmfTR03_FTB311N014C r:30 i:O f:21789 MMF cmfTR03_FTB311N014D r:30 i:O f:19876
+;Trips breaker for PV-146-F003 when operated aet ETLOC28-NRC01-H ETLOC28-NRC01-C
+;WR level A fails as-is                                         cuteg331n019 > 145 aet ETLOC28-NRC01-I                                             IMF annARlOlAOl f:ALARM_ON
 ; RFP B vibration
-{Key[l]} IMF mfFW145007B r:180 f:lO ; RBCCW HX TCV fails {Key[3]} IMF cmfAV04_TV11028 r:lO f:O ; Adjust RBCCW cooling {Key[4]} IMF cmfAV04_TV11028 d:lS r:30 f:5 ; RBCCW discharge header rupture {Key[S]} IMF mfRW114001 f:20 ; Byp CRD pump suet filter {Key[6]} IRF rfRD155028 d:120 f:lOO ; Close CRD chrg wtr isol F034 {Key[7]} IRF rfRD155017 d:120 f:O ; ES-158-002
+{Key[l]} IMF mfFW145007B r:180 f:lO LOC28-NRC-01 Rev 1                                 Examination Material                                          04/14/2016. 19
--ARI {Key[8]} IRF rfDC102129 f:OPEN d:120 {Key[8]} IRF rfDC102103 f:OPEN d:120 ; ES-158-002
--Div 1 RPS {Key[9]} IRF rfRP158039 f:BYPASS d:120 {Key[9]} IRF rfRP158040 f:BYPASS d:120 ; ES-158-002
+LOC28-NRC-01 ETLOC28-N RCOl-D                                            ETLOC28-N RCOl-G
--Div 2 RPS {Key[lO]}
+;SWITCH:RBCCW HX A SW-ESW CHANGEOVER                        ;SWITCH:SBLC MANUAL INITIATION diHS11024A.CurrValue =#OR.diHS11024A.EMERG                  diHSS14804.CurrValue = #OR.diHSS14804.START_B IMF cmfAV04_HV11024Al f:O                                   IMF cmfPM03_1P208B d:45 IMF cmfAV04_HV11024A2 f:O                                   cet ETLOC28-NRC01-F IRF rfSW111032 f:O IMF cmfCV02_110050
-IRF rfRP158041 f:BYPASS d:120 {Key[lO]}
++5 DMF cmfAV04_HV11024Al                                    ETLOC28-N RCOl-H DMF cmfAV04_HV11024A2                                       ;SWITCH:DRIVE WTR PRESS THTLG
-IRF rfRP158042 f:BYPASS d:120 ; Re-open CRD chrg wtr isol F034 {Key[ll]}
+                                                                                 =
-IRF rfRD155017 d:120 f:lOO ; X-Tie CIG and I/A {Key[l2]}
+diHS14603.CurrValue #OR.diHS14603.0PEN IMF cmfMVOl_PV146F003 ETLOC28-NRC01-E
-IRF rfPC125001 f:OPEN ; HPCI OOSVC -isolate and depress steam-side first {Key[40]}
+;SWITCH:MODE SWITCH diHSC72AlS01.CurrValue != #OR.diHSC72AlS01.RUN              ETLOC28-NRC01-I aet ETLOC28-NRC01-J                                         rrlwr < -50 IMF cmfTROl_LT14201A ETLOC28-NRC01-F
-SCN exam\HPB_HPCIOOS HPB.HPCIOOS
+;SWITCH:SBLC MANUAL INITIATION                              ETLOC28-N RCOl-J diHSS14804.CurrValue =#OR.diH5514804.START_A                ;SWITCH:MODE SWITCH IMF cmfPM03_1P208A d:45                                     diHSC72AlS01.CurrValue != #OR.diHSC72AlS01.RUN & (
-;# HV-F002 BRKR OPEN (IB) IRF rfDB106236 f:OPEN ;# HV-F003 BRKR OPEN (OB) IRF rfDC188113 f:OPEN ;# HPCI AOP BRK OPEN IRF rfDC188128 f:OPEN ;#LOSS OF PWR TO HV-FlOO SOLENOID IMF cmfAVOl_HVlSSFlOO ETLOC28-NRC01-B fx1B_LIMITERS_B432.B001
+cet ETLOC28-NRC01-G                                         rp_c721k14a = 1 I rp_c721k14b =1) & rp_c72lkla =0 IMF mfFW148002 d:120 LOC28-NRC-01 Rev 1                             Examination Material                                     04/14/2016
-= 1 MMF cmfTR03_FTB311N014C r:30 i:O f:21789 MMF cmfTR03_FTB311N014D r:30 i:O f:19876 ETLOC28-NRC01-C cuteg331n019
+* 20
-> 145 IMF annARlOlAOl f:ALARM_ON LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
-ETLOC28-N RCOl-D ;SWITCH:RBCCW HX A SW-ESW CHANGEOVER diHS11024A.CurrValue
+LOC28-NRC-01 Event 1 - RFP 'A' Main Lube Oil Pump Swap Instructor Activities                    Operator Activities                        Notes Booth Operator No additional actions required PCO Role Play D Identifies the following alarm windows:
-= #OR.diHS11024A.EMERG IMF cmfAV04_HV11024Al f:O IMF cmfAV04_HV11024A2 f:O IRF rfSW111032 f:O IMF cmfCV02_110050
+As NPO dispatched to 'A' RFP main lube oil pumps for         AR-120-803 and AR-101-H10 pre-start checks, report          D Dispatch NPO to perform pre-start Standing by for test and            checks of RFPT 'A' main lube oil pump swap of 'A' RFP main lube oil pumps.                        D Depress and hold TEST pushbutton for RFPT A ALT MN L-0 PPS HS-11912A D Observes standby lube oil pump starts by appropriate Red light ILLUMINATED D Release TEST pushbutton HS-11912A D Depress RUN pushbutton for RFPT A MN L-0 PP 1P124B D Places 1P124A in Standby D Performs above steps again to test the auto start function of the 'A' lube oil pump us D Directs PCO to test the 'A' RFP main lube oil pumps and perform a pump swap IAW OP-145-003 Instructor Note If the student asks, all prerequistes are completed so that the evolution may proceed.
-+5 DMF cmfAV04_HV11024Al DMF cmfAV04_HV11024A2 ETLOC28-NRC01-E
+LOC28-NRC-01 Rev 1                               Examination Material                          04/14/2016. 21
-;SWITCH:MODE SWITCH diHSC72AlS01.CurrValue
-!= #OR.diHSC72AlS01.RUN aet ETLOC28-NRC01-J ETLOC28-NRC01-F
+LOC28-N RC-01 Event 2 - Control Rod Pattern Adjustment Instructor Activities                     Operator Activities                        Notes Booth Operator When control rod withdrawal is complete, Enter the Control Room as Reactor Engineering and update the CRC book with the. updated shutdown sequence sheets and current control rod pattern.
-;SWITCH:SBLC MANUAL INITIATION diHSS14804.CurrValue
+When the CRC book has been updated, Perform the third role play as the booth or on the floor Initiate Event 3 as soon as the reactivity maneuver is completed.
-= #OR.diH5514804.START_A IMF cmfPM03_1P208A d:45 cet ETLOC28-NRC01-G LOC28-NRC-01 Rev 1 LOC28-NRC-01 ETLOC28-N RCOl-G ;SWITCH:SBLC MANUAL INITIATION diHSS14804.CurrValue
+PCOM Role Play D Withdraws Control Rods 22-23, 38-39, As RE contacted for assistance, reply                    38-23, and 22-39 from position 00 to Core Thermal limits are              position 04 IAW OP-156-001 and within our predictions. You          OP-AD-338 may proceed with the pattern adjustment.               D Uses two finger operation to select the proper Control Rod by depressing the Role Play Control Rod Selection pushbuttons As SM contacted for approval to commence the reactivity        D Verifies the correct Control Rod is manipulation, reply                 selected and in the proper position The Reactivity                    D Withdraws Control rods by depressing manipulation may proceed IAWtheRMR                           the "W/Draw Rod" pushbutton D When all 4 rods have been moved, Role Play                            verifies that the rods are in the proper As RE contact the Control position Room as stated in the booth operator section                  D Depress 'Rod Selct Clear' pushbutton Thermal Limits are sat per        D Plots the power change on the step #4 of the RMR. We will bring the RMR for returning          Power/Flow map to rated power with Recirc        D Monitors diverse indications of reactor flow momentarily. The                power IAW OP-AD-001 Att G updated CRC pages have been replaced. The                PCOP maneuvering envelope is           D Verifies control rods to be withdrawn still 90% to 100% power.
-= #OR.diHSS14804.START_B IMF cmfPM03_1P208B d:45 cet ETLOC28-NRC01-F ETLOC28-N RCOl-H ;SWITCH:DRIVE WTR PRESS THTLG diHS14603.CurrValue
+as directed by RMR IAW OP-AD-338 Role Play                         D IAW OP-AD-300, nulls Manual and As GCC, acknowledge all             Automatic regulars using Man Volt Reg power change updates                Adjust HC-10002 potentiometer, as required D Maintains Load Set -100 MWe above actual generator loads IAW G0-100-012 by depressing Load Selector
-= #OR.diHS14603.0PEN IMF cmfMVOl_PV146F003 ETLOC28-NRC01-I rrlwr < -50 IMF cmfTROl_LT14201A ETLOC28-N RCOl-J ;SWITCH:MODE SWITCH diHSC72AlS01.CurrValue
+                                      'Decrease' and 'Increase' pushbuttons, as required LOC28-NRC-01 Rev 1                               Examination Material                            04/14/2016. 22
-!= #OR.diHSC72AlS01.RUN & ( rp_c721k14a
-= 1 I rp_c721k14b
+LOC28-NRC-01 Event 2 - Control Rod Pattern. Adjustment Instructor Activities                     Operator Activities                     Notes us D Obtains permission from the Shift Manager prior to commencing reactivity manipulations D May, inform GCC of load change on Unit 1 D Conducts a Crew Update prior to commencing rod withdrawal D Directs Control Rod Withdrawal IAW OP-156-001, RMR, and G0-100-012 D Monitors control rod movement with independent copy of RMR Instructor Note The rod pattern adjustment should be completed before moving to Event 3. This will ensure that the rod-line is raised high enough to challenge the MELLA boundary during the runback for the RFP Trip.
-= 1) & rp_c72lkla
+Instructor Cue Initiate Event 3 as soon as power has been raised 5% or on the Lead Examiner's direction. If ill>>)   the next event is started before the RE explaination for the maneuvering envelope, the crew may decide to only use RRPs.
-= 0 IMF mfFW148002 d:120 Examination Material 04/14/2016
+LOC28-NRC-01 Rev 1                              Examination Material                         04/14/2016. 23
-* 20 LOC28-NRC-01 Event 1 -RFP 'A' Main Lube Oil Pump Swap Instructor Activities Booth Operator No additional actions required Role Play As NPO dispatched to 'A' RFP main lube oil pumps for pre-start checks, report Standing by for test and swap of 'A' RFP main lube oil pumps. Instructor Note Operator Activities PCO D Identifies the following alarm windows: AR-120-803 and AR-101-H10 D Dispatch NPO to perform pre-start checks of RFPT 'A' main lube oil pump D Depress and hold TEST pushbutton for RFPT A ALT MN L-0 PPS HS-11912A D Observes standby lube oil pump starts by appropriate Red light ILLUMINATED D Release TEST pushbutton HS-11912A D Depress RUN pushbutton for RFPT A MN L-0 PP 1P124B D Places 1P124A in Standby D Performs above steps again to test the auto start function of the 'A' lube oil pump us D Directs PCO to test the 'A' RFP main lube oil pumps and perform a pump swap IAW OP-145-003 Notes If the student asks, all prerequistes are completed so that the evolution may proceed. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
-LOC28-N RC-01 Event 2 -Control Rod Pattern Adjustment Instructor Activities Operator Activities Notes Booth Operator When control rod withdrawal is complete, Enter the Control Room as Reactor Engineering and update the CRC book with the. updated shutdown sequence sheets and current control rod pattern. When the CRC book has been updated, Perform the third role play as the booth or on the floor Initiate Event 3 as soon as the reactivity maneuver is completed.
+LOC28-N RC-01 Event 3 & 4 - 'B' RFP vibration/ 'B' RFP trip Instructor Activities                   Operator Activities                             Notes Booth Operator When power has been raised 5% or at the Lead Examiner's direction, Insert Key 1 to initiate high vibrations on
-Role Play As RE contacted for assistance, reply Core Thermal limits are within our predictions.
+ 'B' RFP.
-You may proceed with the pattern adjustment.
+{Key[1]} IMF mfFW145007B r:180 f:10             'B' RFP vibration Monitor 'B' RFP vibration in Monitored Parameters.
-Role Play As SM contacted for approval to commence the reactivity manipulation, reply The Reactivity manipulation may proceed IAWtheRMR Role Play As RE contact the Control Room as stated in the booth operator section Thermal Limits are sat per step #4 of the RMR. We will bring the RMR for returning to rated power with Recirc flow momentarily.
+Ensure Event Trigger ETLOC28-NRC01.-B fires when a Recirc LIM2 is actuated by the 'B' RFP trip, to fail the APRM 2 drive flow input from Recirc Loop 'A'.
-The updated CRC pages have been replaced.
+PCOM Role Play D Performs AR-101-A16 for 'B' RFP vibs As FUS/NPO dispatched to
-The maneuvering envelope is still 90% to 100% power. Role Play As GCC, acknowledge all power change updates LOC28-NRC-01 Rev 1 PCOM D Withdraws Control Rods 22-23, 38-39, 38-23, and 22-39 from position 00 to position 04 IAW OP-156-001 and OP-AD-338 D Uses two finger operation to select the proper Control Rod by depressing the Control Rod Selection pushbuttons D Verifies the correct Control Rod is selected and in the proper position D Withdraws Control rods by depressing the "W/Draw Rod" pushbutton D When all 4 rods have been moved, verifies that the rods are in the proper position D Depress 'Rod Selct Clear' pushbutton D Plots the power change on the Power/Flow map D Monitors diverse indications of reactor power IAW OP-AD-001 Att G PCOP D Verifies control rods to be withdrawn as directed by RMR IAW OP-AD-338 D IAW OP-AD-300, nulls Manual and Automatic regulars using Man Volt Reg Adjust HC-10002 potentiometer, as required D Maintains Load Set -100 MWe above actual generator loads IAW G0-100-012 by depressing Load Selector 'Decrease' and 'Increase' pushbuttons, as required Examination Material 04/14/2016.
+ 'B' RFP, wait 2 minutes and     D Reports Reactor Power, pressure, and report                             water level The 'B' RFP sounds out-of-      D If directed, lowers 'B' RFP speed IAW balance and it feels like there are higher vibrations        OP-145-006 by taking manual control around the pump.                   and lowering speed D If directed, lowers Core power IAW Role Play OP-164-002 by manually lowering As FUS/NPO contacted for
-LOC28-NRC-01 Event 2 -Control Rod Pattern. Adjustment Instructor Activities Operator Activities Notes ill>>) Instructor Note us D Obtains permission from the Shift Manager prior to commencing reactivity manipulations D May, inform GCC of load change on Unit 1 D Conducts a Crew Update prior to commencing rod withdrawal D Directs Control Rod Withdrawal IAW OP-156-001, RMR, and G0-100-012 D Monitors control rod movement with independent copy of RMR The rod pattern adjustment should be completed before moving to Event 3. This will ensure that the rod-line is raised high enough to challenge the MELLA boundary during the runback for the RFP Trip. Instructor Cue Initiate Event 3 as soon as power has been raised 5% or on the Lead Examiner's direction.
+ 'B' RFP status post-trip,          RRPs speed report                          D Observes AR-101-A12 and reports 'B'
-If the next event is started before the RE explaination for the maneuvering envelope, the crew may decide to only use RRPs. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
+ 'B' RFP is coasting down on the turning gear. I don't       RFP Tripped see anything abnormal.          D Plots position on Power/Flow map D Performs ON-PWR-101 to monitor Role Play OPRMs for instabilities As NPO dispatched to the Lower Relay Room to report      D If directed, inserts control rods IAW the status of APRMS, wait 2        OP-156-001 and OP-AD-338 minutes and report No APRMs indicate any           D Performs AR-104-H03 and AR-103-alarms.                            E06 for 'A' & 'B' RBM and APRM 2 D Directs NPO to investigate APRMs LOC28-NRC-01 Rev 1                             Examination Material                                 04/14/2016. 24
-LOC28-N RC-01 Event 3 & 4 -'B' RFP vibration/
-'B' RFP trip Instructor Activities Operator Activities Notes Booth Operator When power has been raised 5% or at the Lead Examiner's direction, Insert Key 1 to initiate high vibrations on 'B' RFP. {Key[1]} IMF mfFW145007B r:180 f:10 'B' RFP vibration Monitor 'B' RFP vibration in Monitored Parameters.
+LOC28-N RC-01 Event 3 & 4 .- '8' RFP vibration/ '8' RFP trip Instructor Activities                   Operator Activities               Notes PCOP Role Play D IAW AR-101-A16, Checks alarm As WWM contacted for assistance with 'B' RFP            condition and trend on RFPT Vibration vibrations, wait 5 minutes and     XRSH-12728 and observes rise in 'B' report                             RFP vibration Engineering is looking at the vibration data but           D May direct NPO to report conditions at doesn't have a specific            the 'B' RFP recommendation at this time.
-Ensure Event Trigger ETLOC28-NRC01.-B fires when a Recirc LIM2 is actuated by the 'B' RFP trip, to fail the APRM 2 drive flow input from Recirc Loop 'A'. Role Play As FUS/NPO dispatched to 'B' RFP, wait 2 minutes and report The 'B' RFP sounds balance and it feels like there are higher vibrations around the pump. Role Play As FUS/NPO contacted for 'B' RFP status post-trip, report 'B' RFP is coasting down on the turning gear. I don't see anything abnormal.
+D Performs ON-RECIRC-101 and verifies a LIM2 runback occurred Role Play                        D Monitors Main Steam Line Radiation As WWM contacted. for              Monitor, RR-D12-1 R603, and Offgas assistance with APRM flow reference abnormal alarm,          Pretreatment Log Radiation Monitor, wait 5 minutes and report          RR-D12-1R601 l&C reports that Recirc          us Loop 'A' recirc flow transmitters 831-1 N014C         D If time allows, directs lowering 'B' RFP and 1N014D are indicating          speed IAW AR-101-A16 by either
-Role Play As NPO dispatched to the Lower Relay Room to report the status of APRMS, wait 2 minutes and report No APRMs indicate any alarms. LOC28-NRC-01 Rev 1 PCOM D Performs AR-101-A16 for 'B' RFP vibs D Reports Reactor Power, pressure, and water level D If directed, lowers 'B' RFP speed IAW OP-145-006 by taking manual control and lowering speed D If directed, lowers Core power IAW OP-164-002 by manually lowering RRPs speed D Observes AR-101-A12 and reports 'B' RFP Tripped D Plots position on Power/Flow map D Performs ON-PWR-101 to monitor OPRMs for instabilities D If directed, inserts control rods IAW OP-156-001 and OP-AD-338 D Performs AR-104-H03 and AR-103-E06 for 'A' & 'B' RBM and APRM 2 D Directs NPO to investigate APRMs Examination Material 04/14/2016.
+ -20,000 gpm higher than the other two 'A' Recirc           manual control of the 'B' RFP or Loop drive flow                    manual control of the RRPs transmitters.                    D Contacts WWM for assistance with the
-Instructor Activities Role Play As WWM contacted for assistance with 'B' RFP vibrations, wait 5 minutes and report Engineering is looking at the vibration data but doesn't have a specific recommendation at this time. Role Play As WWM contacted.
+                                    'B' RFP D Directs Transient Actions IAW OP-AD-300 when 'B' RFP trips D Directs entry into ON-RECIRC-101 and ON-LVL-101 D May direct control rod insertion to gain margin to MELLA rod-line IAW the Shutdown Control Rod Sequence package and ON-PWR-101 D Notifies Chemistry, RP, and RE of
-for assistance with APRM flow reference abnormal alarm, wait 5 minutes and report l&C reports that Recirc Loop 'A' recirc flow transmitters 831-1 N014C and 1N014D are indicating
+                                    >15% power change in 1 hour IAW G0-100-012 D Contacts WWM for assistance with the APRM flow compare alarm LOC28-NRC-01 Rev 1                              Examination Material                 04/14/2016
--20,000 gpm higher than the other two 'A' Recirc Loop drive flow transmitters.
+* 25
-LOC28-NRC-01 Rev 1 LOC28-N RC-01 Event 3 & 4 .-'8' RFP vibration/
-'8' RFP trip Operator Activities PCOP D IAW AR-101-A16, Checks alarm condition and trend on RFPT Vibration XRSH-12728 and observes rise in 'B' RFP vibration D May direct NPO to report conditions at the 'B' RFP D Performs ON-RECIRC-101 and verifies a LIM2 runback occurred D Monitors Main Steam Line Radiation Monitor, RR-D12-1 R603, and Offgas Pretreatment Log Radiation Monitor, RR-D12-1R601 us D If time allows, directs lowering 'B' RFP speed IAW AR-101-A16 by either manual control of the 'B' RFP or manual control of the RRPs D Contacts WWM for assistance with the 'B' RFP D Directs Transient Actions IAW OP-AD-300 when 'B' RFP trips D Directs entry into ON-RECIRC-101 and ON-LVL-101 D May direct control rod insertion to gain margin to MELLA rod-line IAW the Shutdown Control Rod Sequence package and ON-PWR-101 D Notifies Chemistry, RP, and RE of >15% power change in 1 hour IAW G0-100-012 D Contacts WWM for assistance with the APRM flow compare alarm Examination Material Notes 04/14/2016
+LOC28-NRC-01 Event 3 & 4 - 'B' RFP vibration/ 'B' RFP trip Instructor Activities                 Operator Activities                     Notes us D Enters Tech Specs 3.3.1.1 Condition
-* 25 LOC28-NRC-01 Event 3 & 4 -'B' RFP vibration/
+                                 'A' for B31N014C and B31N014D Recirc Flow Transmitter inoperable in functions 2.b and 2.f AND TRM 3.1.3 Conditions 'A' and 'B' for Function 1.b Instructor Note The scenario may proceed to Event 5 after 1O minutes have elapsed or once the crew has evaluated the power/flow map and made a determination as to whether control rod insertion is required.
-'B' RFP trip Instructor Activities Operator Activities Notes us D Enters Tech Specs 3.3.1.1 Condition
+LOC28-NRC-01 Rev 1                          Examination Material                          04/14/2016. 26
-'A' for B31N014C and B31N014D Recirc Flow Transmitter inoperable in functions 2.b and 2.f AND TRM 3.1.3 Conditions
-'A' and 'B' for Function 1.b Instructor Note The scenario may proceed to Event 5 after 1 O minutes have elapsed or once the crew has evaluated the power/flow map and made a determination as to whether control rod insertion is required.
+LOC28-NRC-01 Event 5 - RBCCW TCV failure Instructor Activities                   Operator Activities                            Notes Booth Operator IAW Event 3 note, Insert KEY 3 to initiate a failure of the RBCCW HX TCV
-LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
+{Key[3]} IMF cmfAV04_TV11028 r:10 f:O             RBCCW HX TCV fails Ensure Event Trigger ETLOC28-NRC01-C fires when RWCU NRHX inlet temperature reaches 145F to activate RWCU F/D inlet high temperature isolation alarm.
-LOC28-NRC-01 Event 5 -RBCCW TCV failure Instructor Activities Operator Activities Notes Booth Operator IAW Event 3 note, Insert KEY 3 to initiate a failure of the RBCCW HX TCV {Key[3]} IMF cmfAV04_TV11028 r:10 f:O RBCCW HX TCV fails Ensure Event Trigger ETLOC28-NRC01-C fires when RWCU NRHX inlet temperature reaches 145F to activate RWCU F/D inlet high temperature isolation alarm. Monitor RRP bearing temperature on Monitored Parameters.
+Monitor RRP bearing temperature on Monitored Parameters. After RWCU isolates, if required to prevent RRP bearing temperatures exceeding 195F, Insert KEY 4. Adjust the severity of malfunction cmfAV04_TV11028 in 1% increments as necessary to slowly raise bearing temperatures toward the 195F limit without going over.
-After RWCU isolates, if required to prevent RRP bearing temperatures exceeding 195F, Insert KEY 4. Adjust the severity of malfunction cmfAV04_TV11028 in 1 % increments as necessary to slowly raise bearing temperatures toward the 195F limit without going over. {Key[4]} IMF cmfAV04_TV11028 d:15 r:30 f:S Ensure Event Trigger ETLOC28-NRC01-D fires when ESW is aligned to the RBCCW HX to complete the field valve alignments.
+{Key[4]} IMF cmfAV04_TV11028 d:15 r:30 f:S Ensure Event Trigger ETLOC28-NRC01-D fires when ESW is aligned to the RBCCW HX to complete the in-field valve alignments.
-Role Play As NPO dispatched to RBCCW, wait 2 minutes The RBCCW HX TCV is almost full closed. Role Play As NPO directed to open the RBCCW HX TCV bypass, 110062, wait 1 minutes The RBCCW bypass valve, 110062, would not move. I do not hear flow noise through the valve. Role Play As NPO directed to support aligning 'A' ESW to 'A' RBCCW HX, when asked to report local valve position IAW OP-114-001 Step 5.13.9b, report HV-11024A 1 and HV-11024A2 are open, HV-11024A3 is closed. Role Play As NPO directed to RWCU filters, wait 2 minutes The RWCU filters are in hold LOC28-NRC-01 Rev 1 PCOM D Reports Reactor power, pressure, and water level PCOP D Performs AR-123-EOS and checks RBCCW HX DSCH temp and controller D Dispatches N PO to RBCCW pump/heat exchanger area D Performs ON-RBCCW-101 to verify RRP temperatures, TCV-11028 operability, Bypass Valve 110062 operability, and swap RBCCW HX to ESW supply IAW OP-111-001 D Aligns ESW to RBCCW HX 'A' IAW OP-111-001 by starting ESW in one loop and depressing the RBCCW HX A SW/ESW SUP HA 11024 pushbutton Examination Material 04/14/2016.
+PCOM Role Play D Reports Reactor power, pressure, and As NPO dispatched to RBCCW, wait 2 minutes              water level The RBCCW HX TCV is            PCOP almost full closed.            D Performs AR-123-EOS and checks Role Play                          RBCCW HX DSCH temp and As NPO directed to open the        controller RBCCW HX TCV bypass,           D Dispatches NPO to RBCCW 110062, wait 1 minutes The RBCCW bypass valve,            pump/heat exchanger area 110062, would not move. I      D Performs ON-RBCCW-101 to verify do not hear flow noise             RRP temperatures, TCV-11028 through the valve.
-Instructor Activities Role Play As NPO directed to close 11046 IAW step 5.13.9c, wait. 1 minute 110046 is closed Role Play As WWM contacted for assistance with RBCCW HX TCV, Wait 5 minutes l&C believes the positioner is getting a close signal from the controller.
+operability, Bypass Valve 110062 Role Play                          operability, and swap RBCCW HX to As NPO directed to support         ESW supply IAW OP-111-001 aligning 'A' ESW to 'A' D Aligns ESW to RBCCW HX 'A' IAW RBCCW HX, when asked to report local valve position        OP-111-001 by starting ESW in one IAW OP-114-001 Step                loop and depressing the RBCCW HX A 5.13.9b, report HV-11024A 1 and HV-                SW/ESW SUP HA 11024 pushbutton 11024A2 are open, HV-11024A3 is closed.
-Additional investigation is required.
+Role Play As NPO directed to RWCU filters, wait 2 minutes The RWCU filters are in hold LOC28-NRC-01 Rev 1                               Examination Material                              04/14/2016. 27
-Instructor Note LOC28-NRC-01 Event 5 -RBCCW TCV failure Operator Activities us D Directs entry into ON-RBCCW-101 D Contacts WWM for assistance with the RBCCWTCV D Directs aligning ESW to the RBCCW HX IAW OP-111-001, Service Water System D Declares ESW loop to be aligned inoperable IAW OP-111-001 and Enters TS 3.7.2 Condition C for 1 ESW subsystem inoperable for reasons other than Condition B Notes
+LOC28-NRC-01 Event 5 - RBCCW TCV failure Instructor Activities                Operator Activities                    Notes us Role Play D Directs entry into ON-RBCCW-101 As NPO directed to close 11046 IAW step 5.13.9c, wait. D Contacts WWM for assistance with the 1 minute                         RBCCWTCV 110046 is closed               D Directs aligning ESW to the RBCCW Role Play                        HX IAW OP-111-001, Service Water As WWM contacted for             System assistance with RBCCW HX       D Declares ESW loop to be aligned TCV, Wait 5 minutes l&C believes the positioner inoperable IAW OP-111-001 and is getting a close signal        Enters TS 3.7.2 Condition C for 1 ESW from the controller.             subsystem inoperable for reasons Additional investigation is required.                        other than Condition B Instructor Note
 * The RBCCW high temperature alarm is received -3 minutes after the TCV malfunction is inserted.
 * A total loss of RBCCW occurs in the next event.
-* Once ESW has been aligned to RBCCW HX 'A', proceed to Event 5 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016
+* Once ESW has been aligned to RBCCW HX 'A', proceed to Event 5 LOC28-NRC-01 Rev 1                           Examination Material                      04/14/2016
-* 28 LOC28-NRC-01 Event 6 -Complete loss of RBCCW/ SCRAM Instructor Activities Operator Activities Notes Booth Operator IAW Event 4 Note, Depress KEY 5 to insert a 20% rupture on the common discharge header of RBCCW {Key(5]} IMF mfRW114001 f:20 RBCCW discharge header rupture Perform first role play after inserting Key 5 Ensure Event Trigger ETLOC28-NRC01-E fires when the mode switch is placed in SHUTDOWN to activate Event Trigger ETLOC28-NRC01-J Role Play As NPO at RBCCW HX, when Key 5 is inserted, contact the control room There is a rupture on the common discharge header of RBCCW. It is too large to quantify.
+* 28
-Role Play As WWM contacted for assistance with RBCCW rupture, acknowledge request. Role Play As NPO requested to isolate the rupture, report The rupture cannot be isolated.
-LOC28-NRC-01 Rev 1 PCOM D If directed, trips 'A' RRP by depressing MG SET A ORV MTR BKR HS-14001 A STOP PB D Inserts a manual scram by placing the Mode Switch to Shutdown D Identifies more than 1 control rod > position 00 D Reports A TWS D Arms and Depresses the manual Scram Pushbuttons D Performs Scram Report PCOP D Performs AR-201-F03 for 'A' RRP by monitoring motor bearing and seal cavity temperatures and trips RRP when seal cavity exceeds 195F D Initiates ARI by arming and depressing ARI pushbuttons and collars during the ATWS us D Before RRP 'A' temperatures exceed 195F, either Trips the 'A' RRP and scrams the reactor on OPRMs or Manually scrams the reactor and trips the 'A' RRP D IAW ON-RBCCW-101, performs a manual scram of the Unit. D Enters E0-000-102 and transitions to E0-000-113 Examination Material 04/14/2016.
+LOC28-NRC-01 Event 6 - Complete loss of RBCCW/ SCRAM Instructor Activities                        Operator Activities                       Notes Booth Operator IAW Event 4 Note, Depress KEY 5 to insert a 20% rupture on the common discharge header of RBCCW
-LOC28-NRC-01 Event 6 -Complete loss of RBCCW/ SCRAM Instructor Activities Operator Activities Notes Instructor Note If the reactor is not scrammed before the recirc pump is tripped, Region 1 of the power/flow map will be entered and the reactor will automatically scram on OPRMs. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
+{Key(5]} IMF mfRW114001 f:20                              RBCCW discharge header rupture Perform first role play after inserting Key 5 Ensure Event Trigger ETLOC28-NRC01-E fires when the mode switch is placed in SHUTDOWN to activate Event Trigger ETLOC28-NRC01-J PCOM Role Play D If directed, trips 'A' RRP by depressing As NPO at RBCCW HX, when Key 5 is inserted,                MG SET A ORV MTR BKR HS-contact the control room               14001 A STOP PB There is a rupture on the          D Inserts a manual scram by placing the common discharge header of RBCCW. It is too large              Mode Switch to Shutdown to quantify.                       D Identifies more than 1 control rod >
-LOC28-NRC-01 Event 7, 8 & 9-Hydraulic-block ATWS Instructor Activities Operator Activities Notes Booth Operator Ensure Event Trigger ETLOC28-NRC01-F(G) fires when the first SLC pump is started, to trip the running pump due to a motor fault after a time delay. Ensure Event Trigger ETLOC28-NRC01-H fires when the CRD PCV, PV-146-F003 is opened to trip the breaker. When directed, Insert KEY 6 to bypass CRD pump suction filter. Monitor sim RF count and report when complete.
+position 00 Role Play As WWM contacted for D Reports A TWS assistance with RBCCW              D Arms and Depresses the manual rupture, acknowledge                   Scram Pushbuttons request.
-{Key[6]} IRF rfRD155028 d:120 f:100 Byp CRD pump suet filter When directed, Insert KEY 7 to close CRD charging water isolation valve 146-F034.
+D Performs Scram Report PCOP Role Play                          D Performs AR-201-F03 for 'A' RRP by As NPO requested to isolate monitoring motor bearing and seal the rupture, report The rupture cannot be                  cavity temperatures and trips RRP isolated.                              when seal cavity exceeds 195F D Initiates ARI by arming and depressing ARI pushbuttons and collars during the ATWS us D Before RRP 'A' temperatures exceed 195F, either Trips the 'A' RRP and scrams the reactor on OPRMs or Manually scrams the reactor and trips the 'A' RRP D IAW ON-RBCCW-101, performs a manual scram of the Unit.
-Monitor sim RF count and report when complete {Key[7]} IRF rfRD 155017 d:120 f:O Close CRD chrg wtr isol F034 Ensure Event Trigger ETLOC28-NRC01-I fires when RPV level falls below -50" to fail Wide range level transmitter 14201A I
+D Enters E0-000-102 and transitions to E0-000-113 LOC28-NRC-01 Rev 1                                Examination Material                           04/14/2016. 29
-* I Critical Task Inject SLC Critical Task
-* Lowers RPV level to <-60" and maintains until E0-000-113 directs otherwise Role Play As NPO dispatched to CRD PCV breaker 18227-024, wait 2 minutes 18227 breaker 24 is tripped on magnetics Role Play If directed to open CRD PCV bypass valve 146-F004, wait 2 minutes CRD PCV bypass valve 146-F004 is stuck closed Role Play As WWM contacted for assistance, acknowledge and take no action PCOM D If requested, reports reactor power > 5% D Performs actions IAW ON-SCRAM-101, Inserts IRMs and SRMS D Trips both RRPs D Verifies HPCI is overridden D Takes manual control of RFPs and valves, as required, to stop and prevent injection until water level lowers to -60" and then starts injecting to control level in band D Ensures only 2 Condensate pumps are running I LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
+LOC28-NRC-01 Event 6 - Complete loss of RBCCW/ SCRAM Instructor Activities                  Operator Activities                          Notes Instructor Note If the reactor is not scrammed before the recirc pump is tripped, Region 1 of the power/flow map will be entered and the reactor will automatically scram on OPRMs.
-Instructor Activities LOC28-NRC-01 Rev 1 LOC28-NRC-01 7, 8 & 9-ATWS Operator Activities PCOM D Injects SBLC IAW OP-153-001 by placing HS-14804 to 'A' or 'B' and then to the other pump when the first fails D Identifies Wide Range Level 'A' instrument channel failure. Maintains with 'B' Level indicator D Uses FW to maintain RPV water level within A TWS level band, initially
+LOC28-NRC-01 Rev 1                          Examination Material                              04/14/2016. 30
--60" to -110" PCOP D Ensures HV-144-F004 RWCU Inlet OB lso Closes D Inhibits ADS IAW OP-183-001 D If directed, Overrides RCIC by manually lowering flow until -2200 RPM D Bypasses MSIV and CIG interlocks IAW OP-184-001 by taking the 5 switches to BYPASS on 1 C645 and 1C644 D Maximizes CRD by starting the standby pump, fully open CRD flow controller in MANUAL, fully open Drive water pressure valve us D Enters E0-000-113 D Directs PCOP to inhibit ADS D Directs PCOM to perform the A TWS HC D Gives PCOM a RPV water level band of -60" to -11 O" Examination Material Notes 04/14/2016
-* 32 Instructor Activities Instructor Note LOC28-NRC-01 Event 7, 8 & 9-Hydraulic-block ATWS Operator Activities us D Directs PCOP to bypass MSIV and CIG interlocks D Directs PCOP to maximize CRD to drift control rods D Directs PCOM to maintain reactor pressure 800-1050 psig using the main turbine D Contacts WWM for assistance with SBLC ES-158-002 actions are in Event 7 A LOC28-NRC-01 Rev 1 Examination Material Notes 04/14/2016.
+LOC28-NRC-01 Event 7, 8 & 9- Hydraulic-block ATWS Instructor Activities                     Operator Activities                        Notes Booth Operator Ensure Event Trigger ETLOC28-NRC01-F(G) fires when the first SLC pump is started, to trip the running pump due to a motor fault after a time delay.
-LOC28-NRC-01 Event 7 A -Control Rod Insertion Instructor Activities Operator Activities Notes Booth When ES-158-002 is requested, Insert KEY 8. Monitor sim SCN count and when complete, perform the first role play and Key 9. {Key[8)} IRF rfDC102129 f:OPEN d:120 {Key[8]} IRF rfDC102103 f:OPEN d:120 ES-158-002 ARI with 2 min TD ES-158-002 ARI with 2 min TD When moving on to Div 1 RPS, Insert KEY 9. Monitor sim RF count and perform second role play when complete.
+Ensure Event Trigger ETLOC28-NRC01-H fires when the CRD PCV, PV-146-F003 is opened to trip the breaker.
-{Key[9]} IRF rfRP158039J:BYPASS d:120 ES-158-002Div1 RPS {Key[9]} IRF rfRP158040 f:B'(PASS d:120 If requested to bypass DIV 2 RPS b.ecause the scram cannot be reset, Insert KEY 10. Monitor sim RF count and when complete perform fourth role-play.
+When directed, Insert KEY 6 to bypass CRD pump suction filter. Monitor sim RF count and report when complete.
-{Key(10]}
+{Key[6]} IRF rfRD155028 d:120 f:100               Byp CRD pump suet filter When directed, Insert KEY 7 to close CRD charging water isolation valve 146-F034. Monitor sim RF count and report when complete
-IRF rfRP158041 f:BYPASS d:120 ES-158-002 Div 2 RPS {Key[10]}
+{Key[7]} IRF rfRD 155017 d:120 f:O                Close CRD chrg wtr isol F034 Ensure Event Trigger ETLOC28-NRC01-I fires when RPV level falls below -50" to fail Wide range level transmitter 14201A I* I       Critical Task Inject SLC I
-IRF rfRP158042 f:BYPASS d:120 IF requested, Insert KEY 11 to reopen CRD charging water isolation valve 146-F034.
+Critical Task
-Monitor sim RF count and report when complete.
+* Role Play Lowers RPV level to <-60" and maintains until E0-000-113 directs otherwise As NPO dispatched to CRD PCOM D If requested, reports reactor power >
-{Key[11]}
+%
-IRF rfRD155017 d:120 f:100 Re-open CRD chrg wtr isol F034 If directed to X-tie CIG and I/A, Wait 2 minutes, Insert KEY 12 to open 126172 and report when complete {Key[12]}
+PCV breaker 18227-024, wait 2 minutes                        D Performs actions IAW ON-SCRAM-18227 breaker 24 is tripped          101, Inserts IRMs and SRMS on magnetics D Trips both RRPs Role Play                        D Verifies HPCI is overridden If directed to open CRD PCV      D Takes manual control of RFPs and bypass valve 146-F004, wait valves, as required, to stop and 2 minutes CRD PCV bypass valve                 prevent injection until water level 146-F004 is stuck closed             lowers to -60" and then starts injecting Role Play                            to control level in band As WWM contacted for             D Ensures only 2 Condensate pumps are assistance, acknowledge and          running take no action LOC28-NRC-01 Rev 1                               Examination Material                            04/14/2016. 31
-IRF rfPC125001 f:OPEN X-Tie CIG and I/A Critical Task Insert Control Rods IAW E0-000-113
-* PCOM Role Play D Performs hard card for driving control As FUS performing ES-158-002 and ARI is bypassed rods ARI has been disabled.
+LOC28-NRC-01 E~ent 7, 8 & 9- Hydraulic~block ATWS Instructor Activities             Operator Activities             Notes PCOM D Injects SBLC IAW OP-153-001 by placing HS-14804 to 'A' or 'B' and then to the other pump when the first fails D Identifies Wide Range Level 'A' instrument channel failure. Maintains with 'B' Level indicator D Uses FW to maintain RPV water level within ATWS level band, initially -60" to
-D Dispatch NPO to close charging water Proceeding to RPS Div 1. isolation valve 146F034 to attempt to Role Play restore drive water pressure As FUS performing ES-158-D Opens 146F034 when rods will not 002 and Div 1 RPS is insert bypassed D Resets Scram when directed RPS Div 1 has been bypassed, the scram can D Resets rod drift alarm by depressing be reset at this time. Let ROD DRIFT RESET pushbutton me know if the scram cannot be reset. D Reports when SDV hi-hi level alarm AR-103( 4 )-F02 clears LOC28-NRC-01 Rev 1 Examination Material 04/14/2016.
+                            -110" PCOP D Ensures HV-144-F004 RWCU Inlet OB lso Closes D Inhibits ADS IAW OP-183-001 D If directed, Overrides RCIC by manually lowering flow until -2200 RPM D Bypasses MSIV and CIG interlocks IAW OP-184-001 by taking the 5 switches to BYPASS on 1C645 and 1C644 D Maximizes CRD by starting the standby pump, fully open CRD flow controller in MANUAL, fully open Drive water pressure valve us D Enters E0-000-113 D Directs PCOP to inhibit ADS D Directs PCOM to perform the A TWS HC D Gives PCOM a RPV water level band of -60" to -11 O" LOC28-NRC-01 Rev 1                     Examination Material                 04/14/2016
-LOC28-NRC-01 Event 7 A -Control Rod Insertion Instructor Activities Operator Activities Notes PCOM Role Play D When directed, inserts a manual scram As WWM contacted for assistance, acknowledge D Observes control rod motion by AR-request 104-H05, OD?, and 4-rod display D Resets the scram when directed a Role Play second time As FUS performing ES-158-PCOP 002 and Div 2 RPS is D Directs NPO to re-open charging water bypassed isolation valve 146F034 when scram is RPS Div 2 has been bypassed, the scram may reset be reset at this time, ES-us 158-002 section 5.3 is D Directs PCO to manually drive control complete rods D Directs FUS to perform ES-158-002 to defeat ARI and bypass RPS trips D Directs PCO to ensure charging water isolation valve 146F034 is open when the scram is reset D Directs PCOM to insert a manual scram when the SDV is drained D Directs the PCOM to reset the scram after the first attempt fails to fully insert all the control rods Critical Parameter The US should give a Critical Parameter to the PCOM to monitor SDV hi-hi level alarm AR-103(4)-F02 and inform the US when the alarm clears. Instructor Note * ** This scenario will terminate prior to all the control rods being inserted.
+* 32
-The scenario should not be terminated until the scram has been reset twice . The charging water isolation valve 146F034 must be open to be able to have an effective scram. If the student has closed it and does not reopen the valve, they may not be able to clear the alarms. LOC28-NRC-01 Rev 1 Examination Material 04/14/2016
-* 35 LOC28-NRC-01 Event 10 -RFP Trip Instructor Activities Operator Activities Notes Booth Operator Ensure Event Trigger ETLOC28-NRC01-J fires when the scram is reset.
+LOC28-NRC-01 Event 7, 8 & 9- Hydraulic-block ATWS Instructor Activities                 Operator Activities          Notes us D Directs PCOP to bypass MSIV and CIG interlocks D Directs PCOP to maximize CRD to drift control rods D Directs PCOM to maintain reactor pressure 800-1050 psig using the main turbine D Contacts WWM for assistance with SBLC Instructor Note ES-158-002 actions are in Event 7A LOC28-NRC-01 Rev 1                          Examination Material             04/14/2016. 33
-Trips the 'A' RFP after a time delay. Role Play As NPO dispatched to 'A' RFP, wait 2 minutes 'A' RFP is coasting down. I don't see any indication of why it tripped. Role Play As WWM contacted for assistance, acknowledge request PCOM D Observes and reports AR-101-A10 for 'A' RFP trip D Places the standby RFP in service by opening the HV-10603C valve, Manually raising speed on the 'C' RFP until level is steady, and placing 'C' RFP and valves in automatic PCOP D If directed, uses RCIC to restore level until a RFP is restored by raising speed on the speed controller until the desired injection rate is established us D Directs PCO to place standby RFP service IAW OP-145-005 D Directs PCO to maintain RPV water level -60" to -110" using RCIC until Feedwater is restored D May direct using RCIC as the sole injection source if the plant can support D May direct RHR placed in Suppression Pool Cooling Instructor Activity -Termination The scenario may be terminated when RPV water level is stable in the ATWS band, the 'A' RFP has tripped, and the Scram has been reset twice OR at the lead evaluator's discretion.
-LOC28-NRC-01 Rev 1 Examination Material 04/14/2016
+LOC28-NRC-01 Event 7A - Control Rod Insertion Instructor Activities                    Operator Activities                           Notes Booth Op~rator When ES-158-002 is requested, Insert KEY 8. Monitor sim SCN count and when complete, perform the first role play and Key 9.
-* 36 UNIT SUPERVISOR TURNOVER SHEET UNIT 1 SHIFT 1900 to 0700 Start End MODE POWER LEVEL 95 % -------MODE t"o-/dd/yy Date SHIFT 0700 to Start POWER LEVEL 1900 End -------% GENERATOR OUTPUT 1270 MWe GENERATOR OUTPUT MWe CASK STORAGE GATE INSTALLED:
+{Key[8)} IRF rfDC102129 f:OPEN d:120              ES-158-002 ARI with 2 min TD
-YES/NO CASK STORAGE GATE INSTALLED:
+{Key[8]} IRF rfDC102103 f:OPEN d:120              ES-158-002 ARI with 2 min TD When moving on to Div 1 RPS, Insert KEY 9. Monitor sim RF count and perform second role play when complete.
-YES/NO REMARKS: 1) -95% power for control rod pattern adjustment, 500 days on-line 2) HPCI in day 2 of 4-day system outage window for steam-side maintenance
+{Key[9]} IRF rfRP158039J:BYPASS d:120             ES-158-002Div1 RPS
-: 3) LCO 3.5.1 entered for HPCI outage 4) Diesel Generator E substituted for Diesel Generator A for a SOW 5) RFP lube oil conditioner was swapped from RFP A reservoir to B reservoir last shift 6) Test 'A' RFP main lube oil pump 'B' and swap to main lube oil pump 'B' for PMT. Emergency pump is not required to be tested. 7) Perform control rod pattern adjustment per Reactivity Manipulation Package. Contact RxEng when complete for evaluation.
+{Key[9]} IRF rfRP158040 f:B'(PASS d:120 If requested to bypass DIV 2 RPS b.ecause the scram cannot be reset, Insert KEY 10. Monitor sim RF count and when complete perform fourth role-play.
-: 8) 9) 10 11) 12 13 14) 15) COMMON: 1) Unit 2 at rated power 2) Severe thunderstorm watch is in effect for Luzerne County for the next 12 hours 3) 4) 5 6) 7) 8 9) FORM OP-AD-003-7, DUPLEX Page 1 of 2 (Electronic Form) Examination Material NRC SCN 1
+{Key(10]} IRF rfRP158041 f:BYPASS d:120           ES-158-002 Div 2 RPS
-) OFFGOING UNIT SUPERVISOR CHECKLIST:
+{Key[10]} IRF rfRP158042 f:BYPASS d:120 IF requested, Insert KEY 11 to reopen CRD charging water isolation valve 146-F034. Monitor sim RF count and report when complete.
-NRC CODE PRIOR TO 0800 FOXTROT DELTA BRAVO OSCAR NRC CODE AFTER 0800 FOXTROT UNIFORM HOTEL ROMEO 1900-0700-0700 1900 0700 1900 --POST RELIEF 0700 1900 1. Evolutions in progress and items to be completed during next shift, as noted in remarks, have been discussed with oncoming Unit Supervisor (including special evolutions, i.e. SICT/E, OPDRVs, etc.). 2. Problems encountered during past shift and abnormal plant conditions, as noted in remarks, have been discussed with oncoming Unit Supervisor.
+{Key[11]} IRF rfRD155017 d:120 f:100              Re-open CRD chrg wtr isol F034 If directed to X-tie CIG and I/A, Wait 2 minutes, Insert KEY 12 to open 126172 and report when complete
+{Key[12]} IRF rfPC125001 f:OPEN                   X-Tie CIG and I/A Critical Task
+* Role Play Insert Control Rods IAW E0-000-113 As FUS performing ES-158-PCOM D Performs hard card for driving control rods 002 and ARI is bypassed ARI has been disabled.             D Dispatch NPO to close charging water Proceeding to RPS Div 1.             isolation valve 146F034 to attempt to Role Play                            restore drive water pressure As FUS performing ES-158-          D Opens 146F034 when rods will not 002 and Div 1 RPS is                 insert bypassed RPS Div 1 has been                 D Resets Scram when directed bypassed, the scram can            D Resets rod drift alarm by depressing be reset at this time. Let           ROD DRIFT RESET pushbutton me know if the scram cannot be reset.                   D Reports when SDV hi-hi level alarm AR-103( 4 )-F02 clears LOC28-NRC-01 Rev 1                               Examination Material                              04/14/2016. 34
+LOC28-NRC-01 Event 7A - Control Rod Insertion Instructor Activities                   Operator Activities                         Notes PCOM Role Play D When directed, inserts a manual scram As WWM contacted for assistance, acknowledge        D Observes control rod motion by AR-request                           104-H05, OD?, and 4-rod display D Resets the scram when directed a Role Play                         second time As FUS performing ES-158-      PCOP 002 and Div 2 RPS is           D Directs NPO to re-open charging water bypassed RPS Div 2 has been                isolation valve 146F034 when scram is bypassed, the scram may           reset be reset at this time, ES-     us 158-002 section 5.3 is complete                       D Directs PCO to manually drive control rods D Directs FUS to perform ES-158-002 to defeat ARI and bypass RPS trips D Directs PCO to ensure charging water isolation valve 146F034 is open when the scram is reset D Directs PCOM to insert a manual scram when the SDV is drained D Directs the PCOM to reset the scram after the first attempt fails to fully insert all the control rods Critical Parameter The US should give a Critical Parameter to the PCOM to monitor SDV hi-hi level alarm AR-103(4)-F02 and inform the US when the alarm clears.
+Instructor Note
+* This scenario will terminate prior to all the control rods being inserted. The scenario
+ **          should not be terminated until the scram has been reset twice .
+The charging water isolation valve 146F034 must be open to be able to have an effective scram. If the student has closed it and does not reopen the valve, they may not be able to clear the alarms.
+LOC28-NRC-01 Rev 1                             Examination Material                           04/14/2016
+* 35
+LOC28-NRC-01 Event 10 - RFP Trip Instructor Activities                   Operator Activities                        Notes Booth Operator Ensure Event Trigger ETLOC28-NRC01-J fires when the scram is reset. Trips the 'A' RFP after a time delay.
+PCOM Role Play D Observes and reports AR-101-A10 for As NPO dispatched to 'A' RFP, wait 2 minutes               'A' RFP trip
+ 'A' RFP is coasting down. I     D Places the standby RFP in service by don't see any indication of       opening the HV-10603C valve, why it tripped.
+Manually raising speed on the 'C' RFP Role Play                         until level is steady, and placing 'C' As WWM contacted for              RFP and valves in automatic assistance, acknowledge PCOP request D If directed, uses RCIC to restore level until a RFP is restored by raising speed on the speed controller until the desired injection rate is established us D Directs PCO to place standby RFP in-service IAW OP-145-005 D Directs PCO to maintain RPV water level -60" to -110" using RCIC until Feedwater is restored D May direct using RCIC as the sole injection source if the plant can support D May direct RHR placed in Suppression Pool Cooling Instructor Activity - Termination
+  -~     The scenario may be terminated when RPV water level is stable in the ATWS band, the 'A' RFP has tripped, and the Scram has been reset twice OR at the lead evaluator's discretion.
+LOC28-NRC-01 Rev 1                             Examination Material                              04/14/2016
+* 36
+UNIT SUPERVISOR TURNOVER SHEET UNIT            1                   t"o-/dd/yy Date SHIFT    1900     to   0700                                     SHIFT   0700   to  1900 Start        End                                               Start     End MODE                                                     MODE POWER LEVEL
+                  - - - - -     %                   POWER LEVEL
+                                                                          -------           %
+GENERATOR OUTPUT        1270         MWe                 GENERATOR OUTPUT                   MWe CASK STORAGE GATE INSTALLED: YES/NO                      CASK STORAGE GATE INSTALLED: YES/NO REMARKS:
+: 1)    -95% power for control rod pattern adjustment, 500 days on-line
+: 2)    HPCI in day 2 of 4-day system outage window for steam-side maintenance
+: 3)    LCO 3.5.1 entered for HPCI outage
+: 4)    Diesel Generator E substituted for Diesel Generator A for a SOW
+: 5)    RFP lube oil conditioner was swapped from RFP A reservoir to B reservoir last shift
+: 6)    Test 'A' RFP main lube oil pump 'B' and swap to main lube oil pump 'B' for PMT.
+Emergency pump is not required to be tested.
+: 7)    Perform control rod pattern adjustment per Reactivity Manipulation Package. Contact RxEng when complete for evaluation.
+) 9)
+11) 12 13 14) 15)
+COMMON:
+: 1)    Unit 2 at rated power
+: 2)    Severe thunderstorm watch is in effect for Luzerne County for the next 12 hours 3) 4)
+6) 7)
+9)
+FORM OP-AD-003-7, DUPLEX Page 1 of 2 (Electronic Form)
+Examination Material                         NRC SCN 1
+OFFGOING UNIT SUPERVISOR CHECKLIST:
+NRC CODE PRIOR TO 0800      FOXTROT               DELTA                 BRAVO                OSCAR NRC CODE AFTER 0800         FOXTROT               UNIFORM               HOTEL                ROMEO 1900- 0700-0700   1900
+: 1. Evolutions in progress and items to be completed during next shift, as noted in remarks, have been discussed with oncoming Unit Supervisor (including special evolutions, i.e. SICT/E, OPDRVs, etc.).
+: 2. Problems encountered during past shift and abnormal plant conditions, as noted in remarks, have been discussed with oncoming Unit Supervisor.
 : 3. Information in SOMS Log is complete and discussed with oncoming Unit Supervisor.
 : 4. As applicable, turnover plastic Security Badge cover and CRS Monitor function to oncoming Unit Supervisor.
 Offgoing Unit Supervisor ONCOMING UNIT SUPERVISOR CHECKLIST:
+   1900
+   -     -
 : 1. LCOfTRO Log reviewed.
-: 2. SOMS Log reviewed for entries made in past 24 hours. 3. Report any changes to license or medical status PER NDAP-QA-0723.
+)                   2. SOMS Log reviewed for entries made in past 24 hours.
--0700 Oncoming Qualified Unit Supervisor
+: 3. Report any changes to license or medical status PER NDAP-QA-0723.
-: 1. Walk down Control Room panels with Unit Responsible PCO. 2. CRC Book reviewed and Reactivity Brief performed with PCO. 3. Completed System Status Operable audit for open PMT this shift. 4. From the OPS Web page, Review OPS Aggregate Index for Challenges, Work Arounds, and Deficiencies Reports for impact on scheduled work activities and compensatory actions. (2 o) Oncoming Unit Supervisor FORM OP-AD-003-7, DUPLEX Page 2 of 2 (Electronic Form) Examination Material NRC SCN 1 SUSQUEHANNA NUCLEAR, LLC OPERATIONS TRAINING PROGRAM SCENARIO EXAMINATION GUIDE REACTOR SHUTDOWN/
+- 0700 Oncoming Qualified Unit Supervisor POST RELIEF 0700   1900
-FW HEATER TUBE LEAK/ ESS BUS LOCKOUT/ ATWS/ FUEL FAILURE/ RCIC STEAM LEAK/ EMERGENCY DEPRESSURIZATION SCN# LOC28-NRC03 Revision 1 4/21/2016 Examination Material LOC28-NRC03 Lesson Information Title Reactor Shutdown/
+: 1. Walk down Control Room panels with Unit Responsible PCO.
-FW Heater Tube Leak/ ESS Bus Lockout/ A TWS/ Fuel Failure/ RCIC Steam Leak/ Emergency Depressurization Vision ID Accredited
+: 2. CRC Book reviewed and Reactivity Brief performed with PCO.
-*YES D NO Training ID Revision j 1 Date j 4/21/2016 Prerequisites Teaching Time 75 minutes Approval CBT Approval 1 N/A Date N/A Preparer Date Review (lnstructor/SME)
+: 3. Completed System Status Operable audit for open PMT this shift.
-Date Nuclear Engineering 1 N/A Date N/A Training Supervision Date Line Management Date 1 If required, otherwise N/A This simulator scenario has been reviewed and satisfies management expectations for inclusion of OE, Department Fundamentals and HuP, error-reduction techniques and safety standards.
+: 4. From the OPS Web page, Review OPS Aggregate Index for Challenges, Work Arounds, and Deficiencies Reports for impact on scheduled work activities and compensatory actions. (2o)
-Specific applications and/or opportunities for reinforcement of management expectations are noted in the scenario guide or Attachment(s) where applicable.
+Oncoming Unit Supervisor FORM OP-AD-003-7, DUPLEX Page 2 of 2 (Electronic Form)
-Copyrighted by Nuclear Training Group, SUSQUEHANNA NUCLEAR, LLC, 2016. All rights reserved, no part of this training material may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, recording or otherwise, without the prior permission of the Nuclear Training Group. LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+Examination Material                                   NRC SCN 1
-LOC28-NRC03 Revision History Revision Date Comments 0 06/23/2014 New Scenario Placed in new template.
-Changed the setup conditions.
+SUSQUEHANNA NUCLEAR, LLC OPERATIONS TRAINING PROGRAM SCENARIO EXAMINATION GUIDE REACTOR SHUTDOWN/ FW HEATER TUBE LEAK/ ESS BUS LOCKOUT/ ATWS/ FUEL FAILURE/ RCIC STEAM LEAK/
-Changed Event 8 to be a HPCI issue. Changed Event 9 to be triggered off of max safe 1 04/21/2016 Temperature.
+EMERGENCY DEPRESSURIZATION SCN# LOC28-NRC03 Revision 1 4/21/2016 Examination Material
-Removed an unanticipated start of an EOG. Changed the leak sizes to allow for operator actions. Adjusted the sim files to remove the CRD rad release. Swapped event 1 and 2. LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
-LOC28-NRC03 Table of Contents Scenario Overview ................................................................................................................................
+LOC28-NRC03 Lesson Information Title                 Reactor Shutdown/ FW Heater Tube Leak/ ESS Bus Lockout/ A TWS/ Fuel Failure/ RCIC Steam Leak/ Emergency Depressurization Vision ID                                                        Accredited     *YES           D  NO Training ID                                           Revision    j 1            Date  j 4/21/2016 Prerequisites Teaching Time         75 minutes Approval CBT Approval 1              N/A                                              Date       N/A Preparer                                                                     Date Review (lnstructor/SME)                                                      Date Nuclear Engineering 1       N/A                                              Date       N/A Training Supervision                                                          Date Line Management                                                              Date 1
-Objectives
+If required, otherwise N/A This simulator scenario has been reviewed and satisfies management expectations for inclusion of OE, Department Fundamentals and HuP, error-reduction techniques and safety standards. Specific applications and/or opportunities for reinforcement of management expectations are noted in the scenario guide or Attachment(s) where applicable.
-.............................................................................................................................................
+Copyrighted by Nuclear Training Group, SUSQUEHANNA NUCLEAR, LLC, 2016. All rights reserved, no part of this training material may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, recording or otherwise, without the prior permission of the Nuclear Training Group.
-A. Terminal Objective
+LOC28-NRC03 Rev 1                             Examination Material                               4/21/2016. 2
-................................................................................................................
-8. Generic Performance Objectives
+LOC28-NRC03 Revision History Revision           Date                                Comments 0            06/23/2014                            New Scenario Placed in new template.
-...........................................................................................
+Changed the setup conditions. Changed Event 8 to be a HPCI issue. Changed Event 9 to be triggered off of max safe 1            04/21/2016   Temperature. Removed an unanticipated start of an EOG.
-C. Simulator Performance Objectives
+Changed the leak sizes to allow for operator actions. Adjusted the sim files to remove the CRD rad release. Swapped event 1 and 2.
-........................................................................................
+LOC28-NRC03 Rev 1                  Examination Material                             4/21/2016. 3
-D. Task List. ...............................................................................................................................
-Scenario Attributes
+LOC28-NRC03 Table of Contents Scenario Overview................................................................................................................................5 Objectives .............................................................................................................................................6 A. Terminal Objective ................................................................................................................6
-.............................................................................................................................
+: 8. Generic Performance Objectives ...........................................................................................6 C. Simulator Performance Objectives ........................................................................................ 7 D. Task List. ...............................................................................................................................9 Scenario Attributes .............................................................................................................................11 A. Critical Tasks ....................................................................................................................... 11 B. Scenario Malfunctions ......................................................................................................... 12 C. Abnormal Events and Major Transients ............................................................................... 12 D. EOP and EOP Contingencies Used .................................................................................... 13 E. Technical Specifications ...................................................................................................... 13 References ..........................................................................................................................................14 Setup Instructions ..............................................................................................................................15 A. Required Materials .............................................................................................................. 15
-A. Critical Tasks .......................................................................................................................
+: 8. Simulator Initialization ......................................................................................................... 15 C. Simulator Preparation .......................................................................................................... 16 D. Document Training and Performance Feedback ................................................................. 16 E. Scenario Execution ............................................................................................................. 16 F. Simulator Files .................................................................................................................... 16 Event 1 - Test BPV #3 ........................................................................................................................19 Event 2- Insert Control Rods ............................................................................................................20 Event 3- FW 2C tube leak .................................................................................................................22 Event 4- ESS bus 1C lockout ...........................................................................................................24 Event 5- Electrical ATWS ..................................................................................................................25 Event 6 - RCIC injection fails ............................................................................................................25 Event 7 - Fuel failure with high MSL rads ........................................................................................27 Event 8 - HPCI steam leak .................................................................................................................28 Event 9- ED on 2 max safe temp ......................................................................................................30 LOC28-NRC03 Rev 1                                            Examination Material                                                          4/21/2016. 4
-B. Scenario Malfunctions
-.........................................................................................................
+LOC28-NRC03 Scenario Overview The scenario begins with Unit 1 shutting down for an unplanned maintenance outage to identify and repair a small RCS leak in the Drywell, 300 days into the operating cycle. Unidentified OW leakage is steady at approximately 0.5 gpm. Reactor power is 33 percent with RFP A in-service in Flow Control Mode. HPCI is in day 2 of a 4-day unplanned maintenance window. The RFP lube oil conditioner is being placed on the RFP B reservoir after being removed from the RFP A reservoir last shift in preparation for a RFP A main lube oil pump test. Control rods 42-15 and 46-19 were declared slow during the last scram time test.
-C. Abnormal Events and Major Transients
+The first task for the crew is to cycle Main Turbine Bypass valve #3 per S0-182-001 to demonstrate functionality of the valve prior to scram. The crew will then insert control rods to lower power to approximately 30 percent.
-...............................................................................
+When the reactivity maneuver has been completed, a tube leak will develop on the 2C Feedwater heater. The leak will initially be within the capability of the dump valve, but will continue to degrade until a heater isolation on high-high level occurs. The crew will respond to the isolation by isolating the extraction steam supplies to the 3C, 4C and SC heaters and other inputs in accordance with off-normal procedures, and verify the high FW heater levels clear within 15 minutes or trip the main turbine.
-D. EOP and EOP Contingencies Used ....................................................................................
+Once the crew has completed off-normal procedures for the Feedwater heater isolation, Diesel Generator C will spuriously start. ESW Pump C will fail to automatically start and must be manually started to provide cooling to the DG. When the breaker for ESW Pump C closes, a fault in the breaker will result in an ESS Bus 1C lockout. The crew will align Instrument Air to Containment Instrument Gas to maintain AOVs in the Drywell functional. The leak in the Drywell will degrade coincident with the bus lockout, resulting in a more rapid rise in Drywell temperature and pressure. The crew should complete activities associated with the loss of ESS Bus 1C and insert a manual scram before an automatic scram on high Drywell pressure is received.
-E. Technical Specifications
+When the reactor is scrammed RPS will fail to de-energize, resulting in an electrical ATWS. When ARI is initiated, control rods will slowly drift in when ARI is initiated, resulting in significant fuel cladding failure. The Scram Discharge Volume drains will be failed open, allowing the spread of highly radioactive coolant into the CRD HCU area. This will result in radiation levels rapidly exceeding the E0-104 maximum safe values. The magnitude of the fuel failure will also result in MSL high radiation signals that will require the MSIVs to be closed.
-......................................................................................................
+RPV level and pressure control will be with RCIC and SRVs. The RCIC injection valve will fail to automatically open and must be manually opened. Reactor pressure may be lowered to 500-600 psig to allow Condensate to be used for reactor level control.
-References
+Once RCIC has been initiated and the CRD HCU area radiation levels have exceeded the max safe value a steam leak will develop in the RCIC room. The isolation logic will fail and both isolation valves will fail to close automatically or manually. RCIC room radiation levels will quickly rise to maximum safe levels. With radiation levels in two areas above max safe, and an unisolable primary system leak outside the primary containment, E0-104 requires Emergency Depressurization. As reactor pressure lowers, the RCIC outboard isolation valve will stroke fully closed.
-..........................................................................................................................................
+This scenario may be terminated when RPV water level has been stabilized and actions are being taken to place RHR in Suppression Pool cooling OR at the direction of the Chief Examiner.
-Setup Instructions
+LOC28-NRC03 Rev 1                                 Examination Material                                   4/21/2016. 5
-..............................................................................................................................
-A. Required Materials
+LOC28-NRC03 Objectives Mastery of the training content shall be demonstrated by individual and/or crew performance evaluation as specified in this training material and the applicable training program description, in accordance with training procedures.
-..............................................................................................................
-8. Simulator Initialization
-.........................................................................................................
-C. Simulator Preparation
-..........................................................................................................
-D. Document Training and Performance Feedback .................................................................
-E. Scenario Execution
-.............................................................................................................
-F. Simulator Files ....................................................................................................................
-Event 1 -Test BPV #3 ........................................................................................................................
-Event 2-Insert Control Rods ............................................................................................................
-Event 3-FW 2C tube leak .................................................................................................................
-Event 4-ESS bus 1C lockout ...........................................................................................................
-Event 5-Electrical ATWS ..................................................................................................................
-Event 6 -RCIC injection fails ............................................................................................................
-Event 7 -Fuel failure with high MSL rads ........................................................................................
-Event 8 -HPCI steam leak .................................................................................................................
-Event 9-ED on 2 max safe temp ......................................................................................................
-LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
-LOC28-NRC03 Scenario Overview The scenario begins with Unit 1 shutting down for an unplanned maintenance outage to identify and repair a small RCS leak in the Drywell, 300 days into the operating cycle. Unidentified OW leakage is steady at approximately 0.5 gpm. Reactor power is 33 percent with RFP A in-service in Flow Control Mode. HPCI is in day 2 of a 4-day unplanned maintenance window. The RFP lube oil conditioner is being placed on the RFP B reservoir after being removed from the RFP A reservoir last shift in preparation for a RFP A main lube oil pump test. Control rods 42-15 and 46-19 were declared slow during the last scram time test. The first task for the crew is to cycle Main Turbine Bypass valve #3 per S0-182-001 to demonstrate functionality of the valve prior to scram. The crew will then insert control rods to lower power to approximately 30 percent. When the reactivity maneuver has been completed, a tube leak will develop on the 2C Feedwater heater. The leak will initially be within the capability of the dump valve, but will continue to degrade until a heater isolation on high-high level occurs. The crew will respond to the isolation by isolating the extraction steam supplies to the 3C, 4C and SC heaters and other inputs in accordance with off-normal procedures, and verify the high FW heater levels clear within 15 minutes or trip the main turbine. Once the crew has completed off-normal procedures for the Feedwater heater isolation, Diesel Generator C will spuriously start. ESW Pump C will fail to automatically start and must be manually started to provide cooling to the DG. When the breaker for ESW Pump C closes, a fault in the breaker will result in an ESS Bus 1 C lockout. The crew will align Instrument Air to Containment Instrument Gas to maintain AOVs in the Drywell functional.
-The leak in the Drywell will degrade coincident with the bus lockout, resulting in a more rapid rise in Drywell temperature and pressure.
-The crew should complete activities associated with the loss of ESS Bus 1 C and insert a manual scram before an automatic scram on high Drywell pressure is received.
-When the reactor is scrammed RPS will fail to de-energize, resulting in an electrical A TWS. When ARI is initiated, control rods will slowly drift in when ARI is initiated, resulting in significant fuel cladding failure. The Scram Discharge Volume drains will be failed open, allowing the spread of highly radioactive coolant into the CRD HCU area. This will result in radiation levels rapidly exceeding the E0-104 maximum safe values. The magnitude of the fuel failure will also result in MSL high radiation signals that will require the MSIVs to be closed. RPV level and pressure control will be with RCIC and SRVs. The RCIC injection valve will fail to automatically open and must be manually opened. Reactor pressure may be lowered to 500-600 psig to allow Condensate to be used for reactor level control. Once RCIC has been initiated and the CRD HCU area radiation levels have exceeded the max safe value a steam leak will develop in the RCIC room. The isolation logic will fail and both isolation valves will fail to close automatically or manually.
-RCIC room radiation levels will quickly rise to maximum safe levels. With radiation levels in two areas above max safe, and an unisolable primary system leak outside the primary containment, E0-104 requires Emergency Depressurization.
-As reactor pressure lowers, the RCIC outboard isolation valve will stroke fully closed. This scenario may be terminated when RPV water level has been stabilized and actions are being taken to place RHR in Suppression Pool cooling OR at the direction of the Chief Examiner.
-LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
-LOC28-NRC03 Objectives Mastery of the training content shall be demonstrated by individual and/or crew performance evaluation as specified in this training material and the applicable training program description, in accordance with training procedures.
 A. Terminal Objective Perform all system operations required to maintain the plant operating safely, or place the plant in a safe condition if a plant shutdown is required During the specified mode of plant I system operation Without error and in accordance with site procedures and management expectations B. Generic Performance Objectives
-: 1. For all activities, exhibit use of the Human Performance Tools, demonstrating the ability to: Use HU tools to effectively control the plant during normal, abnormal, and emergency conditions Use of HU tools will be observable per the standards in HU-AD-003 (SRO) Take every opportunity to coach the team when HU standards are not being met and provide feedback to the team when the HU standards are being met 2. For all activities, exhibit proper use of procedures by: Applying the correct procedure to operate equipment and respond to abnormalities Ensuring procedures are detailed enough to allow precise control of plant evolutions.
+: 1. For all activities, exhibit use of the Human Performance Tools, demonstrating the ability to:
-Demonstrating the ability to: Apply the correct procedure to the situation Use place keeping for accurate implementation Identify any and all areas for procedure improvement Take ownership of and complete the improvement, whenever an area for procedure improvement is identified
+Use HU tools to effectively control the plant during normal, abnormal, and emergency conditions Use of HU tools will be observable per the standards in HU-AD-003 (SRO) Take every opportunity to coach the team when HU standards are not being met and provide feedback to the team when the HU standards are being met
-: 3. Base actions and decisions with a bias toward conservative, safe operation of the plant, demonstrating the ability to: Assure all plant evolutions and work are assessed for Radiological Safety, Industrial Safety, Nuclear Safety, Environmental Safety, or Corporate Safety Once a risk is determined, take appropriate actions to mitigate or minimize risk Request assistance for any activity which requires additional planning, special precautions, and management oversight to adequately manage the risks (SRO) Champion activities that are biased conservatively LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+: 2. For all activities, exhibit proper use of procedures by:
-LOC28-NRC03
+Applying the correct procedure to operate equipment and respond to abnormalities Ensuring procedures are detailed enough to allow precise control of plant evolutions.
-: 4. Demonstrate complete understanding of plant design and system interrelationships, demonstrating the ability to: Work effectively as a team to interpret plant indications and determine an effective response Understand the bases for, and the plant response to, actions being taken 5. Maintain continuous awareness of critical parameters, demonstrating the ability to: Validate parameters by observing multiple independent indications Relay parameter values with value, units, and trend; and include action being taken for an abnormal value or trend Notify supervision of any change to critical parameters (SRO) Assure critical parameters for operational conditions are understood by the team 6. Operate plant systems and equipment within design and operational limits, maintaining relevant parameters within assigned operating bands, demonstrating the ability to: Anticipate the impact of component operation prior to its operation, and then verify that the expected effects occur during and following the operation Take manual actions (in accordance with procedure direction) when automatic actions do not occur Take prompt action to adjust system operating controls before assigned operating bands are exceeded Make reactivity and mode changes as directed by detailed operating procedures and approved reactivity plans C. Simulator Performance Objectives
+Demonstrating the ability to:
+Apply the correct procedure to the situation Use place keeping for accurate implementation Identify any and all areas for procedure improvement Take ownership of and complete the improvement, whenever an area for procedure improvement is identified
+: 3. Base actions and decisions with a bias toward conservative, safe operation of the plant, demonstrating the ability to:
+Assure all plant evolutions and work are assessed for Radiological Safety, Industrial Safety, Nuclear Safety, Environmental Safety, or Corporate Safety Once a risk is determined, take appropriate actions to mitigate or minimize risk Request assistance for any activity which requires additional planning, special precautions, and management oversight to adequately manage the risks (SRO) Champion activities that are biased conservatively LOC28-NRC03 Rev 1                                Examination Material                             4/21/2016. 6
+LOC28-NRC03
+: 4. Demonstrate complete understanding of plant design and system interrelationships, demonstrating the ability to:
+Work effectively as a team to interpret plant indications and determine an effective response Understand the bases for, and the plant response to, actions being taken
+: 5. Maintain continuous awareness of critical parameters, demonstrating the ability to:
+Validate parameters by observing multiple independent indications Relay parameter values with value, units, and trend; and include action being taken for an abnormal value or trend Notify supervision of any change to critical parameters (SRO) Assure critical parameters for operational conditions are understood by the team
+: 6. Operate plant systems and equipment within design and operational limits, maintaining relevant parameters within assigned operating bands, demonstrating the ability to:
+Anticipate the impact of component operation prior to its operation, and then verify that the expected effects occur during and following the operation Take manual actions (in accordance with procedure direction) when automatic actions do not occur Take prompt action to adjust system operating controls before assigned operating bands are exceeded Make reactivity and mode changes as directed by detailed operating procedures and approved reactivity plans C. Simulator Performance Objectives
 : 1. Plant Shutdown Activities During plant operation in a shutdown condition Perform the activities associated with plant pre-start or shutdown procedures to ensure safe operation of station equipment including the operation of the controls associated with plant equipment that could affect reactivity
-: 2. Operational Actions and Annunciator Response Correctly identify plant annunciators and indications and perform appropriate remedial actions 3. System Operation, Controls and Instrumentation Accurately identify plant instrumentation and correctly interpret instrument readings to respond to normal, abnormal, and emergency conditions LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+: 2. Operational Actions and Annunciator Response Correctly identify plant annunciators and indications and perform appropriate remedial actions
-LOC28-NRC03
+: 3. System Operation, Controls and Instrumentation Accurately identify plant instrumentation and correctly interpret instrument readings to respond to normal, abnormal, and emergency conditions LOC28-NRC03 Rev 1                           Examination Material                                4/21/2016. 7
+LOC28-NRC03
 : 4. Facility Design and Operating Characteristics Demonstrate the following:
 * An understanding of facility operating characteristics
 * The ability to safely control the operating characteristics of the facility within prescribed operating boundaries
-: 5. System Loss and Component Level Malfunctions Perform system control manipulations to obtain desired operating results and demonstrate the ability to correctly respond to malfunction/loss of components and the impact of the malfunction/loss on interfacing plant systems 6. Heat Removal Component Operation Safely operate the plant's heat removal components and demonstrate knowledge of the relationship between the heat removal systems and the operation of facility to prevent exceeding System, Structure, or Component (SSC) design limits which include:
+: 5. System Loss and Component Level Malfunctions Perform system control manipulations to obtain desired operating results and demonstrate the ability to correctly respond to malfunction/loss of components and the impact of the malfunction/loss on interfacing plant systems
+: 6. Heat Removal Component Operation Safely operate the plant's heat removal components and demonstrate knowledge of the relationship between the heat removal systems and the operation of facility to prevent exceeding System, Structure, or Component (SSC) design limits which include:
 * Primary coolant systems
 * Emergency coolant systems
-* Decay heat removal systems 7. Auxiliary and Emergency Component Operations Safely operate the plant's auxiliary and emergency components I systems to include the controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment to control release of radioactivity within regulatory limits 8. Radiation Monitoring Component Operations Demonstrate or describe the use and function of the facility's radiation monitoring systems to maintain radiation levels within regulatory limits 9. Radiation Hazards Demonstrate knowledge of significant radiation hazards and ability to respond to the hazards to prevent exceeding regulatory limits 10. Reactivity Management Demonstrate knowledge of how reactivity is affected by plant operation and ability to respond to the change in reactivity to protect the safety and integrity of the reactor core 11. Technical Specifications During plant operation with the plant or system in a condition requiring Technical Specification action Identify the deviation and any required actions I notifications LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+* Decay heat removal systems
-LOC28-NRC03
+: 7. Auxiliary and Emergency Component Operations Safely operate the plant's auxiliary and emergency components I systems to include the controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment to control release of radioactivity within regulatory limits
+: 8. Radiation Monitoring Component Operations Demonstrate or describe the use and function of the facility's radiation monitoring systems to maintain radiation levels within regulatory limits
+: 9. Radiation Hazards Demonstrate knowledge of significant radiation hazards and ability to respond to the hazards to prevent exceeding regulatory limits
+: 10. Reactivity Management Demonstrate knowledge of how reactivity is affected by plant operation and ability to respond to the change in reactivity to protect the safety and integrity of the reactor core
+: 11. Technical Specifications During plant operation with the plant or system in a condition requiring Technical Specification action Identify the deviation and any required actions I notifications LOC28-NRC03 Rev 1                             Examination Material                                   4/21/2016. 8
+LOC28-NRC03
 : 12. Emergency Plan (if required)
 During plant operation in an emergency condition Recognize conditions covered by the Emergency Plan (SRO) Demonstrate the ability to:
 * Identify and Implement the appropriate Emergency Action Level
-* Use the applicable bases to support an Event Classification on the specified Emergency Action Level 13. Control Room Duties Demonstrate the knowledge and ability to assume the appropriate responsibilities (for the assigned position) associated with the safe operation of the facility 14. Control Room Team Work Demonstrate the ability to function within the Control Room team to comply with station procedures and limits of facility license and respond to plant events using appropriate human performance tools to support safe operation of the facility D. Task List Task Title ID Licensed Operator Apply Technical Specification (TS) And Technical Requirements Manual (TRM) Requirements S-C00-00-1185 Implement Reactivity Manipulations Standards and Communication Requirements S-C00-00-2784 Implement Appropriate Portions Of Operations Standards For System and Equipment Operation S-C00-00-1081 Implement Operations Standards For Error And Event Prevention S-ADM-00-1091 Implement Standards for Shift Operations S-C00-00-2780 Implement Appropriate Portions of Conduct of Operations S-C00-00-1015 Implement Appropriate Portions of Secondary Containment Integrity Control S-C00-00-1020 Implement EOP Cautions S-C00-00-2566 Implement Operations Directives S-C00-00-3130 Ensure Plant Operates IAW the Operating License, Technical Specifications (TS), and Technical S-C00-00-1183 Requirements Manual (TRM) Implement HUMAN PERFORMANCE (HuP) -Standards for Error and Event Prevention S-EPP-00-3068 Reactor Operator Insert a Control Rod One Notch S-201002-01-003 Perform the Monthly Turbine Bypass Valve Cycling S-241001-01-021 Manually Place Feedwater in Startup Level Control Following Reactor Scram S-259003-01-018 Confirm Automatic Initiation of RCIC S-217000-01-001 Perform the Actions of Fire Alarm Response S-286005-01-008 LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+* Use the applicable bases to support an Event Classification on the specified Emergency Action Level
-LOC28-NRC03 Task Title ID Perform a Manual Operation of the Safety/Relief Valves S-218000-01-003 Initiate Suppression Chamber Sprays S-203000-01-088 Initiate Drywell Sprays S-203000-01-089 Operate the RHR System in the Suppression Pool Cooling Mode S-203000-01-093 Direct the Actions for Loss of Feedwater Heater String S-260000-01-007 Direct Actions of Loss of Emergency Service Water (ESW) S-276001-01-012 Direct the actions for a loss of a 4 KV ESS Bus S-262004-01-007 Direct the Actions for a Sustained Loss of 4KV ESS Bus 1 C (2C) S-262001-01-025 Direct the Actions for a Loss of Containment Instrument Gas S-223002-01-005 Direct Actions for Excess Drywell Leakage S-00-005-01-001 Enter EOP RPV Control S-EOPRR-01-006 Direct the Actions for Increasing Offgas/MSL Rad Levels S-272000-01-037 Direct Actions for a +13 Inch Containment Isolation Actuation S-223002-01-006 Scram the Reactor S-EOPRR-01-005 Senior Reactor Operator Implement Appropriate Portions Of Plant Shutdown To Minimum Power 000000-02-1138 Direct Entry into Loss of Feedwater Heater String S-260000-02-002 Direct Entry into Loss of Emergency Service Water (ESW) S-276001-02-001 Direct Entry into Loss of 4KV ESS Bus 1 (2)A(B)(C)(D)
+: 13. Control Room Duties Demonstrate the knowledge and ability to assume the appropriate responsibilities (for the assigned position) associated with the safe operation of the facility
-S-262001-02-010 Direct Entry into Loss of Containment Instrument Gas S-223002-02-001 Direct or Concur with entry into Excess Drywell Leakage S-00-005-02-001 Direct entry into ON-SCRAM-101 (201) Reactor Scram 000000-02-1147 Direct and Coordinate Implementation of RPV Control 000000-02-1125 Direct Entry into Increasing Offgas/MSL Rad Levels S-272000-02-006 Direct and Coordinate Implementation of Secondary Containment Control 000000-02-1127 Direct Entry into Containment Isolation S-223002-02-002 Direct and Coordinate Implementation of Emergency Depressurization 000000-02-1129 LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+: 14. Control Room Team Work Demonstrate the ability to function within the Control Room team to comply with station procedures and limits of facility license and respond to plant events using appropriate human performance tools to support safe operation of the facility D. Task List Task Title                                                                                    ID Licensed Operator Apply Technical Specification (TS) And Technical Requirements Manual (TRM) Requirements       S-C00-00-1185 Implement Reactivity Manipulations Standards and Communication Requirements                   S-C00-00-2784 Implement Appropriate Portions Of Operations Standards For System and Equipment Operation     S-C00-00-1081 Implement Operations Standards For Error And Event Prevention                                 S-ADM-00-1091 Implement Standards for Shift Operations                                                      S-C00-00-2780 Implement Appropriate Portions of Conduct of Operations                                       S-C00-00-1015 Implement Appropriate Portions of Secondary Containment Integrity Control                     S-C00-00-1020 Implement EOP Cautions                                                                        S-C00-00-2566 Implement Operations Directives                                                               S-C00-00-3130 Ensure Plant Operates IAW the Operating License, Technical Specifications (TS), and Technical S-C00-00-1183 Requirements Manual (TRM)
-LOC28-NRC03 Scenario Attributes A. Critical Tasks 1. Manually initiate ARI Safety Significance Control rod insertion initiates power reduction immediately.
+Implement HUMAN PERFORMANCE (HuP) - Standards for Error and Event Prevention                  S-EPP-00-3068 Reactor Operator Insert a Control Rod One Notch                                                                S-201002-01-003 Perform the Monthly Turbine Bypass Valve Cycling                                              S-241001-01-021 Manually Place Feedwater in Startup Level Control Following Reactor Scram                     S-259003-01-018 Confirm Automatic Initiation of RCIC                                                          S-217000-01-001 Perform the Actions of Fire Alarm Response                                                    S-286005-01-008 LOC28-NRC03 Rev 1                                  Examination Material                                    4/21/2016. 9
-Consequences for Failure Failure to insert control rods allows power to remain elevated with to Perform the Task resultant power oscillations and potential core damage. Indications/
-Cues for Event Exceeding a RPS scram setting with NO reactor scram signal, or Requiring Critical Task RPS/ARI fail to fully insert all control rods. Performance Criteria Arm and depress Division 1 and 2 ARI initiation pushbuttons, HS-147103A(B)1.
+LOC28-NRC03 Task Title                                                                ID Perform a Manual Operation of the Safety/Relief Valves                    S-218000-01-003 Initiate Suppression Chamber Sprays                                       S-203000-01-088 Initiate Drywell Sprays                                                   S-203000-01-089 Operate the RHR System in the Suppression Pool Cooling Mode               S-203000-01-093 Direct the Actions for Loss of Feedwater Heater String                    S-260000-01-007 Direct Actions of Loss of Emergency Service Water (ESW)                   S-276001-01-012 Direct the actions for a loss of a 4 KV ESS Bus                           S-262004-01-007 Direct the Actions for a Sustained Loss of 4KV ESS Bus 1C (2C)            S-262001-01-025 Direct the Actions for a Loss of Containment Instrument Gas               S-223002-01-005 Direct Actions for Excess Drywell Leakage                                 S-00-005-01-001 Enter EOP RPV Control                                                     S-EOPRR-01-006 Direct the Actions for Increasing Offgas/MSL Rad Levels                   S-272000-01-037 Direct Actions for a +13 Inch Containment Isolation Actuation             S-223002-01-006 Scram the Reactor                                                         S-EOPRR-01-005 Senior Reactor Operator Implement Appropriate Portions Of Plant Shutdown To Minimum Power         000000-02-1138 Direct Entry into Loss of Feedwater Heater String                         S-260000-02-002 Direct Entry into Loss of Emergency Service Water (ESW)                   S-276001-02-001 Direct Entry into Loss of 4KV ESS Bus 1(2)A(B)(C)(D)                      S-262001-02-010 Direct Entry into Loss of Containment Instrument Gas                      S-223002-02-001 Direct or Concur with entry into Excess Drywell Leakage                   S-00-005-02-001 Direct entry into ON-SCRAM-101 (201) Reactor Scram                        000000-02-1147 Direct and Coordinate Implementation of RPV Control                       000000-02-1125 Direct Entry into Increasing Offgas/MSL Rad Levels                        S-272000-02-006 Direct and Coordinate Implementation of Secondary Containment Control     000000-02-1127 Direct Entry into Containment Isolation                                   S-223002-02-002 Direct and Coordinate Implementation of Emergency Depressurization        000000-02-1129 LOC28-NRC03 Rev 1                                    Examination Material              4/21/2016. 10
-Performance Feedback ARI Division 1 and 2 vent valves open, block valves close. Rod position full-in indication when control rod insertion complete.
-: 2. Emergency Depressurize the reactor when two Secondary Containment Areas exceed Max Safe Temperature levels High energy leak in the Secondary Containment Area impacts the Safety Significance integrity of Secondary Containment.
+LOC28-NRC03 Scenario Attributes A. Critical Tasks
-Failure of the Secondary Containment directly relates to the 1 OCFR50.67 design criteria of dose to the General Public. Consequences for Failure Failure to take actions to mitigate the energy released to the secondary to Perform the Task containment directly affects the radiation dose to the General Public. Indications/
+: 1. Manually initiate ARI Safety Significance         Control rod insertion initiates power reduction immediately.
-Cues for Event Increasing area temperatures and alarms for RB Areas indicating levels Requiring Critical Task at Max Safe values. Perform an Emergency Depressurization per E0-000-112 when two or Performance Criteria more RB areas exceed max safe temperature per E0-000-104.
+Consequences for Failure     Failure to insert control rods allows power to remain elevated with to Perform the Task          resultant power oscillations and potential core damage.
-Open 6 ADS SRVs. Initiating an emergency depressurization causes Reactor pressure to Performance Feedback lower which lowers the driving force of any primary system breach. Verify ADS valves are open using light red light indication, acoustic monitoring and lowering Reactor pressure and rising reactor water level. LOC28-NRC03 Rev 1 Examination Material 4/21/2016
+Indications/ Cues for Event Exceeding a RPS scram setting with NO reactor scram signal, or Requiring Critical Task     RPS/ARI fail to fully insert all control rods.
-* 11 LOC28-NRC03 B. Scenario Malfunctions Event Malfunction Operator Action in Response 1 N/A Test Turbine Bypass Valve #3 (S0-182-001) 2 N/A Insert Control Rods (OP-156-001, OP-A0-338) 3 cmfHX02_ 1E102C FW heater 2C tube leak (AR-120-C10, 010), Isolate FW heater extraction steam (ON-147-002), TS MCPR limits not applicable (TS 3.2.2) 4 cmfEB01_ 1A203 ESS Bus 1 C lockout, Orywell leak severity rises, mfRR164010 reactor scram required (ON-104-203, TS 3.8.7) 5 mfRP158003 Electrical ATWS (E0-000-113)
+Arm and depress Division 1 and 2 ARI initiation pushbuttons, HS-Performance Criteria 147103A(B)1.
-ARI inserts control rods 6 cmfMV06_HV149F013 RCIC injection valve fails to open on initiation (OP-150-001) 7 mfRR179003 Fuel failure with high MSL radiation, MSIV isolation required (AR-103-001, AR-104-001) 8 cmfMV01_HV155F002 HPCI steam isolation valves fail to automatically cmfMV07 _HV155F003 f:90 close (AR-108-F04, F05), manual isolation successful after reactor pressure reduced 9 mfRC150004 Unisolable RCS leak into Secondary Containment, 2 areas above Max Safe Temp (E0-000-104)
+ARI Division 1 and 2 vent valves open, block valves close. Rod position Performance Feedback full-in indication when control rod insertion complete.
-C. Abnormal Events and Major Transients Malfunction Description R Insert Control Rods (OP-156-001, OP-A0-338)
+: 2. Emergency Depressurize the reactor when two Secondary Containment Areas exceed Max Safe Temperature levels High energy leak in the Secondary Containment Area impacts the integrity of Secondary Containment. Failure of the Secondary Safety Significance Containment directly relates to the 1OCFR50.67 design criteria of dose to the General Public.
-N Test Turbine Bypass Valve #3 (S0-182-001)
+Consequences for Failure     Failure to take actions to mitigate the energy released to the secondary to Perform the Task          containment directly affects the radiation dose to the General Public.
-AE1 FW heater 2C tube leak (AR-120-C10, 010), AE2 ESS Bus 1 C lockout AE3 Electrical ATWS (E0-000-113)
+Indications/ Cues for Event Increasing area temperatures and alarms for RB Areas indicating levels Requiring Critical Task      at Max Safe values.
-MT1 Unisolable RCS leak into Secondary Containment, 2 areas above Max Safe Rad (E0-000-104)
+Perform an Emergency Depressurization per E0-000-112 when two or Performance Criteria         more RB areas exceed max safe temperature per E0-000-104. Open 6 ADS SRVs.
-MAE1 Fuel failure with high MSL radiation, MSIV isolation required LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+Initiating an emergency depressurization causes Reactor pressure to lower which lowers the driving force of any primary system breach. Verify Performance Feedback ADS valves are open using light red light indication, acoustic monitoring and lowering Reactor pressure and rising reactor water level.
-LOC28-NRC03 Malfunction Description MAE2 RCIC injection valve fails to open on initiation MAE3 HPCI steam isolation valves fail to automatically close TS1 TS MCPR limits not applicable (TS 3.2.2) TS2 ESS Bus 1 C lockout (TS 3.8. 7) D. EOP and EOP Contingencies Used EOPs EOP Contingencies IZI E0-000-102, RPV Control D E0-000-102, Alternate Level Control D E0-000-103, Primary Containment Control D E0-000-102, Steam Cooling IZI E0-000-104, Secondary Containment Control IZI E0-000-112, Emergency Depressurization D E0-000-105, Radioactivity Release Control IZI E0-000-113, Power/Level Control D E0-000-114, RPV Flooding E. Technical Specifications
+LOC28-NRC03 Rev 1                             Examination Material                            4/21/2016
-: 1. TS 3.8.1 2. TS 3.7.6 3. TS 3.2.2 4. TR 3.2.1 LOC28-NRC03 Rev 1 AC Sources operating Plant Systems Main Turbine Bypass System Minimum Critical Power Ratio Core Operating Limits Report (COLR) Examination Material 4/21/2016.
+* 11
-: 1. OP-AD-300
+LOC28-NRC03 B. Scenario Malfunctions Event                    Malfunction                         Operator Action in Response 1        N/A                                  Test Turbine Bypass Valve #3 (S0-182-001) 2         N/A                                   Insert Control Rods (OP-156-001, OP-A0-338) 3         cmfHX02_ 1E102C                       FW heater 2C tube leak (AR-120-C10, 010),
-: 2. OP-AD-338
+Isolate FW heater extraction steam (ON-147-002), TS MCPR limits not applicable (TS 3.2.2) 4         cmfEB01_ 1A203                        ESS Bus 1C lockout, Orywell leak severity rises, reactor scram required (ON-104-203, TS 3.8.7) mfRR164010 5         mfRP158003                            Electrical ATWS (E0-000-113)
-: 3. OP-054-001
+ARI inserts control rods 6         cmfMV06_HV149F013                     RCIC injection valve fails to open on initiation (OP-150-001) 7        mfRR179003                            Fuel failure with high MSL radiation, MSIV isolation required (AR-103-001, AR-104-001) 8        cmfMV01_HV155F002                     HPCI steam isolation valves fail to automatically cmfMV07_HV155F003 f:90                close (AR-108-F04, F05), manual isolation successful after reactor pressure reduced 9        mfRC150004                            Unisolable RCS leak into Secondary Containment, 2 areas above Max Safe Temp (E0-000-104)
-: 4. OP-156-001
+C. Abnormal Events and Major Transients Malfunction                                          Description R        Insert Control Rods (OP-156-001, OP-A0-338)
-: 5. S0-182-001
+N        Test Turbine Bypass Valve #3 (S0-182-001)
-: 6. ON-SCRAM-101
+AE1         FW heater 2C tube leak (AR-120-C10, 010),
-: 7. AOP-104-101
+AE2        ESS Bus 1C lockout AE3        Electrical ATWS (E0-000-113)
-: 8. ON-4KV-101
+Unisolable RCS leak into Secondary Containment, 2 areas above Max Safe Rad MT1 (E0-000-104)
-: 9. ON-125-001
+MAE1         Fuel failure with high MSL radiation, MSIV isolation required LOC28-NRC03 Rev 1                           Examination Material                                  4/21/2016. 12
-: 10. ON-147-002
-: 11. ON-179-001
+LOC28-NRC03 Malfunction                                            Description MAE2       RCIC injection valve fails to open on initiation MAE3       HPCI steam isolation valves fail to automatically close TS1       TS MCPR limits not applicable (TS 3.2.2)
-: 12. E0-000-102
+TS2       ESS Bus 1C lockout (TS 3.8. 7)
-: 13. E0-000-103
+D. EOP and EOP Contingencies Used EOPs                                                   EOP Contingencies IZI E0-000-102, RPV Control                            D E0-000-102, Alternate Level Control D E0-000-103, Primary Containment Control              D E0-000-102, Steam Cooling IZI E0-000-104, Secondary Containment Control          IZI E0-000-112, Emergency Depressurization D E0-000-105, Radioactivity Release Control            IZI E0-000-113, Power/Level Control D E0-000-114, RPV Flooding E. Technical Specifications
-: 14. E0-000-104
+: 1. TS 3.8.1        AC Sources operating
-: 15. E0-000-105
+: 2. TS 3.7.6        Plant Systems Main Turbine Bypass System
-: 16. E0-000-112
+: 3. TS 3.2.2        Minimum Critical Power Ratio
-: 17. E0-000-113
+: 4. TR 3.2.1        Core Operating Limits Report (COLR)
-: 18. ES-158-001
+LOC28-NRC03 Rev 1                             Examination Material                             4/21/2016. 13
-: 19. EP-PS-100
-: 20. EP-RM-004
+LOC28-NRC03 References
-: 21. AR-106-F03
+: 1. OP-AD-300    Administration of Operations
-: 22. AR-108-E05
+: 2. OP-AD-338    Reactivity Manipulation Standards and Communication Requirements
-: 23. AR-110-A01
+: 3. OP-054-001   Emergency Service Water
-: 24. AR-110-A02
+: 4. OP-156-001   Reactor Manual Control System
-: 25. AR-110-A03
+: 5. S0-182-001   Monthly Turbine Bypass Valve Testing
-: 26. AR-110-A04
+: 6. ON-SCRAM-101 Reactor Scram
-: 27. AR-120-D10
+: 7. AOP-104-101  Energizing Dead 4KV ESS Bus
-: 28. TS 3.8.1 29. TS 3.7.6 30. TS 3.2.2 31. TR 3.2.1 32. LOC28-NRC03 Rev 1 LOC28-NRC03 References Administration of Operations Reactivity Manipulation Standards and Communication Requirements Emergency Service Water Reactor Manual Control System Monthly Turbine Bypass Valve Testing Reactor Scram Energizing Dead 4KV ESS Bus Loss of 4KV bus Loss of Containment Instrument Gas Anticipated Loss of FW HTR String Increasing Offgas MSL Rad Levels RPV Control Primary Containment Control Secondary Containment Control Radioactivity Release Control Emergency Rapid Depressurization Power/ Level Control De-energizing Scram Pilot Solenoids Emergency Director Control Room Emergency Plan EAL Classification Bases Offgas Hi Hi Radiation RCIC Leak Detection Hi Temp/ Hi Diff Temp ADS Logic A Timer Initiated ADS Logic C Timer Initiated ADS Logic B Timer Initiated ADS Logic D Timer Initiated FW HTR C Dump Viv Open AC Sources operating Plant Systems Main Turbine Bypass System Minimum Critical Power Ratio Core Operating Limits Report (COLR) Examination Material 4/21/2016.
+: 8. ON-4KV-101   Loss of 4KV bus
-LOC28-NRC03 Set.up Instructions A. Required Materials
+: 9. ON-125-001   Loss of Containment Instrument Gas
-: 1. US Turnover Sheet a. Unit 1 1) Reactor Power -33% 2) 1 RFP in FCM 3) Shutdown to identify and repair small RCS leak in Drywell. Unidentified leak is 0.5 gpm for last 36 hours. ON-100-005 actions are complete.
+: 10. ON-147-002   Anticipated Loss of FW HTR String
-hour leakrate calculations are being performed.
+: 11. ON-179-001   Increasing Offgas MSL Rad Levels
-: 4) Insert Control Rods IAW given RMR 5) Perform test of Bypass Valve #3 IAW S0-182-001 for valve functional test b. Common and Unit 2 1) Unit 2 at rated power. 2. Supporting Documents
+: 12. E0-000-102   RPV Control
+: 13. E0-000-103   Primary Containment Control
+: 14. E0-000-104   Secondary Containment Control
+: 15. E0-000-105   Radioactivity Release Control
+: 16. E0-000-112   Emergency Rapid Depressurization
+: 17. E0-000-113   Power/ Level Control
+: 18. ES-158-001   De-energizing Scram Pilot Solenoids
+: 19. EP-PS-100    Emergency Director Control Room Emergency Plan
+: 20. EP-RM-004    EAL Classification Bases
+: 21. AR-106-F03   Offgas Hi Hi Radiation
+: 22. AR-108-E05   RCIC Leak Detection Hi Temp/ Hi Diff Temp
+: 23. AR-110-A01   ADS Logic A Timer Initiated
+: 24. AR-110-A02   ADS Logic C Timer Initiated
+: 25. AR-110-A03   ADS Logic B Timer Initiated
+: 26. AR-110-A04   ADS Logic D Timer Initiated
+: 27. AR-120-D10   FW HTR C Dump Viv Open
+: 28. TS 3.8.1     AC Sources operating
+: 29. TS 3.7.6     Plant Systems Main Turbine Bypass System
+: 30. TS 3.2.2     Minimum Critical Power Ratio
+: 31. TR 3.2.1     Core Operating Limits Report (COLR) 32.
+LOC28-NRC03 Rev 1                  Examination Material                        4/21/2016. 14
+LOC28-NRC03 Set.up Instructions A. Required Materials
+: 1. US Turnover Sheet
+: a. Unit 1
+: 1)    Reactor Power -33%
+: 2)    1 RFP in FCM
+: 3)    Shutdown to identify and repair small RCS leak in Drywell. Unidentified leak is 0.5 gpm for last 36 hours. ON-100-005 actions are complete. 12 hour leakrate calculations are being performed.
+: 4)    Insert Control Rods IAW given RMR
+: 5)    Perform test of Bypass Valve #3 IAW S0-182-001 for valve functional test
+: b. Common and Unit 2
+: 1)    Unit 2 at rated power.
+: 2. Supporting Documents
 : a. S0-182-001
 : b. G0-100-012
-: c. RMR (2 copies) 8. Simulator Initialization
+: c. RMR (2 copies)
-: 1. Reset to exam specific IC, otherwise setup as follows a. Reset to IC-20 b. Place the simulator in RUN c. Insert a LIM2 d. Disable IND RFP FLOW< 16.4% LIM2 runback IAW OP-164-001
+: 8. Simulator Initialization
-: e. Select FWLC to VENTURI f. Insert rfFW145032 to CLOSE for HWC to 'C' RFP g. Place 'C' RFP in STANDBY IAW OP-145-001
+: 1. Reset to exam specific IC, otherwise setup as follows
-: h. Remove 2 condensate pumps from service (prefer 'C' and 'D') when suction pressure is >600 psig i. Shutdown HWC IAW OP-145-002
+: a. Reset to IC-20
+: b. Place the simulator in RUN
+: c. Insert a LIM2
+: d. Disable IND RFP FLOW< 16.4% LIM2 runback IAW OP-164-001
+: e. Select FWLC to VENTURI
+: f. Insert rfFW145032 to CLOSE for HWC to 'C' RFP
+: g. Place 'C' RFP in STANDBY IAW OP-145-001
+: h. Remove 2 condensate pumps from service (prefer 'C' and 'D') when suction pressure is >600 psig
+: i. Shutdown HWC IAW OP-145-002
 : j. Ensure proper number for filter/demins are in-service IAW OP-139-001
-: k. Insert control rods to <60% rod-line I. Lower reactor power to 37-38% using recirc LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+: k. Insert control rods to <60% rod-line I. Lower reactor power to 37-38% using recirc LOC28-NRC03 Rev 1                              Examination Material                           4/21/2016. 15
-LOC28-NRC03
-: m. Place 'B' RFP in STANDBY and Trip 'C' RFP n. Reduce RRP speed to <30% o. Verify Load Set is -1 OOMWe above generator load p. Place the simulator in FREEZE 2. Run SCN file exam\LOC28-NRC-03
+LOC28-NRC03
-: 3. Place the simulator in RUN 4. Perform simulator activities
+: m. Place 'B' RFP in STANDBY and Trip 'C' RFP
-: a. Place the blue reactivity in progress signs up. 5. Verify the simulator matches the following MF RF OR ET CONDITIONS 16:16 4:4 0:0 8 12 6. Ensure FW Control is selected to VENTURI 7. Reset ODAs and all Overhead, PICSY, HMI and RWM alarms 8. Ensure horns and annunciators are on 9. Ensure Overhead Lights Override is off C. Simulator Preparation
+: n. Reduce RRP speed to <30%
-: 1. Ensure the EOL CRC Book is at the PCO Console D. Document Training and Performance Feedback 1. Record crew position assignments in G:\NTGOPS\LOR\REQUAL\lnfo Tracking\ (LOR) 2. Record crew position assignments per TQ-104 (ILO) 3. Complete an IER 11-3 Operator Fundamentals Simulator Observer Aid 4. Complete simulator setup checklists E. Scenario Execution
+: o. Verify Load Set is -1 OOMWe above generator load
-: 1. Identify performance improvement actions that may be addressed during the scenario 2. Provide turnover to the crew using the US Turnover sheet 3. Direct the crew to walk down the Control Room panels 4. Inform the Shift Manager that the crew has the shift F. Simulator Files LOC28-NRC-03 insmp tcvpbv3 changemp tcvpbv3 ,,,BYPASS VALVE POSITION 3 de Imp insmp fwlt10303cl
+: p. Place the simulator in FREEZE
-* SCN rat_mp changemp fwlt10303cl
+: 2. Run SCN file exam\LOC28-NRC-03
-,,,FWH 2C LEVEL LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+: 3. Place the simulator in RUN
-LOC28-NRC03 insmp ycpxnbtOl changemp ycpxnbtOl
+: 4. Perform simulator activities
-,,DEG F,TFW A insmp ycpxghfOl changemp ycpxghfOl
+: a. Place the blue reactivity in progress signs up.
-,,,GEN H2 SUPPLY FLOW insmp ycpxghpOl changemp ycpxghpOl
+: 5. Verify the simulator matches the following MF                RF                   OR                    ET           CONDITIONS 16:16              4:4                  0:0                    8                  12
-,,,GEN H2 PRESSURE insmp ecvp033035 changemp ecvp033035
+: 6. Ensure FW Control is selected to VENTURI
-,,,HYDROGEN EXCESS FLOW A INLET ISO VLV insmp rdpic121r013 changemp rdpic121r013
+: 7. Reset ODAs and all Overhead, PICSY, HMI and RWM alarms
-,,psig,SCRAM AIR HDR PRESS insmp ycpxpar02 changemp ycpxpar02
+: 8. Ensure horns and annunciators are on
-,,MR/HR,RCIC RM ARM LO-RNG insmp ycpxpar57 changemp ycpxpar57
+: 9. Ensure Overhead Lights Override is off C. Simulator Preparation
-,,MR/HR,RCIC RM ARM Hl-RNG insmp ycpxmarOl changemp ycpxmarOl
+: 1. Ensure the EOL CRC Book is at the PCO Console D. Document Training and Performance Feedback
-,,R/HR,CTMT HI-RANGE ARM insmp aoURSG331N605A.CurrValue changemp aoURSG331N605A.CurrValue 0,350,DEG F,RCIC Equip Area Temp insmp aoURSG331N604D.CurrValue changemp aoURSG331N604D.CurrValue 0,350,DEG F,HPCI Equip Area Temp ; 0-G alarms suppressed SDR # IMF annAR106F15 f:ALARM_OFF IMF annAR131A04 f:ALARM_OFF
+: 1. Record crew position assignments in G:\NTGOPS\LOR\REQUAL\lnfo Tracking\ (LOR)
-; small dw leak IMF mfRR164010 f:.1 IMF cmfTROl_LT16102A IMF cmfTROl_LT16102B IMF annAR107A05 f:ALARM_OFF IMF annAR107B05 f:ALARM_OFF
+: 2. Record crew position assignments per TQ-104 (ILO)
-; FWH trouble alarms defeated IMF annAR120H10 f:ALARM_ON IMF annAR120H07 f:ALARM_ON IMF annAR120H04 f:ALARM_ON
+: 3. Complete an IER 11-3 Operator Fundamentals Simulator Observer Aid
-; HVAC Div 1&2 alarms locked in IMF annAR106A16 f:ALARM_ON IMF annAR106B16 f:ALARM_ON
+: 4. Complete simulator setup checklists E. Scenario Execution
-; Electrical ATWS IMF mfRP158003
+: 1. Identify performance improvement actions that may be addressed during the scenario
-; ARI outlets partially blocked IRF rfRD155030 f:l ; RCIC F013 valve auto-open failure IMF cmfMV06_HV149F013
+: 2. Provide turnover to the crew using the US Turnover sheet
-; HPCI isol valve auto logic fail IMF cmfMV06_HV155F002 IMF cmfMV06_HV155F003 aet ETLOC28-NRC03-A scram aet ETLOC28-NRC03-B init on rod drift aet ETLOC28-NRC03-C MSIV closure aet ETLOC28-NRC03-D
+: 3. Direct the crew to walk down the Control Room panels
-; terminate LOCA severity on ; Fuel failure and spurious RCIC ; Delete MSIV rad malfunction on ; RCIC room steam leak aet ETLOC28-NRC03-E; HPCI room steam leak aet ETLOC28-NRC03-F; HPCI F002 valve breaker trips when stroked aet ETLOC28-NRC03-G stroked aet ETLOC28-NRC03-H blowdown ; 2C FWH tube leak ; HPCI F003 valve binds when ; HPCI F003 valve closes on {Key[l]} IMF cmfHX02_1E102C r:300 i:5 f:15 ; 2C FWH tube leak degrades {Key[2]} IMF cmfHX02_1E102C r:60 f:20 ; 2C FWH dump/drain 3C drain {Key[3]} SCN exam\LOC28-NRC03-A
+: 4. Inform the Shift Manager that the crew has the shift F. Simulator Files LOC28-NRC-03                                                 insmp tcvpbv3 changemp tcvpbv3 ,,,BYPASS VALVE POSITION 3 de Imp                                                       insmp fwlt10303cl
-; lC ESS Bus Lockout {Key[4]} IMF mfDS104001C
+* SCN rat_mp                                                   changemp fwlt10303cl ,,,FWH 2C LEVEL LOC28-NRC03 Rev 1                               Examination Material                                     4/21/2016. 16
-; Xtie I/ A to CIG {Key[S]} IRF rfPC125001 f:OPEN ; Local Evac Alarm {Key[G]} SCN exam\LOCAL_EVAC_ALARM
-; ADS Keys {Key[7]} IOR diHS14113G2 d:60 f:OPEN {Key[7]} IOR diHS14113J2 d:66 f:OPEN {Key[7]} IOR diHS14113K2 d:72 f:OPEN {Key[7]} IOR diHS14113L2 d:78 f:OPEN {Key[7]} IOR diHS14113M2 d:84 f:OPEN {Key[7]} IOR diHS14113N2 d:90 f:OPEN LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+LOC28-NRC03 insmp ycpxnbtOl changemp ycpxnbtOl ,,DEG F,TFW A                               ; HPCI isol valve auto logic fail IMF cmfMV06_HV155F002 insmp ycpxghfOl                                                IMF cmfMV06_HV155F003 changemp ycpxghfOl ,,,GEN H2 SUPPLY FLOW aet ETLOC28-NRC03-A               ; terminate LOCA severity on insmp ycpxghpOl                                                scram changemp ycpxghpOl ,,,GEN H2 PRESSURE aet ETLOC28-NRC03-B               ; Fuel failure and spurious RCIC insmp ecvp033035                                               init on rod drift changemp ecvp033035 ,,,HYDROGEN EXCESS FLOW A INLET ISO VLV                                                            aet ETLOC28-NRC03-C               ; Delete MSIV rad malfunction on MSIV closure insmp rdpic121r013 changemp rdpic121r013 ,,psig,SCRAM AIR HDR PRESS               aet ETLOC28-NRC03-D               ; RCIC room steam leak insmp ycpxpar02                                                aet ETLOC28-NRC03-E; HPCI room steam leak changemp ycpxpar02 ,,MR/HR,RCIC RM ARM LO-RNG aet ETLOC28-NRC03-F; HPCI F002 valve breaker trips when insmp ycpxpar57                                                stroked changemp ycpxpar57 ,,MR/HR,RCIC RM ARM Hl-RNG aet ETLOC28-NRC03-G               ; HPCI F003 valve binds when insmp ycpxmarOl                                                stroked changemp ycpxmarOl ,,R/HR,CTMT HI-RANGE ARM aet ETLOC28-NRC03-H               ; HPCI F003 valve closes on insmp aoURSG331N605A.CurrValue                                 blowdown changemp aoURSG331N605A.CurrValue 0,350,DEG F,RCIC Equip Area Temp
-LOC28-NRC03-A IOR diLIC10306CD_Q f:MANUAL IOR diLIC10306CB_Q f:OPEN IOR diLIC10302CD_Q f:MANUAL IOR diLIC10302CA_Q f:OPEN IOR diLIC10407CD_Q f:MANUAL IOR diLIC10407CB_Q f:CLOSE LOC28-NRC03-B IMF mfRR179003 i:2 f:S r:600 ;IMF cmfTR02 RIT13705 r:68 f:lOOO ;IMF cmfTR02_RIT13706 r:S9 f:lOOO ;IMF cmfTR02_RIT13750 d:45 r:30:00 f:65 ;IMF cmfTR02_RIT13751 d:40 r:30:00 f:66 IMF mfRM179004A r:300 f:SOOOO IMF mfRM179004B r:300 f:SOOOO IMF mfRM179004C r:300 f:SOOOO IMF mfRM179004D r:300 f:SOOOO Sound Local Evac Alarm +1 IOR di20A02A02S001B f:OUT +1 IOR di20A02A02S002 f:WARBLE +l IOR di20A02A02S001A f:6 +l IOR di20A02A02S001B f:IN +5 IOR di20A02A02S001B f:OUT +l IOR di20A02A02S001A f:4 +1 IOR di20A02A02S002 f:SIREN +1 IOR di20A02A02S001B f:IN DOR di20A02A02S001A DOR di20A02A02S001B DOR di20A02A02S002 ETLOC28-NRC03-A pcpdwg > 1.8 I diHSC72AlSOl.CurrValue
+                                                               ; 2C FWH tube leak insmp aoURSG331N604D.CurrValue                                 {Key[l]} IMF cmfHX02_1E102C r:300 i:5 f:15 changemp aoURSG331N604D.CurrValue 0,350,DEG F,HPCI Equip Area Temp                                                ; 2C FWH tube leak degrades
-!= #OR.diHSC72AlSOl.RUN MMF mfRR164010 f:O.O LOC28-NRC03 Rev 1 LOC28-NRC03 ETLOC28-N RC03-B rdpic121r013
+{Key[2]} IMF cmfHX02_1E102C r:60 f:20
-< 42 SCN exam\LOC28-NRC03-B IMF mfRC150006 ETLOC28-NRC03-C msvsphv14lf022a
+; 0-G alarms suppressed SDR #                                  ; 2C FWH dump/drain 3C drain IMF annAR106F15 f:ALARM_OFF                                    {Key[3]} SCN exam\LOC28-NRC03-A IMF annAR131A04 f:ALARM_OFF
-< .1 & msvsphv14lf022b
+                                                               ; lC ESS Bus Lockout
-< .1 & msvsphv14lf022c
+; small dw leak                                                {Key[4]} IMF mfDS104001C IMF mfRR164010 f:.1 IMF cmfTROl_LT16102A                                           ; Xtie I/A to CIG IMF cmfTROl_LT16102B                                           {Key[S]} IRF rfPC125001 f:OPEN IMF annAR107A05 f:ALARM_OFF IMF annAR107B05 f:ALARM_OFF                                    ; Local Evac Alarm
-< .1 & msvsphv14lf022d
+{Key[G]} SCN exam\LOCAL_EVAC_ALARM
-< .1 MMF mfRM179004A r:300 f:SO c:300 MMF mfRM179004B r:300 f:SO c:300 MMF mfRM179004C r:300 f:SO c:300 MMF mfRM179004D r:300 f:SO c:300 ETLOC28-N RC03-D rcvsphv150f045
+; FWH trouble alarms defeated IMF annAR120H10 f:ALARM_ON                                     ; ADS Keys IMF annAR120H07 f:ALARM_ON                                     {Key[7]} IOR   diHS14113G2 d:60 f:OPEN IMF annAR120H04 f:ALARM_ON                                     {Key[7]} IOR   diHS14113J2 d:66 f:OPEN
-> 0.1 IMF mfRC150004 r:120 f:20 ETLOC28-NRC03-E
+{Key[7]} IOR   diHS14113K2 d:72 f:OPEN
-;HPCI steam leak hpvsphvlSSfOOl
+; HVAC Div 1&2 alarms locked in                                {Key[7]} IOR   diHS14113L2 d:78 f:OPEN IMF annAR106A16 f:ALARM_ON                                     {Key[7]} IOR   diHS14113M2 d:84 f:OPEN IMF annAR106B16 f:ALARM_ON                                     {Key[7]} IOR   diHS14113N2 d:90 f:OPEN
-> 0.1 IMF mfHP152009 r:120 f:20 IMF mfHP152003 r:360 f:20 ETLOC28-N RC03-F ;HPCI l/B F002 breaker trip diHS15502.CurrValue
+; Electrical ATWS IMF mfRP158003
-= #OR.diHS15502.CLS IMF cmfMVOl_HV155F002 ETLOC28-N RC03-G ;HPCI O/B F003 Binds diHS15503.CurrValue
+; ARI outlets partially blocked IRF rfRD155030 f:l
-= #OR.diHS15503.CLS IMF cmfMV07 _HV155F003 f:90 ETLOC28-NRC03-H rrpdome < 200 MMF cmfMV07 _HV155F003 f:O r:60 c:70 Examination Material 4/21/2016.
+; RCIC F013 valve auto-open failure IMF cmfMV06_HV149F013 LOC28-NRC03 Rev 1                                 Examination Material                                                 4/21/2016. 17
-Instructor Activities Booth Operator No additional activities required.
-Role Play As GCC/TCC informed of turbine test Grid conditions are stable thank you for the notification.
+LOC28-NRC03 LOC28-NRC03-A                                         ETLOC28-N RC03-B IOR diLIC10306CD_Q f:MANUAL                           rdpic121r013 < 42 IOR diLIC10306CB_Q f:OPEN                             SCN exam\LOC28-NRC03-B IOR diLIC10302CD_Q f:MANUAL                           IMF mfRC150006 IOR diLIC10302CA_Q f:OPEN IOR diLIC10407CD_Q f:MANUAL IOR diLIC10407CB_Q f:CLOSE                            ETLOC28-NRC03-C msvsphv14lf022a < .1 & msvsphv14lf022b < .1 &
-Inform us when testing is complete.
+msvsphv14lf022c < .1 & msvsphv14lf022d < .1 LOC28-NRC03-B                                         MMF mfRM179004A r:300 f:SO c:300 IMF mfRR179003 i:2 f:S r:600                          MMF mfRM179004B r:300 f:SO c:300
-Role Play If required to prompt the crew
+;IMF cmfTR02 RIT13705 r:68 f:lOOO                     MMF mfRM179004C r:300 f:SO c:300
-* to perform t.he BPV testing, contact the control room as the Shift Manager Have we sta.rted the bypass valve testing? LOC28-NRC03 Rev 1 LOC28-NRC03 Event 1 -Turbine Bypass Valve #3 Test Operator Activities PCOM D Monitor diverse indications of reactor power IAW OP-AD-001 D As required, performs peer checks PCOP D When directed, performs BPV #3 testing D Selects position 3 on the BPV TEST SELECT D Depress AND Hold TEST BYPASS VAL VE pushbutton D Observes proper light indications and BPV #3 opens fully D Releases TEST BYPASS VALVE pushbutton D Observes proper light indications and BPV #3 closes us D Performs update for performing S0-182-001, Monthly Turbine Bypass Valve Cycling for BPV #3 D Directs PCOP to perform S0-182-001 Examination Material Notes 4/21/2016.
+;IMF cmfTR02_RIT13706 r:S9 f:lOOO                     MMF mfRM179004D r:300 f:SO c:300
-LOC28-NRC03 Event 2 -Control Rod insertion to lower power Instructor Activities Operator Activities Booth Operator No additional activities are required.
+;IMF cmfTR02_RIT13750 d:45 r:30:00 f:65
-Role Play As RE contacted for assistance Core thermal limits are within our predictions.
+;IMF cmfTR02_RIT13751 d:40 r:30:00 f:66 IMF mfRM179004A r:300 f:SOOOO                         ETLOC28-N RC03-D IMF mfRM179004B r:300 f:SOOOO                         rcvsphv150f045 > 0.1 IMF mfRM179004C r:300 f:SOOOO                         IMF mfRC150004 r:120 f:20 IMF mfRM179004D r:300 f:SOOOO ETLOC28-NRC03-E Sound Local Evac Alarm                                ;HPCI steam leak hpvsphvlSSfOOl > 0.1
-You may proceed with the power reduction.
++1 IOR di20A02A02S001B f:OUT                          IMF mfHP152009 r:120 f:20
-Role Play As Shift Manager contacted for approval The reactivity manipulation may proceed /AW the RMR. LOC28-NRC03 Rev 1 PCOM D Inserts Control Rods IAWOP-156-001, OP-AD-338, and the RMR to lower power to -30% D Uses two-handed operation to select the correct control rod D Inserts the selected control rod by depressing and holding the Insert pushbutton D Depress the Rod Selct Clear pushbutton when rod movement is complete D Plots power change on Power/ Flow map D Monitors diverse indications of reactor power IAW OP-AD-001 PCOP D Peer Checks the reactivity maneuver D IAW OP-AD-300, nulls Manual and Automatic regulators using MAN VOLT REG ADJUST HC-10002 D Maintains Load Set -1 OOMWe above actual generator load us D Obtains permission from the SM prior to commencing reactivity manipulations D Informs TCC/GCC of load changes on Unit 1 D Conducts crew update prior to commencing rod insertion D Directs control rod insertion IAW OP-156-001, RMR, and G0-100-012 D Monitors control rod movement with independent RMR Examination Material Notes 4/21/2016.
++1 IOR di20A02A02S002 f:WARBLE                        IMF mfHP152003 r:360 f:20
-LOC28-NRC03 Event 2 -Control Rod insertion to lower power Instructor Activities Operator Activities Notes LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
++l IOR di20A02A02S001A f:6
-LOC28-NRC03 Event 3 -FW Heater 2C Tube Leak Instructor Activities Operator Activities Notes Booth Operator When the bypass valve test circuit has been turned off, Insert KEY ,1 to initiate a tube leak in FW heater 2C. The tube leak will take 2-3 minutes to result in a noticeable rise in FW heater level. {Key[1]} IMF cmfHX02_ 1E102C r:300 i:5 f:15 FWH 2C tube leak Once the crew has diagnosed the tube leak and initiated actions to isolate FW heater 2C, if desired, lnse.rt KEY 2 to raise the severity of the leak {Key[2]} IMF cmfHX02_1E102C r:60 f:20 FWH 2C tube leak degrades When directed, Insert KEY 3 to configure FW heater 2C and 3C drains and dumps IAW ON-147-002 Step 3.8 {Key[3]} SCN exam\LOC28-NRC03-A RFP seal water iso Role Play As NPO dispatched to FWH 'C' panel 1C103, wait2 minutes The 2C FW heater level control and emergency dump valves are responding.
++l IOR di20A02A02S001B f:IN                           ETLOC28-N RC03-F
-Heater level is continuing to rise. Role Play As WWM contacted for assistance with FW heater 'C', wait 5 minutes Engineering recommends removing the 2C FW heater from service and isolating it. Role Play As NPOto check FWH level after the isolation, wait 1 minute The 2C FW heater level is slowly lowering Instructor Cue PCOM D Monitors neutron instrumentation for indication of core instability PCOP D Performs AR-120-D10, FW HTR String 'C' Dump VLV Full Open D Dispatches NPO to 1C103 to ensure FW Heater 3C to 2C lso VLV is 100% OPEN and if FW level control valve 100% open D Performs ON-147-002 to isolate extraction steam supplies to 3C, 4C, and 5C and to isolated FW heater string 'C' D Dispatches NPO to perform ON-147-002 step 3. 7 to configure FW heater vent and drain valves D Dispatches NPO to perform ON-147-002 step 3.8 to close the RFP Seal Water Bleed Off HV-10244C us D Enters ON-147-002 for Anticipated Loss/Loss of Feedwater Heater String D Enters TS 3.2.2 -4>>) When the SSE and MSEP drain valves are closed, proceed to Event 4 LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
++5 IOR di20A02A02S001B f:OUT                          ;HPCI l/B F002 breaker trip
-LOC28-NRC03 Event 3 -FW Heater 2C Tube Leak Instructor Activities Operator Activities Notes LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
++l IOR di20A02A02S001A f:4                            diHS15502.CurrValue =#OR.diHS15502.CLS
-LOC28-NRC03 Event 4 -ESS. Bus 1 C lockout/ Reactor Scram Instructor Activities Operator Activities Notes Booth Operatol'
++1 IOR di20A02A02S002 f:SIREN                         IMF cmfMVOl_HV155F002
-.. When the crew has completed the isolation of 2C FW heater, Insert KEY 4 to initiate a lockout of 1 C ESS Bus {Key(4]} IMF mfDS104001C 1 C ESS Bus Lockout When directed, Wait 2 Insert KEY 5 to cross-tie Instrument Air to CIG and report when complete {Key[S]} IRF rfPC125001 f:OPEN X-tie I/A to CIG Ensure Event Trigger ETLOC28-NRC03-A fires when the mode switch is placed i.n SHUTDOWN or DW pressure reaches 1.72 psig to terminate the rise in DW leak severity.
++1 IOR di20A02A02S001B f:IN DOR di20A02A02S001A                                   ETLOC28-N RC03-G DOR di20A02A02S001B                                   ;HPCI O/B F003 Binds DOR di20A02A02S002                                    diHS15503.CurrValue = #OR.diHS15503.CLS IMF cmfMV07 _HV155F003 f:90 ETLOC28-NRC03-A pcpdwg > 1.8 I diHSC72AlSOl.CurrValue !=              ETLOC28-NRC03-H
-Role Play As NPO dispatched to ESS Bus 1 C, wait 2 minutes The '1C' ESS bus has a differential trip lockout. Role Play As NPO directed to perform post start checks on the 'C' EOG, wait 2 minutes Post Start checks on the 'C' diesel are SAT. Critical Parameter PCOM D When directed, inserts a manual scram by placing the Mode Switch to SHUTDOWN D Identifies more than 1 control rod > position 00 D Performs Scram report PCOP D IAW ON-104-203, directs NPO to crosstie I/A to CIG D Performs ON-4KV-101 D Informs US of rising OW pressure D Ensures cooling to the 'C' EOG us D Enters ON-4KV-101 D Enters ON-125-001 D Enters TS 3.8.7.A for a required AC distribution system inoperable D Contacts WWM for assistance with the 1C ESS Bus D Prior to 1. 72# in the OW, directs a manual SCRAM The US should direct updates of Drywell Pressure and an action to scram the Unit prior to 1. 72#. Preffered update is every 0.2 psig and preffered scram is at 1.2 psig. LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+#OR.diHSC72AlSOl.RUN                                  rrpdome < 200 MMF mfRR164010 f:O.O                                  MMF cmfMV07 _HV155F003 f:O r:60 c:70 LOC28-NRC03 Rev 1                        Examination Material                                       4/21/2016. 18
-LOC28-NRC03 Event 5, 6 -Electrical ATWS Instructor Activities Operator Activities Notes Bootll Operator Ensure Event Trigger ETLOC28-NRC03-B fires when scram air header pressure falls below 42 psig to initiate a spurious RCIC initiation and fuel failure. I
-* I Critical Task Manually initiate ARI Role Play As NPO dispatched to vent the scram air header, wait 3 minutes I am having issues with the scram air header cap. I am going to get a pipe wrench. Role Play As NPO sent to scram air header, 2 minutes after the above report I still can't get the cap off. I am going to get maintenance support. Role Play As FUS contacted to implement ES-158-001, acknowledge the request PCOM D Arm and Depress Manual Scram Pushbuttons on 1 C651 D Inserts IRMs and SRMs D If directed, Lowers RRP speed to Minimum D If directed, trips RRPs one at a time D If directed, Injects SBLC with HS-14804 D Maintains RPV water level within the ATWS band D Reports Control Rods drifting and "All Rods in" when ARI completes PCOP D Initiates ARI by Arming and Depressing HS-147103A1
+LOC28-NRC03 Event 1 - Turbine Bypass Valve #3 Test Instructor Activities                   Operator Activities            Notes Booth Operator No additional activities required.
-& 81 D If directed, inhibits ADS D If directed, maximizes CRD D If directed, Bypasses MSIV and CIG interlocks us D Enters E0-000-102, RPV control D Transitions to E0-000-113, Level/ Power Control D Transitions back to E0-000-102 when all rods are inserted D May direct PCOP to Inhibit ADS D May direct PCOM to perform the ATWS HC I LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+PCOM Role Play D Monitor diverse indications of reactor As GCC/TCC informed of turbine bypa~s test                  power IAW OP-AD-001 Grid conditions are stable         D As required, performs peer checks thank you for the                  PCOP notification. Inform us when testing is complete.          D When directed, performs BPV #3 testing Role Play                          D Selects position 3 on the BPV TEST If required to prompt the crew
-Instructor Activities Instructor Note LOC28-NRC03 Event 5, 6 -Electrical ATWS Operator Activities us D Directs PCOP to override HPCI D May Direct PCOM to stop and prevent injection with Feedwater and maintain Water level -60" to -11 O" D Directs PCOM to maintain RPV pressure 800 to 1050 psig with Bypass Valves D May direct PCOP to bypass MSIV and CIG interlocks D May direct PCOP to maximize CRD Notes Actions for the fuel failure and high MSL radiation levels are in the next event. Actions for the A TWS in E0-000-113 are dependent upon when all the control rods are inserted with ARI. All of these steps start with 'If directed" or "May direct." LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+* SELECT to perform t.he BPV testing, contact the control room as        D Depress AND Hold TEST BYPASS the Shift Manager                    VALVE pushbutton Have we sta.rted the bypass valve testing?                     D Observes proper light indications and BPV #3 opens fully D Releases TEST BYPASS VALVE pushbutton D Observes proper light indications and BPV #3 closes us D Performs update for performing S0-182-001, Monthly Turbine Bypass Valve Cycling for BPV #3 D Directs PCOP to perform S0-182-001 LOC28-NRC03 Rev 1                               Examination Material               4/21/2016. 19
-LOC28-NRC03 Event 7 -Fuel Failure/ MSIV closure Instructor Activities Operator Activities Notes Booth Operator Ensure Event Trigger ETLOC28-NRC03-C fires when all inboard MSIVs are closed to terminate the elevated radiation readings If directed to evacuate any portion of the power block, use KEY 6 to sound the local evacuation alarm. Perform OP:-009-004 attachment A for the announcement and order for the alarm. {Key[6]} SCN exam\LOCAL_EVAC_ALARM Role Play As WWM contacted for assistance with the fuel failure, wait 5 minutes. The scram air header vented very slowly. The vent ports are somehow restricted.
-The slow control rod drifting caused a number of fuel rods to fail. Role Play As NPO dispatched to investigate a fire alarm in the Reactor Building sump room area, wait 2 minutes Steam was coming from the Reactor Building sumps. I had to leave the room due to dose rates in the area. Role Play As Chemistry contacted for sampling d.ue to the fuel failure, wait 5 minutes Dose rates by the sample stations are preventing us from collecting samples. We are working with RP to gain access. LOC28-NRC03 Rev 1 PCOM D Performs AR-106-F03, Offgas Hi Hi Radiation Alarm D Performs AR-103(104)-D01, Main Steam Line Hi Hi Radiation PCOP D Performs ON-179-001, Increasing Offgas/ MSL Rad Levels D Performs AR-SP-002 for X108_Z1 alarm, observes Fire Pumps Start D Dispatches NPO to investigate RB sump area D When directed, closes all MSIVs and MSL drains us D Enters ON-179-001 for MSL/ Offgas Hi Rad conditions D Directs Unit 2 to perform evacuations of Unit 1 and Unit 2 Turbine Building D Contacts WWM to assist with elevated dose rates D Contacts Chemistry to collect samples due to the fuel failure D Contacts RP to support Chemistry with the samples D Directs closure of MSIVs and MSL drains when MSL Hi Hi Rad Alarm is received Examination Material 4/21/2016.
+LOC28-NRC03 Event 2 - Control Rod insertion to lower power Instructor Activities                      Operator Activities           Notes Booth Operator No additional activities are required.
-LOC28-NRC03 Event 8 -Steam Leaks Instructor Activities Operator Activities Notes Booth Operator Ensure Event Trigger .ETLOC28-NRC03-D fires when the RCIC steam supply valve HV-150-F045 opens to cause a steam leak in the RCIC room. Ensure Event Trigger ETLOC28-NRC03-E fires when the HPCI steam supply valve HV-155-F001 opens to cause an unisolable steam leak in the HPCI room. This trigger may be forced if HPCI is not initiated for water level control. Ensure Event Trigger ETLOC28-NRC03-F fires when HPCI inboard isolation valve HV-155-F002 is stroked to trip its breaker 18237-082.
+PCOM Role Play D Inserts Control Rods IAWOP-156-001, As RE contacted for assistance                             OP-AD-338, and the RMR to lower Core thermal limits are                power to -30%
+within our predictions. You        D Uses two-handed operation to select may proceed with the power reduction.                      the correct control rod D Inserts the selected control rod by Role Play depressing and holding the Insert As Shift Manager contacted for approval                           pushbutton The reactivity manipulation        D Depress the Rod Selct Clear may proceed /AW the RMR.               pushbutton when rod movement is complete D Plots power change on Power/ Flow map D Monitors diverse indications of reactor power IAW OP-AD-001 PCOP D Peer Checks the reactivity maneuver D IAW OP-AD-300, nulls Manual and Automatic regulators using MAN VOLT REG ADJUST HC-10002 D Maintains Load Set -1 OOMWe above actual generator load us D Obtains permission from the SM prior to commencing reactivity manipulations D Informs TCC/GCC of load changes on Unit 1 D Conducts crew update prior to commencing rod insertion D Directs control rod insertion IAW OP-156-001, RMR, and G0-100-012 D Monitors control rod movement with independent RMR LOC28-NRC03 Rev 1                                 Examination Material              4/21/2016. 20
+LOC28-NRC03 Event 2 - Control Rod insertion to lower power Instructor Activities              Operator Activities               Notes LOC28-NRC03 Rev 1                        Examination Material                  4/21/2016. 21
+LOC28-NRC03 Event 3 - FW Heater 2C Tube Leak Instructor Activities                      Operator Activities                               Notes Booth Operator When the bypass valve test circuit has been turned off, Insert KEY ,1 to initiate a tube leak in FW heater 2C.
+The tube leak will take 2-3 minutes to result in a noticeable rise in FW heater level.
+{Key[1]} IMF cmfHX02_1E102C r:300 i:5 f:15                FWH 2C tube leak Once the crew has diagnosed the tube leak and initiated actions to isolate FW heater 2C, if desired, lnse.rt KEY 2 to raise the severity of the leak
+{Key[2]} IMF cmfHX02_1E102C r:60 f:20                     FWH 2C tube leak degrades When directed, Insert KEY 3 to configure FW heater 2C and 3C drains and dumps IAW ON-147-002 Step 3.8
+{Key[3]} SCN exam\LOC28-NRC03-A                           RFP seal water iso PCOM Role Play D Monitors neutron instrumentation for As NPO dispatched to FWH
+ 'C' panel 1C103, wait2               indication of core instability minutes                           PCOP The 2C FW heater level            D Performs AR-120-D10, FW HTR String control and emergency dump valves are                      'C' Dump VLV Full Open responding. Heater level is       D Dispatches NPO to 1C103 to ensure continuing to rise.
+FW Heater 3C to 2C lso VLV is 100%
+Role Play                            OPEN and if FW level control valve As WWM contacted for                 100% open assistance with FW heater         D Performs ON-147-002 to isolate
+ 'C', wait 5 minutes Engineering recommends               extraction steam supplies to 3C, 4C, removing the 2C FW heater            and 5C and to isolated FW heater from service and isolating           string 'C' it.
+D Dispatches NPO to perform ON-147-Role Play                            002 step 3. 7 to configure FW heater As NPOto check FWH level             vent and drain valves after the isolation, wait 1 minute                            D Dispatches NPO to perform ON-147-The 2C FW heater level is           002 step 3.8 to close the RFP Seal slowly lowering                      Water Bleed Off HV-10244C us D Enters ON-147-002 for Anticipated Loss/Loss of Feedwater Heater String D Enters TS 3.2.2 Instructor Cue
+ -4>>)     When the SSE and MSEP drain valves are closed, proceed to Event 4 LOC28-NRC03 Rev 1                                 Examination Material                                  4/21/2016. 22
+LOC28-NRC03 Event 3 - FW Heater 2C Tube Leak Instructor Activities         Operator Activities      Notes LOC28-NRC03 Rev 1                   Examination Material         4/21/2016. 23
+LOC28-NRC03 Event 4 - ESS. Bus 1C lockout/ Reactor Scram Instructor Activities                   Operator Activities                            Notes Booth Operatol' ..
+When the crew has completed the isolation of 2C FW heater, Insert KEY 4 to initiate a lockout of 1C ESS Bus
+{Key(4]} IMF mfDS104001C                                1C ESS Bus Lockout When directed, Wait 2 minut~s. Insert KEY 5 to cross-tie Instrument Air to CIG and report when complete
+{Key[S]} IRF rfPC125001 f:OPEN                         X-tie I/A to CIG Ensure Event Trigger ETLOC28-NRC03-A fires when the mode switch is placed i.n SHUTDOWN or DW pressure reaches 1.72 psig to terminate the rise in DW leak severity.
+PCOM Role Play D When directed, inserts a manual scram As NPO dispatched to ESS Bus 1C, wait 2 minutes             by placing the Mode Switch to The '1C' ESS bus has a             SHUTDOWN differential trip lockout.       D Identifies more than 1 control rod >
+Role Play                          position 00 As NPO directed to perform       D Performs Scram report post start checks on the 'C'     PCOP EOG, wait 2 minutes Post Start checks on the 'C' D IAW ON-104-203, directs NPO to diesel are SAT.                    crosstie I/A to CIG D Performs ON-4KV-101 D Informs US of rising OW pressure D Ensures cooling to the 'C' EOG us D Enters ON-4KV-101 D Enters ON-125-001 D Enters TS 3.8.7.A for a required AC distribution system inoperable D Contacts WWM for assistance with the 1C ESS Bus D Prior to 1. 72# in the OW, directs a manual SCRAM Critical Parameter The US should direct updates of Drywell Pressure and an action to scram the Unit prior to
+: 1. 72#. Preffered update is every 0.2 psig and preffered scram is at 1.2 psig.
+LOC28-NRC03 Rev 1                               Examination Material                                4/21/2016. 24
+LOC28-NRC03 Event 5, 6 - Electrical ATWS Instructor Activities                     Operator Activities                     Notes Bootll Operator Ensure Event Trigger ETLOC28-NRC03-B fires when scram air header pressure falls below 42 psig to initiate I* I a spurious RCIC initiation and fuel failure.
+Critical Task Manually initiate ARI PCOM I
+Role Play D Arm and Depress Manual Scram As NPO dispatched to vent the scram air header, wait 3         Pushbuttons on 1C651 minutes                          D Inserts IRMs and SRMs I am having issues with the      D If directed, Lowers RRP speed to scram air header cap. I am going to get a pipe wrench.          Minimum D If directed, trips RRPs one at a time Role Play                        D If directed, Injects SBLC with HS-As NPO sent to scram air 14804 header, 2 minutes after the above report                     D Maintains RPV water level within the I still can't get the cap off. I     ATWS band am going to get maintenance support.             D Reports Control Rods drifting and "All Rods in" when ARI completes Role Play                        PCOP As FUS contacted to D Initiates ARI by Arming and implement ES-158-001, acknowledge the request              Depressing HS-147103A1 & 81 D If directed, inhibits ADS D If directed, maximizes CRD D If directed, Bypasses MSIV and CIG interlocks us D Enters E0-000-102, RPV control D Transitions to E0-000-113, Level/
+Power Control D Transitions back to E0-000-102 when all rods are inserted D May direct PCOP to Inhibit ADS D May direct PCOM to perform the ATWS HC LOC28-NRC03 Rev 1                                Examination Material                          4/21/2016. 25
+LOC28-NRC03 Event 5, 6 - Electrical ATWS Instructor Activities                    Operator Activities                        Notes us D Directs PCOP to override HPCI D May Direct PCOM to stop and prevent injection with Feedwater and maintain Water level -60" to -11 O" D Directs PCOM to maintain RPV pressure 800 to 1050 psig with Bypass Valves D May direct PCOP to bypass MSIV and CIG interlocks D May direct PCOP to maximize CRD Instructor Note Actions for the fuel failure and high MSL radiation levels are in the next event.
+Actions for the A TWS in E0-000-113 are dependent upon when all the control rods are inserted with ARI. All of these steps start with 'If directed" or "May direct."
+LOC28-NRC03 Rev 1                              Examination Material                           4/21/2016. 26
+LOC28-NRC03 Event 7 - Fuel Failure/ MSIV closure Instructor Activities                    Operator Activities                            Notes Booth Operator Ensure Event Trigger ETLOC28-NRC03-C fires when all inboard MSIVs are closed to terminate the elevated radiation readings If directed to evacuate any portion of the power block, use KEY 6 to sound the local evacuation alarm.
+Perform OP:-009-004 attachment A for the announcement and order for the alarm.
+{Key[6]} SCN exam\LOCAL_EVAC_ALARM PCOM Role Play D Performs AR-106-F03, Offgas Hi Hi As WWM contacted for assistance with the fuel             Radiation Alarm failure, wait 5 minutes.          D Performs AR-103(104)-D01, Main The scram air header                 Steam Line Hi Hi Radiation vented very slowly. The vent ports are somehow            PCOP restricted. The slow              D Performs ON-179-001, Increasing control rod drifting caused Offgas/ MSL Rad Levels a number of fuel rods to fail.                             D Performs AR-SP-002 for X108_Z1 alarm, observes Fire Pumps Start Role Play D Dispatches NPO to investigate RB As NPO dispatched to investigate a fire alarm in the      sump area Reactor Building sump room        D When directed, closes all MSIVs and area, wait 2 minutes MSL drains Steam was coming from the Reactor Building              us sumps. I had to leave the         D Enters ON-179-001 for MSL/ Offgas Hi room due to dose rates in the area.
+Rad conditions D Directs Unit 2 to perform evacuations Role Play                            of Unit 1 and Unit 2 Turbine Building As Chemistry contacted for        D Contacts WWM to assist with elevated sampling d.ue to the fuel failure, wait 5 minutes              dose rates Dose rates by the sample          D Contacts Chemistry to collect samples stations are preventing us due to the fuel failure from collecting samples.
+We are working with RP to         D Contacts RP to support Chemistry with gain access.                         the samples D Directs closure of MSIVs and MSL drains when MSL Hi Hi Rad Alarm is received LOC28-NRC03 Rev 1                                Examination Material                                 4/21/2016. 27
+LOC28-NRC03 Event 8 - Steam Leaks Instructor Activities                   Operator Activities                             Notes Booth Operator Ensure Event Trigger .ETLOC28-NRC03-D fires when the RCIC steam supply valve HV-150-F045 opens to cause a steam leak in the RCIC room.
+Ensure Event Trigger ETLOC28-NRC03-E fires when the HPCI steam supply valve HV-155-F001 opens to cause an unisolable steam leak in the HPCI room. This trigger may be forced if HPCI is not initiated for water level control.
+Ensure Event Trigger ETLOC28-NRC03-F fires when HPCI inboard isolation valve HV-155-F002 is stroked to trip its breaker 18237-082.
 Ensure Event Trigger ETLOC28-NRC03-G fires when HPCI outboa.rd isolation valve HV-155-F003 is stroked to bind the valve in place.
-* Role Play As NPO dispatched to the RCIC room, wait 2 minutes I can hear a steam leak in the RCIC room Role Play As NPO dispatched to the RCIC room after RCIC has been isolated, wait 2 minutes unless already there then report I do not hear steam in the RC/Croom Role Play As NPO dispatched to the HPCI room, wait 2 minutes I can hear steam in the HPClroom Role Play As NPO dispatched to 18237-082, HPCI IB lso valve breaker, wait 2 minutes 18237 breaker 82 is tripped on magnetics Role Play As NPO dispatched to HPCI OB isolation valve F003, wait 2 minutes HV-155-F003 HPCI OB valve is about 50% closed LOC28-NRC03 Rev 1 PCO D Performs AR-108-EOS, RCIC Leak Detection Hi Temp/Hi Diff Temp D Performs AR-114-EOS, HPCI Leak Detection Hi Temp/Hi Diff Temp D Performs AR-SP-002 for X108_Z3 alarm D Dispatches NPO to RCIC room to investigate leak D Dispatches NPO to HPCI room to investigate leak D Isolates RCIC by closing the steam valves D Attempts to isolate HPIC by closing the steam isolation valves D Dispatches NPO to HPCI IB valve breaker 18237-082 D Dispatches NPO to HPCI OB valve to manually close HV-155-F003 D Starts an ESW pump in each loop Examination Material 4/21/2016.
+* PCO Role Play D Performs AR-108-EOS, RCIC Leak As NPO dispatched to the RCIC room, wait 2 minutes           Detection Hi Temp/Hi Diff Temp I can hear a steam leak in      D Performs AR-114-EOS, HPCI Leak the RCIC room                       Detection Hi Temp/Hi Diff Temp Role Play                       D Performs AR-SP-002 for X108_Z3 As NPO dispatched to the           alarm RCIC room after RCIC has        D Dispatches NPO to RCIC room to been isolated, wait 2 minutes investigate leak unless already there then report                          D Dispatches NPO to HPCI room to I do not hear steam in the         investigate leak RC/Croom D Isolates RCIC by closing the steam Role Play                          valves As NPO dispatched to the        D Attempts to isolate HPIC by closing the HPCI room, wait 2 minutes steam isolation valves I can hear steam in the HPClroom                        D Dispatches NPO to HPCI IB valve breaker 18237-082 Role Play D Dispatches NPO to HPCI OB valve to As NPO dispatched to 18237-082, HPCI IB lso             manually close HV-155-F003 valve breaker, wait 2 minutes   D Starts an ESW pump in each loop 18237 breaker 82 is tripped on magnetics Role Play As NPO dispatched to HPCI OB isolation valve F003, wait 2 minutes HV-155-F003 HPCI OB valve is about 50% closed LOC28-NRC03 Rev 1                              Examination Material                                    4/21/2016. 28
-Instructor Activities Role Play As NPO dispatched to manually close HPCI OB valve wait 2 minutes The HPCI OB valve F003 will not move manually.
-Role Play As WWM. contacted for assistance with the HPCI IB valve F002, wait 5 minutes Maintenance believes there is a fault on the HPCI IB valve F002 actuator motor. A Drywell entry will be required to troubleshoot.
+LOC28-NRC03 Event 8 - Steam Leaks Instructor Activities                   Operator Activities                     Notes us Role Play D Enters E0-000-104, Secondary As NPO dispatched to manually close HPCI OB             Containment Control valve HV-155~F003, wait 2       D Directs starting ESW minutes                         D Directs PCO to isolate RCIC The HPCI OB valve F003 will not move manually.         D Directs PCO to isolate HPCI D Contacts WWM for assistance with Role Play isolating HPCI As WWM. contacted for assistance with the HPCI IB     D Contacts WWM for assistance with valve F002, wait 5 minutes         RCIC leak Maintenance believes there is a fault on the HPCI IB valve F002 actuator motor.
-Role Play As WWM contacted for assistance with the HPCI IB valve F003, acknowledge request. If contacted later, report Engineering and Maintenance are still discussing the issue. Critical Parameter LOC28-NRC03 Event 8 -Steam Leaks Operator Activities us D Enters E0-000-104, Secondary Containment Control D Directs starting ESW D Directs PCO to isolate RCIC D Directs PCO to isolate HPCI D Contacts WWM for assistance with isolating HPCI D Contacts WWM for assistance with RCIC leak Notes The US should direct a PCO to monitor RCIC and HPCI room temperatures and Radiation levels. These are key to determining if an Emergency Depressurization is required.
+A Drywell entry will be required to troubleshoot.
+Role Play As WWM contacted for assistance with the HPCI IB valve F003, acknowledge request. If contacted later, report Engineering and Maintenance are still discussing the issue.
+Critical Parameter The US should direct a PCO to monitor RCIC and HPCI room temperatures and Radiation levels. These are key to determining if an Emergency Depressurization is required.
 Instructor Note Event Trigger ETLOC28-NRC03-E will have to be forced if HPCI was not initiated for level control. This will be at the direction of the Chief Evaluator.
-LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+LOC28-NRC03 Rev 1                              Examination Material                         4/21/2016. 29
-LOC28-NRC03 Event 9 -Emergency Depressurization Instructor Activities Operator Activities Notes Booth Operator Ensure Eve.nt Trigger ETLOC28.-NRC03-H fires when reactor pressure falls below 200 psig to allow the HPCI OB isolation valve F003 to close When directed; Insert KEY 7 to opeh ADS SRVs from the Upper Relay Room. Monitor 1C601 ADS SRV solenoid status and report when complete.
-{Key(7]} IOR diHS14113G2 d:60 f:OPEN {Key(7]}10RdiHS14113J2 d:66 f:OPEN {Key(7]} IOR diHS14113K2 d:72 f:OPEN {Key[7]} IOR diHS1.4113L2 d:78 f:OPEN {Key[7]} IOR diHS1411.3M2 d:84 f:OPEN {Key[7]} IOR diHS14113N2 d:90 f:OPEN Critical Task
+LOC28-NRC03 Event 9 - Emergency Depressurization Instructor Activities                   Operator Activities                           Notes Booth Operator Ensure Eve.nt Trigger ETLOC28.-NRC03-H fires when reactor pressure falls below 200 psig to allow the HPCI OB isolation valve F003 to close When directed; Insert KEY 7 to opeh ADS SRVs from the Upper Relay Room. Monitor 1C601 ADS SRV solenoid status and report when complete.
-* Emergency Depressurize the reactor when two Secondary Containment Areas exceed Max Safe Temperature levels LOC28-NRC03 Rev 1 PCO D Prevents injection from RHR pumps not required for adequate core cooling D Prevents injection of Core Spray pumps not required for adequate core cooling D Opens all ADS valves by placing hand switches for the ADS SRVs to open D Restores and maintains RPV level using condensate as reactor pressure lowers D Places RHR is Suppression Pool Cooling IAW OP-149-004 D Places RHRSW in service IAW OP-149-004 Examination Material 4/21/2016.
+{Key(7]} IOR diHS14113G2 d:60 f:OPEN
-Instructor Activities Instructor Note LOC28-NRC03 Event 9 -Emergency Depressurization Operator Activities us D Enters E0-000-112, Emergency De pressurization D Enters E0-000-105 for an unisolated primary leak into secondary containment and SGTS not running D Directs PCO to prevent injection from LPCI and Core Spray pumps not required for adequate core cooling D Directs PCO to open all ADS valves D Directs PCO to restore and maintain RPV level using Condensate D Directs PCO to place Suppression Pool Cooling in service Notes E0-000-105 should be entered when the HPCI leak occurs and after the scram. Ventilation has been secured due to the power failure, SGTS is not running, and a primary leak is occuring.
+{Key(7]}10RdiHS14113J2 d:66 f:OPEN
-This is an unmonitored release. If the crew starts SBGT before the leak, then it will not need to be entered. After the ED, HPCI will isolate and terminate the requirement for entering E0-000-105.
+{Key(7]} IOR diHS14113K2 d:72 f:OPEN
-Instructor Activity -Termination This scenario may be terminated when RPV water level has been stabilized and actions are being taken to place RHR in Suppression Pool cooling OR at the direction of the Chief Examiner.
+{Key[7]} IOR diHS1.4113L2 d:78 f:OPEN
-LOC28-NRC03 Rev 1 Examination Material 4/21/2016.
+{Key[7]} IOR diHS1411.3M2 d:84 f:OPEN
-UNIT SUPERVISOR TURNOVER SHEET UNIT SHIFT 1900 to 0700 Start End MODE POWER LEVEL 33 % 1 MODE "to(dd(yy Date SHIFT 0700 to Start POWER LEVEL 1900 End % --------------GENERATOR OUTPUT 351 MWe GENERATOR OUTPUT MWe CASK STORAGE GATE INSTALLED:
+{Key[7]} IOR diHS14113N2 d:90 f:OPEN Critical Task Emergency Depressurize the reactor when two Secondary Containment Areas exceed
-YES/NO CASK STORAGE GATE INSTALLED:
+* Max Safe Temperature levels PCO D Prevents injection from RHR pumps not required for adequate core cooling D Prevents injection of Core Spray pumps not required for adequate core cooling D Opens all ADS valves by placing hand switches for the ADS SRVs to open D Restores and maintains RPV level using condensate as reactor pressure lowers D Places RHR is Suppression Pool Cooling IAW OP-149-004 D Places RHRSW in service IAW OP-149-004 LOC28-NRC03 Rev 1                             Examination Material                                 4/21/2016. 30
-YES/NO REMARKS: 1) Reactor power approximately 33 percent, 1 RFP in FCM 2) Shutdown in progress to identify and repair small RCS leak in Drywell. Unidentified leak rate 0.5 gpm. ON-100-005 actions are complete.
-Leak rate is stable and 12-hour calculations are being performed.
+LOC28-NRC03 Event 9 - Emergency Depressurization Instructor Activities                 Operator Activities                         Notes us D Enters E0-000-112, Emergency De pressurization D Enters E0-000-105 for an unisolated primary leak into secondary containment and SGTS not running D Directs PCO to prevent injection from LPCI and Core Spray pumps not required for adequate core cooling D Directs PCO to open all ADS valves D Directs PCO to restore and maintain RPV level using Condensate D Directs PCO to place Suppression Pool Cooling in service Instructor Note E0-000-105 should be entered when the HPCI leak occurs and after the scram. Ventilation has been secured due to the power failure, SGTS is not running, and a primary leak is occuring. This is an unmonitored release. If the crew starts SBGT before the leak, then it will not need to be entered. After the ED, HPCI will isolate and terminate the requirement for entering E0-000-105.
-AR-106-A 16 & B 16 are locked in for this condition.
+Instructor Activity - Termination This scenario may be terminated when RPV water level has been stabilized and actions are being taken to place RHR in Suppression Pool cooling OR at the direction of the Chief Examiner.
-: 3) Perform test of Bypass Valve #3 per S0-182-001 for troubleshooting
+LOC28-NRC03 Rev 1                           Examination Material                             4/21/2016. 31
-: 4) Insert Control Rod IAW the RMR to 30% APRM power 5) 6) 7 8) 9) 10 11 12 13 14) 15) COMMON: 1) Unit 2 at rated power 2 3) 4) 5 6) 7) 8 9) FORM OP-AD-003-7, Rev. 23, DUPLEX Page 1 of 2 (Electronic Form) Examination Material NRC SCN 3 OFFGOING UNIT SUPERVISOR CHECKLIST:
-NRC CODE PRIOR TO 0800 FOXTROT DELTA BRAVO OSCAR NRC CODE AFTER 0800 FOXTROT UNIFORM HOTEL ROMEO 1900-0700-0700 1900 0700 1900 --) POST RELIEF 0700 1900 1. Evolutions in progress and items to be completed during next shift, as noted in remarks, have been discussed with oncoming Unit Supervisor (including special evolutions, i.e. SICT/E, OPDRVs, etc.). 2. Problems encountered during past shift and abnormal plant conditions, as noted in remarks, have been discussed with oncoming Unit Supervisor.
+UNIT SUPERVISOR TURNOVER SHEET UNIT          1                   "to(dd(yy Date SHIFT     1900     to   0700                                    SHIFT  0700   to   1900 Start          End                                            Start       End MODE                                                     MODE POWER LEVEL        33               %                    POWER LEVEL                         %
+                  -------                                                -------
+GENERATOR OUTPUT         351        MWe                  GENERATOR OUTPUT                    MWe CASK STORAGE GATE INSTALLED: YES/NO                      CASK STORAGE GATE INSTALLED: YES/NO REMARKS:
+: 1)    Reactor power approximately 33 percent, 1 RFP in FCM
+: 2)    Shutdown in progress to identify and repair small RCS leak in Drywell. Unidentified leak rate 0.5 gpm. ON-100-005 actions are complete. Leak rate is stable and 12-hour calculations are being performed. AR-106-A 16 & B 16 are locked in for this condition.
+: 3)    Perform test of Bypass Valve #3 per S0-182-001 for troubleshooting
+: 4)    Insert Control Rod IAW the RMR to 30% APRM power 5) 6)
+8) 9)
+11 12 13 14) 15)
+COMMON:
+: 1)    Unit 2 at rated power 2
+) 4)
+6) 7)
+9)
+FORM OP-AD-003-7, Rev. 23, DUPLEX Page 1 of 2 (Electronic Form)
+Examination Material                          NRC SCN 3
+OFFGOING UNIT SUPERVISOR CHECKLIST:
+NRC CODE PRIOR TO 0800      FOXTROT               DELTA                BRAVO                 OSCAR NRC CODE AFTER 0800         FOXTROT               UNIFORM              HOTEL                 ROMEO 1900-  0700-0700   1900
+: 1. Evolutions in progress and items to be completed during next shift, as noted in remarks, have been discussed with oncoming Unit Supervisor (including special evolutions, i.e. SICT/E, OPDRVs, etc.).
+: 2. Problems encountered during past shift and abnormal plant conditions, as noted in remarks, have been discussed with oncoming Unit Supervisor.
 : 3. Information in SOMS Log is complete and discussed with oncoming Unit Supervisor.
 : 4. As applicable, turnover plastic Security Badge cover and CRS Monitor function to oncoming Unit Supervisor.
 Offgoing Unit Supervisor ONCOMING UNIT SUPERVISOR CHECKLIST:
+   1900
+  -      -
 : 1. LCO/TRO Log reviewed.
-: 2. SOMS Log reviewed for entries made in past 24 hours. 3. Report any changes to license or medical status PER NDAP-QA-0723.
+)                   2. SOMS Log reviewed for entries made in past 24 hours.
--1900
+: 3. Report any changes to license or medical status PER NDAP-QA-0723.
------------
+-1900 - - - - - - - - - - -
-Oncoming Qualified Unit Supervisor
+Oncoming Qualified Unit Supervisor POST RELIEF 0700   1900
-: 1. Walk down Control Room panels with Unit Responsible PCO. 2. CRC Book reviewed and Reactivity Brief performed with PCO. 3. Completed System Status Operable audit for open PMT this shift. 4. From the OPS Web page, Review OPS Aggregate Index for Challenges, Work Arounds, and Deficiencies Reports for impact on scheduled work activities and compensatory actions. (20 l Oncoming Unit Supervisor FORM OP-AD-003-7, Rev. 23, DUPLEX Page 2 of 2 (Electronic Form) Examination Material NRC SCN 3 SUSQUEHANNA NUCLEAR, LLC OPERATIONS TRAINING PROGRAM SCENARIO EXAMINATION GUIDE EOG SHUTDOWN/
+: 1. Walk down Control Room panels with Unit Responsible PCO.
-CONTROL ROD DRIFT/ T-20 LOCKOUT/ DRYWELL STEAM LEAK/ RPV FLOODING SCN# LOC28-NRC-04 Revision 1 4/26/2016 Examination Material LOC28-NRC-04 Lesson Information Title EOG Shutdown/
+: 2. CRC Book reviewed and Reactivity Brief performed with PCO.
-Failed RPS Reactor Pressure Channel/ Control Rod Drift/ T-20 LockouU Drywell Steam Leak/ RPV Flooding Vision ID Accredited
+: 3. Completed System Status Operable audit for open PMT this shift.
-*YES D NO Training ID Revision 11 Date 14/26/2016 Prerequisites Teaching Time 75 minutes Approval CBT Approval 1 N/A Date N/A Preparer Date Review (lnstructor/SME)
+: 4. From the OPS Web page, Review OPS Aggregate Index for Challenges, Work Arounds, and Deficiencies Reports for impact on scheduled work activities and compensatory actions. (20l Oncoming Unit Supervisor FORM OP-AD-003-7, Rev. 23, DUPLEX Page 2 of 2 (Electronic Form)
-Date Nuclear Engineering 1 N/A Date N/A Training Supervision Date Line Management Date l If required, otherwise N/A This simulator scenario has been reviewed and satisfies management expectations for inclusion of OE, Department Fundamentals and HuP, error-reduction techniques and safety standards.
+Examination Material                                   NRC SCN 3
-Specific applications and/or opportunities for reinforcement of management expectations are noted in the scenario guide or Attachment(s) where applicable.
-Copyrighted by Nuclear Training Group, SUSQUEHANNA NUCLEAR, LLC, 2016. All rights reserved, no part of this training material may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, recording or otherwise, without the prior permission of the Nuclear Training Group. LOC28-NRC-04 Rev 1 Examination Material 4/26/2016.
+SUSQUEHANNA NUCLEAR, LLC OPERATIONS TRAINING PROGRAM SCENARIO EXAMINATION GUIDE EOG SHUTDOWN/ CONTROL ROD DRIFT/ T-20 LOCKOUT/
-LOC28-NRC-04 Revision History Revision Date Comments 0 6/10/2014 New Scenario Updated to new format. Removed the Pressure transmitter failure Event. Changed the 1 4/26/2016 drifting control rod events from drifting in then out to only drifting in. Removed Event to fail an injection valve for a loop of RHR. Added runaway RRP with Event 2. LOC28-NRC-04 Rev 1 Examination Material 4/26/2016
+DRYWELL STEAM LEAK/ RPV FLOODING SCN# LOC28-NRC-04 Revision 1 4/26/2016 Examination Material
-* 3 LOC28-NRC-04 Table of Contents Scenario Overview ................................................................................................................................
-Objectives
+LOC28-NRC-04 Lesson Information Title                EOG Shutdown/ Failed RPS Reactor Pressure Channel/ Control Rod Drift/ T-20 LockouU Drywell Steam Leak/ RPV Flooding Vision ID                                                        Accredited      *YES          D NO Training ID                                          Revision 11                Date 14/26/2016 Prerequisites Teaching Time        75 minutes Approval CBT Approval 1              N/A                                              Date      N/A Preparer                                                                     Date Review (lnstructor/SME)                                                      Date Nuclear Engineering 1       N/A                                              Date      N/A Training Supervision                                                          Date Line Management                                                              Date l
-.............................................................................................................................................
+If required, otherwise N/A This simulator scenario has been reviewed and satisfies management expectations for inclusion of OE, Department Fundamentals and HuP, error-reduction techniques and safety standards. Specific applications and/or opportunities for reinforcement of management expectations are noted in the scenario guide or Attachment(s) where applicable.
-A. Terminal Objective
+Copyrighted by Nuclear Training Group, SUSQUEHANNA NUCLEAR, LLC, 2016. All rights reserved, no part of this training material may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, recording or otherwise, without the prior permission of the Nuclear Training Group.
-................................................................................................................
+LOC28-NRC-04 Rev 1                            Examination Material                               4/26/2016. 2
-B. Generic Performance Objectives
-...........................................................................................
+LOC28-NRC-04 Revision History Revision            Date                                Comments 0             6/10/2014                             New Scenario Updated to new format.
-C. Simulator Performance Objectives
+Removed the Pressure transmitter failure Event. Changed the 1            4/26/2016 drifting control rod events from drifting in then out to only drifting in. Removed Event to fail an injection valve for a loop of RHR.
-........................................................................................
+Added runaway RRP with Event 2.
-D. Task List. ...............................................................................................................................
+LOC28-NRC-04 Rev 1                  Examination Material                                  4/26/2016
-Scenario Attributes
+* 3
-.............................................................................................................................
-A. Critical Tasks .......................................................................................................................
+LOC28-NRC-04 Table of Contents Scenario Overview................................................................................................................................5 Objectives .............................................................................................................................................6 A. Terminal Objective ................................................................................................................6 B. Generic Performance Objectives ...........................................................................................6 C. Simulator Performance Objectives ........................................................................................7 D. Task List. ...............................................................................................................................9 Scenario Attributes .............................................................................................................................11 A. Critical Tasks ....................................................................................................................... 11 B. Scenario Malfunctions ......................................................................................................... 12 C. Abnormal Events and Major Transients ............................................................................... 12 D. EOP and EOP Contingencies Used .................................................................................... 13 E. Technical Specifications ...................................................................................................... 13 References ..........................................................................................................................................14 Setup Instructions ..............................................................................................................................15 A. Required Materials .............................................................................................................. 15 B. Simulator Initialization ......................................................................................................... 15 C. Simulator Preparation .......................................................................................................... 16 D. Document Training and Performance Feedback ................................................................. 16 E. Scenario Execution ............................................................................................................. 16 F. Simulator Files .................................................................................................................... 17 Event 1 - Secure 'B' EDG ....................................................................................................................20 Event 2 - Raise Reactor Power 5% using Recirc flow ......................................................................21 Event 3 - Control rod drift in ..............................................................................................................22 Event 4 - Startup Transformer 20 lockout ......................................................................................... 23 Event 5 - Small RCS steam leak in the Drywell.. ............................................................................... 24 Event 6 - HPCI fails to automatically initiate .....................................................................................24 Event 7 - RHR F016 Drywell Spray valve failure .........................................................................*.....26 Event 8 - RPV Flooding ......................................................................................................................27 LOC28-NRC-04 Rev 1                                          Examination Material                                                          4/26/2016. 4
-B. Scenario Malfunctions
-.........................................................................................................
+LOC28-NRC-04 Scenario Overview The scenario begins with Unit 1 at 90 percent power in a power ascension following a control rod pattern adjustment. Unit 2 is at rated power. RCIC is out of service due to oil system contamination.
-C. Abnormal Events and Major Transients
+The station experienced a less-than-OBE seismic event 6 hours ago due to a magnitude 5.6 earthquake in the Lehigh Valley. The actions of ON-NATPHENOM-001 for the seismic event have been completed. Unit 2 is at rated power.
-...............................................................................
+Diesel Generator B is running and synchronized to ESS Bus 1B in accordance with S0-024-001 B, with the 15-minute run at 1000 KW complete. The first action of the crew is to shutdown DG B in accordance with S0-024-001 B. Then, the crew will raise reactor power by 5 percent per G0-100-012 and Reactor Engineering Reactivity Maneuver Request. During the flow change, the 'A' RRP will runaway. The crew will have to lock the scoop tube to stop the flow change. TS 3.4.1 will have to be reviewed for loop mismatch.
-D. EOP and EOP Contingencies Used ....................................................................................
+Once the DG is shutdown and the power ascension is complete, reactor pressure switch PS-B21-1N023C will spike and then fail downscale. The spike high will result in a reactor half-scram, which must be reset. The pressure switch will be inoperable per TS 3.3.1.1. When the half-scram occurs control rod 50-23 will scram in due to a blown fuse to its B RPS solenoid. When the half-scram is reset, control rod 50-23 will begin drifting out of the core due to stuck collet fingers. The crew will respond per ON-CRD-101 and fully insert the control rod. Action will be required to maintain the control rod fully inserted until the CRD can be hydraulically disarmed per the ON and OP-155-001.
-E. Technical Specifications
-......................................................................................................
-References
-..........................................................................................................................................
-Setup Instructions
-..............................................................................................................................
-A. Required Materials
-..............................................................................................................
-B. Simulator Initialization
-.........................................................................................................
-C. Simulator Preparation
-..........................................................................................................
-D. Document Training and Performance Feedback .................................................................
-E. Scenario Execution
-.............................................................................................................
-F. Simulator Files ....................................................................................................................
-Event 1 -Secure 'B' EDG ....................................................................................................................
-Event 2 -Raise Reactor Power 5% using Recirc flow ......................................................................
-Event 3 -Control rod drift in ..............................................................................................................
-Event 4 -Startup Transformer 20 lockout .........................................................................................
-Event 5 -Small RCS steam leak in the Drywell..
-...............................................................................
-Event 6 -HPCI fails to automatically initiate .....................................................................................
-Event 7 -RHR F016 Drywell Spray valve failure .........................................................................*.....
-Event 8 -RPV Flooding ......................................................................................................................
-LOC28-NRC-04 Rev 1 Examination Material 4/26/2016.
-LOC28-NRC-04 Scenario Overview The scenario begins with Unit 1 at 90 percent power in a power ascension following a control rod pattern adjustment.
-Unit 2 is at rated power. RCIC is out of service due to oil system contamination.
-The station experienced a less-than-OBE seismic event 6 hours ago due to a magnitude 5.6 earthquake in the Lehigh Valley. The actions of ON-NATPHENOM-001 for the seismic event have been completed.
-Unit 2 is at rated power. Diesel Generator B is running and synchronized to ESS Bus 1 B in accordance with S0-024-001 B, with the 15-minute run at 1000 KW complete.
-The first action of the crew is to shutdown DG B in accordance with S0-024-001 B. Then, the crew will raise reactor power by 5 percent per G0-100-012 and Reactor Engineering Reactivity Maneuver Request. During the flow change, the 'A' RRP will runaway. The crew will have to lock the scoop tube to stop the flow change. TS 3.4.1 will have to be reviewed for loop mismatch.
-Once the DG is shutdown and the power ascension is complete, reactor pressure switch PS-B21-1N023C will spike and then fail downscale.
-The spike high will result in a reactor half-scram, which must be reset. The pressure switch will be inoperable per TS 3.3.1.1. When the half-scram occurs control rod 50-23 will scram in due to a blown fuse to its B RPS solenoid.
-When the half-scram is reset, control rod 50-23 will begin drifting out of the core due to stuck collet fingers. The crew will respond per ON-CRD-101 and fully insert the control rod. Action will be required to maintain the control rod fully inserted until the CRD can be hydraulically disarmed per the ON and OP-155-001.
 When the control rod has been hydraulically disarmed, Startup Transformer 20 will experience a lockout. The crew will respond per ON-SUB-001 to restore Recirc Pump cooling and verify ESS Buses transferred to the alternate source. The crew will enter TS 3.8.1 for one offsite AC source inoperable.
-Once activities associated with the loss of T-20 are complete, a small steam leak will develop in the Drywell. The crew will perform ON-RPR-101 actions and will scram the reactor. The leak will degrade after the scram, resulting in a Plant Aux Load Shed and loss of the Feedwater and the normal heat sink. Condensate Pump discharge valves fail open preventing recovery of Condensate.
+Once activities associated with the loss of T-20 are complete, a small steam leak will develop in the Drywell. The crew will perform ON-RPR-101 actions and will scram the reactor. The leak will degrade after the scram, resulting in a Plant Aux Load Shed and loss of the Feedwater and the normal heat sink. Condensate Pump discharge valves fail open preventing recovery of Condensate. HPCI will fail to auto-start, requiring the crew to perform a component by component start of the system for injection.
-HPCI will fail to auto-start, requiring the crew to perform a component by component start of the system for injection.
+The leak size will allow the crew to maintain reactor level during the transient with HPCI.
-The leak size will allow the crew to maintain reactor level during the transient with HPCI. The crew will initiate Suppression Chamber sprays. Once Suppression Chamber pressure exceeds 13 psig, Drywell sprays are required.
+The crew will initiate Suppression Chamber sprays. Once Suppression Chamber pressure exceeds 13 psig, Drywell sprays are required. When Drywell spray is attempted, the first Drywell spray valve opened will experience stem-to-disk separation. The other division of RHR will be placed in Drywell spray.
-When Drywell spray is attempted, the first Drywell spray valve opened will experience stem-to-disk separation.
+Once Drywell sprays are established, high drywell temperature combined with reduced reactor pressure will result in all reactor level instrumentation becoming erratic and unusable. E0-100-114, RPV Flooding, will be used to depressurize the reactor and flood the RPV to the Main Steam Lines.
-The other division of RHR will be placed in Drywell spray. Once Drywell sprays are established, high drywell temperature combined with reduced reactor pressure will result in all reactor level instrumentation becoming erratic and unusable.
+Neither division of RHR will automatically align in the LPCI mode due to failure of the low reactor pressure permissive logic, but both can be manually aligned.
-E0-100-114, RPV Flooding, will be used to depressurize the reactor and flood the RPV to the Main Steam Lines. Neither division of RHR will automatically align in the LPCI mode due to failure of the low reactor pressure permissive logic, but both can be manually aligned. The scenario may be terminated when the crew acknowledges indications of being flooded to the main steam lines OR at the direction of the Chief Examiner.
+The scenario may be terminated when the crew acknowledges indications of being flooded to the main steam lines OR at the direction of the Chief Examiner.
-LOC28-NRC-04 Rev 1 Examination Material 4/26/2016.
+LOC28-NRC-04 Rev 1                              Examination Material                                 4/26/2016. 5
-LOC28-NRC-04 Objectives Mastery of the training content shall be demonstrated by individual and/or crew performance evaluation as specified in this training material and the applicable training program description, in accordance with training procedures.
+LOC28-NRC-04 Objectives Mastery of the training content shall be demonstrated by individual and/or crew performance evaluation as specified in this training material and the applicable training program description, in accordance with training procedures.
 A. Terminal Objective Perform all system operations required to maintain the plant operating safely, or place the plant in a safe condition if a plant shutdown is required During the specified mode of plant I system operation Without error and in accordance with site procedures and management expectations B. Generic Performance Objectives
-: 1. For all activities, exhibit use of the Human Performance Tools, demonstrating the ability to: Use HU tools to effectively control the plant during normal, abnormal, and emergency conditions Use of HU tools will be observable per the standards in HU-AD-003 (SRO) Take every opportunity to coach the team when HU standards are not being met and provide feedback to the team when the HU standards are being met 2. For all activities, exhibit proper use of procedures by: Applying the correct procedure to operate equipment and respond to abnormalities Ensuring procedures are detailed enough to allow precise control of plant evolutions.
+: 1. For all activities, exhibit use of the Human Performance Tools, demonstrating the ability to:
-Demonstrating the ability to: Apply the correct procedure to the situation Use place keeping for accurate implementation Identify any and all areas for procedure improvement Take ownership of and complete the improvement, whenever an area for procedure improvement is identified
+Use HU tools to effectively control the plant during normal, abnormal, and emergency conditions Use of HU tools will be observable per the standards in HU-AD-003 (SRO) Take every opportunity to coach the team when HU standards are not being met and provide feedback to the team when the HU standards are being met
-: 3. Base actions and decisions with a bias toward conservative, safe operation of the plant, demonstrating the ability to: Assure all plant evolutions and work are assessed for Radiological Safety, Industrial Safety, Nuclear Safety, Environmental Safety, or Corporate Safety Once a risk is determined, take appropriate actions to mitigate or minimize risk Request assistance for any activity which requires additional planning, special precautions, and management oversight to adequately manage the risks (SRO) Champion activities that are biased conservatively LOC28-NRC-04 Rev 1 Examination Material 4/26/2016.
+: 2. For all activities, exhibit proper use of procedures by:
-LOC28-NRC-04
+Applying the correct procedure to operate equipment and respond to abnormalities Ensuring procedures are detailed enough to allow precise control of plant evolutions.
-: 4. Demonstrate complete understanding of plant design and system interrelationships, demonstrating the ability to: Work effectively as a team to interpret plant indications and determine an effective response Understand the bases for, and the plant response to, actions being taken 5. Maintain continuous awareness of critical parameters, demonstrating the ability to: Validate parameters by observing multiple independent indications Relay parameter values with value, units, and trend; and include action being taken for an abnormal value or trend Notify supervision of any change to critical parameters (SRO) Assure critical parameters for operational conditions are understood by the team 6. Operate plant systems and equipment within design and operational limits, maintaining relevant parameters within assigned operating bands, demonstrating the ability to: Anticipate the impact of component operation prior to its operation, and then verify that the expected effects occur during and following the operation Take manual actions (in accordance with procedure direction) when automatic actions do not occur Take prompt action to adjust system operating controls before assigned operating bands are exceeded Make reactivity and mode changes as directed by detailed operating procedures and approved reactivity plans C. Simulator Performance Objectives
+Demonstrating the ability to:
-: 1. Plant Startup/Heatup/Power Maneuvers With the plant operating at off-rated conditions Demonstrate the ability to manipulate console controls to safely operate the facility between shutdown and the designated power level 2. Operational Actions and Annunciator Response Correctly identify plant annunciators and indications and perform appropriate remedial actions 3. System Operation, Controls and Instrumentation Accurately identify plant instrumentation and correctly interpret instrument readings to respond to normal, abnormal, and emergency conditions
+Apply the correct procedure to the situation Use place keeping for accurate implementation Identify any and all areas for procedure improvement Take ownership of and complete the improvement, whenever an area for procedure improvement is identified
+: 3. Base actions and decisions with a bias toward conservative, safe operation of the plant, demonstrating the ability to:
+Assure all plant evolutions and work are assessed for Radiological Safety, Industrial Safety, Nuclear Safety, Environmental Safety, or Corporate Safety Once a risk is determined, take appropriate actions to mitigate or minimize risk Request assistance for any activity which requires additional planning, special precautions, and management oversight to adequately manage the risks (SRO) Champion activities that are biased conservatively LOC28-NRC-04 Rev 1                               Examination Material                             4/26/2016. 6
+LOC28-NRC-04
+: 4. Demonstrate complete understanding of plant design and system interrelationships, demonstrating the ability to:
+Work effectively as a team to interpret plant indications and determine an effective response Understand the bases for, and the plant response to, actions being taken
+: 5. Maintain continuous awareness of critical parameters, demonstrating the ability to:
+Validate parameters by observing multiple independent indications Relay parameter values with value, units, and trend; and include action being taken for an abnormal value or trend Notify supervision of any change to critical parameters (SRO) Assure critical parameters for operational conditions are understood by the team
+: 6. Operate plant systems and equipment within design and operational limits, maintaining relevant parameters within assigned operating bands, demonstrating the ability to:
+Anticipate the impact of component operation prior to its operation, and then verify that the expected effects occur during and following the operation Take manual actions (in accordance with procedure direction) when automatic actions do not occur Take prompt action to adjust system operating controls before assigned operating bands are exceeded Make reactivity and mode changes as directed by detailed operating procedures and approved reactivity plans C. Simulator Performance Objectives
+: 1. Plant Startup/Heatup/Power Maneuvers With the plant operating at off-rated conditions Demonstrate the ability to manipulate console controls to safely operate the facility between shutdown and the designated power level
+: 2. Operational Actions and Annunciator Response Correctly identify plant annunciators and indications and perform appropriate remedial actions
+: 3. System Operation, Controls and Instrumentation Accurately identify plant instrumentation and correctly interpret instrument readings to respond to normal, abnormal, and emergency conditions
 : 4. Facility Design and Operating Characteristics Demonstrate the following:
-* An understanding of facility operating characteristics LOC28-NRC-04 Rev 1 Examination Material 4/26/2016
+* An understanding of facility operating characteristics LOC28-NRC-04 Rev 1                            Examination Material                                4/26/2016
-* 7 LOC28-NRC-04
+* 7
+LOC28-NRC-04
 * The ability to safely control the operating characteristics of the facility within prescribed operating boundaries
-: 5. System Loss and Component Level Malfunctions Perform system control manipulations to obtain desired operating results and demonstrate the ability to correctly respond to malfunction/loss of components and the impact of the malfunction/loss on interfacing plant systems 6. Heat Removal Component Operation Safely operate the plant's heat removal components and demonstrate knowledge of the relationship between the heat removal systems and the operation of facility to prevent exceeding System, Structure, or Component (SSC) design limits which include:
+: 5. System Loss and Component Level Malfunctions Perform system control manipulations to obtain desired operating results and demonstrate the ability to correctly respond to malfunction/loss of components and the impact of the malfunction/loss on interfacing plant systems
+: 6. Heat Removal Component Operation Safely operate the plant's heat removal components and demonstrate knowledge of the relationship between the heat removal systems and the operation of facility to prevent exceeding System, Structure, or Component (SSC) design limits which include:
 * Primary coolant systems
 * Emergency coolant systems
-* Decay heat removal systems 7. Auxiliary and Emergency Component Operations Safely operate the plant's auxiliary and emergency components I systems to include the controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment to control release of radioactivity within regulatory limits 8. Reactivity Management Demonstrate knowledge of how reactivity is affected by plant operation and ability to respond to the change in reactivity to protect the safety and integrity of the reactor core 9. Technical Specifications During plant operation with the plant or system in a condition requiring Technical Specification action Identify the deviation and any required actions I notifications
+* Decay heat removal systems
+: 7. Auxiliary and Emergency Component Operations Safely operate the plant's auxiliary and emergency components I systems to include the controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment to control release of radioactivity within regulatory limits
+: 8. Reactivity Management Demonstrate knowledge of how reactivity is affected by plant operation and ability to respond to the change in reactivity to protect the safety and integrity of the reactor core
+: 9. Technical Specifications During plant operation with the plant or system in a condition requiring Technical Specification action Identify the deviation and any required actions I notifications
 : 10. Emergency Plan (if required)
 During plant operation in an emergency condition Recognize conditions covered by the Emergency Plan (SRO) Demonstrate the ability to:
 * Identify and Implement the appropriate Emergency Action Level
-* Use the applicable bases to support an Event Classification on the specified Emergency Action Level LOC28-NRC-04 Rev 1 Examination Material 4/26/2016.
+* Use the applicable bases to support an Event Classification on the specified Emergency Action Level LOC28-NRC-04 Rev 1                             Examination Material                                  4/26/2016. 8
-LOC28-NRC-04
-: 11. Control Room Duties Demonstrate the knowledge and ability to assume the appropriate responsibilities (for the assigned position) associated with the safe operation of the facility 12. Control Room Team Work Demonstrate the ability to function within the Control Room team to comply with station procedures and limits of facility license and respond to plant events using appropriate human performance tools to support safe operation of the facility D. Task List Task Title ID Licensed Operator Apply Technical Specification (TS) And Technical Requirements Manual (TRM) Requirements S-C00-00-1185 Implement Reactivity Manipulations Standards and Communication Requirements S-C00-00-2784 Implement Appropriate Portions Of Operations Standards For System and Equipment Operation S-C00-00-1081 Implement Operations Standards For Error And Event Prevention S-ADM-00-1091 Implement Standards for Shift Operations S-C00-00-2780 Implement Appropriate Portions of Conduct of Operations S-C00-00-1015 Implement Appropriate Portions of Secondary Containment Integrity Control S-C00-00-1020 Implement EOP Cautions S-C00-00-2566 Implement Operations Directives S-C00-00-3130 Ensure Plant Operates IAW the Operating License, Technical Specifications (TS), and Technical S-C00-00-1183 Requirements Manual (TRM) Implement HUMAN PERFORMANCE (HuP) -Standards for Error and Event Prevention S-EPP-00-3068 Reactor Operator Perform the Monthly Diesel Generator Operability Test S-264001-01-013 Implement Reactor Power Maneuvering Envelope for Normal Daily Power Operations (ICS) S-C00-01-4764 Direct the Actions for Loss of Startup Bus 20 S-262001-01-017 Perform Manual HPCI System Startup to Maintain Reactor Water Level S-206000-01-005 Perform the Required Actions for a Rod Drift or Rod Scram S-201001-01-021 Initiate Drywell Sprays S-203000-01-089 Initiate Suppression Chamber Sprays S-203000-01-088 Operate the RHR System in the Suppression Pool Cooling Mode S-203000-01-093 Perform a Manual Initiation of the Automatic Depressurization System S-218000-01-002 Direct ESW System Manual Startup S-276001-01-002 Perform a Manual Startup of the RHR System in LPCI Mode with the System Filled S-203000-01-073 LOC28-NRC-04 Rev 1 Examination Material 4/26/2016.
+LOC28-NRC-04
-LOC28-NRC-04 Task Title ID Senior Reactor Operator Direct and Coordinate Implementation of RPV Control 000000-02-1125 Direct and Coordinate Implementation of Primary Containment Control 000000-02-1126 Direct and Coordinate Implementation of RPV Flooding 000000-02-1131 Implement Reactor Power Maneuvering Envelope for Normal Daily Power Operations (ICS) 000000-02-4 764 Direct Entry into Loss of Startup Bus 20 S-262001-02-007 Direct Entry into CONTROL ROD PROBLEMS S-201001-02-001 LOC28-NRC-04 Rev 1 Examination Material 4/26/2016
+: 11. Control Room Duties Demonstrate the knowledge and ability to assume the appropriate responsibilities (for the assigned position) associated with the safe operation of the facility
-* 10 LOC28-NRC-04 Scenario Attributes A. Critical Tasks 1. Spray the Drywell when Suppression Chamber pressure exceeds 13 psig. Safety Significance Maintenance of primary containment integrity.
+: 12. Control Room Team Work Demonstrate the ability to function within the Control Room team to comply with station procedures and limits of facility license and respond to plant events using appropriate human performance tools to support safe operation of the facility D.      Task List Task Title                                                                                    ID Licensed Operator Apply Technical Specification (TS) And Technical Requirements Manual (TRM) Requirements       S-C00-00-1185 Implement Reactivity Manipulations Standards and Communication Requirements                   S-C00-00-2784 Implement Appropriate Portions Of Operations Standards For System and Equipment Operation     S-C00-00-1081 Implement Operations Standards For Error And Event Prevention                                 S-ADM-00-1091 Implement Standards for Shift Operations                                                      S-C00-00-2780 Implement Appropriate Portions of Conduct of Operations                                       S-C00-00-1015 Implement Appropriate Portions of Secondary Containment Integrity Control                     S-C00-00-1020 Implement EOP Cautions                                                                        S-C00-00-2566 Implement Operations Directives                                                               S-C00-00-3130 Ensure Plant Operates IAW the Operating License, Technical Specifications (TS), and Technical S-C00-00-1183 Requirements Manual (TRM)
+Implement HUMAN PERFORMANCE (HuP) - Standards for Error and Event Prevention                  S-EPP-00-3068 Reactor Operator Perform the Monthly Diesel Generator Operability Test                                         S-264001-01-013 Implement Reactor Power Maneuvering Envelope for Normal Daily Power Operations (ICS)          S-C00-01-4764 Direct the Actions for Loss of Startup Bus 20                                                 S-262001-01-017 Perform Manual HPCI System Startup to Maintain Reactor Water Level                            S-206000-01-005 Perform the Required Actions for a Rod Drift or Rod Scram                                     S-201001-01-021 Initiate Drywell Sprays                                                                       S-203000-01-089 Initiate Suppression Chamber Sprays                                                           S-203000-01-088 Operate the RHR System in the Suppression Pool Cooling Mode                                   S-203000-01-093 Perform a Manual Initiation of the Automatic Depressurization System                          S-218000-01-002 Direct ESW System Manual Startup                                                              S-276001-01-002 Perform a Manual Startup of the RHR System in LPCI Mode with the System Filled                S-203000-01-073 LOC28-NRC-04 Rev 1                                   Examination Material                                  4/26/2016. 9
+LOC28-NRC-04 Task Title                                                                           ID Senior Reactor Operator Direct and Coordinate Implementation of RPV Control                                  000000-02-1125 Direct and Coordinate Implementation of Primary Containment Control                  000000-02-1126 Direct and Coordinate Implementation of RPV Flooding                                 000000-02-1131 Implement Reactor Power Maneuvering Envelope for Normal Daily Power Operations (ICS) 000000-02-4 764 Direct Entry into Loss of Startup Bus 20                                             S-262001-02-007 Direct Entry into CONTROL ROD PROBLEMS                                               S-201001-02-001 LOC28-NRC-04 Rev 1                                 Examination Material                           4/26/2016
+* 10
+LOC28-NRC-04 Scenario Attributes A. Critical Tasks
+: 1. Spray the Drywell when Suppression Chamber pressure exceeds 13 psig.
+Safety Significance        Maintenance of primary containment integrity.
 Consequences for Failure Potential failure of primary containment.
-to Perform Task Indications/Cues for Event Multiple control board and control room indications of suppression Requiring Critical Task chamber and drywell pressures.
+to Perform Task Indications/Cues for Event Multiple control board and control room indications of suppression Requiring Critical Task    chamber and drywell pressures.
-Performance Criteria Start an operable RHR loop. Perform a valve alignment to provide a flowpath for spray. Performance Feedback RHR pump, valve and system flow indications are available.
+Start an operable RHR loop. Perform a valve alignment to provide a Performance Criteria flowpath for spray.
-Multiple indications of Drywell pressure dropping.
+RHR pump, valve and system flow indications are available. Multiple Performance Feedback indications of Drywell pressure dropping.
 : 2. Performs RPV Flooding when RPV water level becomes indeterminate by establishing RPV Flooded to Steamlines.
-Safety Significance Adequate core cooling may be challenged if core submergence cannot be verified.
+Safety Significance        Adequate core cooling may be challenged if core submergence cannot be verified.
-Consequences for Failure Failure to take the EOP actions may result in uncovering the core and to Perform Task breach of the fuel clad due to overheating.
+Consequences for Failure   Failure to take the EOP actions may result in uncovering the core and to Perform Task            breach of the fuel clad due to overheating.
-Indications/Cues for Event RPV water level indication is believed to be erroneous or unbelievable Requiring Critical Task due to failure of all reactor water level indications upscale with no injection and a reactor coolant leak into the Drywell in progress.
+Indications/Cues for Event RPV water level indication is believed to be erroneous or unbelievable due to failure of all reactor water level indications upscale with no Requiring Critical Task injection and a reactor coolant leak into the Drywell in progress.
-Recognize failure of RPV level indication, initiate emergency depressurization by opening ADS Valves, and then increasing RPV Performance Criteria injection until RPV flooded to Main Steam Lines as indicated by a combination of conditions as shown in FLOODED TO STEAMLINES TABLE. Initiating an emergency depressurization causes Reactor pressure to lower to the shutoff head of the low pressure injection systems allowing RPV water level to rise to the point that it reaches the main steam lines and returns to the suppression pool via the SRVs. No single indication can be relied upon in all events to determine conclusively that the RPV has been flooded to the main steam lines, therefore, some combination of Performance Feedback the following conditions need to be established to ensure water fills the lines:
+Recognize failure of RPV level indication, initiate emergency depressurization by opening ADS Valves, and then increasing RPV Performance Criteria       injection until RPV flooded to Main Steam Lines as indicated by a combination of conditions as shown in FLOODED TO STEAMLINES TABLE.
+Initiating an emergency depressurization causes Reactor pressure to lower to the shutoff head of the low pressure injection systems allowing RPV water level to rise to the point that it reaches the main steam lines and returns to the suppression pool via the SRVs. No single indication can be relied upon in all events to determine conclusively that the RPV has been flooded to the main steam lines, therefore, some combination of Performance Feedback       the following conditions need to be established to ensure water fills the lines:
 * SRV tail pipe acoustic monitors cycling .
 * Tail pipe temperatures of open SRVs decrease to subcooled values .
 * Increasing RPV pressure .
 * Suppression Pool Water Level not lowering Verify ADS Valves are open using light red light indication, acoustic monitoring and lowering Reactor pressure.
-LOC28-NRC-04 Rev 1 Examination Material 4/26/2016
+LOC28-NRC-04 Rev 1                         Examination Material                                4/26/2016
-* 11 LOC28-NRC-04 B. Scenario Malfunctions Event Malfunction Operator Action in Response 1 N/A Secure 'B' EOG (S0-024-001 B) 2 Various Raise Reactor Power 5% using Recirc flow, 'A' RRP runs away 3 mfR015500850230055023 Control rod drift in (TS 3.1.3) 4 mfDS003008 Startup Transformer 20 lockout (TS 3.8.1) 5 mfMS183007 Small RCS steam leak in the Orywell 6 Multiple HPCI fails to automatically initiate on high Orywell pressure, all other high-pressure injection lost 7 mfRH149011A(B)
+* 11
-Stem-to-disk separation of RHR F016 Orywell Spray valve 8 Multiple Loss of reactor level indication
--RPV Flooding (E0-000-114)
+LOC28-NRC-04 B. Scenario Malfunctions Event                     Malfunction                           Operator Action in Response 1        N/A                                      Secure 'B' EOG (S0-024-001 B) 2        Various                                  Raise Reactor Power 5% using Recirc flow, 'A' RRP runs away 3        mfR015500850230055023                    Control rod drift in (TS 3.1.3) 4         mfDS003008                               Startup Transformer 20 lockout (TS 3.8.1) 5        mfMS183007                               Small RCS steam leak in the Orywell 6        Multiple                                 HPCI fails to automatically initiate on high Orywell pressure, all other high-pressure injection lost 7        mfRH149011A(B)                           Stem-to-disk separation of RHR F016 Orywell Spray valve 8        Multiple                                 Loss of reactor level indication - RPV Flooding (E0-000-114)
-C. Abnormal Events and Major Transients Malfunction Description R Raise Reactor Power 5% using Recirc flow, 'A' RRP Runaway N Secure 'B' EOG (S0-024-001 B) AE1 Control rod drift in/out AE2 Startup Transformer 20 lockout MT1 Small RCS steam leak in the Orywell MT2 Loss of reactor level indication
+C. Abnormal Events and Major Transients Malfunction                                              Description R         Raise Reactor Power 5% using Recirc flow, 'A' RRP Runaway N         Secure 'B' EOG (S0-024-001 B)
--RPV Flooding (E0-000-114)
+AE1          Control rod drift in/out AE2          Startup Transformer 20 lockout MT1          Small RCS steam leak in the Orywell MT2          Loss of reactor level indication - RPV Flooding (E0-000-114)
-MAE1 HPCI fails to automatically initiate on high Orywell pressure, all other high-pressure injection lost MAE2 Stem-to-disk separation of RHR F016 Orywell Spray valve TS1 RRP flow mismatch (TS 3.4.1) TS2 Control rod drift in/out (TS 3.1.3) TS3 Startup Transformer 20 lockout (TS 3.8.1) LOC28-NRC-04 Rev 1 Examination Material 4/26/2016
+HPCI fails to automatically initiate on high Orywell pressure, all other high-pressure MAE1 injection lost MAE2          Stem-to-disk separation of RHR F016 Orywell Spray valve TS1         RRP flow mismatch (TS 3.4.1)
-* 12 LOC28-NRC-04 D. EOP and EOP Contingencies Used EOPs EOP Contingencies 1Z1 E0-000-102, RPV Control D E0-000-102, Alternate Level Control IZI E0-000-103, Primary Containment Control D E0-000-102, Steam Cooling D E0-000-104, Secondary Containment Control D E0-000-112, Emergency Depressurization D E0-000-105, Radioactivity Release Control D E0-000-113, Power/Level Control 1Z1 E0-000-114, RPV Flooding E. Technical Specifications
+TS2         Control rod drift in/out (TS 3.1.3)
-: 1. TS 3.1.3 2. TS 3.9.5 3. TS 3.8.1 4. TS 3.4.1 LOC28-NRC-04 Rev 1 Control Rod Operability Control Rod Operability
+TS3          Startup Transformer 20 lockout (TS 3.8.1)
--Refueling Electrical Power Systems AC Sources Operating Recirc Loop Flow Mismatch Examination Material 4/26/2016
+LOC28-NRC-04 Rev 1                             Examination Material                                  4/26/2016
+* 12
+LOC28-NRC-04 D. EOP and EOP Contingencies Used EOPs                                                EOP Contingencies 1Z1 E0-000-102, RPV Control                         D E0-000-102, Alternate Level Control IZI E0-000-103, Primary Containment Control         D E0-000-102, Steam Cooling D E0-000-104, Secondary Containment Control         D E0-000-112, Emergency Depressurization D E0-000-105, Radioactivity Release Control         D E0-000-113, Power/Level Control 1Z1 E0-000-114, RPV Flooding E. Technical Specifications
+: 1. TS 3.1.3        Control Rod Operability
+: 2. TS 3.9.5        Control Rod Operability - Refueling
+: 3. TS 3.8.1        Electrical Power Systems AC Sources Operating
+: 4. TS 3.4.1        Recirc Loop Flow Mismatch LOC28-NRC-04 Rev 1                         Examination Material                             4/26/2016
 * 13
-: 1. OP-AD-055
-: 2. OP-AD-300
+LOC28-NRC-04 References
-: 3. OP-AD-338
+: 1. OP-AD-055       Operations Procedure Program
-: 4. OP-054-001
+: 2. OP-AD-300      Administration of Operations
-: 5. OP-155-001
+: 3. OP-AD-338       Reactivity Manipulations Standards and Communication Requirements
-: 6. OP-158-001 G0-100-012 LOC28-NRC-04 References Operations Procedure Program Administration of Operations Reactivity Manipulations Standards and Communication Requirements Emergency Service Water System Control Rod Drive Hydraulic System RPS System Power Maneuvers
+: 4. OP-054-001      Emergency Service Water System
-: 7. 8. S0-024-001 B Monthly Diesel Generator B Operability Test 9. ON-NATPHENOM-001 Severe Weather Natural Phenomena
+: 5. OP-155-001      Control Rod Drive Hydraulic System
-: 10. ON-SUB-001 Loss of Startup Bus 10 or 20 11. ON-SCRAM-101 Reactor Scram 12. ON-CRD-101 Control Rod Malfunctions
+: 6. OP-158-001      RPS System
-: 13. ON-4KV-101 Loss of 4KV Bus 14. ON-RPS-101 Loss of RPS 15. E0-000-102
+: 7. G0-100-012      Power Maneuvers
-: 16. E0-000-103
+: 8. S0-024-001 B   Monthly Diesel Generator B Operability Test
-: 17. E0-000-104
+: 9. ON-NATPHENOM-001      Severe Weather Natural Phenomena
-: 18. E0-000-105
+: 10. ON-SUB-001      Loss of Startup Bus 10 or 20
-: 19. E0-000-112
+: 11. ON-SCRAM-101    Reactor Scram
-: 20. E0-000-114
+: 12. ON-CRD-101      Control Rod Malfunctions
-: 21. EP-RM-004
+: 13. ON-4KV-101      Loss of 4KV Bus
-: 22. EP-PS-100
+: 14. ON-RPS-101      Loss of RPS
-: 23. AR-103-A01
+: 15. E0-000-102      RPV Control
-: 24. AR-103-B02
+: 16. E0-000-103      Primary Containment Control
-: 25. AR-104-H05
+: 17. E0-000-104      Secondary Containment Control
-: 26. AR-109-C05
+: 18. E0-000-105     Radioactivity Release Control
-: 27. TS 3.1.3 28. TS 3.9.5 29. TS 3.8.1 30. TS 3.4.1 LOC28-NRC-04 Rev 1 RPV Control Primary Containment Control Secondary Containment Control Radioactivity Release Control Emergency Rapid Depressurization RPV Flooding EAL Classification Bases Emergency Director Control Room RPS Channel A1/A2 Auto Scram RX Vessel Hi Press Trip Rod Drift LOCA ISO Switch LOOP A Manual Override Control Rod Operability Control Rod Operability-Refueling Electrical Power Systems AC Sources Operating Recirc Loop Flow Mismatch Examination Material 4/26/2016.
+: 19. E0-000-112      Emergency Rapid Depressurization
-LOC28-NRC-04 Setup Instructions A. Required Materials
+: 20. E0-000-114      RPV Flooding
-: 1. US Turnover Sheet a. Unit 1 1) Unit 1 is at -90% power following a rod pattern adjustment
+: 21. EP-RM-004       EAL Classification Bases
-: 2) RCIC is OOS due to contamination of the lube oil system. Estimated RTS is 4 days 3) LCO 3.5.3 entered. Day 2 of the 14 day LCO. 4) Shutdown 'B' EOG IAW S0-024-001 B 5) Raise Reactor Power 5% IAW RMR b. Common and Unit 2 1) Unit 2 at rated power. 2) SSES experienced a less-than-QBE seismic event 6 hours ago due to expected blasting activities by neighboring industrial facilities.
+: 22. EP-PS-100       Emergency Director Control Room
-: 3) Actions IAW ON-NATPHENOM-001 have been completed
+: 23. AR-103-A01      RPS Channel A1/A2 Auto Scram
+: 24. AR-103-B02      RX Vessel Hi Press Trip
+: 25. AR-104-H05      Rod Drift
+: 26. AR-109-C05      LOCA ISO Switch LOOP A Manual Override
+: 27. TS 3.1.3        Control Rod Operability
+: 28. TS 3.9.5        Control Rod Operability- Refueling
+: 29. TS 3.8.1        Electrical Power Systems AC Sources Operating
+: 30. TS 3.4.1        Recirc Loop Flow Mismatch LOC28-NRC-04 Rev 1                    Examination Material                      4/26/2016. 14
+LOC28-NRC-04 Setup Instructions A. Required Materials
+: 1. US Turnover Sheet
+: a.      Unit 1
+: 1)    Unit 1 is at -90% power following a rod pattern adjustment
+: 2)    RCIC is OOS due to contamination of the lube oil system. Estimated RTS is 4 days
+: 3)    LCO 3.5.3 entered. Day 2 of the 14 day LCO.
+: 4)    Shutdown 'B' EOG IAW S0-024-001 B
+: 5)    Raise Reactor Power 5% IAW RMR
+: b.      Common and Unit 2
+: 1)    Unit 2 at rated power.
+: 2)    SSES experienced a less-than-QBE seismic event 6 hours ago due to expected blasting activities by neighboring industrial facilities.
+: 3)    Actions IAW ON-NATPHENOM-001 have been completed
 : 2. Supporting Documents
-: a. S0-024-001 B b. RMR (2 copies) 8. Simulator Initialization
+: a.      S0-024-001 B
+: b.      RMR (2 copies)
+: 8. Simulator Initialization
 : 1. Reset to exam specific IC, Otherwise perform the following
-: a. Reset to IC-20 b. Place the simulator in RUN c. Lower power to 90% with flow d. Set Xe to fast time to burn Xe until power returns to 90% and starts rising e. Set Xe to normal time f. Start the 'B' EOG and sync to 1 B ESS bus IAW S0-024-001 B g. Load the 'B' EOG to 800KW h. Close HV-149-FOO?
+: a.      Reset to IC-20
-& FOOS to isolate RCIC i. Depressurize RCIC using LV-149-F054
+: b.      Place the simulator in RUN
-: j. Run SCN file exam\RCB_RCICOOS
+: c.      Lower power to 90% with flow
-: k. Place the simulator in FREEZE LOC28-NRC-04 Rev 1 Examination Material 4/26/2016
+: d.      Set Xe to fast time to burn Xe until power returns to 90% and starts rising
-* 15 LOC28-NRC-04
+: e.      Set Xe to normal time
+: f.      Start the 'B' EOG and sync to 1B ESS bus IAW S0-024-001 B
+: g. Load the 'B' EOG to 800KW
+: h. Close HV-149-FOO? & FOOS to isolate RCIC
+: i. Depressurize RCIC using LV-149-F054
+: j.      Run SCN file exam\RCB_RCICOOS
+: k.      Place the simulator in FREEZE LOC28-NRC-04 Rev 1                               Examination Material                          4/26/2016
+* 15
+LOC28-NRC-04
 : 2. Run SCN file exam\LOC28-NRC-04.scn
-: 3. Place the simulator in RUN 4. Perform simulator activities
+: 3. Place the simulator in RUN
-: a. Place a status control tags on HV-149-FOO?, F008 & F088 b. Place the protected equipment magnets on HPCI c. Place the 'surveillance in progress' sign on 'B' EOG d. Ensure the 'Diesel B Power & Vars' R*Time screen under 'Trends' is displayed by the EDGs with it ranged properly e. Post Blue reactivity signs 5. Verify the simulator matches the following MF RF OR ET CONDITIONS 18:18 2:2 0:0 4 16 6. Ensure FW Control is selected to LEFM 7. Reset ODAs and all Overhead, R*TIME, HMI and RWM alarms 8. Ensure horns and annunciators are on 9. Ensure Overhead Lights Override is off C. Simulator Preparation
+: 4. Perform simulator activities
-: 1. Ensure the EOL CRC Book is at the PCO Console D. Document Training and Performance Feedback 1. Record crew position assignments in G:\NTGOPS\LOR\REQUAL\lnfo Tracking\ (LOR) 2. Record crew position assignments per TQ-104 (ILO) 3. Complete an IER 11-3 Operator Fundamentals Simulator Observer Aid 4. Complete simulator checklists E. Scenario Execution
+: a. Place a status control tags on HV-149-FOO?, F008 & F088
-: 1. Identify performance improvement actions that may be addressed during the scenario 2. Provide turnover to the crew using the US Turnover sheet 3. Direct the crew to walk down the Control Room panels 4. Inform the Shift Manager that the crew has the shift LOC28-NRC-04 Rev 1 Examination Material 4/26/2016
+: b. Place the protected equipment magnets on HPCI
-* 16 LOC28-NRC-04 F. Simulator Files LOC28-NRC-04 de Imp SCN rat_mp insmp lssblpos(68) changemp lssblpos(68)
+: c. Place the 'surveillance in progress' sign on 'B' EOG
-,,,CONTROL ROD 50-23 POS insmp aoTRSHB311R601E.CurrValue changemp aoTRSHB311R601E.CurrValue 0,300,DEG F,RECIRC PP A MTR WDG TEMP insmp aoTRSHB311R601Q.CurrValue changemp aoTRSHB311R601Q.CurrValue 0,300,DEG F,RECIRC PP B MTR WDG TEMP insmp aoFl15120AB.CurrValue changemp aoFl15120AB.CurrValue 0,750,GPM,RHR A SC SPRAY FL insmp aoFl15120BB.CurrValue changemp aoFl15120BB.CurrValue 0,750,GPM,RHR B SC SPRAY FL insmp aoFl15120AA.CurrValue changemp aoFl15120AA.CurrValue 0,12000,GPM,RHR A DW SPRAY FL insmp aoFl15120BA.CurrValue changemp aoFl15120BA.CurrValue 0,12000,GPM,RHR B DW SPRAY FL insmp aoTRSB211R614A.CurrValue changemp aoTRSB211R614A.CurrValue 0,600,DEG F,ADS/SRV G TAILPIPE TEMP ;B CRM spurious alarm suppressed IMF annAR112G04 f:ALARM_OFF
+: d. Ensure the 'Diesel B Power & Vars' R*Time screen under 'Trends' is displayed by the EDGs with it ranged properly
-; DW spray valves stem-to-disk failure IMF mfRH149011A f:O.O IMF mfRH149011B f:O.O ; Condensate pump discharge valves fail IMF cmfMV09_HV10502A f:lOO IMF cmfMV09_HV10502B f:lOO IMF cmfMV09_HV10502C f:lOO IMF cmfMV09_HV10502D f:lOO ; H PCI auto-start fa ii u re IMF mfHP152002 IMF cmfMV06_HV155F001 IMF cmfMV06_HV155F006 IMF cmfMV06_HV156F059 IMF cmfPM04_1P213
+: e. Post Blue reactivity signs
-; LPCI injection valves fail IMF cmfRLOl_ElllK66A IMF cmfRLOl_ElllK66B IMF cmfRLOl_ElllK67A IMF cmfRLOl_ElllK67B aet ETLOC28-NRC04-A aet ETLOC28-NRC04-B aet ETLOC28-NRC04-C aet ETLOC28-NRC04-E Flow ; Steam leak degrades on scram ; Allow other division of DW spray ; Allow other division of DW spray ; Runaway RRP at 95.5 Mlbm Core ; Drift Control Rod 50-23 In {Key[l]} IMF mfRD1550085023
+: 5. Verify the simulator matches the following MF                 RF                 OR           ET          CONDITIONS 18:18               2:2                0:0           4                16
-; Hyd disarm HCU 50-23 {Key[2)} IRF rfRD1550075023 d:120 f:DISARM {Key[2)} DMF mfRD1550085023
+: 6. Ensure FW Control is selected to LEFM
-; T-20 lockout {Key[3)} IMF mfDS003008
+: 7. Reset ODAs and all Overhead, R*TIME, HMI and RWM alarms
-; Small steam leak in DW {Key(4)} IMF mfMS183007 r:600 f:0.02 ; Raise severity of steam leak {Key[5)} MMF mfMS183007 r:O f:0.05 ; Failure of rx level instr {Key[6)} SCN exam\LOC28-NRC04-C
+: 8. Ensure horns and annunciators are on
-; Backup ADS {Key[7)} IOR diHS14113G2 d:60 f:OPEN {Key[7)} IOR diHS14113J2 d:66 f:OPEN {Key[7)} IOR diHS14113K2 d:72 f:OPEN {Key[7)} IOR diHS14113L2 d:78 f:OPEN {Key(7)} IOR diHS14113M2 d:84 f:OPEN {Key[7)} IOR diHS14113N2 d:90 f:OPEN ; Reset Rad Monitors {Key[8)} SCN exam\RMA_DIV2RST LOC28-NRC04-A
+: 9. Ensure Overhead Lights Override is off C. Simulator Preparation
-; NR/WR ref leg break ;IMF mfRR180002 f:lOO ;IMF mfRR180001 f:lOO ;RCIC/HPCI L8 trip IMF cmfRL02_E411Kll IMF cmfRLOl_E411K4 IMF cmfRL02_E511K58 IMF cmfRLOl_ElllK79B IMF cmfRLOl_ElllK80B IMF mfRC150001
+: 1. Ensure the EOL CRC Book is at the PCO Console D. Document Training and Performance Feedback
-;ADS L3 confirmatory IMF cmfRLOl_B21ClK12A IMF cmfRLOl_B21ClK12B
+: 1. Record crew position assignments in G:\NTGOPS\LOR\REQUAL\lnfo Tracking\ (LOR)
-;NR N004 ;IMF cmfTR02 PDTC321N004A f:60 IMF cmfTD03_PDTC321N004A f:60 IMF mfRR164022A f:61.2 LOC28-NRC-04 Rev 1 Examination Material 4/26/2016
+: 2. Record crew position assignments per TQ-104 (ILO)
-* 17
+: 3. Complete an IER 11-3 Operator Fundamentals Simulator Observer Aid
-;IMF cmfTR02_PDTC321N004B f:60 IMF cmfTD03_PDTC321N004B f:60 IMF mfRR164022B f:61.2 ;IMF cmfTR02_PDTC321N004C f:60 IMF cmfTD03_PDTC321N004C f:60 IMF mfRR164022C f:61.2 ;NR N042 IMF cmfNBOl_LISB211N042A IOR aoLISB211N042A_Q f:60 IMF cmfNBOl_LISB211N042B IOR aoLISB211N042B_Q f:60 ;NR N024 IMF cmfNBOl_LISB211N024Al IOR aoLISB211N024A_Q f:60 IMF cmfNBOl_LISB211N024Bl IOR aoLISB211N024B_Q f:60 IMF cmfNBOl_LISB211N024Cl IOR aoLISB211N024C_Q f:60 IMF cmfNBOl_LISB211N024Dl IOR aoLISB211N024D_Q f:60 ;WR N031 IMF cmfNBOl_LISB211N031Al IMF cmfNBOl_LISB211N031A2 IOR aoLISB211N031A_Q f:+60 IMF cmfNBOl_LISB211N031Bl IMF cmfNBOl_LISB211N031B2 IOR aoLISB211N031B_Q f:+60 IMF cmfNBOl_LISB211N031Cl IMF cmfNBOl_LISB211N031C2 IOR aoLISB211N031C_Q f:+60 IMF cmfNBOl_LISB211N031Dl IMF cmfNBOl_LISB211N031D2 IOR aoLISB211N031D_Q f:+60 ;WR N025 IMF cmfNBOl_LISB211N025A IOR aoLISB211N025A_Q f:+60 IMF cmfNBOl_LISB211N025B IOR aoLISB211N025B_Q f:+60 IMF cmfNBOl_LISB211N025C IOR aoLISB211N025C_Q f:+60 IMF cmfNBOl_LISB211N025D IOR aoLISB211N025D_Q f:+60 ;WR n026 IMF cmfNBOl_LISB211N026Al IMF cmfNBOl_LISB211N026A2 IMF cmfTR02_LITSB211N026A f:60 IMF cmfNBOl_LISB211N026Bl IMF cmfNBOl_LISB211N026B2 IMF cmfTR02_LITSB211N026B f:60 IMF cmfNBOl_LISB211N026Cl IMF cmfNBOl_LISB211N026C2 IMF cmfTR02_LITSB211N026C f:60 IMF cmfNBOl_LISB211N026Dl IMF cmfNBOl_LISB211N026D2 IMF cmfTR02_LITSB211N026D f:60 ;other wr LOC28-NRC-04 Rev 1 LOC28-NRC-04 IMF cmfTR02_LT14201A f:60 IMF cmfTR02_LT14201B f:60 ;dwclg IMF cmfNBOl_LIS14221C IOR aoLIS14221C_Q f:60 IMF cmfNBOl_LIS14221D IOR aoLIS14221D_Q f:60 ; ER IMF cmfTR02_LT14203A f:180 IMF cmfTR02_LT14203B f:180 ; UR ;IMF cmfTR02_PDTC321N017 f:180 IMF cmfTD03_PDTC321N017 f:180 ; S/D IMF cmfTR02_LTB211N027 f:SOO ; fuel zone IMF cmfTR02_LT14202A f:-110 IMF cmfTR02_LT14202B f:-110 LOC28-NRC04-B
+: 4. Complete simulator checklists E. Scenario Execution
-; NR/WR ref leg break ;DMF mfRR180002 f:lOO ;DMF mfRR180001 f:lOO ;RCIC/HPCI LS trip DMF cmfRL02_E411Kll DMF cmfRLOl_E411K4 DMF cmfRL02_E511K58 DMF cmfRLOl_ElllK79B DMF cmfRLOl_ElllK80B DMF mfRC150001
+: 1. Identify performance improvement actions that may be addressed during the scenario
-;ADS L3 confirmatory DMF cmfRLOl_B21ClK12A DMF cmfRLOl_B21ClK12B
+: 2. Provide turnover to the crew using the US Turnover sheet
-;NR N004 ;DMF cmfTR02 PDTC321N004A DMF cmfTD03_PDTC321N004A DMF mfRR164022A
+: 3. Direct the crew to walk down the Control Room panels
-;DMF cmfTR02_PDTC321N004B DMF cmfTD03_PDTC321N004B DMF mfRR164022B
+: 4. Inform the Shift Manager that the crew has the shift LOC28-NRC-04 Rev 1                             Examination Material                          4/26/2016
-;DMF cmfTR02_PDTC321N004C DMF cmfTD03_PDTC321N004C DMF mfRR164022C
+* 16
-;NR N042 DMF cmfNBOl_LISB211N042A DOR aoLISB211N042A_Q DMF cmfNBOl_LISB211N042B DOR aoLISB211N042B_Q
-;NR N024 DMF cmfNBOl_LISB211N024Al DOR aoLISB211N024A_Q Examination Material 4/26/2016.
+LOC28-NRC-04 F.       Simulator Files LOC28-NRC-04                                                    IMF cmfRLOl_ElllK67B de Imp SCN rat_mp                                                      aet ETLOC28-NRC04-A            ; Steam leak degrades on scram aet ETLOC28-NRC04-B            ; Allow other division of DW spray insmp lssblpos(68)                                              aet ETLOC28-NRC04-C            ; Allow other division of DW spray changemp lssblpos(68) ,,,CONTROL ROD 50-23 POS                  aet ETLOC28-NRC04-E            ; Runaway RRP at 95.5 Mlbm Core Flow insmp aoTRSHB311R601E.CurrValue changemp aoTRSHB311R601E.CurrValue 0,300,DEG F,RECIRC           ; Drift Control Rod 50-23 In PP A MTR WDG TEMP                                               {Key[l]} IMF mfRD1550085023 insmp aoTRSHB311R601Q.CurrValue                                 ; Hyd disarm HCU 50-23 changemp aoTRSHB311R601Q.CurrValue 0,300,DEG F,RECIRC           {Key[2)} IRF rfRD1550075023 d:120 f:DISARM PP B MTR WDG TEMP                                               {Key[2)} DMF mfRD1550085023 insmp aoFl15120AB.CurrValue                                     ; T-20 lockout changemp aoFl15120AB.CurrValue 0,750,GPM,RHR A SC SPRAY         {Key[3)} IMF mfDS003008 FL
-DMF emfNBOl_LISB211N024Bl DOR aoLISB211N024B_Q DMF emfNBOl_LISB211N024Cl DOR aoLISB211N024C_Q DMF emfNBOl_LISB211N024Dl DOR aoLISB211N024D_Q
+                                                                ; Small steam leak in DW insmp aoFl15120BB.CurrValue                                     {Key(4)} IMF mfMS183007 r:600 f:0.02 changemp aoFl15120BB.CurrValue 0,750,GPM,RHR B SC SPRAY FL                                                              ; Raise severity of steam leak
-;WR N031 DMF emfNBOl_LISB211N031Al DMF emfNBOl_LISB211N031A2 DOR aoLISB211N031A_Q DMF emfNBOl_LISB211N031Bl DMF emfNBOl_LISB211N031B2 DOR aoLISB211N031B_Q DMF emfNBOl_LISB211N031Cl DMF emfNBOl_LISB211N031C2 DOR aoLISB211N031C_Q DMF emfNBOl_LISB211N031Dl DMF emfNBOl_LISB211N031D2 DOR aoLISB211N031D_Q
+{Key[5)} MMF mfMS183007 r:O f:0.05 insmp aoFl15120AA.CurrValue changemp aoFl15120AA.CurrValue 0,12000,GPM,RHR A DW             ; Failure of rx level instr SPRAY FL                                                        {Key[6)} SCN exam\LOC28-NRC04-C insmp aoFl15120BA.CurrValue                                     ; Backup ADS changemp aoFl15120BA.CurrValue 0,12000,GPM,RHR B DW             {Key[7)} IOR diHS14113G2 d:60 f:OPEN SPRAY FL                                                        {Key[7)} IOR diHS14113J2 d:66 f:OPEN
-;WR N025 DMF cmfNBOl_LISB211N025A DOR aoLISB211N025A_Q DMF emfNBOl_LISB211N025B DOR aoLISB211N025B_Q DMF emfNBOl_LISB211N025C DOR aoLISB211N025C_Q DMF emfNBOl_LISB211N025D DOR aoLISB211N025D_Q
+{Key[7)} IOR diHS14113K2 d:72 f:OPEN insmp aoTRSB211R614A.CurrValue                                  {Key[7)} IOR diHS14113L2 d:78 f:OPEN changemp aoTRSB211R614A.CurrValue 0,600,DEG F,ADS/SRV G         {Key(7)} IOR diHS14113M2 d:84 f:OPEN TAILPIPE TEMP                                                   {Key[7)} IOR diHS14113N2 d:90 f:OPEN
-;WR n026 DMF cmfNBOl_LISB211N026Al DMF cmfNBOl_LISB211N026A2 DMF cmffR02_LITSB211N026A DMF cmfNBOl_LISB211N026Bl DMF cmfNBOl_LISB211N026B2 DMF cmffR02_LITSB211N026B DMF cmfNBOl_LISB211N026Cl DMF cmfNBOl_LISB211N026C2 DMF cmffR02_LITSB211N026C DMF cmfNBOl_LISB211N026Dl DMF cmfNBOl_LISB211N026D2 DMF cmffR02_LITSB211N026D
+;B CRM spurious alarm suppressed                                ; Reset Rad Monitors IMF annAR112G04 f:ALARM_OFF                                     {Key[8)} SCN exam\RMA_DIV2RST
-;other wr DMF cmffR02_LT14201A DMF cmffR02_LT14201B
+; DW spray valves stem-to-disk failure                          LOC28-NRC04-A IMF mfRH149011A f:O.O                                           ; NR/WR ref leg break IMF mfRH149011B f:O.O                                           ;IMF mfRR180002 f:lOO
-;dwclg DMF cmfNBOl_LIS14221C DOR aoLIS14221C_Q DMF emfNBOl_LIS14221D DOR aoLIS14221D_Q
+                                                                ;IMF mfRR180001 f:lOO
-; ER DMF cmffR02_LT14203A DMF cmffR02_LT14203B
+; Condensate pump discharge valves fail IMF cmfMV09_HV10502A f:lOO                                      ;RCIC/HPCI L8 trip IMF cmfMV09_HV10502B f:lOO                                      IMF cmfRL02_E411Kll IMF cmfMV09_HV10502C f:lOO                                      IMF cmfRLOl_E411K4 IMF cmfMV09_HV10502D f:lOO                                      IMF cmfRL02_E511K58 IMF cmfRLOl_ElllK79B
-; UR ;DMF cmffR02_PDTC321N017 DMF cmffD03_PDTC321N017 LOC28-NRC-04 Rev 1 LOC28-NRC-04
+; H PCI auto-start fa ii u re                                   IMF cmfRLOl_ElllK80B IMF mfHP152002                                                  IMF mfRC150001 IMF cmfMV06_HV155F001 IMF cmfMV06_HV155F006                                           ;ADS L3 confirmatory IMF cmfMV06_HV156F059                                           IMF cmfRLOl_B21ClK12A IMF cmfPM04_1P213                                               IMF cmfRLOl_B21ClK12B
-; S/D DMF emffR02_LTB211N027
+; LPCI injection valves fail                                    ;NR N004 IMF cmfRLOl_ElllK66A                                            ;IMF cmfTR02 PDTC321N004A f:60 IMF cmfRLOl_ElllK66B                                            IMF cmfTD03_PDTC321N004A f:60 IMF cmfRLOl_ElllK67A                                            IMF mfRR164022A f:61.2 LOC28-NRC-04 Rev 1                                 Examination Material                                             4/26/2016
-; fuel zone DMF emffR02_LT14202A DMF emffR02_LT14202B LOC28-NRC04-C sen exam\LOC28-NRC04-A
+* 17
-+5 sen exam\LOC28-NRC04-B
-+30 sen exam\LOC28-NRC04-A
+LOC28-NRC-04
-+3 sen exam\LOC28-NRC04-B
+;IMF cmfTR02_PDTC321N004B f:60              IMF cmfTR02_LT14201A f:60 IMF cmfTD03_PDTC321N004B f:60               IMF cmfTR02_LT14201B f:60 IMF mfRR164022B f:61.2
-+30 sen exam\LOC28-NRC04-A LOC28-NRC04-D
+;IMF cmfTR02_PDTC321N004C f:60              ;dwclg IMF cmfTD03_PDTC321N004C f:60               IMF cmfNBOl_LIS14221C IMF mfRR164022C f:61.2                      IOR aoLIS14221C_Q f:60 IMF cmfNBOl_LIS14221D
-;Revision/Date:
+;NR N042                                    IOR aoLIS14221D_Q f:60 IMF cmfNBOl_LISB211N042A IOR aoLISB211N042A_Q f:60                   ; ER IMF cmfNBOl_LISB211N042B                    IMF cmfTR02_LT14203A f:180 IOR aoLISB211N042B_Q f:60                   IMF cmfTR02_LT14203B f:180
-/09/18/2016
+;NR N024                                    ; UR IMF cmfNBOl_LISB211N024Al                   ;IMF cmfTR02_PDTC321N017 f:180 IOR aoLISB211N024A_Q f:60                   IMF cmfTD03_PDTC321N017 f:180 IMF cmfNBOl_LISB211N024Bl IOR aoLISB211N024B_Q f:60                   ; S/D IMF cmfNBOl_LISB211N024Cl                   IMF cmfTR02_LTB211N027 f:SOO IOR aoLISB211N024C_Q f:60 IMF cmfNBOl_LISB211N024Dl                   ; fuel zone IOR aoLISB211N024D_Q f:60                   IMF cmfTR02_LT14202A f:-110 IMF cmfTR02_LT14202B f:-110
-;Deseription:Recirc A speed failure High set fx1A_MAN_MODE_B200D.BI01=1
+;WR N031 IMF cmfNBOl_LISB211N031Al IMF cmfNBOl_LISB211N031A2                   LOC28-NRC04-B IOR aoLISB211N031A_Q f:+60                  ; NR/WR ref leg break IMF cmfNBOl_LISB211N031Bl                   ;DMF mfRR180002 f:lOO IMF cmfNBOl_LISB211N031B2                   ;DMF mfRR180001 f:lOO IOR aoLISB211N031B_Q f:+60 IMF cmfNBOl_LISB211N031Cl                   ;RCIC/HPCI LS trip IMF cmfNBOl_LISB211N031C2                   DMF cmfRL02_E411Kll IOR aoLISB211N031C_Q f:+60                  DMF cmfRLOl_E411K4 IMF cmfNBOl_LISB211N031Dl                   DMF cmfRL02_E511K58 IMF cmfNBOl_LISB211N031D2                   DMF cmfRLOl_ElllK79B IOR aoLISB211N031D_Q f:+60                  DMF cmfRLOl_ElllK80B DMF mfRC150001
-+l set fx1A_MAN_MODE_B200D.BI01=1
+;WR N025 IMF cmfNBOl_LISB211N025A                    ;ADS L3 confirmatory IOR aoLISB211N025A_Q f:+60                  DMF cmfRLOl_B21ClK12A IMF cmfNBOl_LISB211N025B                    DMF cmfRLOl_B21ClK12B IOR aoLISB211N025B_Q f:+60 IMF cmfNBOl_LISB211N025C                    ;NR N004 IOR aoLISB211N025C_Q f:+60                  ;DMF cmfTR02 PDTC321N004A IMF cmfNBOl_LISB211N025D                    DMF cmfTD03_PDTC321N004A IOR aoLISB211N025D_Q f:+60                  DMF mfRR164022A
-+1 set fx1A_MAN_MODE_B200D.BI01=1
+                                            ;DMF cmfTR02_PDTC321N004B
-+l set fx1A_MAN_MODE_B200D.BI01=1
+;WR n026                                    DMF cmfTD03_PDTC321N004B IMF cmfNBOl_LISB211N026Al                   DMF mfRR164022B IMF cmfNBOl_LISB211N026A2                   ;DMF cmfTR02_PDTC321N004C IMF cmfTR02_LITSB211N026A f:60              DMF cmfTD03_PDTC321N004C IMF cmfNBOl_LISB211N026Bl                   DMF mfRR164022C IMF cmfNBOl_LISB211N026B2 IMF cmfTR02_LITSB211N026B f:60              ;NR N042 IMF cmfNBOl_LISB211N026Cl                   DMF cmfNBOl_LISB211N042A IMF cmfNBOl_LISB211N026C2                   DOR aoLISB211N042A_Q IMF cmfTR02_LITSB211N026C f:60              DMF cmfNBOl_LISB211N042B IMF cmfNBOl_LISB211N026Dl                   DOR aoLISB211N042B_Q IMF cmfNBOl_LISB211N026D2 IMF cmfTR02_LITSB211N026D f:60              ;NR N024 DMF cmfNBOl_LISB211N024Al
-+1 set fx1A_MAN_MODE_B200D.BI01=1
+;other wr                                   DOR aoLISB211N024A_Q LOC28-NRC-04 Rev 1             Examination Material                        4/26/2016. 18
-+ 1 set fx1A_MAN_MODE_B200D.BI01=1
-+ 1 set fx1A_MAN_MODE_B200D.BI01=1
+LOC28-NRC-04 DMF emfNBOl_LISB211N024Bl DOR aoLISB211N024B_Q                   ; S/D DMF emfNBOl_LISB211N024Cl              DMF emffR02_LTB211N027 DOR aoLISB211N024C_Q DMF emfNBOl_LISB211N024Dl              ; fuel zone DOR aoLISB211N024D_Q                   DMF emffR02_LT14202A DMF emffR02_LT14202B
-+1 set fx1A_MAN_MODE_B200D.BI01=1
+;WR N031 DMF emfNBOl_LISB211N031Al DMF emfNBOl_LISB211N031A2              LOC28-NRC04-C DOR aoLISB211N031A_Q                      sen exam\LOC28-NRC04-A DMF emfNBOl_LISB211N031Bl              +5 sen exam\LOC28-NRC04-B DMF emfNBOl_LISB211N031B2              +30 sen exam\LOC28-NRC04-A DOR aoLISB211N031B_Q                   +3 sen exam\LOC28-NRC04-B DMF emfNBOl_LISB211N031Cl              +30 sen exam\LOC28-NRC04-A DMF emfNBOl_LISB211N031C2 DOR aoLISB211N031C_Q DMF emfNBOl_LISB211N031Dl               LOC28-NRC04-D DMF emfNBOl_LISB211N031D2              ;Revision/Date: 1/09/18/2016 DOR aoLISB211N031D_Q                   ;Deseription:Recirc A speed failure High
-+ 1 set fx1A_MAN_MODE_B200D.BI01=1
+;WR N025                               set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N025A               +l set fx1A_MAN_MODE_B200D.BI01=1 DOR aoLISB211N025A_Q                   +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF emfNBOl_LISB211N025B               +l set fx1A_MAN_MODE_B200D.BI01=1 DOR aoLISB211N025B_Q                   +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF emfNBOl_LISB211N025C               +1 set fx1A_MAN_MODE_B200D.BI01=1 DOR aoLISB211N025C_Q                   +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF emfNBOl_LISB211N025D               +1 set fx1A_MAN_MODE_B200D.BI01=1 DOR aoLISB211N025D_Q                   + 1 set fx1A_MAN_MODE_B200D.BI01=1
-+1 set fx1A_MAN_MODE_B200D.BI01=1
+                                       +1 set fx1A_MAN_MODE_B200D.BI01=1
-+1 set fx1A_MAN_MODE_B200D.BI01=1
+;WR n026                               +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026Al              +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026A2              +l set fx1A_MAN_MODE_B200D.BI01=1 DMF cmffR02_LITSB211N026A              +l set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026Bl              +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026B2              +1 set fxlA_MAN_MODE_B200D.BIOl=l DMF cmffR02_LITSB211N026B              + 1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026Cl              +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026C2              +l set fx1A_MAN_MODE_B200D.BI01=1 DMF cmffR02_LITSB211N026C              +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026Dl              +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmfNBOl_LISB211N026D2              +1 set fx1A_MAN_MODE_B200D.BI01=1 DMF cmffR02_LITSB211N026D
-+1 set fx1A_MAN_MODE_B200D.BI01=1
+;other wr                              RCB_RCICOOS DMF cmffR02_LT14201A                   IMF mfRC150011 DMF cmffR02_LT14201B                   IRF rfDC188073 f:OPEN IRF rfDB106383 f:OPEN
-+l set fx1A_MAN_MODE_B200D.BI01=1
+;dwclg                                 IMF cmfAOl_HV149F088 DMF cmfNBOl_LIS14221C DOR aoLIS14221C_Q DMF emfNBOl_LIS14221D                  ETLOC28-NRC04-A DOR aoLIS14221D_Q                      ;SWITCH:MODE SWITCH diHSC72AlS01.CurrValue != #OR.diHSC72AlS01.RUN
-+l set fx1A_MAN_MODE_B200D.BI01=1
+; ER                                   MMF mfMS183007 r:300 i:0.5 f:2 DMF cmffR02_LT14203A                   IMF mfDS103010 d:lO DMF cmffR02_LT14203B
-+ 1 set fx1A_MAN_MODE_B200D.BI01=1
+; UR
-+1 set fxlA_MAN_MODE_B200D.BIOl=l
+;DMF cmffR02_PDTC321N017 DMF cmffD03_PDTC321N017 LOC28-NRC-04 Rev 1        Examination Material                                     4/26/2016
-+ 1 set fx1A_MAN_MODE_B200D.BI01=1
+* 19
-+1 set fx1A_MAN_MODE_B200D.BI01=1
-+l set fx1A_MAN_MODE_B200D.BI01=1
+LOC28-NRC-04 ETLOC28-N RC04-B
-+1 set fx1A_MAN_MODE_B200D.BI01=1
+;SWITCH:DRYWELL SPRAY OB ISO HV-1F016A (E11A-S9A)              ETLOC28-N RC04-E diHS15116A.CurrValue != #OR.diHS15116A.CLOSE                   ;A RRP runaway at 95.5 Mlbm DMF mfRH149011B                                                aoXR14301F.CurrValue>95.5 cet ETLOC28-NRC04-C                                            SCN exam\LOC28-NRC04-D aet ETLOC28-NRC04-D ETLOC28-NRC04-C
-+1 set fx1A_MAN_MODE_B200D.BI01=1
+;SWITCH:DRYWELL SPRAY OB ISO HV-1F016B (EllA-S9B) diHS15116B.CurrValue != #OR.diHS15116B.CLOSE DMF mfRH149011A cet ETLOC28-NRC04-B ETLOC28-NRC04-D
-+1 set fx1A_MAN_MODE_B200D.BI01=1 RCB_RCICOOS IMF mfRC150011 IRF rfDC188073 f:OPEN IRF rfDB106383 f:OPEN IMF cmfAOl_HV149F088 ETLOC28-NRC04-A
+;A RRP failure stops with scoop tube lock diHSB311503A.CurrValue=#OR.diHSB311S03A.TRIP abort exam\LOC28-NRC04-D set fx1A_MAN_MODE_B200D.BI01=0 LOC28-NRC-04 Rev 1                                Examination Material                     4/26/2016. 20
-;SWITCH:MODE SWITCH diHSC72AlS01.CurrValue
-!= #OR.diHSC72AlS01.RUN MMF mfMS183007 r:300 i:0.5 f:2 IMF mfDS103010 d:lO Examination Material 4/26/2016
+LOC28-NRC-04 Event 1 - Shutdown the '8' EOG Instructor Activities                     Operator Activities                      Notes Booth Operator No additional activities are required PCOM Role Play D Monitor diverse plant indications As NPO at the 'B' EOG, acknowledge requests and           PCOP report actions complete when       D Adjusts EOG KW to the proper setting the 'B' EOG is secured (-5            with HS-000548, Speed governor minutes)
-* 19 ETLOC28-N RC04-B ;SWITCH:DRYWELL SPRAY OB ISO HV-1F016A (E11A-S9A) diHS15116A.CurrValue
+D Adjusts EOG Kvars - 0 with HS-000538, Voltage Adjust D Opens 1A20204 to divorce from the EOG D Adjusts voltage to 4250V using HS-000538 for 5 minute unloaded run D Depresses HS-000528, DG 8 Stop pushbutton D Directs NPO to perform field actions us D Directs PCOP to secure the '8' EOG IAW S0-024-0018 Instructor Note There is a 5 minute unloaded cooldown time in the SO. No actions are taken during that time period. Time compression is allowed for that section of the procedure if authorized by the Chief Examiner.
-!= #OR.diHS15116A.CLOSE DMF mfRH149011B cet ETLOC28-NRC04-C ETLOC28-NRC04-C
+LOC28-NRC-04 Rev 1                               Examination Material                          4/26/2016. 21
-;SWITCH:DRYWELL SPRAY OB ISO HV-1F016B (EllA-S9B) diHS15116B.CurrValue
-!= #OR.diHS15116B.CLOSE DMF mfRH149011A cet ETLOC28-NRC04-B ETLOC28-NRC04-D
+LOC28-NRC-04 Event 2 - Raise .Reactor Power 5% with RRPs, 'A' RRP Runaway Instructor Activities                      Operator Activities                           Notes Booth    Oper~tor After the stop p4shbutton has been depressed for the 'B' EOG and the crew is not proceeding to raise power, perform the first role play.
-;A RRP failure stops with scoop tube lock diHSB311503A.CurrValue=#OR.diHSB311S03A.TRIP abort exam\LOC28-NRC04-D set fx1A_MAN_MODE_B200D.BI01=0 LOC28-NRC-04 Rev 1 LOC28-NRC-04 ETLOC28-N RC04-E ;A RRP runaway at 95.5 Mlbm aoXR14301F.CurrValue>95.5 SCN exam\LOC28-NRC04-D aet ETLOC28-NRC04-D Examination Material 4/26/2016.
+Ensure Event Trigger ETLOC28-NRC04-E fires when Core Flow reaches 95.5 Mlbm .. This should occur the third time 'A' RRP flow is adjusted, The Event Trigger will cause the 'A' RRP to run away and activate ETLOC28-NRC04~D.
-LOC28-NRC-04 Event 1 -Shutdown the '8' EOG Instructor Activities Operator Activities Booth Operator No additional activities are required Role Play As NPO at the 'B' EOG, acknowledge requests and report actions complete when the 'B' EOG is secured (-5 minutes) Instructor Note PCOM D Monitor diverse plant indications PCOP D Adjusts EOG KW to the proper setting with HS-000548, Speed governor D Adjusts EOG Kvars -0 with HS-000538, Voltage Adjust D Opens 1A20204 to divorce from the EOG D Adjusts voltage to 4250V using HS-000538 for 5 minute unloaded run D Depresses HS-000528, DG 8 Stop pushbutton D Directs NPO to perform field actions us D Directs PCOP to secure the '8' EOG IAW S0-024-0018 Notes There is a 5 minute unloaded cooldown time in the SO. No actions are taken during that time period. Time compression is allowed for that section of the procedure if authorized by the Chief Examiner.
+Ensure Event Trigger E;TLOC28-NRC04-D fires when the scoop tube is locked to stop the scenario and the RRP malfunction.
-LOC28-NRC-04 Rev 1 Examination Material 4/26/2016.
+PCOM Role Play D Raises Reactor Power with RRPs IAW As Shift Manager contact the control room                         provided RMR and OP-AD-338 If we have depressed the          D Plots power on the power/flow map stop pushbutton for the 'B'          prior to the power change and Diesel,. you have my permission to continue               following the power change with the 5% power                 D Depresses the single or double up ascension while the stop chevron to raise reactor power. (A 2%
-LOC28-NRC-04 Event 2 -Raise .Reactor Power 5% with RRPs, 'A' RRP Runaway Instructor Activities Operator Activities Notes Booth After the stop p4shbutton has been depressed for the 'B' EOG and the crew is not proceeding to raise power, perform the first role play. Ensure Event Trigger ETLOC28-NRC04-E fires when Core Flow reaches 95.5 Mlbm .. This should occur the third time 'A' RRP flow is adjusted, The Event Trigger will cause the 'A' RRP to run away and activate Ensure Event Trigger E;TLOC28-NRC04-D fires when the scoop tube is locked to stop the scenario and the RRP malfunction.
+timers and field actions are proceeding.                          change in speed on both RRPs equates to - 1% change in reactor power)
-Role Play As Shift Manager contact the control room If we have depressed the stop pushbutton for the 'B' Diesel,. you have my permission to continue with the 5% power ascension while the stop timers and field actions are proceeding.
+D Monitors diverse indications of reactor power D Reports 'A' RRP speed is raising D May attempt to lower flow by depressing the up chevron D Locks 'A' RRP MG Scoop Tube.
-LOC28-NRC-04 Rev 1 PCOM D Raises Reactor Power with RRPs IAW provided RMR and OP-AD-338 D Plots power on the power/flow map prior to the power change and following the power change D Depresses the single or double up chevron to raise reactor power. (A 2% change in speed on both RRPs equates to -1 % change in reactor power) D Monitors diverse indications of reactor power D Reports 'A' RRP speed is raising D May attempt to lower flow by depressing the up chevron D Locks 'A' RRP MG Scoop Tube. PCOP D Peer checks the PCOM during the power maneuver D As required, adjusts manual voltage to zero manual and auto voltage regulators D Performs ON-RECIRC-101 Examination Material 4/26/2016
+PCOP D Peer checks the PCOM during the power maneuver D As required, adjusts manual voltage to zero manual and auto voltage regulators D Performs ON-RECIRC-101 LOC28-NRC-04 Rev 1                               Examination Material                                 4/26/2016
-* 22 LOC28-NRC-04 Event 2 -Raise Reactor Power 5% with RRPs, 'A' RRP Runaway Instructor Activities Instructor Note Operator Activities us D Obtains permission from the SM to perform the reactivity manipulation D Directs PCOM to raise reactor power using RRPs IAW the RMR and AD-338 D Directs PCOP to peer check the PCOM D May conduct update after the reactivity maneuver D Enters ON-RECIRC-101 on runaway RRP D Evaluates entering TS 3.4.1.B for loop flows not matched. Notes When the crew locks the Scoop Tube, speed may continue to raise. This is because the RRP will match speed to the location of the scoop tube. If speed was lower than the position of the scoop tube, it will continue to rise until it reaches that position and then stop moving. The crew may discuss tripping the 'A' RRP if they do not notice that the scoop tube position is not moving. LOC28-NRC-04 Rev 1 Examination Material 412612016
+* 22
-* 23 LOC28-NRC-04 Event 3 -Control rod scram Instructor Activities Operator Activities Notes Booth Operator When the power change has been completed, Insert KEY 1 to scram control rod 50-23 due to blown fuses. {Key[1]} IMF mfRD1550085023 Drift Control rod 50-23 In If directed, Insert KEY 2 to disarm co.ntrol rod 50-23. Report when the actions are complete, {Key[2]} IRF rfR01550075023 d:120 f:DISARM {Key[2]} DMF mfRD1550085023 Disarms Control rod 50-23 Removes the drift in malfunction Role Play As NPO dispatched to HCU 50-23, wait 2 minutes Scram inlet and outlet valves on HCU 50-23 are open. Role Play As WWM contacted for assistance with control rod 50-23, wait 5 minutes l&C discovered a blown fuse on the 'B' RPS solenoid for the scram pilot solenoid valve for HCU 50-23. They are still troubleshooting.
-Role Play As NPO dispatched to 1 C007 for high temperatures, wait 2 minutes Control rod 50-23 has elevated temperature on 1C007. LOC28-NRC-04 Rev 1 PCOM D Reports RPV power, pressure, and water level after the plant stabilizes D Reports control rod 50-23 is at position 00 D Plots position on the Power/Flow Map PCOP D Performs ON-CRD-101 condition D D Verifies position of control rod 50-23 D Resets rod drift alarm D Informs US to address LCO 3.1.3 and 3.9.5 us D Enters ON-CRD-101 condition D D Enters ON-PWR-101 for power change D Enters TS 3.1.3.C for a control rod inoperable fully inserted Examination Material 4/26/2016.
+LOC28-NRC-04 Event 2 - Raise Reactor Power 5% with RRPs, 'A' RRP Runaway Instructor Activities                    Operator Activities                           Notes us D Obtains permission from the SM to perform the reactivity manipulation D Directs PCOM to raise reactor power using RRPs IAW the RMR and OP-AD-338 D Directs PCOP to peer check the PCOM D May conduct update after the reactivity maneuver D Enters ON-RECIRC-101 on runaway RRP D Evaluates entering TS 3.4.1.B for loop flows not matched.
-LOC28-NRC-04 Event 4 -T-20 Lockout Instructor Activities Operator Activities Notes Booth Operator When the US has reviewed TS for the drifted control rod, Insert KEY 3 to initiate a lockout of Start Up Transformer 20 (T-20). {Key[3]} IMF mfDS003008.
+Instructor Note When the crew locks the Scoop Tube, speed may continue to raise. This is because the RRP will match speed to the location of the scoop tube. If speed was lower than the position of the scoop tube, it will continue to rise until it reaches that position and then stop moving. The crew may discuss tripping the 'A' RRP if they do not notice that the scoop tube position is not moving.
-T-20 lockout If requested to reset Div 2 rad monitors for the loss of RPS, Wait 1 minute, Insert KEY 8 and report when complete {Key[8]} SCN exam\RMA_DIV2RST Reset Rad monitors Role Play As NPO dispatched to T-20, wait 2 minutes There is nothing abnormal at the T-20 transformer.
+LOC28-NRC-04 Rev 1                             Examination Material                               412612016
-Role Play As WWM contacted for assistance with T-20 lockout, wait 5 minutes Electrical Maintenance reports the backup transformer lockouts were tripped on T-20. It looks like a bad lockout relay and we are getting a package to replace it. Role Play As NPO dispatched to SUB-20, wait 2 minutes The backup lockout relay for T-20 is tripped on Startup Bus 20. Role Play As NPO dispatched to verify the position of the 'E' EOG OATS, wait 3 minutes The 'E' diesel OATS is on SUB-10. LOC28-NRC-04 Rev 1 PCOM D Reports RPV Power, Pressure, and Water Level PCOP D Reports loss of Startup Bus 20 D Dispatches NPO to Startup Bus 20 D Dispatches NPO to Startup Transformer 20 D Performs ON-SUB-001 D Performs ON-4KV-101 D Performs ON-RPS-101 D Restores cooling to the RRPs us D Enters ON-SUB-001, Loss of Startup Bus 10 or 20 D Enters TS 3.8.1.A, Actions A.1 & A.3 D Enters TRO 3.4.1 Examination Material 4/26/2016.
+* 23
-LOC28-NRC-04 Event 5, 6 -Small Steam Leak/ Manual Scram/ HPCI failure Instructor Activities Operator Activities Notes Booth Operator When RRP cooling has been restored, Insert KEY 4 to initiate a small steam leak in the Drywell {Key[4]} IMF mfMS183007 r:600 f:0.02 Small steam leak When the crew recognized the steam leak, Insert KEY 5 when desired to raise the severity of the steam leak and proceed to reactor scram. {Key[5]} MMF mfMS183007 r:9 f:0.05 Raise severity of the leak Ensure EventTrigger ETLOC28-NRC04-A fires when the Mode Switch is placed to SHUTDOWN to raise the severity of the steam leak AND cause a Plant Aux Load Shed Role Play As NPO dispatched to investigate Condensate Pump discharge valves, wait 2 minutes The Condensate Pump discharge valves all indicate full open. The breakers are closed and reset. Role Play As WWM contacted for assistance with the Drywell steam leak, wait 5 minutes I have activated the forced outage response team at the direction of the Duty Manager. Role Play As WWM contacted for assistance with Condensate Pump discharge valves, acknowledge the request, if asked* about status Engineering and maintenance are still investigating.
-Instructor Note PCOM D If directed, Inserts a LIM #2 on RRPs D When directed, Places Mode Switch in SHUTDOWN to Scram the reactor D Performs Scram Report IAW OP-AD-300 D Inserts IRMS and SRMS D Reports trip of all RFPs D If observed, Reports failure of condensate discharge valves to close PCOP D Reports rising Drywell Pressure D Verifies Isolations, Initiations, and EOG starts D Reports an Aux Bus Load Shed happened D Reports failure of HPCI to auto start D Performs Component by component startup of HPCI IAW OP-152-001 The initial steam leak is very small in severity and takes -5 minutes to be readily detected LOC28-NRC-04 Rev 1 Examination Material 4/26/2016
+LOC28-NRC-04 Event 3 - Control rod scram Instructor Activities                      Operator Activities                             Notes Booth Operator When the power change has been completed, Insert KEY 1 to scram control rod 50-23 due to blown fuses.
-* 26 LOC28-NRC-04 Event 5, 6 -Small Steam Leak/ Manual Scram/ HPCI failure Instructor Activities Operator Activities Notes us D Performs ON-RPR-101 D Directs PCOM to scram the plant D Enters E0-000-102, RPV Control D Enters E0-000-103, PC Control Directs PCOP to maintain RPV water level with HPCI and RCIC Critical Parameter Once Drywell pressure is noticed to be rising, it would be expected that the US gives a Critical Parameter to the PCOP on Drywell pressure and an action to place the Mode Switch to SHUTDOWN when it is reached. LOC28-NRC-04 Rev 1 Examination Material 4/26/2016
+{Key[1]} IMF mfRD1550085023                                    Drift Control rod 50-23 In If directed, Insert KEY 2 to disarm co.ntrol rod 50-23. Report when the actions are complete,
-* 27 LOC28-NRC-04 Event 7 -Containment Cooling Instructor Activities Operator Activities Notes Booth Event Trigger ETLOC28-NRC04-B(C) fires when the first RHR F016A(B) valve is opened to clear the stem-to-disk malfunction on the other division.
+{Key[2]} IRF rfR01550075023 d:120 f:DISARM                     Disarms Control rod 50-23
+{Key[2]} DMF mfRD1550085023                                    Removes the drift in malfunction PCOM Role Play D Reports RPV power, pressure, and As NPO dispatched to HCU 50-23, wait 2 minutes               water level after the plant stabilizes Scram inlet and outlet            D Reports control rod 50-23 is at position valves on HCU 50-23 are              00 open.
+D Plots position on the Power/Flow Map Role Play                         PCOP As WWM contacted for              D Performs ON-CRD-101 condition D assistance with control rod 50-23, wait 5 minutes D Verifies position of control rod 50-23 l&C discovered a blown            D Resets rod drift alarm fuse on the 'B' RPS               D Informs US to address LCO 3.1.3 and solenoid for the scram pilot solenoid valve for HCU 50-           3.9.5
+: 23. They are still                us troubleshooting.                  D Enters ON-CRD-101 condition D Role Play                         D Enters ON-PWR-101 for power change As NPO dispatched to 1C007        D Enters TS 3.1.3.C for a control rod for high temperatures, wait 2        inoperable fully inserted minutes Control rod 50-23 has elevated temperature on 1C007.
+LOC28-NRC-04 Rev 1                                Examination Material                                4/26/2016. 24
+LOC28-NRC-04 Event 4 - T-20 Lockout Instructor Activities                     Operator Activities                            Notes Booth Operator When the US has reviewed TS for the drifted control rod, Insert KEY 3 to initiate a lockout of Start Up Transformer 20 (T-20).
+{Key[3]} IMF mfDS003008.                                 T-20 lockout If requested to reset Div 2 rad monitors for the loss of RPS, Wait 1 minute, Insert KEY 8 and report when complete
+{Key[8]} SCN exam\RMA_DIV2RST                            Reset Rad monitors PCOM Role Play D Reports RPV Power, Pressure, and As NPO dispatched to T-20, wait 2 minutes                       Water Level There is nothing abnormal        PCOP at the T-20 transformer.         D Reports loss of Startup Bus 20 Role Play                        D Dispatches NPO to Startup Bus 20 As WWM contacted for             D Dispatches NPO to Startup assistance with T-20 lockout,        Transformer 20 wait 5 minutes Electrical Maintenance D Performs ON-SUB-001 reports the backup               D Performs ON-4KV-101 transformer lockouts were        D Performs ON-RPS-101 tripped on T-20. It looks like a bad lockout relay and     D Restores cooling to the RRPs we are getting a package to      us replace it.                      D Enters ON-SUB-001, Loss of Startup Role Play                            Bus 10 or 20 As NPO dispatched to SUB-        D Enters TS 3.8.1.A, Actions A.1 & A.3 20, wait 2 minutes               D Enters TRO 3.4.1 The backup lockout relay for T-20 is tripped on Startup Bus 20.
+Role Play As NPO dispatched to verify the position of the 'E' EOG OATS, wait 3 minutes The 'E' diesel OATS is on SUB-10.
+LOC28-NRC-04 Rev 1                                Examination Material                                  4/26/2016. 25
+LOC28-NRC-04 Event 5, 6 - Small Steam Leak/ Manual Scram/ HPCI failure Instructor Activities                    Operator Activities                           Notes Booth Operator When RRP cooling has been restored, Insert KEY 4 to initiate a small steam leak in the Drywell
+{Key[4]} IMF mfMS183007 r:600 f:0.02                   Small steam leak When the crew recognized the steam leak, Insert KEY 5 when desired to raise the severity of the steam leak and proceed to reactor scram.
+{Key[5]} MMF mfMS183007 r:9 f:0.05                     Raise severity of the leak Ensure EventTrigger ETLOC28-NRC04-A fires when the Mode Switch is placed to SHUTDOWN to raise the severity of the steam leak AND cause a Plant Aux Load Shed PCOM Role Play D If directed, Inserts a LIM #2 on RRPs As NPO dispatched to investigate Condensate           D When directed, Places Mode Switch in Pump discharge valves, wait         SHUTDOWN to Scram the reactor 2 minutes                        D Performs Scram Report IAW OP-AD-The Condensate Pump discharge valves all                300 indicate full open. The          D Inserts IRMS and SRMS breakers are closed and reset.
+D Reports trip of all RFPs D If observed, Reports failure of Role Play                           condensate discharge valves to close As WWM contacted for             PCOP assistance with the Drywell steam leak, wait 5 minutes       D Reports rising Drywell Pressure I have activated the forced      D Verifies Isolations, Initiations, and EOG outage response team at             starts the direction of the Duty Manager.                         D Reports an Aux Bus Load Shed happened Role Play D Reports failure of HPCI to auto start As WWM contacted for assistance with Condensate       D Performs Component by component Pump discharge valves,              startup of HPCI IAW OP-152-001 acknowledge the request, if asked* about status Engineering and maintenance are still investigating.
+Instructor Note The initial steam leak is very small in severity and takes -5 minutes to be readily detected LOC28-NRC-04 Rev 1                              Examination Material                                4/26/2016
+* 26
+LOC28-NRC-04 Event 5, 6 - Small Steam Leak/ Manual Scram/ HPCI failure Instructor Activities                   Operator Activities                        Notes us D Performs ON-RPR-101 D Directs PCOM to scram the plant D Enters E0-000-102, RPV Control D Enters E0-000-103, PC Control Directs PCOP to maintain RPV water level with HPCI and RCIC Critical Parameter Once Drywell pressure is noticed to be rising, it would be expected that the US gives a Critical Parameter to the PCOP on Drywell pressure and an action to place the Mode Switch to SHUTDOWN when it is reached.
+LOC28-NRC-04 Rev 1                           Examination Material                             4/26/2016
+* 27
+LOC28-NRC-04 Event 7 - Containment Cooling Instructor Activities                     Operator Activities                    Notes Booth Op~rator Ensur~ Event Trigger ETLOC28-NRC04-B(C) fires when the first RHR F016A(B) valve is opened to clear the stem-to-disk malfunction on the other division.
+Critical Task
+* Spray the Drywell when Suppression Chamber pressure exceeds 13 psig.
+Role Play As NPO dispatched to RHR PCO D When directed, initiates suppression chamber sprays IAW OP-149-004 F016A(B), wait 2 minutes The RHR Drywe/I spray OB         D Aligns RHRSW to the RHR heat valve HV-151-F016A(B)              exchanger IAW OP-149-004 indicates full open. I do NOT hear any flow.               D When directed, initiates Drywell Sprays IAW OP-149-004 Role Play                        D Requests plant status IAW the DSIL As WWM contacted for curve before spraying the Drywell assistance with RHR F016A(B), acknowledge            D Reports failure to achieve flow through request, if contacted about        the RHR F016A(B) and moves to the status Engineering and                    other RHR Loop for Drywell sprays Maintenance are still            D Dispatches NPO to investigate RHR troubleshooting.                   F016A(B) us D Directs PCO to initiate Suppression Chamber Sprays D Directs PCO to line-up for Drywell Sprays D Verifies plant conditions are in the
+                                    'Safe to Spray' region of the DISL curve before directing PCO to spray the Drywell LOC28-NRC-04 Rev 1                               Examination Material                         4/26/2016
+* 28
+LOC28-NRC-04 Event 8 - RPV Flooding Instructor Activities                    Operator Activities                           Notes Booth Operator When the crew has established Drywell Spray and Drywell pressure is trending down, Insert KEY 6 to initiate reactor level notching and subsequent failure of all reactor level indications upscale.
+{Key[6]} SCN examlLOC28-NRC04-C If directed, Insert KEY 7 to back up ADS with the keylock switches from the relay room. When complete, report to the control room.
+{Key[7]} IOR d.iHS14113G2 d:60 f:OPEN
+{Key[7]} IOR diHS14113J2 d:66 f:OPEN
+{Key[7]} IOR diHS14113K2 d:72 f:OPEN
+{Key[7]} IOR diHS14113L2 d:78 f:OPEN
+{Key[7]} IOR diHS14113M2 d:84 f:OPEN
+{Key[7]} IOR diHS14113N2 d:90 f:OPEN Monitor 'E0114' on R*Time and 'Vesvoid' on the Simulator in the booth and inform the Lead Evaluator when the simulator is Flooded to the Main Steam Lines (MSL)
 Critical Task
-* Spray the Drywell when Suppression Chamber pressure exceeds 13 psig. Role Play As NPO dispatched to RHR F016A(B), wait 2 minutes The RHR Drywe/I spray OB valve HV-151-F016A(B) indicates full open. I do NOT hear any flow. Role Play As WWM contacted for assistance with RHR F016A(B), acknowledge request, if contacted about status Engineering and Maintenance are still troubleshooting.
-LOC28-NRC-04 Rev 1 PCO D When directed, initiates suppression chamber sprays IAW OP-149-004 D Aligns RHRSW to the RHR heat exchanger IAW OP-149-004 D When directed, initiates Drywell Sprays IAW OP-149-004 D Requests plant status IAW the DSIL curve before spraying the Drywell D Reports failure to achieve flow through the RHR F016A(B) and moves to the other RHR Loop for Drywell sprays D Dispatches NPO to investigate RHR F016A(B) us D Directs PCO to initiate Suppression Chamber Sprays D Directs PCO to line-up for Drywell Sprays D Verifies plant conditions are in the 'Safe to Spray' region of the DISL curve before directing PCO to spray the Drywell Examination Material 4/26/2016
-* 28 LOC28-NRC-04 Event 8 -RPV Flooding Instructor Activities Operator Activities Notes Booth Operator When the crew has established Drywell Spray and Drywell pressure is trending down, Insert KEY 6 to initiate reactor level notching and subsequent failure of all reactor level indications upscale. {Key[6]} SCN examlLOC28-NRC04-C If directed, Insert KEY 7 to back up ADS with the keylock switches from the relay room. When complete, report to the control room. {Key[7]} IOR d.iHS14113G2 d:60 f:OPEN {Key[7]} IOR diHS14113J2 d:66 f:OPEN {Key[7]} IOR diHS14113K2 d:72 f:OPEN {Key[7]} IOR diHS14113L2 d:78 f:OPEN {Key[7]} IOR diHS14113M2 d:84 f:OPEN {Key[7]} IOR diHS14113N2 d:90 f:OPEN Monitor 'E0114' on R*Time and 'Vesvoid' on the Simulator in the booth and inform the Lead Evaluator when the simulator is Flooded to the Main Steam Lines (MSL) Critical Task
 * Performs RPV Flooding when RPV water level becomes indeterminate by establishing RPV Flooded to Steamlines.
-Role Play As NPO dispatched to Instrument racks C004/C005, wait 2 minutes All reactor level indicators at the 4 and 5 racks show full upscale. Role Play As WWM contacted for assistance with Reactor level indications, acknowledge request and if contacted about status Engineering and Maintenance are developing a plan to go troubleshoot.
+PCO Role Play D Reports erratic and unusable level As NPO dispatched to Instrument racks C004/C005,         instrumentation wait 2 minutes                   D Verifies ALL level indications are All reactor level indicators        erratic at the 4 and 5 racks show full upscale.                    D When directed, Opens the 6 ADS SRVs on 1 C601 Role Play D May, dispatch NPO to backup ADS As WWM contacted for with the keylocks in the relay room assistance with Reactor level indications, acknowledge         D Verify ADS SRVs are open by request and if contacted            temperature recorders, acoustic about status Engineering and                     monitors, and reactor pressure Maintenance are                     lowering developing a plan to go          D Closes all MSIVs and MSL drains troubleshoot.
-LOC28-NRC-04 Rev 1 PCO D Reports erratic and unusable level instrumentation D Verifies ALL level indications are erratic D When directed, Opens the 6 ADS SRVs on 1 C601 D May, dispatch NPO to backup ADS with the keylocks in the relay room D Verify ADS SRVs are open by temperature recorders, acoustic monitors, and reactor pressure lowering D Closes all MSIVs and MSL drains D Aligns RHR to LPCI mode IAW OP-149-004 Examination Material 4/26/2016
+D Aligns RHR to LPCI mode IAW OP-149-004 LOC28-NRC-04 Rev 1                              Examination Material                               4/26/2016
-* 29 Instructor Activities Critical Parameter LOC28-NRC-04 Event 8 -RPV Flooding Operator Activities PCO D Isolates HPCI and RCIC when the supply valves close on low pressure D May bring up on R*Time page E0114 to aid in monitoring for filling to the MSL us D Enters E0-000-114, RPV Flooding D Directs opening all ADS SRVs D Directs isolating all MSIVs and MSL drains D Directs aligning RHR for LPCI injection D Directs maximizing RPV injection to flood the RPV to the MSL Notes When flooding to the MSL, the US may give a critical parameter to inform the US when flooded conditions are met. Instructor Activity -Termination The scenario may be terminated when the crew acknowledges indications of being flooded to the main steam lines OR at the direction of the Chief Examiner.
+* 29
-LOC28-NRC-04 Rev 1 Examination Material 4/26/2016.
-UNIT SUPERVISOR TURNOVER SHEET UNIT 1 SHIFT 1900 to 0700 Start End MODE POWER LEVEL 90 % -------MODE t"o(dd(yy Date SHIFT 0700 to Start POWER LEVEL 1900 End -------% GENERATOR OUTPUT 1206 MWe GENERATOR OUTPUT MWe CASK STORAGE GATE INSTALLED:
+LOC28-NRC-04 Event 8 - RPV Flooding Instructor Activities                  Operator Activities                       Notes PCO D Isolates HPCI and RCIC when the supply valves close on low pressure D May bring up on R*Time page E0114 to aid in monitoring for filling to the MSL us D Enters E0-000-114, RPV Flooding D Directs opening all ADS SRVs D Directs isolating all MSIVs and MSL drains D Directs aligning RHR for LPCI injection D Directs maximizing RPV injection to flood the RPV to the MSL Critical Parameter
-YES/NO CASK STORAGE GATE INSTALLED:
+(~;     When flooding to the MSL, the US may give a critical parameter to inform the US when flooded conditions are met.
-YES/NO REMARKS: 1) Power ascension from control rod pattern adjustment in progress, 90 percent power 2) RCIC is out-of-service due to contamination of lube oil system. Estimated RTS is 4 days 3) LCO 3.5.3 Entered. Day 2 of the 14 day LCO 4) Shutdown Diesel Generator B per S0-024-001 B 5) Raise power 5 percent per Reactor Engineering RMR to 94% APRM power 6) Perform all briefings prior to taking the shift 7 8 9) 10 11 12 13 14 15) COMMON: 1) Unit 2 is at rated power 2) SSES experienced a less-than-OBE seismic event 6 hours ago due to expected blasting activities by neighboring industrial facilities
+Instructor Activity - Termination The scenario may be terminated when the crew acknowledges indications of being flooded to the main steam lines OR at the direction of the Chief Examiner.
-: 3) Actions of ON-000-002 for a seismic event have been completed 4 5) 6 7 8) 9) FORM OP-AD-003-7, DUPLEX Page 1 of 2 (Electronic Form) Examination Material NRC SCN 4 c OFFGOING UNIT SUPERVISOR CHECKLIST:
+LOC28-NRC-04 Rev 1                           Examination Material                          4/26/2016. 30
-NRC CODE PRIOR TO 0800 FOXTROT DELTA BRAVO OSCAR NRC CODE AFTER 0800 FOXTROT UNIFORM HOTEL ROMEO 1900-0700-0700 1900 0700 1900 --) POST RELIEF 0700 1900 1. Evolutions in progress and items to be completed during next shift, as noted in remarks, have been discussed with oncoming Unit Supervisor (including special evolutions, i.e. SICT/E, OPDRVs, etc.). 2. Problems encountered during past shift and abnormal plant conditions, as noted in remarks, have been discussed with oncoming Unit Supervisor.
+UNIT SUPERVISOR TURNOVER SHEET UNIT              1                  t"o(dd(yy Date SHIFT      1900     to   0700                                      SHIFT  0700   to 1900 Start         End                                               Start     End MODE                                                        MODE POWER LEVEL         90                 %                    POWER LEVEL                      %
+                   -  ------                                                -------
+GENERATOR OUTPUT          1206         MWe                  GENERATOR OUTPUT                 MWe CASK STORAGE GATE INSTALLED: YES/NO                         CASK STORAGE GATE INSTALLED: YES/NO REMARKS:
+: 1)    Power ascension from control rod pattern adjustment in progress, 90 percent power
+: 2)    RCIC is out-of-service due to contamination of lube oil system. Estimated RTS is 4 days
+: 3)    LCO 3.5.3 Entered. Day 2 of the 14 day LCO
+: 4)    Shutdown Diesel Generator B per S0-024-001 B
+: 5)    Raise power 5 percent per Reactor Engineering RMR to 94% APRM power
+: 6)    Perform all briefings prior to taking the shift 7
+9) 10 11 12 13 14 15)
+COMMON:
+: 1)    Unit 2 is at rated power
+: 2)    SSES experienced a less-than-OBE seismic event 6 hours ago due to expected blasting activities by neighboring industrial facilities
+: 3)    Actions of ON-000-002 for a seismic event have been completed 4
+) 6 7
+) 9)
+FORM OP-AD-003-7, DUPLEX Page 1 of 2 (Electronic Form)
+Examination Material                       NRC SCN 4
+OFFGOING UNIT SUPERVISOR CHECKLIST:
+NRC CODE PRIOR TO 0800      FOXTROT               DELTA                 BRAVO                OSCAR NRC CODE AFTER 0800         FOXTROT               UNIFORM               HOTEL                ROMEO 1900- 0700-0700   1900
+: 1. Evolutions in progress and items to be completed during next shift, as noted in remarks, have been discussed with oncoming Unit Supervisor (including special evolutions, i.e. SICT/E, OPDRVs, etc.).
+: 2. Problems encountered during past shift and abnormal plant conditions, as noted in remarks, have been discussed with oncoming Unit Supervisor.
 : 3. Information in SOMS Log is complete and discussed with oncoming Unit Supervisor.
 : 4. As applicable, turnover plastic Security Badge cover and CRS Monitor function to oncoming Unit Supervisor.
--0700
+-0700 - - - - - - - - - - -
------------
+- 1900 - - - - - - - - - - -
--1900 -----------
 Offgoing Unit Supervisor ONCOMING UNIT SUPERVISOR CHECKLIST:
+   1900
+    -      -
 : 1. LCOfTRO Log reviewed.
-: 2. SOMS Log reviewed for entries made in past 24 hours. 3. Report any changes to license or medical status PER NDAP-QA-0723.
+c)                   2. SOMS Log reviewed for entries made in past 24 hours.
--1900 ------------
+: 3. Report any changes to license or medical status PER NDAP-QA-0723.
--0700 Oncoming Qualified Unit Supervisor
+- 1900 - - - - - - - - - - - -
-: 1. Walk down Control Room panels with Unit Responsible PCO. 2. CRC Book reviewed and Reactivity Brief performed with PCO. 3. Completed System Status Operable audit for open PMT this shift. 4. From the OPS Web page, Review OPS Aggregate Index for Challenges, Work Arounds, and Deficiencies Reports for impact on scheduled work activities and compensatory actions. (2 o) 0700-1900
+-0700 - - - - - - - - - - -
------------
+Oncoming Qualified Unit Supervisor POST RELIEF 0700   1900
--0700 Oncoming Unit Supervisor FORM OP-AD-003-7, DUPLEX Page 2 of 2 (Electronic Form) Examination Material NRCSCN4}}
+: 1. Walk down Control Room panels with Unit Responsible PCO.
+: 2. CRC Book reviewed and Reactivity Brief performed with PCO.
+: 3. Completed System Status Operable audit for open PMT this shift.
+: 4. From the OPS Web page, Review OPS Aggregate Index for Challenges, Work Arounds, and Deficiencies Reports for impact on scheduled work activities and compensatory actions. (2o) 0700-1900 - - - - - - - - - - -
+- 0700 - - - - - - - - - - - -
+Oncoming Unit Supervisor FORM OP-AD-003-7, DUPLEX Page 2 of 2 (Electronic Form)
+Examination Material                                    NRCSCN4}}

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