ML15176A580

Hatch Initial Exam 2015-301 Final Administrative JPMs

ML15176A580
Person / Time
Site:	Hatch
Issue date:	06/22/2015
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
References
50-321/15-301, 50-366/15-301 50-321/15-301, 50-366/15-301
Download: ML15176A580 (87)

Text

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 1 of 16 Southern Nuclear Company Operations Training JPM FINAL ADMIN 1 - ALL WITH SRO PORTION Title: CORRECT RWL INDICATORS FOR HIGH DRYWELL TEMPERATURES & SRO ONLY TS Author: Anthony Ball Media Number:

2015-301 ADMIN 1 Time: 30.0 Minutes (45 Minutes) Line Technical Review By (N/A for minor revisions) Date: Reviewed by Instructional Technologist or designee: Date: Approved By (Training Program Manager or Lead Instructor) Ed Jones Date 03/10/2015 Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 2 of 16 This page intentionally left blank

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 3 of 16 Course Number N/A Program Name OPERATIONS TRAINING Media Number 2015-301 ADMIN 1 Rev. No. Date Reason for Revisions Author's Initials Sup's Initials 00 03/10/2015 Modified from LR-JP-25101 for use on 2015-301 NRC Exam. Incorporated SRO TS determination for RWL instruments. After exam will be incorporated into JPM database and renumbered. ARB ELJ 2015-301 ADMIN 1 Page 4 of 16 Line Contributors The following individuals contributed to the development of this lesson plan.

Rev. No. List of Contributors

2015-301 ADMIN 1 Page 5 of 16 UNIT 1 (X) UNIT 2 ( ) TASK TITLE: CORRECT RWL INDICATORS FOR HIGH DRYWELL TEMPERATURES & SRO ONLY TS JPM NUMBER: 2015-301 ADMIN 1 TASK STANDARD: The RO portion of this task shall be successfully completed when all of the JPM Critical Steps corresponding to 34AB-B21-002-1 have been correctly performed to identify which RWL instruments are valid and invalid and the corrected RWL. For a SRO to successfully complete the RO and SRO portion of this task the RO standard must be met and the SRO has determined TS Required Action 3.3.5.2.B.2 is required to be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by placing a channel in trip and that TS Required Action 3.3.5.2.B.1 is required to be performed. TASK NUMBER: 201.099 OBJECTIVE NUMBER: 201.099.B PLANT HATCH JTA IMPORTANCE RATING: RO 4.57 SRO 3.83 STA 4.00 K/A CATALOG NUMBER: G2.1.35 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.90 SRO 4.20 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO) GENERAL

REFERENCES:

Unit 1 Unit 2 34AB-B21-002-1 (current version) 34AB-B21-002-2 (current version) REQUIRED MATERIALS: Unit 1 Unit 2 34AB-B21-002-1 (current version) 34AB-B21-002-2 (current version) APPROXIMATE COMPLETION TIME: 30.0 Minutes (45 Minutes)

SIMULATOR SETUP: N/A

UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS: 1. Plant conditions are indicated on Attachments 1 & 2. 2. The NPO has reported the following Reactor Water Levels (RWL): 1C32-R606A, B and C (Narrow Range) is +8 inches 1B21-R605, (Flood Up Range) is +28 inches 1C32-R655, (Flood Up Range) is +28 inches 1B21-R604A (Wide Range) failed Upscale 1B21-R623A (Wide Range) are +30 inches 1B21-R604B and 1B21-R623B (Wide Range) are +35 inches 1B21-R623A and 1B21-R623B (Fuel Zone) are indicating **** 3. NO erratic behavior for the specified instruments has been observed. INITIATING CUES: Determine which of these RWL indications are valid and which RWL indications are invalid And Report the corrected RWL for EACH valid RWL instrument. ***CAUTION: DO NOT GIVE SECOND INITIATING CUE SHEET TO SRO CANDIDATES UNTIL FIRST PART IS COMPLETE*** DO NOT give this to applicant UNIT 1 READ TO THE OPERATOR

INITIAL CONDITIONS:

1. Plant conditions are indicated on Attachments 1 & 2. 2. The NPO has reported the following Reactor Water Levels (RWL): 1C32-R606A, B and C (Narrow Range) is +8 inches 1B21-R605, (Flood Up Range) is +28 inches 1C32-R655, (Flood Up Range) is +28 inches 1B21-R604A (Wide Range) failed Upscale 1B21-R623A (Wide Range) are +30 inches 1B21-R604B and 1B21-R623B (Wide Range) are +35 inches 1B21-R623A and 1B21-R623B (Fuel Zone) are indicating **** 3. NO erratic behavior for the specified instruments has been observed.

INITIATING CUES: Determine which of these RWL indications are valid and which RWL indications are invalid And Report the corrected RWL for EACH valid RWL instrument.

2015-301 ADMIN 1 Page 8 of 16 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) For INITIAL Operator Programs: For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance. For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance. IF THEN PASS Human performance tools, safety, PPE met (1), AND For initial trg all steps completed correctly OR For continuing trg, critical steps (if used) completed correctly Mark the JPM as a PASS FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-111, "On-The-Job Training and Task Performance Evaluation". START TIME:__________ 1. Operator identifies the procedure needed to perform the task. Operator has identified the correct procedure as 34AB-B21-002-1. NOTE: If the operator indicates that SPDS would be checked, give the operator . PROMPT: IF the operator addresses Drywell temperature indications, INDICATE for the operator that temperature is greater than 150°F (Use Attachment 1 if SPDS is addressed). 2. Determine if RWL corrections are required. Using SPDS (or Drywell temp indications) the operator DETERMINES: Drywell temperature is greater than 150°F. RWL corrections ARE required. 3. Review Caution 1 and Caution 2 on Attachment 1 of 34AB-B21-002-1. The operator has REVIEWED Caution 1 and Caution 2 on of 34AB-B21-002-1.

2015-301 ADMIN 1 Page 9 of 16 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) 4. Confirm there is no indication of erratic instrument behavior. The operator has VERIFIED, by observation or by addressing the panel operator, that the following RWL instruments show NO erratic instrument behavior: 1B21-R604B 1B21-R605, (Flood Up Range) 1C32-R655, (Flood Up Range) 1B21-R623A (Wide Range) 1B21-R623B (Wide Range) 1B21-R623A (Fuel Zone) PROMPT: WHEN the operator indicates use of the Diagnostic screen of SPDS, GIVE the operator Attachment 2. 5. Determine highest temperature for RTD Group 1 and 2 (Maximum Run Temperature). At SPDS panel, the operator has DETERMINED the following Maximum Run Temperatures: RTD Group 1 - 293°F RTD Group 2 - 290°F PROMPT: IF the operator addresses temperature indications on Panels P654 and P657; indications can be SIMULATED using the values from Attachment 2. 6. Determine highest temperature for RTD Group 5 (Maximum Run Temperature). At SPDS panel, the operator has DETERMINED the following Maximum Run Temperatures: RTD Group 5 - 263°F PROMPT: IF the operator addresses temperature indications on Panels P654 and P657; indications can be SIMULATED using the values from Attachment2.

2015-301 ADMIN 1 Page 10 of 16 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) **6. Determine if the RWL instrument may be used by comparing the Minimum Indicated Level for the associated Maximum Run Temperature. The operator has DETERMINED the following RWL instruments are VALID: 1C32-R606A (Narrow Range) 1C32-R606B (Narrow Range) 1C32-R606C (Narrow Range) NOTE: With RWL instruments, 1B21-R623A and 1B21-R623B (Fuel Zone), indicating **** (asterisks), these instruments are indicating UPSCALE (>-17 inches) for the current RWL. This is normal for the current RWL and the instruments are still valid. **7. Determine if the RWL instrument may be used by comparing the Minimum Indicated Level for the associated Maximum Run Temperature. The operator has DETERMINED the following RWL instruments are INVALID: 1B21-R604B 1B21-R605, (Flood Up Range) 1C32-R655, (Flood Up Range) 1B21-R623A (Wide Range) 1B21-R623B (Wide Range) **8. Determine correct RWL from the following; 1C32-R606A 1C32-R606B 1C32-R606C. Using 34AB-B21-002-1, the operator has DETERMINED Correct RWL for 1C32-R606A, B & C (narrow range) is +8 inches (accept 1 inch). END TIME:__________ NOTE: The terminating cue shall be given to the Operator when: After JPM step #8 is complete. With NO reasonable progress, the Operator exceeds double the allotted time. Operator states the task is complete. TERMINATING CUE FOR THE REACTOR OPERATORS: We will stop here. EVALUATOR - PICK UP the Initiating Cue sheet AND Attachments 1 & 2 for the Reactor Operators. PROMPT: Hand the Initiation Cue on the following page to the SROs for second half of JPM and then read the Initiation Cue to the SRO.

UNIT 1 READ TO THE OPERATOR

INITIAL CONDITIONS:

1. 1B21-N091A instrument detector has failed causing 1B21-R604A, Wide Range Instrument, to indicate High Upscale. 2. 1B21-N691B, Master Trip Unit (MTU), has failed and will NOT provide a trip signal.

INITIATING CUES: Determine Technical Specification required actions with regards to RCIC ONLY.

2015-301 ADMIN 1 Page 12 of 16 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) For INITIAL Operator Programs: For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance. For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance. IF THEN PASS Human performance tools, safety, PPE met (1), AND For initial trg all steps completed correctly OR For continuing trg, critical steps (if used) completed correctly Mark the JPM as a PASS FAIL Above standards not met Mark the JPM as a FAIL (2) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-111, "On-The-Job Training and Task Performance Evaluation". START TIME:__________ 9. Operator identifies the procedure needed to perform the task. Operator has identified the correct procedure as Unit 1 TRM/TS. 10. Determines the correct LFD by using section Table T10.1-1 Master Equipment Cross Reference-Sorted by MPL of the TRM. Determines the correct LFD to be LFD-1-RCIC-01 by referencing 1B21-N691 A, B, C, D. (1B21-N091A and 1B21-N691B both reference LFD-1-RCIC-01) 11. Determines correct Technical Specifications section to be entered by using section Table T10.1-1 Master Equipment Cross Reference-Sorted by MPL of the TRM. Determines Technical Specification section to be referenced by TRM section Table T10.1-1 Master Equipment Cross Reference is TS 3.3.5.2-1(1.) **12. Determines if RCIC Initiation is being maintained by using LFD. Determines that 1E11-K79A contact (Channel A1) will NOT close since the instrument has failed high as given in the Initiating Cue. NOTE: Contact 1E11-K79A will only close on RLW Low Level 2 (-35 inches). (** Indicates critical step) 2015-301 ADMIN 1 Page 13 of 16 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) **13. Determines if RCIC Initiation is being maintained by using LFD. Determines that 1E11-K79B (Channel B1) contact will NOT close since the MTU will NOT trip as given in the Initiating Cue. **14. Determines if RCIC Initiation is being maintained by using LFD. Determines that RCIC Initiation is NOT being maintained since relay E51-K2, K3, K81, K85 can NOT be energized by using drawing for the TRIP Logic or by using the Minimum Channel Requirements for System Initiation Capability at bottom of LFD. NOTE: Minimum Channel Requirements for System Initiation Capability: A1 & A2 A1 & B2 B1 & A2 B1 & B2 15. Determines Technical Specification Required Actions SRO determines that TS Table 3.3.5.2-1(1.) requires 4 channels to be operable AND SRO determines 2 of the 4 required Channels (A1 and B1) are INOP. **16. Determines Technical Specification Required Actions SRO enters TS 3.3.5.2.A and performs Required Action A.1 Immediately by Entering Condition referenced in Table 3.3.5.2-1 for the channel. The SRO immediately enters Condition 3.3.5.2.B (** Indicates critical step) 2015-301 ADMIN 1 Page 14 of 16 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) **17. Determines Technical Specification Required Actions SRO determines Required Action B.1 is required to be performed since RCIC Initiation Capability is NOT maintained and will declare RCIC inoperable within one hour. **18. Determines Technical Specification Required Actions SRO performs Required Action B.2 by directing Channel placed in trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> END TIME:__________ NOTE: The terminating cue shall be given to the Operator when: After JPM step #18 is complete. With NO reasonable progress, the Operator exceeds double the allotted time. Operator states the task is complete. TERMINATING CUE FOR THE SROs: We will stop here. EVALUATOR - PICK UP the Initiating Cue sheets AND Attachments 1 & 2. (** Indicates critical step)

Page 15 of 16 Page 16 of 16 Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.1 Page 1 of 11 Southern Nuclear Company Operations Training JPM FINAL ADMIN 2 - ALL Title: IRM Alternate Power Checks Prior To Taking The Mode Switch To Run (Admin) Author: ANTHONY BALL Media Number: 2015-301 ADMIN 2 Time: 15 Minutes Line Technical Review By (N/A for minor revisions) Date: Reviewed by Instructional Technologist or designee:

Date: Approved By (Training Program Manager or Lead Instructor) Ed Jones Date 03/10/2015

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.1 Page 2 of 11 This page intentionally left blank

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.1 Page 3 of 11 Course Number N/A Program Name OPERATIONS TRAINING Media Number 2015-301 ADMIN 2 Rev. No. Date Reason for Revisions Author's Initials Sup's Initials 01 03/10/2015 Revised ILT-1 Admin JPM LR-JP-25047 to match updated 34GO-OPS-001. New IRM Multipliers are included. After 2015 NRC Exam will be re-numbered to LR-JP-25047. ARB ELJ Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.1 Page 4 of 11 Line Contributors The following individuals contributed to the development of this lesson plan.

Rev. No. List of Contributors

UNIT 1 (X) UNIT 2 (X) TASK TITLE: IRM Alternate Power Checks Prior To Taking The Mode Switch To Run (Admin) JPM NUMBER: 2015-301 ADMIN 2 TASK STANDARD: This task shall be successfully completed when all of the JPM Critical Steps corresponding to 34GO-OPS-001-1, Attachment 15, have been correctly performed to determine that Average % power calculated is higher then current APRM power readings and an evaluation of power level indication is required. TASK NUMBER: xxx.xxx OBJECTIVE NUMBER: xxx.xxx.x PLANT HATCH JTA IMPORTANCE RATING: RO x.xx SRO x.xx K/A CATALOG NUMBER: G2.1.23 K/A CATALOG JTA IMPORTANCE RATING:

RO 4.3 SRO 4.0 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO) GENERAL

REFERENCES:

Unit 1 Unit 2 34GO-OPS-001-1 (current version) N/A REQUIRED MATERIALS: Unit 1 Unit 2 34GO-OPS-001-1 Attachment 15 (current version) N/A APPROXIMATE COMPLETION TIME: 15 Minutes SIMULATOR SETUP: N/A

UNIT 1 READ TO THE OPERATOR

INITIAL CONDITIONS:

1. Reactor Startup is in progress. 2. The crew is making preparations to startup the Steam Jet Air Ejector prior to securing the Mechanical Vacuum Pump. 3. All APRMs are currently reading 4.0% power. 4. Pre-Job Brief is NOT required.

INITIATING CUES: IAW 34GO-OPS-001-1, perform Alternate Power Level check per Attachment 15.

2015-301 ADMIN 2 Page 7 of 11 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) For INITIAL Operator Programs: For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance. For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance. IF THEN PASS Human performance tools, safety, PPE met (1), AND For initial trg all steps completed correctly OR For continuing trg, critical steps (if used) completed correctly Mark the JPM as a PASS FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. START TIME:__________ 1. Operator has DETERMINED the correct procedure section to use. Operator has OBTAINS the correct procedure section to use starting at Attachment 15 PROMPT: AT this time GIVE the operator Attachment 1 (34GO-OPS-001-1, ATTACHMENT 15).

PROMPT: AT this time, GIVE the Operator Attachment 2 of this JPM (IRM Data).

2. The operator identifies where he will obtain IRM power and range information to record on Attachment 15. The operator identifies where the IRM power information is obtained, At 1H11-P603. NOTE: ATTACHMENT 3 is the marked up answer key. 3. The operator copies the IRM range and power level data onto the copy of 34GO-OPS-001-1 Attachment 15. Using the copy of 34GO-OPS-001-1 Attachment 15 the data is recorded by operator. (** Indicates critical step) 2015-301 ADMIN 2 Page 8 of 11 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) **4. The operator performs the calculation to the IRM data. The operator uses the recorded IRM data and MULTIPLIES it by the correct constant of (0.212). PROMPT: IF the operator request that the Calculations be verified, THEN as another operator perform verification but DO NOT correct any errors.

• • 5. The operator determines that Average % power is greater than APRM power settings. Using the Average % power, the operator DETERMINES that APRMs readings are NOT greater than the Average IRM power.

• • 6. The operator determines an evaluation of power level is required. The operator informs the Shift Supervisor that an evaluation of power level indication is required. END TIME:__________ NOTE: The terminating cue shall be given to the Operator when: After JPM step #6 is complete. With NO reasonable progress, the Operator exceeds double the allotted time. Operator states the task is complete. TERMINATING CUE: We will stop here. EVALUATOR - PICK UP the Initiating Cue sheet AND ATTACHMENT 1& 2.

(** Indicates critical step)

ATTACHMENT 1 ATTACHMENT 2 IRM DATA IRMS RANGE READING A 9 18 C 9 20 E 9 20 G 10 20 B 9 18 D 9 22 F 10 20 H 9 18 ATTACHMENT 3 ** KEY ** DO NOT give this to applicant Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 1 of 18 Southern Nuclear Company Operations Training JPM

FINAL ADMIN 3 - ALL Title: REVIEW OF RCIC PUMP OPERABILITY SURVEILLANCE Author:

Anthony Ball Media Number:

2015-301 ADMIN 3 Time:

15.0 Minutes Line Technical Review By (N/A for minor revisions)

Date:

Reviewed by Instructional Technologist or designee: Date:

Approved By (Training Program Manager or Lead Instructor) Ed Jones Date 03/10/2015

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 2 of 18 This page intentionally left blank

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 3 of 18 Course Number N/A Program Name OPERATIONS TRAINING Media Number 2015-301 ADMIN 3 Rev. No. Date Reason for Revisions Author's Initials Sup's Initials 00 03/10/2015 Initial Development. ARB ELJ

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 4 of 18 Line Contributors

The following individuals contributed to the development of this lesson plan.

Rev. No. List of Contributors

2015-301 ADMIN 3 Page 5 of 18 5 UNIT 1 ( ) UNIT 2 (X) TASK TITLE: REVIEW OF RCIC PUMP OPERABILITY SURVEILLANCE JPM NUMBER: 2015-301 ADMIN 3 TASK STANDARD: This task shall be successfully completed when all of the JPM Critical Steps corresponding to 34SV-E51-002-2, Section 7.5 TEST RESULTS, step 7.5.1 through step 7.5.6, have been correctly performed to determine the RCIC surveillance is unsat due to RCIC pump Outlet Pressure (Running) Po, Differential Pressure & Differential Pressure dPr. TASK NUMBER: 300.011 OBJECTIVE NUMBER: 300.011.O K/A CATALOG NUMBER: Generic 2.2.12 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.7 SRO 4.1 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO) / Senior Reactor Operator (SRO)

GENERAL

REFERENCES:

Unit 2 34SV-E51-002-2 (current version) REQUIRED MATERIALS: Unit 2 Completed surveillance package: 34SV-E51-002-2.

APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: N/A 3 Page 6 of 16

UNIT 2 READ TO THE OPERATOR

INITIAL CONDITIONS:

1. Unit 2 is at 100% power. 2. A Normal RCIC Pump Quarterly Inservice Test (IST) Data Test has just been completed for the RCIC pump IAW 34SV-E51-002-2, RCIC Pump Operability. 3. Response Time Test was performed 30 days ago. 4. Unit 2 reactor pressure is 1043 psig.

INITIATING CUES: Review Attachment 1 of 34SV-E51-002-2, RCIC Pump Operability.

Complete any calculations required by the surveillance data sheets.

Using Attachment 1 of 34SV-E51-002-2 data, COMPLETE Section 7.5 TEST RESULTS, step 7.5.1 through step 7.5.6.

2015-301 ADMIN 3 Page 7 of 18 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) (** Indicates critical step)

For INITIAL Operator Programs: For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance. IF THEN PASS Human performance tools, safety, PPE met (1), AND For initial trg all steps completed correctly OR For continuing trg, critical steps (if used) completed correctly Mark the JPM as a PASS FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-111, "On-The-Job Training and Task Performance Evaluation". START TIME:__________

PROMPT: AT this time, GIVE the Operator a complete copy of 34SV-E51-002-2, RCIC Pump Operability.

PROMPT: AT this time, GIVE the Operator Attachment 2 of this JPM (Data has been filled in for this JPM).

PROMPT: IF the Operator addresses the IST Book, INFORM the Operator that a supervisor has verified the reference data.

NOTE: JPM Steps 1 - 8 can be performed in any order. 1. The Operator evaluates parameters on and finds Turbine Speed Nr is acceptable. On Attach. 1 of 34SV-E51-002-2, the Operator EVALUATES Turbine Speed Nr data is SATISFACTORY. 3900 rpm (Acceptable Range:

3861 (0.99) to 3939 (1.01) rpm) 2015-301 ADMIN 3 Page 8 of 18 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) (** Indicates critical step) 2. The Operator evaluates parameters on and finds Inlet Pressure (Stopped) (Pi) is acceptable. On Attach. 1 of 34SV-E51-002-2, the Operator EVALUATES Inlet Pressure (Still) (Pi) data is SATISFACTORY. 34 psig Acceptable Range: >7 psig. 3. The Operator evaluates parameters on and finds Inlet Pressure (Running) (Pi) is acceptable. On Attach. 1 of 34SV-E51-002-2, the Operator EVALUATES Inlet Pressure (Running) (Pi) data is SATISFACTORY. 31 psig Acceptable Range: >7 psig. **4. The Operator evaluates parameters on Attachment 1 and finds Outlet Pressure (Running) Po is NOT acceptable. At step 7.5.2.1 of 34SV-E51-002-2, the Operator EVALUATES Outlet Pressure data IS NOT SATISFACTORY. 1072 psig is NOT in the Acceptable Range of

> 1135 psig.

NOTE: At this time, the Operator may elect to inform the Shift Supervisor that Outlet Pressure (Running) Po is NOT acceptable and RCIC has failed the surveillance. This action IS acceptable. It IS also acceptable for the Operator to complete the review before bringing this to the supervisor's attention. PROMPT: IF the Operator addresses the out of spec. item(s), DIRECT the Operator to finish the data package review.

2015-301 ADMIN 3 Page 9 of 18 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) (** Indicates critical step) **5. The Operator calculates and then evaluates on Attachment 1 and finds Differential Pressure (2) dPr is NOT acceptable. On Attach. 1 of 34SV-E51-002-2, the Operator CALCULATES AND EVALUATES Differential Pressure (2) dPr data IS NOT SATISFACTORY. 0.88 dPr is NOT in the Acceptable Range of 0.90 to 1.10 dPr.

NOTE: Ratio Differential Pressure (2) dPr is equal to the Test Value dPr divided by the Reference Value dPr. 1041/1183 = 0.88.

At this time, the Operator may elect to inform the Shift Supervisor that Differential Pressure (2) dPr is NOT acceptable and RCIC must be declared inoperable. This action IS acceptable. It IS also acceptable for the Operator to complete the review before bringing this to the supervisor's attention. PROMPT: IF the Operator addresses the out of spec. item(s), DIRECT the Operator to finish the data package review.

6. The Operator evaluates parameters on and finds Flowrate (4)

(Qr) is acceptable. On Attach. 1 of 34SV-E51-002-2, the Operator EVALUATES Flowrate (4) (Qr) data (400 gpm) is SATISFACTORY. Acceptable value is 400 gpm.

PROMPT: WHEN the Operator addresses the Out of Spec readings, INFORM the Operator to finish the data package review.

7. The Operator performs step 7.5.1 Reason for test: The Operator places a check mark for "Norm. Surv." per the initial conditions. 8. The Operator performs step 7.5.2.1 RCIC pump delivers at least 400 gpm at a pump discharge pressure of greater than OR equal to 1135 psig with reactor pressure of > 920 psig AND < 1058 psig. The Operator has determined RCIC pump Outlet Pressure (Running) Po <1135 psig has failed to meet the acceptance criteria of step 7.5.2.1.

2015-301 ADMIN 3 Page 10 of 18 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) (** Indicates critical step) 9. The Operator performs step 7.5.2.2 RCIC pump discharge lines up stream of valves 2E51-F013 AND F022 are filled. The Operator has verified that RCIC pump discharge lines up stream of valves 2E51-F013 AND F022 are filled.

PROMPT: WHEN the Operator addresses the RCIC pump discharge lines upstream of valves 2E51-F013 AND F022 are filled, INFORM the Operator that RCIC pump discharge lines up stream of valves 2E51-F013 AND F022 are filled.

10. The Operator performs step 7.5.2.3 2T41-B004A AND 2T41-B004B, RCIC Pump Rm Cooling Fans, auto start, WHEN RCIC is started. The Operator has verified that 2T41-B004A AND 2T41-B004B, RCIC Pump Rm Cooling Fans, auto start, WHEN RCIC started.

PROMPT: WHEN the Operator addresses the 2T41-B004A AND 2T41-B004B, RCIC Pump Rm Cooling Fans, INFORM the Operator that 2T41-B004A AND 2T41-B004B, RCIC Pump Rm Cooling Fans, auto started.

11. The Operator performs step 7.5.2.4 2P41-F040A AND 2P41-F040B, RCIC Pump Rm Cooler Valves, OPEN, WHEN cooler is running. The Operator has verified that 2P41-F040A AND 2P41-F040B, RCIC Pump Rm Cooler Valves, OPEN, WHEN cooler is running.

PROMPT: WHEN the Operator addresses the 2P41-F040A AND 2P41-F040B, RCIC Pump Rm Cooler Valves, open when RCIC is running, INFORM the Operator that 2P41-F040A AND 2P41-F040B, RCIC Pump Rm Cooler Valves, auto opened.

12. The Operator performs step 7.5.2.5 Oil level AND pressure is observed. The Operator has verified that Oil level AND pressure is observed.

PROMPT: WHEN the Operator addresses the Oil level AND pressure is observed, INFORM the Operator that Oil level AND pressures were observed.

2015-301 ADMIN 3 Page 11 of 18 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) (** Indicates critical step) **13. The Operator evaluates step 7.5.2.6.1 RCIC pump Outlet Pressure (Running) Po data. The Operator has determined that RCIC pump Outlet Pressure (Running) Po has FAILED to meet the acceptance criteria of step 7.5.2.1. NOTE: At this time, the Operator may elect to inform the Shift Supervisor that Outlet Pressure (Running) Po is NOT acceptable and RCIC has failed the surveillance. This action IS acceptable. It IS also acceptable for the Operator to complete the review before bringing this to the supervisor's attention. **14. The Operator evaluates step 7.5.2.6.2 RCIC pump dPr data. The Operator has determined that Differential Pressure dPr has FAILED to meet the acceptance criteria of step 7.5.2.6.2. NOTE: At this time, the Operator may elect to inform the Shift Supervisor that Differential Pressure (2) dPr is NOT acceptable. This action IS acceptable. It IS also acceptable for the Operator to complete the review before bringing this to the supervisor's attention. 15. The Operator evaluates step 7.5.2.6.2 Flowrate (4) (Qr) data. The Operator has determined that Flowrate (Qr) data meets the acceptance criteria of step 7.5.2.6.2. 16. The Operator evaluates step 7.5.2.7 if Response Time Test was performed. The Operator evaluates if Response Time Test was performed. PROMPT: WHEN the Operator addresses Response Time Test, INFORM the Operator to review Initial Conditions provided.

2015-301 ADMIN 3 Page 12 of 18 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) (** Indicates critical step) **17. The Operator performs step 7.5.4 Test Result. The Operator completes step 7.5.4 and marks the step UNSAT.

NOTE: JPM Steps 26 - 28 can be performed in any order.

• • 18. The Operator performs step 7.5.5 for RCIC pump Outlet Pressure (Running) Po <1135 psig has failed to meet the acceptance criteria of step 7.5.2.6.1. The Operator lists in step 7.5.5 that RCIC pump Outlet Pressure (Running) Po has FAILED to meet the acceptance criteria of step 7.5.2.1 & 7.5.2.6.1

(<1135 psig).

• • 19. The Operator performs step 7.5.5 RCIC Differential Pressure dPr. The Operator also lists in step 7.5.5 that RCIC Differential Pressure dPr has FAILED to meet the acceptance criteria of step 7.5.2.6.1 (dPr < 0.90). NOTE: If the Operator addresses writing a Condition Report (CR) based on this surveillance, inform the Operator that another operator will write the CR. END TIME:__________ NOTE: The terminating cue shall be given to the Operator when: - After JPM step #19 is complete. - With NO reasonable progress, the Operator exceeds double the allotted time. - Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR - PICK UP the Initiating Cue sheet.

SNC PLANT E. I. HATCH Pg 45 of 59 DOCUMENT TITLE: RCIC PUMP OPERABILITY DOCUMENT NUMBER: 34SV-E51-002-2 Version No: 24.1 ATTACHMENT 1 Attachment Page TITLE: RCIC PUMP QUARTERLY IST DATA AND ACCEPTANCE CRITERIA 1 of 1 (** Indicates critical step) Page 13 of 18 ATTACHMENT 1 ** KEY ** DO NOT give this to applicant Reference Data Changes: Is reference data being changed? ( ) Yes () No IF YES, list justification for so doing: (2E51-C001) PARAMETER INSTRU MPL NO. REFERENCE VALUE DATE REF VALUE TAKEN TEST VALUE ACCEPT. RANGE ALERT RANGE REQ'D ACTION RANGE (1) RATIO (3) Turbine Speed (Nr) 2E51-R610 OR, Calibrated Handheld Tachometer 3900* 01/18/12* 3900* 0.99 to 1.01 RPM N/A N/A N/A Pump Suction Pressure (Still) 2E51-R604 N/A N/A 34* ³7 PSIG N/A < 7 PSIG N/A Pump Suction Pressure (Running) (Pi) 2E51-R604 31*

01/18/12*

31* ³7 PSIG N/A < 7 PSIG N/A Outlet Pressure (Po) 2E51-R601 1215*

01/18/12*

1072* N/A N/A N/A N/A Differential Pressure (2) (DPr) N/A 1183*

01/18/12*

1041* 0.90 to 1.10 dPr N/A <0.90 or >1.10 dPr 0.88* Flowrate (4) (Qr) 2E51-R612 400 N/A 400* N/A N/A N/A 1.0

(1) Pump declared inoperable according to 31GO-INS-001-0. (2) Differential pressure must be calculated as: dP = Outlet Pressure (pump running) - Inlet Pressure (Pump running) (3) Ratio = Test Value divided by Reference Value (4) Test value must equal reference value. Ratio for flowrate must equal 1.0.

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 42 OF 59 DOCUMENT TITLE: RCIC PUMP OPERABILITY DOCUMENT NUMBER: 34SV-E51-002-2 VERSION NO: 24.1 Page 14 of 18 ATTACHMENT 1 ** KEY ** DO NOT give this to applicant 7.5 TEST RESULTS 7.5.1 Reason for test: ( ) Norm. Surv. ( ) WO # ____________________________________ ( ) Other ________________________________________________________________

7.5.2 Acceptance Criteria 7.5.2.1 RCIC pump delivers at least 400 gpm at a pump discharge pressure of ³1135 psig with reactor pressure between 920 and 1058 psig.

• 7.5.2.2 RCIC Pump discharge lines up stream of valves 2E51-F013 and 2E51-F022 are filled.

7.5.2.3 2T41-B004A and 2T41-B004B, RCIC Pump Rm Cooler Fans, AUTO START WHEN RCIC is started.

7.5.2.4 2P41-F040A and 2P41-F040B, RCIC Pump Rm Cooler Valves, OPEN, WHEN cooler is running.

7.5.2.5 Oil levels observed in the normal range, OR LOR written.

7.5.2.6 IF the 92 day test or CPT was performed: 7.5.2.6.1 Steps 7.5.2.1 through 7.5.2.5 are acceptable. 7.5.2.6.2 RCIC pump data matches the reference data WITHIN the limits stated on Attachment 1, 5 or 6.

• 7.5.2.7 IF Response Time Test was performed, RCIC Pump obtained rated flow and pressure in less than OR equal to 45 seconds.

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 43 OF 59 DOCUMENT TITLE: RCIC PUMP OPERABILITY DOCUMENT NUMBER: 34SV-E51-002-2 VERSION NO: 24.1 Page 15 of 18 ATTACHMENT 1 ** KEY ** DO NOT give this to applicant 7.5.4 Test Result:

( ) Satisfactory ( ) Unsatisfactory 7.5.5 Unsatisfactory Conditions: (1) RCIC pump Outlet Pressure (Running) Po has FAILED to meet the acceptance criteria of step 7.5.2.1 (<1135 psig)___________________ (2) RCIC Differential Pressure dPr has FAILED to meet the acceptance criteria of step 7.5.2.6.2

_________________________________________________________________________

_________________________________________________________________________

_________________________________________________________________________

_________________________________________________________________________

7.5.6 Comments/Corrective Actions: ______________________________________________

_________________________________________________________________________

_________________________________________________________________________ 7.5.7 Test completed and/or verified by:

__________________________________________ / ____________ / ____________ Print Name / Initial / Date __________________________________________ / ____________ / ____________ Print Name / Initial / Date __________________________________________ / ____________ / ____________ Print Name / Initial / Date __________________________________________ / ____________ / ____________ Print Name / Initial / Date

SNC PLANT E. I. HATCH Pg 45 of 59 DOCUMENT TITLE: RCIC PUMP OPERABILITY DOCUMENT NUMBER: 34SV-E51-002-2 Version No: 24.1 ATTACHMENT 1 Attachment Page TITLE: RCIC PUMP QUARTERLY IST DATA AND ACCEPTANCE CRITERIA 1 of 1 Page 16 of 18 ATTACHMENT 2 PROVIDE TO APPLICANT Reference Data Changes:

Is reference data being changed? ( ) Yes ( ) No IF YES, list justification for so doing: (2E51-C001) PARAMETER INSTRU MPL NO. REFERENCE VALUE DATE REF VALUE TAKEN TEST VALUE ACCEPT. RANGE ALERT RANGE REQ'D ACTION RANGE (1) RATIO (3) Turbine Speed (Nr) 2E51-R610 OR, Calibrated Handheld Tachometer 3900* 01/18/12* 3900* 0.99 to 1.01 RPM N/A N/A N/A Pump Suction Pressure (Still) 2E51-R604 N/A N/A 34* ³7 PSIG N/A < 7 PSIG N/A Pump Suction Pressure (Running) (Pi) 2E51-R604 31*

01/18/12*

31* ³7 PSIG N/A < 7 PSIG N/A Outlet Pressure (Po) 2E51-R601 1215*

01/18/12*

1072* N/A N/A N/A N/A Differential Pressure (2) (DPr) N/A 1183*

01/18/12*

1041* 0.90 to 1.10 dPr N/A <0.90 or >1.10 dPr

Flowrate (4) (Qr) 2E51-R612 400 N/A 400* N/A N/A N/A 1.0

(1) Pump declared inoperable according to 31GO-INS-001-0.

(2) Differential pressure must be calculated as: dP = Outlet Pressure (pump running) - Inlet Pressure (Pump running)

(3) Ratio = Test Value divided by Reference Value

(4) Test value must equal reference value. Ratio for flowrate must equal 1.0.

SNC PLANT E. I. HATCH Pg 42 of 59 DOCUMENT TITLE: RCIC PUMP OPERABILITY DOCUMENT NUMBER: 34SV-E51-002-2 Version No: 24.1 Page 17 of 18 ATTACHMENT 2 PROVIDE TO APPLICANT 7.5 TEST RESULTS 7.5.1 Reason for test: ( ) Norm. Surv. ( ) WO # ____________________________________ ( ) Other ________________________________________________________________

7.5.2 Acceptance Criteria 7.5.2.1 RCIC pump delivers at least 400 gpm at a pump discharge pressure of ³1135 psig with reactor pressure between 920 and 1058 psig.

• 7.5.2.2 RCIC Pump discharge lines up stream of valves 2E51-F013 and 2E51-F022 are filled.

7.5.2.3 2T41-B004A and 2T41-B004B, RCIC Pump Rm Cooler Fans, AUTO START WHEN RCIC is started.

7.5.2.4 2P41-F040A and 2P41-F040B, RCIC Pump Rm Cooler Valves, OPEN, WHEN cooler is running.

7.5.2.5 Oil levels observed in the normal range, OR LOR written.

7.5.2.6 IF the 92 day test or CPT was performed: 7.5.2.6.1 Steps 7.5.2.1 through 7.5.2.5 are acceptable.

7.5.2.6.2 RCIC pump data matches the reference data WITHIN the limits stated on Attachment 1, 5 or 6.

• 7.5.2.7 IF Response Time Test was performed, RCIC Pump obtained rated flow and pressure in less than OR equal to 45 seconds. 7.5.4 Test Result:

( ) Satisfactory ( ) Unsatisfactory 7.5.5 Unsatisfactory Conditions: __________________________________________________ ________________________________________________________________________ ________________________________________________________________________

7.5.6 Comments/Corrective Actions: _______________________________________________ ________________________________________________________________________ ________________________________________________________________________

SNC PLANT E. I. HATCH Pg 43 of 59 DOCUMENT TITLE: RCIC PUMP OPERABILITY DOCUMENT NUMBER: 34SV-E51-002-2 Version No: 24.1 Page 18 of 18 ATTACHMENT 2 PROVIDE TO APPLICANT 7.5.7 Test completed and/or verified by:

___________________________________________________________________ Print Name / Initial / Date

___________________________________________________________________ Print Name / Initial / Date

___________________________________________________________________ Print Name / Initial / Date

___________________________________________________________________ Print Name / Initial / Date

___________________________________________________________________ Print Name / Initial / Date

___________________________________________________________________ Print Name / Initial / Date Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 1 of 14 Southern Nuclear Company Operations Training JPM FINAL ADMIN 4 - RO ONLY Title: DETERMINE THE EVACUATION ROUTE DURING AN EMERGENCY Author: Anthony Ball Media Number: 2015-301 ADMIN 4 Time: 9.0 Minutes Line Technical Review By (N/A for minor revisions) Date: Reviewed by Instructional Technologist or designee: Date: Approved By (Training Program Manager or Lead Instructor) Ed Jones Date 03/10/2015

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 2 of 14 This page intentionally left blank

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 3 of 14 Course Number N/A Program Name OPERATIONS TRAINING Media Number 2015-301 ADMIN 4 Rev. No. Date Reason for Revisions Author's Initials Sup's Initials 17 5/26/11 Revise JPM LR-JP-20059, due to implementation of NMP-EP 110 and NMP-EP-111 and for NRC Exam 2011-3011. ELJ CME 17.1 03/10/2015 Minor revision for procedure comparison and modified wind direction to obtain a different evacuation route. After 2015 NRC Exam will be incorporated into JPM Database with new media number. ARB ELJ

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 4 of 14 Line Contributors The following individuals contributed to the development of this lesson plan.

Rev. No. List of Contributors

2015-301 ADMIN 4 Page 5 of 14 UNIT 1 (X) UNIT 2 (X) TASK TITLE: DETERMINE THE EVACUATION ROUTE DURING AN EMERGENCY JPM NUMBER: 2015-301 ADMIN 4 TASK STANDARD: This task shall be successfully completed when all of the JPM Critical Steps corresponding to NMP-EP-111-002, Instruction 5 Section IV, have been correctly performed to evacuate via the PESB, then using THE ROAD BEHIND THE LOW LEVEL RADWASTE BUILDING and then SOUTH on US Highway 1. TASK NUMBER: 200.059 OBJECTIVE NUMBER: 200.059.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.86 SRO 3.96 K/A CATALOG NUMBER: G2.4.39 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.9 SRO 3.80 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO) GENERAL

REFERENCES:

Unit 1 & 2 NMP-EP-111-002 (current version) REQUIRED MATERIALS: Unit 1 & 2 NMP-EP-111-002 (current version)

APPROXIMATE COMPLETION TIME: 9.0 Minutes SIMULATOR SETUP: N/A 4

UNIT 1 & 2 READ TO THE OPERATOR

INITIAL CONDITIONS:

1. A Reactor scram has occurred. 2. Plant conditions have resulted in an Elevated Radioactive release. 3. A Prompt Off-Site Dose Assessment calculation has been performed and an Offsite Release has been verified to be in progress. 4. Peak calculated TEDE is 100 mRem/hr. 5. The Emergency Director (ED) has declared a Site Area Emergency. 6. The ED has directed a PA announcement to be performed IAW NMP-EP-111. 7. SPDS is available.

INITIATING CUES: Your task is to fill out the appropriate form required to make the PA announcement for this emergency IAW NMP-EP-111-002, "EMERGENCY NOTIFICATION NETWORK COMMUNICATOR INSTRUCTIONS - HATCH." NOTE: Another Operator will make the actual page announcement IAW NMP-EP-111 Checklist 1 "Page Announcements."

2015-301 ADMIN 4 Page 7 of 14 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) For INITIAL Operator Programs: For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance. For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance. IF THEN PASS Human performance tools, safety, PPE met (1), AND For initial trg all steps completed correctly OR For continuing trg, critical steps (if used) completed correctly Mark the JPM as a PASS FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-111, "On-The-Job Training and Task Performance Evaluation". START TIME:__________ NOTE: The Operator may review NMP-EP-111 Checklist 1 "Page Announcements". PROMPT: AT THIS TIME PROVIDE the operator with the following: o NMP-EP-111-002, "EMERGENCY NOTIFICATION NETWORK COMMUNICATOR INSTRUCTIONS - HATCH." AND o Also PROVIDE the attached SPDS Attachments. 1. Select correct section of NMP-EP-111-002. The operator uses NMP-EP-111-002, Table of Contents and determines that Instruction 5 - Emergency Page Announcement Selection Guidance is the required section.

(** Indicates critical step) 2015-301 ADMIN 4 Page 8 of 14 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) **2. Select the correct form to use for a Site-Area Emergency announcement. The operator uses NMP-EP-111-002, Instruction 5 to determine that "IV. Standard Announcement For Notification Of Site-Area Or General Emergency" (see page

14) is the required form. NOTE: The operator may review the NOTES at the top of NMP-EP-111-002, "IV. Standard Announcement For Notification Of SAE Or GE"

3. IV. a. Refer to "Selection Guidance" information on page 11 to determine the applicable rally point, exit route and evacuation route. Record the applicable information. The operator determines that wind direction is required in order to select the correct evacuation route.

• • 4. Check wind direction. At panel 1H11-P690, wind direction checked on one of the following: SPDS MIDAS screen OR SPDS MET Data screen

(** Indicates critical step) 2015-301 ADMIN 4 Page 9 of 14 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) **5. Determine the applicable rally point, Record the applicable information. The Operator uses "Selection Guidance" information on page 11 to determine: Rally point: PESB The Operator then RECORDS the information in appropriate section of "IV. Standard Announcement For Notification Of Site-Area Or General Emergency." **6. Determine the applicable, exit route; Record the applicable information. The Operator uses "Selection Guidance" information on page 11 to determine: Exit Route: Road behind Low Level Radwaste Building The Operator then RECORDS the information in appropriate section of "IV. Standard Announcement For Notification Of Site-Area Or General Emergency." **7. Determine the applicable evacuation route. Record the applicable information. The Operator uses "Selection Guidance" information on page 11 to determine:

Evacuation Route: U.S. Highway 1 - South to Appling Co. High School/ Baxley The Operator then RECORDS the information in appropriate section of "IV. Standard Announcement For Notification Of Site-Area Or General Emergency." NOTE: If the operator uses the 10 Meter, 23 Meter or the 60 Meter wind direction, the Site Exit Route will (INCORRECTLY) state "Main Access Road." (** Indicates critical step) 2015-301 ADMIN 4 Page 10 of 14 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) NOTE: The Operator may select DRILL for item 1. This is an ACCEPTABLE practice for the purpose of training evaluations at Plant Hatch.

PROMPT: IF the Operator addresses contacting Security to activate the PA system in the Simulator and Skills Buildings INFORM the Operator that Security has been directed to activate the PA system in the Simulator and Skills Buildings PROMPT: IF the Operator addresses NMP-EP-111 Checklist 1 "Page Announcements," as the Shift Supervisor, INFORM the Operator that this will performed by another Operator. END TIME:__________ NOTE: The terminating cue shall be given to the Operator when: With NO reasonable progress, the Operator exceeds double the allotted time. Operator states the task is complete. TERMINATING CUE: We will stop here. (** Indicates critical step)

EVALUATOR ANSWER KEY IV. STANDARD ANNOUNCEMENT INSTRUCTIONS FOR SITE-AREA OR GENERAL EMERGENCY NOTES: The appropriate emergency tone and announcement must be made as soon as possible, but not to exceed 15 minutes after the initial emergency declaration The person making this announcement is expected to announce all applicable information. a. Refer to "Selection Guidance" information on page 11 to determine the applicable rally point, exit route and evacuation route. Record the applicable information below needed for this announcement. b. Contact Security to direct activation of the Public Address system in the Simulator and Skills Buildings PRIOR to beginning the announcement. c. Perform IAW NMP-EP-111 Checklist 1 "Page Announcements". (Select one) Site-Area Emergency or General Emergency 1. ATTENTION ALL PERSONNEL. THIS (IS / IS NOT) A DRILL. A/AN Site-Area Emergency HAS BEEN DECLARED. 2. (Select one): A RADIOLOGICAL RELEASE (IS / IS NOT) IN PROGRESS. 3. ALL EMERGENCY RESPONSE PERSONNEL ARE TO REPORT TO YOUR EMERGENCY RESPONSE FACILITY AND INITIATE EMERGENCY IMPLEMENTING PROCEDURES. NOTE: Announcement of items 4 or 5 may be discontinued upon verification that non-essential personnel have left the plant site. 4. Use if a radiological release is not in progress ALL NON-ESSENTIAL PERSONNEL ARE TO EXIT THE PLANT SITE USING THE MAIN ACCESS ROAD. THE EVACUATION ROUTE IS EITHER DIRECTION ON U. S. HIGHWAY 1. 5. Use if a radiological release is in progress ALL NON-ESSENTIAL PERSONNEL ARE TO EXIT THE PLANT SITE USING (select one): THE MAIN ACCESS ROAD, THE ROAD BEHIND THE LOW LEVEL RADWASTE BUILDING, OTHER (specify another exit route) _______________________. AND THE EVACUATION ROUTE IS (Select one): EITHER DIRECTION ON U.S. HIGHWAY 1. REPORT TO THE STATE RECEPTION CENTER AT EITHER TOOMBS CO. HIGH SCHOOL IN LYONS OR APPLING CO. HIGH SCHOOL IN BAXLEY. SOUTH ON U. S. HIGHWAY 1. REPORT TO THE STATE RECEPTION CENTER AT APPLING CO. HIGH SCHOOL IN BAXLEY. NORTH ON U. S. HIGHWAY 1. REPORT TO THE STATE RECEPTION CENTER AT TOOMBS CO. HIGH SCHOOL IN LYONS.

EVALUATOR ANSWER KEY SELECTION GUIDANCE FOR STANDARD ANNOUNCEMENT RALLY POINT/SITE EXIT ROUTE/ EVACUATION ROUTE Is a radiological release in progress? Yes No IF a. A radiological release Is Not in progress: THEN b. The following rally point, site exit route, and evacuation route will be used: Rally Point - Plant Entry & Security Building (PESB) Site Exit Route - Main Access Road Evacuation Route - Either direction on U. S. Hwy 1. IF c. A radiological release Is in progress: THEN Use the chart below to determine the rally point, site exit route, evacuation route and State Reception Center, based on wind direction. Consult with Security to determine alternative(s) IF designated rally point and/or site exit route cannot be used. The use of an alternate rally point requires notifying Security and HP prior to making the announcement. NOTE: The 15 minute average wind direction information should be read using the meteorological instrumentation that corresponds to the primary release point. Wind Direction From: Rally Point: Site Exit Route: Evacuation Route/State Reception Center 340º - 60º Gate 17 Main Access Road U.S. Highway 1 - North to Toombs Co. High School/Lyons 61º - 110º PESB Road behind Low Level Radwaste Building U.S. Highway 1 - South to Appling Co. High School/ Baxley 111º - 225º PESB Main Access Road U.S. Highway 1 - South to Appling Co. High School/ Baxley 226º - 339º PESB Main Access Road Either direction on U.S. Highway 1 to Toombs Co. High School/Lyons or Appling Co. High School/Baxley 2015-301 ADMIN 4 Page 13 of 14 2015-301 ADMIN 4 Page 14 of 14 Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 1 of 13 Southern Nuclear Company Operations Training JPM FINAL ADMIN 5 (SRO ONLY) Title: Evaluate Venting DW Irrespective of Offsite Release rates IAW PCG (ALTERNATE PATH) Author: Anthony Ball Media Number: 2015-301 ADMIN 5 Time:

20.0 Minutes Line Technical Review By (N/A for minor revisions) Date: Reviewed by Instructional Technologist or designee: Date: Approved By (Training Program Manager or Lead Instructor) Ed Jones Date 03/10/2015

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 2 of 13 This page intentionally left blank

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 3 of 13 Course Number N/A Program Name OPERATIONS TRAINING Media Number 2015-301 ADMIN 5 Rev. No. Date Reason for Revisions Author's Initials Sup's Initials 00 03/10/2015 Modified 2011-301 Admin 4 to use on ILT-9 NRC Exam 2015-301. After exam both JPMs will be renumbered and incorporated into JPM bank. ARB ELJ Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 4 of 13 Line Contributors The following individuals contributed to the development of this lesson plan.

Rev. No. List of Contributors

2015-301 ADMIN 5 Page 5 of 13 UNIT 1 ( ) UNIT 2 (X) TASK TITLE: Evaluate Venting DW Irrespective of Offsite Release rates IAW PCG (ALTERNATE PATH) JPM NUMBER: 2015-301 ADMIN 5 TASK STANDARD: This task shall be successfully completed when all of the JPM Critical Steps corresponding to 31EO-PCG-001-2, Path G2 have been correctly performed to first initiate Containment venting and then securing Containment venting after release rates exceed limits. TASK NUMBER: 201.072 PLANT HATCH JTA IMPORTANCE RATING:

RO 4.57 SRO 3.88 K/A CATALOG NUMBER: G2.3.11 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.80 SRO 3.70 OPERATOR APPLICABILITY: Senior Reactor Operator (SRO)

GENERAL

REFERENCES:

Unit 2 31EO-PCG-001-2 REQUIRED MATERIALS: Unit 2 31EO-PCG-001-2 APPROXIMATE COMPLETION TIME: 20.0 Minutes SIMULATOR SETUP: N/A 5

UNIT 2 READ TO THE OPERATOR

INITIAL CONDITIONS:

1. You are the SS on Unit 2. 2. A reactor scram occurred due to a LOCA. 3. An Emergency Depressurization has been performed. 4. RWL is being maintained using all available Core Spray and RHR pumps. 5. NO Primary Containment Venting is in progress. 6. NO Primary Containment Purging is in progress. 7. Estimated Offsite Dose has been calculated at 300 mR/hr. 8. A Projected Offsite Dose has been calculated at 400 mR/hr. 9. Plant conditions are indicated on Attachment 1.

INITIATING CUES: Evaluate the PCG EOP flowchart, "31EO-PCG-001-2" ONLY. Raise your hand when you are ready to give direction to your crew.

2015-301 ADMIN 5 Page 7 of 13 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) For INITIAL Operator Programs: For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance. For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance. IF THEN PASS Human performance tools, safety, PPE met (1), AND For initial trg all steps completed correctly OR For continuing trg, critical steps (if used) completed correctly Mark the JPM as a PASS FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-111, "On-The-Job Training and Task Performance Evaluation". START TIME:__________ PROMPT: At this time PROVIDE ALL ATTACHMENTS to the student. **1. Enters the PCG flowchart. The operator ENTERS 31EO-PCG-001 flowchart. 2. Confirm the H2O2 analyzers are in service. The operator DETEMINES that the the H2O2 analyzers are in service by checking 2H11-P700 or SPDS. **3. Evaluate the override at C-5. The operator DETERMINES that path G-2 Point "S" is to be entered. 4. At D-6 on path G-2, determine if Projected TEDE is >1000 mr/hr. The operator DETERMINES Projected TEDE is <1000 mr/hr based on Initial conditions. 5. At D-6 on path G-2, determine if there is detectable Hydrogen in drywell or torus. The operator DETERMINES there is Hydrogen in drywell or torus based on Initial conditions. 6. Determines Estimated Offsite Dose. The operator DETERMINES and RECORDS at E-7 the Estimated Offsite Dose to be 300 mr/hr based on Initial conditions. (** Indicates critical step) 2015-301 ADMIN 5 Page 8 of 13 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) 7. Determines Projected Offsite Dose. The operator DETERMINES and RECORDS at E-7 the Projected Offsite Dose to be 400 mr/hr based on Initial conditions. 8. Determines the TOTAL Estimated and Projected Peak TEDE. The operator DETERMINES and RECORDS at F-7 the TOTAL Estimated and Projected Peak TEDE to be 700 mr/hr (300 + 400 = 700). NOTE: The operator will raise their hand and the debrief will begin here. **9. Uses step at J-5 on path G-2, to direct an NPO to start Drywell Cooling Fans and Return Fans. The operator DIRECTS an NPO to start Drywell Cooling Fans and Return Fans. PROMPT: WHEN the operator directs the starting of DW Cooling Fans and Return Fans, INFORM the operator that DW Cooling Fans and Return Fans are running. 10. Evaluates decision step at G-7, on path G-2, to determine whether Torus Water level is below 300 inches. The operator DETERMINES that Torus level is below 300 inches. (Chooses YES, proceeds to the right to vent the Torus). **11. Using step at H-7, on path G-2, directs Vent torus per 31EO-EOP-104-2. If necessary, defeat isolation interlocks. The operator DIRECTS an NPO to Vent torus per 31EO-EOP-104-2. If necessary, defeat isolation interlocks. PROMPT: WHEN directed to initiate venting of the Torus, INFORM the operator that, using Time Compression, Torus venting is in progress. PROMPT: IF ASKED whether the DW is being vented throught the Torus, INFORM the operator the indications are DW pressure and Torus pressure are both slowly decreasing. (** Indicates critical step) 2015-301 ADMIN 5 Page 9 of 13 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) **12. Using step at J-7, on path G-2, directs Initiate and maximize drywell nitrogen purge flow per 31EO-EOP-104-2. The operator DIRECTS an NPO to Initiate and maximize primary containment purge flow per 31EO-EOP-104-2. PROMPT: WHEN directed to initiate Primary Containment Purge flow, INFORM the operator that, using Time Compression, Primary Containment purge flow has been initiated and maximized. PROMPT: AFTER operator is informed that Primary Containment purge flow has been initiated and maximized, INFORM the operator that 30 minutes has elapsed and the TSC RP Supervisor reports that the Projected Offsite Dose is now 1100 mr/hr. 13. Evaluates the override at D-6 on path G-2, to determine if Projected TEDE is >1000 mr/hr. The operator DETERMINES Projected TEDE is >1000 mr/hr (1100 mr/hr). 14. Evaluates the override at D-6 on path G-2, to determine if adequate core cooling is assured. The operator DETERMINES adequate core cooling is assured based on Initial conditions. **15. Using step at D-6, on path G-2, directs torus venting secured. The operator DIRECTS an NPO to secure torus venting. PROMPT: WHEN the operator addresses securing Torus venting, INFORM the operator that torus venting has been secured. **16. Using step at D-6, on path G-2, directs nitrogen purge flow secured. The operator DIRECTS an NPO to secure nitrogen purge flow. PROMPT: WHEN the operator addresses securing Torus venting, INFORM the operator that nitrogen purge flow has been secured. END TIME:__________ NOTE: The terminating cue shall be given to the operator when: With NO reasonable progress, the operator exceeds double the allotted time. Operator states the task is complete. TERMINATING CUE: We will stop here. (** Indicates critical step)

UNIT 2 READ TO THE OPERATOR

INITIAL CONDITIONS:

1. You are the SS on Unit 2 2. A reactor scram occurred due to a LOCA 3. An Emergency Depressurization has been performed 4. RWL is being maintained using all available Core Spray and RHR pumps 5. NO Primary Containment Venting is in progress 6. NO Primary Containment Purging is in progress 7. Estimated Offsite Dose has been calculated at 300 mR/hr 8. A Projected Offsite Dose has been calculated at 400 mR/hr 9. Plant conditions are indicated on Attachment 1.

INITIATING CUES: Evaluate the PCG EOP flowchart, "31EO-PCG-001-2" ONLY. Raise your hand when you are ready to give direction to your crew.

(** Indicates critical step) 3.5 4.0 Page 11 of 13 Page 12 of 13 Page 13 of 13 Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 1 of 15 Southern Nuclear Company Operations Training JPM FINAL ADMIN 6 SRO ONLY Title: Emergency Classification - Complete NMP-EP-110 Checklist 1 Author: Anthony Ball Media Number:

2015-301 ADMIN 6 Time Critical:

15 Minutes Line Technical Review By (N/A for minor revisions) Date: Reviewed by Instructional Technologist or designee: Date: Approved By (Training Program Manager or Lead Instructor) Ed Jones Date 03/10/2015

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 2 of 15 This page intentionally left blank

Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 3 of 15 Course Number N/A Program Name OPERATIONS TRAINING Media Number 2015-301 ADMIN 6 Rev. No. Date Reason for Revisions Author's Initials Sup's Initials 00 8/23/11 Initial Development SDH DNM 01 10/15/13 Made left hand column match procedure steps. Ensured each critical step only has one action. ADDED Checklist 1 answer key. MMG ALS 1.1 03/10/2015 Updated to latest procedure revision and will be used on ILT-9 NRC Exam. After exam will be renamed back to original JPM Title (LR-JP-25071-01). ARB ELJ Southern Nuclear Operating Company Nuclear Management Form Training Material Cover/Revision Sheet NMP-TR-214-F01 Version 2.0 Page 4 of 15 Line Contributors The following individuals contributed to the development of this lesson plan.

Rev. No. List of Contributors

2015-301 ADMIN 6 Page 5 of 15 UNIT 1 (X) UNIT 2 (X) TASK TITLE: Emergency Classification - Complete NMP-EP-110 Checklist 1 JPM NUMBER: 2015-301 ADMIN 6 TASK STANDARD: This task shall be successfully completed when all of the JPM Critical Steps corresponding to NMP-EP-110 Checklist 1, Step 1.0 through 6.0, have been correctly performed to classify the event. TASK NUMBER: 200.052 OBJECTIVE NUMBER: 200.052.A PLANT HATCH JTA IMPORTANCE RATING:

RO 4.67 SRO 4.04 K/A CATALOG NUMBER: Generic 2.4.41 K/A CATALOG JTA IMPORTANCE RATING:

RO 2.30 SRO 4.1 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 & 2 NMP-EP-110 (current version) REQUIRED MATERIALS: Unit 1 & 2 NMP-EP-110 (current version)

APPROXIMATE COMPLETION TIME: 15 Minutes SIMULATOR SETUP: NA UNIT 1 & 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. You are the On Shift Shift Manager. 2. Units 1 and 2 are operating at 100% power. The FAA Atlanta calls Plant Hatch control room on the telephone. A NPO answers the phone. The following information is rapidly confirmed with the NRC Operations Center using the Emergency Notification System (ENS) phone. 3. The NRC Operations Center confirms: One (1) hour ago, a DC 10, Delta Flight D-1492, took off from Atlanta, headed for Houston Texas. The plane has inexplicably changed course, is now headed east, and is 20 miles west of Macon, Georgia. Atlanta Flight Control has tried all available methods to communicate with the flights' crew, but has been unsuccessful. Based on the planes flight path and rate of descent, it appears that Plant Hatch is in the flight path of a Track of Interest (TOI). The flight will reach Plant Hatch, by best estimate, in 29 minutes. 4. The Control Room has contacted the NRC and NRC has confirmed the information. 5. NO Peer Check is available. INITIATING CUES: Classify the Event by Completing NMP-EP-110 Checklist 1 Steps 1 through 5.

Raise your hand when you have completed Checklist 1, Step 5. This JPM is TIME CRITICAL.

Current time is: ___________________

2015-301 ADMIN 6 Page 7 of 15 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) For INITIAL Operator Programs: For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance. For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance. IF THEN PASS Human performance tools, safety, PPE met (1), AND For initial trg all steps completed correctly OR For continuing trg, critical steps (if used) completed correctly Mark the JPM as a PASS FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples) NOTE: The CLASSIFICATION must be made within 15 minutes of the initial prompt and the Student states they understand the initial conditions. NOTE: The Student is expected to obtain a copy of Checklist 1 if the Initiating Cue is given in the Simulator or Control Room. 1st START TIME:_________ 1. Operator identifies the procedure needed to perform the task. The operator has OBTAINED Check List 1, which is contained in NMP-EP-110. 2. Determine the appropriate Initiating Condition Matrix for classification of the event based on the current operating mode: HOT IC/EAL Matrix Eval Chart COLD IC/EAL Matrix Eval Chart Both HOT & COLD IC/EAL Matrix (Checklist 1, Step 1) On Checklist 1, Step 1, The operator has selected HOT IC/EAL Matrix Evaluation Chart (** Indicates critical step) 2015-301 ADMIN 6 Page 8 of 15 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) 3. Evaluate the status of the fission product barrier using Figure 1, Fission Product Barrier Evaluation. Select the condition of each fission product barrier: Fuel Cladding Integrity ******************* *******************

(Checklist 1, Step 2) On Checklist 1, Step 2.a, The operator has selected INTACT for Fuel Cladding Integrity. 4. Evaluate the status of the fission product barrier using Figure 1, Fission Product Barrier Evaluation. Select the condition of each fission product barrier: ******************* Reactor Coolant System *******************

(Checklist 1, Step 2) On Checklist 1, Step 2.a, The operator has selected INTACT for Reactor Cooling System. 5. Evaluate the status of the fission product barrier using Figure 1, Fission Product Barrier Evaluation. Select the condition of each fission product barrier: ******************* ******************* Containment Integrity (Checklist 1, Step 2) On Checklist 1, Step 2.a, The operator has selected INTACT for Containment Integrity. 6. Determine the highest applicable fission product barrier Initiating Condition (IC). (Checklist 1, Step 2.b.) On Checklist 1, Step 2.b, The operator has selected NONE (** Indicates critical step) 2015-301 ADMIN 6 Page 9 of 15 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) 7. Evaluate AND determine the highest applicable IC/EAL using the Matrix Evaluation Chart(s) identified in step 1 THEN Go To step 4. (Checklist 1, Step 3) On Checklist 1, Step 3. The operator has identified HA4 8. Check the highest emergency classification level identified from either step 2b or 3: Classification *********** (Checklist 1, Step 4) On Checklist 1, Step 4. The operator has selected ALERT as the Classification. **9. Check the highest emergency classification level identified from either step 2b or 3: ********** Based on IC # (Checklist 1, Step 4) On Checklist 1, Step 4. The operator has selected HA4 for the Based on IC#. NOTE: It is expected that the IC# be filled in on Checklist 1 (in the above step). Credit for this step will be given if the proper IC# is announced during the Crew Update announcing the classification to the crew. 10. Remarks (Identify the specific EAL, as needed). (Checklist 1, Step 4) On Checklist 1, Step 4. The operator has written A validated notification from NRC of an airliner attack threat less than 30 minutes away in the space provided. NOTE: If follow-up questioning reveals that a classification was declared and based on another IC #, the classification should be evaluated for validity. (** Indicates critical step) 2015-301 ADMIN 6 Page 10 of 15 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) 11. Declare the event by approving the Emergency Classification. (Checklist 1, Step 5) On Checklist 1, Step 5. The operator has signed their name as the Emergency Director in the space provided. **12. Fill in the Date in the space provided. (Checklist 1, Step 5) On Checklist 1, Step 5. The operator has entered the current Date in the space provided. **13. Fill in the Time in the space provided. (Checklist 1, Step 5) On Checklist 1, Step 5. The operator has entered the current Time in the space provided. Time Critical Stop Time: . NOTE: For this step to be completed considered SAT, the time entered must be within 15 minutes of the time recorded on the Initial Conditions sheet provided to the operator. 1st END TIME:__________

(** Indicates critical step)

UNIT 1 & 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. You are the On Shift Shift Manager. 2. You have just completed NMP-EP-110, Checklist 1 Steps 1 through 5.

INITIATING CUES: Complete NMP-EP-110 Checklist 1 Step 6. Raise your hand when you have completed Checklist 1, Step 6. This JPM is TIME CRITICAL. Current time is: ___________________

2015-301 ADMIN 6 Page 12 of 15 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) 2nd START TIME:_________ PROMPT: WHEN the operator enquires about meteorological conditions, GIVE the operator the MIDAS Information Sheet if not given earlier when performing a Group JPM. 14. Obtain Meteorological Data (not required prior to event declaration).

(Checklist 1, Step 6) The operator has obtained Meteorological Data (i.e. MIDAS Information Sheet). **15. Record the following: Wind Direction (from) ************ *********** ********* (Checklist 1, Step 6) On Checklist 1, Step 6. The operator has entered 130 in the space provided for Wind Direction (from). **16. Record the following: ******************* Wind Speed *********** *********** (Checklist 1, Step 6) On Checklist 1, Step 6. The operator has entered 5 in the space provided for Wind Speed. 17. Record the following: ***************** ********** Stability Class ********** (Checklist 1, Step 6) On Checklist 1, Step 6. The operator has entered D in the space provided for Stability Class. ** Indicates critical step) 2015-301 ADMIN 6 Page 13 of 15 STEP # PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS) 18. Record the following: **************** *********** *********** Precipitation (Checklist 1, Step 6) On Checklist 1, Step 6. The operator has entered 0 in the space provided for Precipitation. NOTE: The Operator may perform a "Crew Update" and announce what the Classification is and the IC# the classification is based on. PROMPT: If the operator addresses performance of Checklist 1 Step 7 Initiate Checklist 2, Emergency Plan Initiation, INFORM the operator that another operator will Initiate Checklist 2. 2nd END TIME:__________ NOTE: The terminating cue shall be given to the operator when: With NO reasonable progress, the operator exceeds double the allotted time. Operator states the task is complete. TERMINATING CUE: We will stop here. ** Indicates critical step) 2015-301 ADMIN 6 Page 14 of 15 INSTRUCTOR ANSWER KEY Checklist 1 - Classification Determination Initial Actions Completed by 1. Determine the appropriate Initiating Condition Matrix for classification of the event based on the current operating mode: HOT IC/EAL Matrix Evaluation Chart (Go To Step 2) to evaluate the Barriers) COLD IC/EAL Matrix Evaluation Chart (Go To Step 3) Both HOT & COLD IC/EAL Matrix Evaluation Chart apply (Go To Step 2) Student 2. Evaluate the status of the fission product barrier using Figure 1, Fission Product Barrier Evaluation. a. Select the condition of each fission product barrier: LOSS POTENTIAL LOSS INTACT Fuel Cladding Integrity Reactor Coolant System Containment Integrity Student b. Determine the highest applicable fission product barrier Initiating Condition (IC): Student (select one) FG1 FS1 FA1 FU1 None 3. Evaluate AND determine the highest applicable IC/EAL using the Matrix Evaluation Chart(s) identified in step 1 THEN Go To step 4. Hot IC# HA4 Unit 1&2 and/or Cold IC# __________ Unit___ or None Student 4. Check the highest emergency classification level identified from either step 2b or 3: Classification Based on IC# Classification Based on IC# General Alert HA4 Site-Area NOUE None N/A Remarks (Identify the specific EAL, as needed): A validated notification from NRC of an airliner attack threat less than 30 minutes away. Student 5. Declare the event by approving the Emergency Classification. Student Date: ***** / ***** / **** Time: ****** Emergency Director Student 6. Obtain Meteorological Data (not required prior to event declaration): Wind Direction (from) 130 Wind Speed 5 Stability Class D Precipitation 0 Student 7. Initiate Attachment 2, Checklist 2 - Emergency Plan Initiation. ____________ NOTE Key Parameters should be allowed to stabilize to accurately represent plant conditions prior to classifying an event ** Indicates critical step)

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