ML110200558

Susquehanna - Draft - Operating Exam (Sections a, B and C) (Folder 2)

ML110200558
Person / Time
Site:	Susquehanna
Issue date:	10/26/2010
From:	Susquehanna
To:	Caruso J G Operations Branch I
Hansell S
Shared Package
ML102180025	List: IR 05000387/2011301 ML102530213 ML102650461 ML110070539 ML110130101 ML110200472 ML110200500 ML110200547 ML110200558 ML110400227 ML110400252 ML110400267 ML110400275 ML110811006
References
TAC U01793
Download: ML110200558 (276)

Text

SRO 00.AD.1021.101 Appl. JPM Number To PPL SUSQUEHANNA, JOB PERFORMANCE APPROVAL AND ADMINISTRATIVE DATA o 8/2/10 215002 Rev. Date NUREG 1123 No. Sys. No. 2.1.37 4.6 KIA No. KIA Imp. Task Authorize Bypassing the Rod Block Monitor In Accordance With NDAP-QA-0338, "Reactivity Management and Controls Program" Completed Validated:

T.North 11/11/10 P. Moran 11/29/10 Writer Date Instructor/Writer Date Approval:

Date 20 Date of Performance:

Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name: First M.1. Employee # 1 S.S. # Performance Evaluation:

Satisfactory ) Unsatisfactory Evaluator Name: Signature Typed or Printed Comments:

FORM NTP-QA-31.8-1, Rev. 0 REQUIRED TASK JOB PERFORMANCE SRO SAFETY CONSIDERATIONS 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. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. 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. 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. 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. REFERENCES NDAP-QA-0338, "Reactivity Management and Controls Program", Rev. 14 AR-103-001 (C04), "RBM UPSCALE OR INOP ROD BLOCK", Rev 15 TS 3.3.2.1, "Control Rod Block Instrumentation", Amendment 242 TRM 3.2.1, "Core Operating Limits Report", Rev 11 OPERATIONAL ACTIVITIES None TASK CONDITIONS A plant startup is in progress on Unit 1 :

• Reactor Power is 30%

• Total Core flow is 50 Mlbm/Hr. When PCOM selected Rod 10-43 (A2SU Step 313 position 04-08), the RBM UPSCALE OR INOP ROD BLOCK, AR-103-001 (C04), annunciator alarmed. The PCOM verified the correct rod was selected per the pull sheet. It has been determined that Rod Block Monitor A has a Critical Self Test Fault. All external inputs to the Rod Block Monitor A have been determined to be valid. F. The PCOM has suggested bypassing Rod Block Monitor A and continuing with the .. rod withdrawals and reactor startup . Reactor Engineering determined that MCPR is 1.5. FORM NTP-QA-31.8-1, Rev. 0

) V. INITIATING Determine if it is allowable to bypass Rod Block Monitor A under these circumstances, and complete all necessary documentation to justify your decision.

VI. TASK STANDARD Completes the Reactivity Control System Bypass Authorization Form, determines entry into LCO 3.3.2.1 is required, and authorizes bypassing the Rod Block Monitor. VII. TASK SAFETY SIGNIFICANCE Limiting Conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility.

When a Limiting Condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the Technical Specifications until the condition can be met. [1 OCFRSO.36(c)(1

)(B)(ii)(B)(2)(i)] FORM NTP-QA-31.8-1, Rev. 0

) PERFORMANCE CHECKLIST Appl. To/JPM No.: SRO OO.AD.1021.001 Student Name: Step Standard Eval Comments EVALUATOR NOTE: Ensure the following material is to support performance of this A copy of NDAP-QA-0338 A blank copy of Attachment Unit 1 Technical Specifications Unit 1 TRM (COLR) AR-l03-001 (C04), "RBM OR INOP ROD EVALUATOR CUE: To begin this JPM, provide the with the Task Conditions and Cue Obtain a controlled copy of Controlled copy EVALUATOR CUE When the candidate NDAP-QA-0338, Attachment must be completed, give the blank If asked, provide AR-103-001 FORM NTP-QA-31.8-1 , Rev. Page 3 of 10

) Step Action 2. Complete NDAP-QA-0338, Attachment A. Enter initiating condition data. Determine if power is <28%. Determine if Rod Block Monitor A is providing a valid rod block per TRM 3.2 Table 7.2-1. EVALUATOR CUE: If asked, provide student with a Unit 1 TRM. FORM NTP-QA-31.8-1, Rev. 0 Standard Eval Comments Review NDAP-QA-0338, Section 6.4 and/or Attachment A. Enter the following data for Initiating Condition:

• Rod 10 10-43

• Notch 04

• Unit 1

• Circle RBM Channel A

• Power Level 30 percent

• DatefTime Place checkmark in "NO" Box, from Task Conditions Reactor Power is 30%. Refers to Table 7.2-1 and cue sheet. Determines Rod Block is being generated due to the Critical Self Test Fault, not as a result of exceeding a Table 7.2-1 setpoint.

Place a checkmark in the "NO" Box. Page 4 of 10 i

) ) Step Action Standard Eval Comments 6. Determine if inputs to the Rod Block Monitor A are valid. Refer to provided task conditions, and place a checkmark in the "NO" Box. 7. Contact I&C to repair the Rod Block Monitor A. Contact I&C to investigate and repair the Rod Block Monitor A failure. EVALUATOR CUE: I&C has been contacted.

• 8. Determine Technical Specification impact. Refer to TS LCO 3.3.2.1, Table 3.3.2.1-1 for Functions 1.a. 1.d., and associated footnotes.

Refer to cue sheet, and:

• TRM 3.2 COLR Figure 5.2-1 and determines MCPR value of 1.5 is below the MCPR Operating Limit for current core flow. AND

• Refers to TRM 3.2 COLR Figure 5.2-2 and determines MCPR value of 1.5 is below the MCPR Operating Limit for current core power level. OR Refer to cue sheet and Table 2 and determines MCPR of 1.5 is below the valve required for RBM operability. (continued)

FORM NTP-QA-31.8-1, Rev. 0 Page 5 of 10

} v Step Standard Eval Comments (continued from Step 8) Determines LCO 3.3.2.1 Condition A: Required Action A.1 requires the RBM channel to be restored to operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Determine that it is allowable to bypass Determine that Rod Rod Block Monitor A. Monitor A can be Authorize bypassing Rod Block Monitor Sign, date, and enter time on Attachment A in the" Shift Supervision Authorization To EVALUATOR NOTE: bypass the RBM channef block The correct authorization block is on the on the lower right-hand side of lower right-hand side of the page. the page, and enter current time/date. EVALUATOR \,\If student indicates need to address TS /TRM for MCPR not within limits, tell them it is not required for this JPM. L/EVALUATUtt Vl '-. This completes the FORM NTP-QA-31.8-1, Rev. Page 6 of 10

) J v Step Action Standard Eval Comments Do you have ALL your JPM materials?

Task Cue

• Critical Step #Critical Sequence FORM NTP-QA-31.8-1, Rev. 0 Page 7 of 10 TASK CONDITIONS A plant startup is in progress on Unit 1:

• Reactor power is 30%.

• Total Core flow is 50 Mlbm/hr. When PCOM selected Rod 10-43 (A2SU Step 313 position 04-08), the RBM UPSCALE OR INOP ROD BLOCK, AR-103-001 (C04) , annunciator alarmed. The PCOM verified the correct rod was selected per the pull sheet. It has been determined that Rod Block Monitor Pl.' has a Critical Self Test Fault. All external inputs to Rod Block Monitor A have been determined to be valid. The PCOM has suggested bypassing Rod Block Monitor A and continuing with the rod withdrawals and reactor startup. Reactor Engineering determined that MCPR is currently

1.5. INITIATING

CUE Determine if it is allowable to bypass Rod Block Monitor A under these circumstances, and complete all necessary documentation to justify your decision.

FORM NTP*QA*31.8*1, Rev. 0 PPL SUSQUEHANNA, JOB PERFORMANCE APPROVAL AND ADMINISTRATIVE DATA SIRO 45.0N.1829.101 o 11/1/10 Generic 2.1.25 3.9/4.2 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task Implement ON-145-004, "Reactor Water Level Anomaly", Determine Cause For Erroneous RPV Water Level Indications, And Identify Required Tech Spec Actions Completed Validated:

Tracy North 11/1/10 Writer Date Date Approval: uc ea Trng. Date 25 Date of Performance:

Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name: Last First M.1. Employee # I S.S. # Performance Evaluation: ) Satisfactory ( Unsatisfactory Evaluator Name: Signature Typed or Printed Comments:

FORM NTP-QA-31.8-1, Rev. Page 1 of 10 REQUIRED TASK JOB PERFORMANCE S/RO 45.0N.1829.1 I. SAFETY 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. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. 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. 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. 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. REFERENCES ON-145-001, "RPV Water Level Anomaly" (Rev 18) ON-117-001, "Loss Of Instrument Bus" (Rev 31) Tech Spec 3.3.3.1, PAM Instrumentation (Rev 2), and Bases (Rev 8) OPERATIONAL ACTIVITIES None TASK CONDITIONS Unit 1 is in MODE 1 at full power. The following 1 C601 RPV Water Level indicators are ENERGIZED, but indicate FULL DOWNSCALE: U-14201 B Extended Range U-14201 B Wide Range U-14203B Extended Range LI-14203B Wide Range FORM NTP-QA-31.8-1, Rev. Page 2 of 10 The following 1 C651 RPV Water Level indicators are ENERGIZED, but indicate FULL DOWNSCALE: U-14201B1 Extended Range U-14201 B1 Wide Range UR-14201 B is ENERGIZED, but ALL THREE (3) parameters are indicating FULL DOWNSCALE. RPV Water Level has been verified to be +36" on narrow range instruments.

V. INITIATING CUE Implement ON-145-001 "RPV Water Level Anomaly" to determine the cause of the erroneous RPV Water Level Indicators.

SRO CANDIDA TES ONL Y: Determine the required Tech Spec actions. Document your results on the task condition sheet in the space provide on the task condition sheet. VI. TASK STANDARD Identify that the faulty instrument readings are due to Instrument Bus 1Y125 breaker 05 tripped or de-energized.

SRO Only; Determine that Tech Spec 3.3.3.1, action A is applicable.

VI. TASK SAFETY SIGNIFICANCE Post accident monitoring instrumentation is required by technical specifications to be operable.

The operability of PAM instrumentation ensures that there is sufficient information available on selected parameters to monitor and assess plant status and behavior following an accident.

FORM NTP-QA-31.8-1, Rev. Page 3 of 10 PERFORMANCE CHECKLIST Appl. To: SIRO JPM No.: 45.0N.1829.101 Student Name: Step Action Standard Eval Comments EVALUATOR NOTE: This JPM may be performed in the Classroom, Simulator, or other similar Ensure a copy of ON-145-004, "RPV Water Anomaly" (rev 18), and Unit 1 Tech Specs & are available for candidate EVALUATOR CUE: Read the Task Conditions (for the list of erroneous WIL indicators refer the candidate to the task condition sheet provided), and the initiating cue. Provide the task condition sheet to the candidate.

1. Obtain a controlled copy of ON-145-004.

Controlled copy obtained.

EVALUATOR CUE: < Provide a copy of ON-145-004

2. Review procedure Symptoms and Observations.

Review procedure.

3. Record DatelTime Record date and time in procedure step 3.1 4. Determine steps 3.2, 3.3, 3.4 not applicable.

Mark steps 3.2, 3.3, 3.4 N/A. FORM NTP-QA-31.8-1, Rev. 0 Page 4 of 10 PERFORMANCE Appl. To: JPM No.: 45.0N.1829.101 Student Name: Step Standard Eval Comments Refer to Attachment B per step 3.5.1. Determine step 3.5 is applicable, and to Attachment B to perform step Check for instruments with common Evaluate failed water level instruments

• 6. leg condensing chambers or excess flow against Attachment B page 1 and 2 to valves determine if the instruments share common REFERENCE leg or excess check Determine that these instruments DO NOT share these components.

i Check for instruments with common VARIABLE Evaluate failed water level instruments i *7. supplies or excess flow check valves against Attachment B page 1 and 2 determine if the instruments share common VARIABLE leg or excess check Determine that these instruments DO NOT share these components.

FORM NTP-QA-31.8-1, Rev. Page 5 of 10 I PERFORMANCE Appl. To: JPM No.: 45.0N.1829.101 Student Name: Step Standard Eval Comments Check for instruments with common POWER Evaluate failed water level instruments SUPPLIES (3.5.1.c) against Attachment B page 1 and 2 determine if the instruments share common POWER EVALUATOR NOTE: Although the indicators themselves a/l share Determine that ALL the erroneous common power supply, 1Y125-01, the Water Level indicators are provided conditions state that the so candidates must determine that thi is NOT tN by transmitters L T -14201 B, L T -14202B cause. L T -14203B and ALL are powered by 1 breaker Additionally, the wide range pressure indication UR-14201B is also downscale since its comes from a transmitter powered by Recognition of this helps ensure the determines the correct Check for automatic actions and alarms. Evaluate Attachment B and determine there are NO automatic actions or associated with these

10. Evaluate level, if level cannot be determined to Determine that level can be determined to 2! +13", Enter EO-1 00-1 02. be +13" by referring to task Comply with TS 3.3.1.1, 3.3.2.2, 3.3.6.1, 3.3.6.2, Inform Unit Supervisor to refer to 3.3.5.1, 3.3.4.2, 3.3.5.2 Specifications for the failed FORM NTP-QA-31.8-1, Rev. Page 6 of 10 PERFORMANCE CHECKLIST Appl. To: SIRO JPM No.: 45.0N.1829.101 Student Name: Step Standard Eval Comments EVALUATOR CUE: Acknowledge report of Tech Spec review requirement.

FOR RO ONL Y: This completes the JPM, ensure results are entered on task condition sheet. SRO Candidates ONL Evaluate Tech Spec 3.3.3.1, "PAM *12. Obtain and evaluate Tech Instrumentation", and determine Condition A is applicable since there less than the required number of channels of Wide Range Level, Range Level, and Fuel Zone Level accordance with Table 3.3.3.1-1 2a, 2b and 2c; and the following action Restore required channels to OPERABLE status within 30 days. EVALUATOR CUE:. This completes the JPM; ensure results are on task condition FORM NTP-QA-31.8-1, Rev. Page 7 of 10 PERFORMANCE Appl. To: S/RO JPM No.: 45.0N.1829.101 Student Name: Step Action EVALUATOR:

Do you have ALL your JPM exam materials?

Task Cue Sheets? Procedures?

Standard Eval Comments FORM NTP-QA-31.8-1, Rev. 0 Page 8 of 10 TASK Unit 1 is in MODE 1 at full power. The following 1 C601 RPV Water Level indicators are ENERGIZED, but indicate FULL DOWNSCALE: U-14201 B Extended Range U-14201 B Wide Range U-14203B Extended Range U-14203B Wide Range The following 1C651 RPV Water Level indicators are ENERGIZED, but indicate FULL DOWNSCALE: U-14201B1 Extended Range U-14201B1 Wide Range UR-14201B is ENERGIZED, but ALL THREE (3) parameters are indicating FULL DOWNSCALE. RPV Water Level has been verified to be +36" on narrow range instruments.

INITIATING CUE Implement ON-145-001 "RPV Water Level Anomaly" to determine the cause of the erroneous RPV Water Level Indicators.

SRO CANDIDATES ONL Y: Determine the required Tech Spec actions (if any). Document your results on the task condition sheet in the space provided below. Cause for Erroneous Instrument Readings:

SRO ONLY; Tech Spec Required Actions (If Any): FORM NTP-QA-31.8-1, Rev. 0

---

PPL SUSQUEHANNA, JOB PERFORMANCE APPROVAL AND ADMINISTRATIVE DATA SIRO 78.AD.2319.102 o 11/2/10 Generic 2.2.14 4.3/3.9 Appl. JPM Number Rev. No. Date NUREG 1123 KIA No. KIA Imp. To Sys. No. Task Perform LPRM Upscale Alarm Operability Tracking In Accordance With 01-078-001 and Determine Reguired Actions. Completed Validated Tracy North 11/2/10 M. Jacopetti 11/27/10 Writer Date InstructorlW riter Date Approval:

Date 30 (RO) 35 (SRO) Date of Performance:

Validation Time (Min.) Time Taken (Min.) .JPM Performed By: Student Name: Last First M.1. Employee # I S.S. # Performance ( Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name: Signature Typed or Printed Comments:

FORM NTP-QA-31.8-1, Rev. 0 REQUIRED TASK JOB PERFORMANCE SIRO I. SAFETY 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. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. 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. 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. 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. REFERENCES 01-078-001 LPRM STATUS CONTROL, (Rev. 11) TRM 3.3.9. rev 3 LCO 3.3.1.1 rev 3 III. OPERATIONAL ACTIVITIES This JPM satisfies the requirements of Operational IV. TASK CONDITIONS Unit 1 is in MODE 1 at 80% power. ALL OPRM channels are OPERABLE APRM Gain Calibration was last performed 30 days ago. LPRM detector 40-57A caused a downscale alarm, 1& C determined the detector failed, and 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 40-57 A in accordance with 01-078-001.

FORM NTP-QA-31.8-1, Rev. Page 2 of 35 VI. TASK STANDARD For both 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 MET for APRM trip functions.

VII. TASK SAFETY SIGNIFICANCE Operability of the APRM system and associated LPRM detectors provides the primary indication of neutron flux within the core and the resulting Reactor Protection System inputs. FORM NTP-QA-31.8-1, Rev. 0

---

PERFORMANCE Appl. To/JPM No.: SIRO Student Name: __________

_ Step Action Standard Eval EVALUATOR Ensure the following material is available support performance of this A working copy of rev 11 of 01-078-001.

CAUTION: Ensure the answer which precedes the two Cue pages in the JPM package, is given to the Previously filled out Attachments A (with zone 8 having exactly operable LPRM upscale Blank copy of attachments A -O. A copy of SO-100-008 EVALUATOR CUE: To begin this JPM, provide the candidate with: Task Conditions and Initiating Cue Sheet Working copy of 01-078-001, and attachments A -Previously filled out attachments A -0 Obtain a controlled copy of procedure.

Controlled copy of 01-078-001 (Provided with initiating --.... -.... -._-.... -.... _.._-....-.... -..._-.... -_ ..._-.... _ .. _---*Critical Step #Critical Page 3 of 7 FORM NTP-QA-31.8-1, Rev. 0 PERFORMANCE Appl. To/JPM No.: SIRO Student Name: __________ Action Refer to correct section. Determine current LPRM status. Complete new Attachment A. Enter a check (--1) in column (2) for LPRM alarms determined inoperable or bypassed for all other reasons. Determine if ;?:50% of LPRM Upscale alarms in each zone are operable. Notify Reactor Engineering of all LPRM upscale alarms determined inoperable.

Eval Comments Refer to section 4. Refer to the previously completed copy of Attachments A & B. Enter 1 for Unit. Transfer the previous LPRM data to the new Attachment A Place a checkmark in column 2 adjacent to LPRM detector 40-57 A in Zone 8. Consider all LPRM Upscale Alarms with a check in column (1) or (2) of Attachment A as inoperable, and evaluate the number of inoperable LPRMs for each zone. Circle YES for zone 1,2,3,4,5,6,7, and 9. Conclude that there are LESS THAN 50% operable LPRMs in zone 8, AND circle NO for zone 8. N/A Previously stated in JPM task conditions.

• Critical Step #Critical Sequence Page 4 of 7 FORM NTP-QA-31.8-1, Rev. 0 PERFORMANCt:

CHECKLIST Appl. To/JPM No.: S/RO 7B.AD.2319.102 Action Evaluate the need to place placard to 1C651 indicating

< required # of LPRM Upscale Alarms. {reguires com(2letion of Attachments C & 0 1 which a(2(2ears in Ste(2 111 below.} Complete an LPRM vs. APRM/LPRM Group Status Control Log (Attachment B) each time LPRM operability status is changed. Circle all inoperable LPRM's on LPRM vs. APRM/LPRM Group Status Control Log (Attachment B). Refer to weekly surveillance SO-100-00B to confirm APRM operability requirements maintained.

Student Name: __________

_

Eval Comments Determine that placard is NOT required since ALL OPRM channels are OPERABLE.

Transfer the previous LPRM data to the new Attachment B. Circle LPRM detector 40-57 A for APRM 1, under the column 'A' Level, and enter today's date. Compare the following criteria to current APRMlLPRM operability status: 2: 20 total operable LPRMs per 2: 3 LPRM inputs per level (A, B, C, or D) s 9 LPRMs inop since last APRM calibration (after date provided in 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 OB-49A) *Critical Step #Critical Sequence Page 5 of 7 FORM NTP-QA-31.B-1, Rev. 0 I 11 Appl. To/JPM No.: S/RO 78.AD.2319.102 Step Action Identifies Inoperable OPRM cells. EVALUATOR CUE FOR ROs: This completes the JPM 12. SRO ONLY PORTION EVALUATOR NOTE: Inform the SRO that they need to determine actions required (if any). Evaluate Tech Spec 3.3.1.1 for RPS Instrumentation and TR 3.1.3 for Control Rod Block Instrumentation EVALUATOR NOTE: LCO 3.3.1.1 and TRM 3.1.3 Condition A is met and action A.1 is NOT required since only one APRM channel is inoperable.

• Critical Step #Critical Sequence FORM NTP-QA-31.8-1, Rev. 0 PERFORMANCE CHECKLIST Student Name: __________

_ Standard Eval Comments Transfers the previous LPRM data to the Attachment C and circles "A LEVEL" for 40-57. Determines it inputs to APRM1 Cell Transfers the previous LPRM data to the Attachment D and circles LPRM 40-57 A in Cell 03 row, in the LPRM#2 Determines OPRM cell remains operable due to at least three operable LPRMs. Refer to Tech Spec 3.3.1.1 and determine that minimum of 3 operable APRM channels required in MODE 1 per table 3.3.1.1-1, NO TS actions are 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 NO TRM actions are required.

Page 6 of 7 PERFORMANCE CHECKLIST Appl. To/JPM No.: SIRO 78.AD.2319.102 Student Step Action Standard Eval Comments EVALUATOR CUE FOR SROs: This completes the JPM. *Critical Step #Critical Sequence Page 7 of 7 FORM NTP-QA-31.8-1, Rev. 0 EVALUATOR:

Do you have ALL your JPM exam materials?

Task Cue Sheets? Procedures?

JPM (next 11 pages) Do Not Provide (They are given the 11 pages that follow the 2 nd cue sheet.)

JPM 78.AD.2319.102 KEY Attachment A 01-078-001 LPRM UPSCALE ALARM STATUS CONTROL LOG Revision 11 Page 6 of 16 UNIT __As least 50% LPRMs Operable per Zone (Circle YES or NO) (1} (2) (1) (2) (11 (2) (1) (2) (1) (2) Zone 1 16-49A 16-41A 24-49A 24-41 A -L 16-49B 16-418 24-498 24-418 @NO-L 16-41C 24-49C 24-41CZone 40-49A -L 40-41 A -L 48-49A 48-41 A 40-49B 40-418 48-498 48-418 @NO 40-49C 40-41C 48-49C -"-48-41C Zone 16-17A 16-25A 24-17A 24-25A 16-17B 16-258 24-176 24-258 @NO 16-17C 16-25C 24-17C 24-25C-L Zone 4O-17A 40-25A 48-17A 48-25A 40-17B 40-258 "48-178 48*256 @NO 40-17C 4O-25C 48-17C 48-25C " Zone 24-33A 32-25A 32-33A 32-41 A 40-33A 24-33B -"-32-256 32*336 32-418 40-33B @NO 24-33C -"-32-25C 32-33C 32-41C -"-4O-33CZone 16-09A 24-09A 32*09A 4O-09A 32-17A 16-09B 24-098 32-098 -L 40-09B 32-178 @No l6-09C 24-09C 32-09C 40-09C 32-17CZone 08-17A 08-25A 08-33A 08-41 A 16-33A-L 08-178 08-256 08-336 08-416 16-336 @NO 08-17C 08-25C 08-33C -L 08-41C 16*33C " Zone 24-57A 32-57A 4O-57A 32-49A ..L 24-578 32-578 40-57B -"-YE@-L 32-57C -"-4O-57C 32-49C-L Zone 48-33A 56-25A 56-33A 56-41 A 48-338 56-258 56-338 -"-56-41B -"-@NO 48-33C 56-25C 56-33C 56-41C LPAM Upscale Alarm Status Assessment Complete Only an SRO signs here / ##/##/## / #### Shift Supervision Date Time FORM 01-078-001-1, Rev. 4, Page 1 of 1 JPM 78.AO.2319.102 KEY Attachment B 01-078-001 LPRM VS. APRM Status Control Log Revision 11 (Inoperable LPRM's are circled) Page 7 of 16 UNITl1)or

2. (Circle Unit) I A APRM CHANNEL LEVEL Date inop. APRM1 04/05/10 96/19/19 40-17A 07/98/19 (Q8-17N 99/19/10 08-49A (08-25A) 95/29/19 (40-57 TO/DAlY (24-41 /19 <24-09 /19 (56-41/y 07/11/19 09/99/19 32-57A 16-41A 48-41A 32-25A 16-09A 05/19/19 08-41 A I '/I.56-25A 40-41 A 08-33A 24-49A 24-17A 40-33A 94/01/10 32-33A 16-17A 48-17A 48-49A 16-49A LPRM LOCATIONS 8 Date C LEVEL inop. LEVEL G2-096> 06/15/10 W8-33C)16-258 40-33C 16-578 24-17C 48-258 (g4-499 G2-416) .7/87/19 32-338 16-178 (j6-49ij) 99/16/19 48-178 19/31/10 (40-09C)-56-338 32-09C 40-178 32-41C 08-498 <i6-25C)40-498 16-57C 98/08/19 08-178 32-178 <32-496> 05/97/10 16-338 48-338 1(32-576) 96/05/10 (56-33C> 48-418 16-418 40-49C 48-098 08-17C 32-258 08-49C 40-17C 56-258 (32-49C)40-418 32-17C 24-578 48-33C 24-258 16-33C 08-418 40-098 Date D inop LEVEL 11/02/19 32-57D (16-41 D)48-09D 93/19/19 48-410 95/96/10 32-17D 12/01/19 48-33D 16-33D 10/25/10 08-330 24-170 05/91/19 56-170 (40-330) 04/11/19 24-490 32-330 48-490 48-17D 16-17D (J6-49q) 08/29/19 32-090 08/08/19 48-250 <i6-25W 16-570 32-410 (08-25W 05/97/19 24-410 24-09D 56-41 D 40-570 40-25D Date inop. 97/99/10 09/10/10 08/12/19 FORM 01-078-001-2, Rev. 2, Page 1 of 2 I 09/95/19 JPM 78.AD.2319.1 02 KEY LPRM vs. APRM Status Control Log (Inoperable LPRM's are circled) UNIT(1"kr 2 (Circle Unit) I LPRM LOCATIONS APRM4 32-09A 08-338 32-57C 16-25A 24-498 32-25C 48-25A 24-178 16-41C 32-41A (56-176> 04/01/10 48-41C 16-57A 40-338 16-09C 32-17A 56-418 48-09C 05/07/10 40-258 32-33C 16-33A 24-418 16-49C 48-33A 08-258 48-49C (40-578) 05/30/10 16-17C 24-098 48-17C LPRM Operability Assessment Complete Only SROs sign here Shift Supervision Attachment B 01-078-001 Revision 11 Page 8 of 16 56-33D 40-49D 08-17W 24-33D 08-49D 40-17D 08-41 D (40-09W 24-25D 56-25D (z4-57J>> 40-41 D ##1##1## Date 08/11/10 04/12/10 05/06/10 #### Time FORM 01-078-001-2, Rev. 2, Page 2 of 2 08-17 LEVEL APRM1-Cell 08-25 C 08-33 A 08-41 A 08-49 A 16-09 A 16-17 A 16-25 A 16-33 A 16-41 A 16-49 A 16-57 A 24*09 A 24-17 A JPM 78.AD.2319.102 Attachment Revision Page 9 of LPRM VB. OPRM OPRM Cells (APRMlOPRM

-B LEVEL C LEVEL D 2-21 3-21 4-21 B LEVEL C LEVEL o 4-15 2-15 4-21 2-21 B LEVEL C C LEVE[""':)

D 4-09 '-09 4-15 1-15 B LEVEL C LEVEL D 3-04 1-04 3-09 1-09 B LEVEL C LEVEL D 2-04 3-04 BLEVEL C LEVEL D 3-27 4-27 B LEVEL C LEVEL D 1-21 4-21 1-22 4-22 1-27 4-27 B LEVEL C:CLEVED D 1-15 2-15 1-16 2-16 1-21 2-21 1-22 2-22 B LEVEL C LEVEL D 2-09 3-09 2-10 3-10 2*15 3-15 2-16 3*16 B LEVEL c: .c LEVEL ::::> D 3-04 4-04 3-05 4-05 3-09 4-09 3-10 4-10 CJ3LEVEL C LEVEL D 1-01 4-01 1*04 4*04 1-05 4-05 B LEVEL C LEVEL D LEVEL 1-01 2-01 B LEVEL <: C D 4-27 2-27 3-27 4-28 2-28 B LEVEL C LEVEL D 4-22 1-22 4-23 1-23 4-27 1-27 4-28 1*28 Page 1 of LPRM 24-25 A LEVEL APRM2-CeIl16 2-17 2-22 2-23 24-33 CALEVEL") 1-10 1*11

• 1-16 1-17 24-41 lALEVELJ .:00 1-06 1-10 1-11 24-49 A LEVEL 3-01 3-02 3-05 3-06 24-57 A LEVEL 2-01 2-02 32-09 A LEVEL 4-28 4-29 32-17 A LEVEL 4-23 4-24 4-28 4-29 32-25 A LEVEL 2-17 2-18 2-23 2-24 32-33 A LEVEL 3-11 3-12 3-17 3-18 32-41 A LEVEL 4-06 4-07 4-11 4-12 32-49 CALEVEl) --.<f-UZ 4-03 4-06 4-07 Page 2 of 4 JPM 78.AD.2319.102 KEY LPRM vs. OPRM Status OPRM Cells (APRM/OPRM

-Cell) B LEVEL C LEVEL 3-16 1-16 3-17 1-17 3-22 1-22 3-23 1-23 CBLEVEl) ('C LEVEL) " .. I' 2-11 3-11 2-16 3-16 2-17 3-17 B LEVEL C LEVEL 4-05 2-05 4-06 2-06 4-10 2-10 4-11 2-11 B LEVEL cCLEVEL) 4-01 4-02 1-02 4-05 1-05 4-06 1-06 B LEVEL ("'C LEVEL) 3-01 r-v 3-02 1-02 cBLEVEC) C LEVEL -'::0 2-28 1-29 2-29 B LEVEL C LEVEL 2-23 3-23 2-24 3-24 2-28 3-28 2-29 3-29 B LEVEL C LEVEL 3-17 4-17 3-18 4-18 3-23 4-23 3-24 4-24 B LEVEL C LEVEL 1-11 4-11 1-12 4-12 1-17 4-17 1-18 4-18 CBLEVEL) C I-U6 1-07 1-11 1-12 (' B LEVEl:) CCLEVEl) -z;v.::: 2-03 3-03 2-06 3-06 2-07 3-07 Attachment C 01-078-001 Revision 11 Page 10 of 16 D LEVEL 4-16 4-17 4-22 4-23 D LEVEL 4-10 4-11 4-16 4-17 D LEVEL 3-05 3-06 3-10 3-11 D LEVEL 2-01 2-02 2-05 2-06 D LEVEL 4-01 4-02 D LEVEL 3-28 3-29 D LEVEL 1-23 1-24 1-28 1-29 D LEVEL 1-17 1-18 1-23 1-24 D LEVEL 2-11 2-12 2-17 2-18 D LEVEL 3-06 3-07 3-11 3-12 D LEVEL 1-02 1-03 1-06 1-07 LPRM 32-57 A LEVEL APRM2-Cell 02 2-03 40-09 A LEVEL 2-29 2-30 40-17 A LEVEL 1-24 1-25 1-29 1-30 40-25 C ALEVED 1-18 1-19 1-24 1-25 40-33 A LEVEL 3-12 3-13 3-18 3-19 40-41 CA LEVEL :::> 2-07 2-08 2-12 2-13 40-49 C A LEVEL"::>

1-03 1-07 1-08 40-57 CA LEVEL-=>

48-09 A LEVEL 2-30 48-17 A LEVEL 3-25 3-26 3-30 48-25 A LEVEL 4-19 4-20 4-25 4-26 48-33 A LEVEL 4-13 4-14 4-19 4-20 JPM 78.AD.2319.102 KEY lPRM vs. OPRM Status OPRM Cells (APRMlOPRM

-Cell) C.B LEVEL:> C LEVEL 3-02 4-02 3-03 4-03 B LEVEL ( C LEVEL:::>

3-29 1=29 3-30 1-30 B LEVEL C LEVEL 2-24 3-24 2-25 3-25 2-29 3-29 2-30 3-30 BLEVEL C LEVEL 4-18 2-18 4-19 2-19 4-24 2-24 4-25 2-25 BLEVEL C LEVEL 4-12 1-12 4-13 ",3 4-18 1-18 4-19 1-19 B LEVEL 3-07 1-07 3-08 1-08 3-12 1-12 3-13 1-13 B LEVEL C CLEVEi) 2-03 3-03 2-07 3-07 2-08 3-08 CBLEVED C LEVEL 4-03 2-03 B LEVEL C LEVEL 3-30 4-30 B LEVEL C LEVEL 1-25 4-25 1-26 4-26 1-30 4-30 BLEVEL C CLEVED 1-19 1-20 2-20 1-25 2-25 1-26 2-26 B LEVEL C LEVEL 2-13 3-13 2-14 3-14 2-19 3-19 2-20 3-20 Attachment C 01-078-001 Revision 11 Page 11 of 16 D LEVEL 1-02 1-03 D LEVEL 4-29 4-30 D LEVEL 4-24 4-25 4-29 4-30 n LEVEL 3-18 3-19 3-24 3-25 D LEVEL 2-12 2-13 2-18 2-19 D LEVEL 4-07 4-08 4-12 4-13 D LEVEL 4-03 4-07 4-08 D LEVEL 3-03 D LEVEL 1-30 D LEVEL 2-25 2-26 2-30 D LEVEL 3-19 3-20 3-25 3-26 D LEVEL 1-13 1-14 ",9 1-20 ! Page 3 of 4 I LPRM 48-41 A LEVEL APRM2-Cell 08 2-13 2-14 48-49 A LEVEL 3-08 56-17 A LEVEL 3-26 56-25 A LEVEL 2-20 2-26 56-33 cALEVEL) -I q. 1-20 56-41 C JPM 78.AD.2319.1 02 KEY Attachment C 01-078-001 Revision 11 Page 12 of 16 LPRM vs. OPRM Status OPRM Cells (APRM/OPRM

-Cell) C B

s-ut$ c BLEVEL ..-=mY B LEVEL 4-26 B LEVEL 3-20 3-26 B LEVEL 2-14 2-20 B LEVEL 4-14 C LEVEL D LEVEL 4-08 1-08 4-13 1-13 4-14 1-14 C LEVEL D LEVEL 4-08 2-08 C LEVEL D LEVEL 1-26 2-26 C LEVEL D LEVEL 1-20 4-20 1-26 4-26 cCLEVEL) D LEVEL 4-14 3-20 4-20 C LEVEL D LEVEL 2-14 3-14 Page 4 of 4 JPM 78.AD.2319

f 02 KEY OPRM Status Control Log OPRM Cell Assignments for APRM 1 LPRM(s)

4()"'57 A (to be bypassed)

Impacted Cell(s): 3 (from Attachment C) Operable Cells: 24 (from OOA ST A81L1TY display) Attachment C 01-078-001 Revision 11 Page 13 of 16 Circle LPRMs inoperable in cell with LPRM(s) to be bypassed (already and one to be bypassed).

CELL 10: LPRM #1 01 16-578 02 (24-570 03 32-570 04 OS-49A 05 (16-498:)

06 (24-49<:;)

07 32-490 OS 09 OS-41C 10 16-410 11 C24-41A:)

12 ("32-418) 13 C40-41C) 14 48-410 15 c...oa-33cJ 16 16-330 17 (.24-3W I 18 32-338 19 40-33C 20 21 <..oB-2SAJ 22 16-258 23 24-25C 24 32-250 25 (40-25A) 26 4S-258 27 16-178 28 24-17C 29 32-170 30 40-17A LPRM #2 32-570 (4(),.57A)

(16-49fD (24-49C:)32-490 (40-49A:) ( 48-49ID 16-410 ("24-41/!:)

32-41B:> C40-41C) = 48-410 16-330 (z4-33P 32-338 40-33C 48-330 (5.6-33A)16-258 24-25C 32-250 LPRM#3 C24-49(;)32-490 40-49A 16-410 C24-41/f)

C32-41 a) (40-41G)48-410 16-330 (24-3311:)32-338 40-33C 4S-330 C"A-33A)16-258 24-25C 32-250 C4.0-25A)48-258 56-25C 16-178 24-17C 32-170 40-17A 48-178 56-17C 24-09A I '-...32-0gs)

C40-09C> 48-090 LPRM #4 (16-49ED (24-490 32-490 08-41C 16-410 (32-41fD (40-41C:) (OS-33C)16-330 C24-33,lt;)32-338 40-33C 48-330 Co8-25A)16-258 24-25C 32-250 48-258 (J)8-17A)16-178 24-17C 32-170 40-17A 48-178 16-090 24-09A C32::0913)

\....4.0-0gc)

If bypassing LPRM will results in < 2 LPRMs operable in impacted cell, the cell will inoperable once the LPRM is Inoperable Cells due to bypassing LPRM(s): Operable Cells: 24 (following bypass of If <22 cells remain operable, the OPRM will become inoperable following bypass of Page 1 of 4 JPM 78 * .4.0.2319"102 KEY Attachment C 01-078-001 Revision 11 Page 14 of 16 OPRM Cell Assignments for APRM 2 LPRM(s): 40-57 A to be Impacted Cell(s): None (from Attachment Operable Cells: 30 (from aOA STABILITY Circle LPRMs inoperable in cell with LPRM(s) to be bypassed (already and one to be CELL 10: LPRM #1 LPRM #2 LPRM #3 LPRM#4 1 16-57C 24-57A 24-490 16-490 2 24-57A 32-57A (32-49!D 24-490 3 32-57A 40-57C 40-49B Q.2-49B:;J 4 08-49B 16-490 16-41.4. 08-41 A 5 16-490 24-490 24-41C 16-41A 6 24-490 (32-49B:)32-41C 24-41C 7 C32-49B)40-49B (.40-41 A)32-41C 8 40-49B 48-490 48-41 A (40-41 A) 9 08-41 A 16-41A 16-33B 08-330 10 16-41A 24-41C (24-33B)16-33B 11 24-41C 32:A1C 32-330 (24-33B")

12 32-41C '-4o-4W 40-330 32-330 13 C40-41..e) 48-41 A 48-33B 40-330 14 48-41 A 56-41C 56-33B 48-33B 15 08-330 16-33B 08-25C 16 16-33B (24-33B)24-25A (16-259 17 (24-33W 32-330 32-25A 24-25A 18 32-330 40-330 40-25C 32-25A 19 40-330 48-33B Q8-259 40-25C 20 48-33B 56-33B 56-25A C.48-25..c,)

21 08-25C (16-25C)16-170 08-17B 22 24-25A 24-170 16-170 23 24-25A 32-25A 32-17B 24-170 24 32-25A 40-25C 40-17B 32-17B 25 40-25C (48-25C)48-170 40-17B 26 C.48-250 56-25A 56-170 48-170 27 16-170 24-170 (2.4-09C) 16:.Q.9A 28 24-170 32-17B 32-09C <-24-090 29 32-17B 40-17B 40-09A 32-09C 30 40-17B 48-170 48-09A 40-09A If bypassing LPRM will results in < 2 LPRMs operable in impacted cell, the cell will become inoperable once the LPRM is bypassed.

Inoperable Cells due to bypassing LPRM(s): None Operable Cells: 30 (following bypass of LPRM(s>> If <22 cells remain operable, the aPRM will become inoperable following bypass of LPRM(s). Page 2 of 4 JPM 78.AD.2319.102 KEY OPRM Cell Assignments for APRM 3 LPRM(s): 40-57 A to be bypassed)

Impacted Cell(s): None (from Attachment C) Operable Cells: 29 (from ODA STABILITY display) Attachment C 01-078-001 Revision 11 Page 15 of 16 Circle LPRMs inoperable in cell with LPRM(s) to be bypassed (already and one to be bypassed).

CELL ID: LPRM #1 1 16-57D 2 2..!:.QlB 3 (32-57B) 4 08-49C 5 16-49A 6 24-49A 7 8 (,40-49G) 9 08-418 10 16-418 11 24-41D 12 32-41 D 13 40-41B 14 (1i8-418")

15 0B=3'3'A 16 16:.a3C 17 (24-33C) 18 32=33A 19 40-33A 20 48-33C 21 08-25D 22 16-25D 23 24-25B 24 32-25B 25 otv-25D 26 48-25D 27 16-17A 28 24-17A 29 32-17C 30 40-17C LPRM#2 24-57B (32-57B) 4cr-57D 16-49A (32-49C) (40-49C) 48"::4§"A 16-418 24-41D 32-41D 40-418 (48-418) 56-41D 16-33C (24-33C)40-33A 48-33C (b6-33C) lO"Z!)U 24-258 32-25B 40-25D 48-25D 56-25B 24-17A 32*17C 40-17C 48-17A LPRM#3 LPRM#4 I 16-49A (32-49C)24-49A (40-49C) (32-49Cj 16-4"1 B OF1B 24-41D 16-418 32-41D 24*41D 40-41B 32-41D (48-418)40-418 08-33A (24-33C)16-33C 32-33A (24-33Cj 40-33A 48-33C 40-33A 48-33C 08-25D 24-258 16-25D 32-25B 24-25B 40-25D 32-258 48-25D 40-25D 56-258 48-25D 16-17A 08-17C 24-17A 16-17A 32-17C 24-17A 40-17C 32-17C 48-17A 40-17C 56-17A 48-17A 24-09D 16-09B 32-09D 24-09D 40-098 32-09D 48-09B 40-09B If bypassing LPRM will results in < 2 LPRMs operable in impacted cell, the cell will become inoperable once the LPRM is bypassed.

Inoperable Cells due to bypassing LPRM(s): None . Operable Cells: 29 (following bypass of LPRM(s>> If <22 cells remain operable, the OPRM will become inoperable following bypass of LPRM(s). Page 3 of 4 LPRM(s}: 40-57 A Impacted Cell(s): Operable Cells: JPM 78.AD.2319.1 02 KEY OPRM Cell Assignments for APRM 4 (to be bypassed)

None (from Attachment C) 30 (from ODA ST A81L1TY display) Attachment C 01-078-001 Revision 11 Page 16 of 16 Circle LPRMs inoperable in cell with LPRM(s) to be bypassed (already and one to be bypassed).

CELL ID: LPRM #1 1 16-57A 2 24-57D 3 32-57C 4 08-49D 5 16-49C 6 24*498 7 (32-49A) 8 I 40-49D 9 08-41D 10 11 24-418 I 12 32-41 A 13 40-41D 14 48-41C 15 08-338 16 16-33A 17 24-33D 18 32-33C 19 40-338 20 48-33A 21 08-258 22 16-25A 23 24-25D 24 32-25C 25 40-258 26 48-25A 27 16-17C 28 24-178 29 32-17A 30 40-17D LPRM #2 24-57D 3WC (40-57EV 16-49C 24-498 (32-49A)40-49D 48-49C (16-41C) 24-418 32-41 A 40-41 D 48-41C 56-418 16-33A 24-33D 32-33C 40-338 48-33A 56-33D 16-25A 24-25D 32-25C 40-258 48-25A 56-250 24-178 32-17A 40-170 48-17C LPRM #3 LPRM #4 24-498 16-49C 24-498 40-49D (16-41C)08-41D 24-418 (16-41 C) 32-41 A 24-418 40-41D 32-41 A 48-41C 40-41D 16-33A 08-338 24-33D 16-33A 32-33C 24-33D 40-338 32-33C 48-33A 40-338 56-33D 48-33A 16-25A 08-258 24-25D 16-25A I 32-25C 24-25D 40-258 32-25C 48-25A 40-258 56-25D 48-25A 16-17C 08-17D 24-178 16-17C 32-17A 24-178 40-17D 32-17A 48-17C 40-17D =56-178 48-17C 24-098 16-09C 32-09A 24-098 40-090 32-09A 48-09C 40-090 If bypassing LPRM will results in < 2 LPRMs operable in impacted cell, the cell will inoperable once the LPRM is Inoperable Cells due to bypassing LPRM(s): 0 Operable Cells: 30 (following bypass of If <22 cells remain operable, the OPRM will become inoperable following bypass of If <22 cells remain operable, the OPRM will become inoperable following bypass of LPRM(s). OPRM Operability Assessment Complete Only SROs sign here / ##1##1## / #### Shift Supervision Date Time Page 4 of 4 PPL SUSQUEHANNA, JOB PERFORMANCE APPROVAL AND ADMINISTRATIVE DATA SRO 00.AD.1018.001 o 8/9/10 Generic 2.3.11 4.3 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task Respond to SGTS Exhaust Radiation Monitor 'A' Failure While Purging Primary Containment.

Completed By: Validated:

Tracy North 8/9/10 Writer Date Instructor:

nter Date Approval:

10 Date of Performance:

Validation Time (Min.) Time Taken (Min.) ..IPM Performed By: Student Name: Employee # / S.S. # Performance Evaluation: ( Satisfactory ( ) Unsatisfactory Evaluator Name: Signature Typed or Printed Comments:

FORM NTP-QA-31.8-1, Rev. Page 1 of 7 REQUIRED TASK JOB PERFORMANCE SRO 00.AD.1 SAFETY CONSIDERATIONS 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. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required andlor posted as being necessary. 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. 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. REFERENCES NDAP-QA-0309, Primary Containment Access and Control, rev 26 Tech Spec 3.3.6.1, Primary Containment Isolation Instrumentation.

rev 4 TRM 3.6.1, Containment Venting and Purging, rev 0 OP-173-001.

Containment Atmosphere Control System, rev 37 AR-015-001, 13.8/4 KV Switchgear Distribution And Diesel Generators A, B, & C OC653, rev 36 OPERATIONAL ACTIVITIES None IV. TASK CONDITIONS Unit 1 is in Mode 3. Primary Containment purge is in progress in preparation for containment entry in accordance with NDAP-QA-0309, Primary Containment Access and Control, and OP-173-001, Containment Atmosphere Control System using the "B" SGTS Train. Annunciator AR-015-001 (H03), SGTS EXH VENT RADIATION MON DNSCALElINOP has illuminated, and I&C reports that the "A" SGTS Exhaust Radiation Monitor (RE-D12-0N017A) has failed. FORM NTP-QA-31.8-1, Rev. Page 2 of 7 INITIATING CUE Determine the procedural, Tech Spec, and TRM actions required due to the SGTS Exhaust Radiation Monitor failure. Document your conclusions on the Task Condition sheet provided.

VI. TASK STANDARD Determine that BOTH SGTS Exhaust Radiation Monitors are required to be operable while purging containment in Mode 3, and: The failed channel must be placed in TRI P per TS LCO 3.3.6.1 action A.1 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Primary Containment Purge must be suspended IMMEDIATELY per TRO 3.6.1 action A.1 , and NDAP-QA-0309.

VII. TASK SAFETY SIGNIFICANCE High SGTS exhaust radiation indicates possible gross failure of the fuel cladding.

Purging primary containment in Mode 3 without required radiation monitors available could lead to a radiation release to the environment in excess of allowed limits. FORM NTP-QA-31.8-1, Rev. Page 3 of 7 PERFORMANCE CHECKLIST Appl. To: SRO JPM No.: OO.AD.1018.051 Student Name: Step Action Standard Eval Comments EVALUATOR NOTE: This JPM should be performed in the classroom or similar environment.

Ensure copies of Unit 1 Tech Specs, TRM and NDAP-QA-0309, and AR-015-001 (H03) are available for candidate use. EVALUATOR CUE: To begin this JPM, provide the candidate with Task Conditionsllnitiating Cue The steps of this JPM may be performed in 1. Obtain and refer to NDAP-QA-0309 section 6.2. Obtain and refer to NDAP-QA-0309, section 6.2. EVALUATOR NOTE: The candidate may also wish to refer to AR-01S-001 Review AR-015-001 (H03) if desired (not (H03). If asked, provide this to the candidate.

required)

FORM NTP-QA-31.8-1, Rev. 0 Page 4 of 7 PERFORMANCE CHECKLIST Appl. To: JPM No.: OO.AD.1018.051 Student Name: Step Standard Eval Comments Determine that BOTH SGTS Exhaust Radiation Review step 6.2.3 and determine High trips are required to be operable for insufficient SGTS Exhaust Rad Monitors containment purge in Mode 3. available to continue containment and TRM 3.6.1 should be evaluated.

Document on Task Condition sheet. *3. Evaluate TRM Refer to TRM 3.6.1, and determine action A.1 is required with less than minimum number of SGTS Exhaust Radiation isolation channels operable, primary containment purging must immediately Document on Task Condition sheet. *4. Evaluate Tech Spec Refer to TS 3.3.6.1 and determine action A.1 is required since less than required number of channels is and the failed channel must be placed EVALUATOR CUE: TRIP within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (function 2.e) This completes the JPM. Document on Task Condition sheet. EVALUATOR:

Do you have ALL your JPM exam materials?

Task Cue Sheets? Procedures?

-_._................

__._.................... FORM NTP-QA-31.8-1, Rev. Page 5 of 7 TASK CONDITIONS Unit 1 is in Mode 3. Primary Containment purge is in progress in preparation for containment entry in accordance with NDAP-QA-0309, Primary Containment Access and Control, and OP-173-001, Containment Atmosphere Control System. Annunciator AR-015-001 (H03). SGTS EXH VENT RADIATION MON DNSCALE/INOP.

has illuminated, and I&C reports that the "A" SGTS Exhaust Radiation Monitor (RE-D12-0N017 A) has failed. INITIATING CUE Determine the procedural, Technical Specification, and TRM actions required due to the SGTS Exhaust Radiation Monitor failure. Document your conclusions below. Procedural Requirement(s):

Technical Requirement Manual: Tech Specs: THIS JPM IS COMPLETE WHEN YOUR CONCLUSIONS ARE DOCUMENTED ABOVE. FORM NTP-QA-31.8-1, Rev. 0 TASK CONDITIONS Unit 1 is in Mode 3. Primary Containment purge is in progress in preparation for containment entry in accordance with NDAP-QA-0309, Primary Containment Access and Control, and OP-173-001, Containment Atmosphere Control System. Annunciator AR-015-001 (H03), SGTS EXH VENT RADIATION MON DNSCALElINOP.

has illuminated, and I&C reports that the N' SGTS Exhaust Radiation Monitor (RE-D12-0N017 A) has failed. INITIATING CUE Determine the procedural, Technical Specification, and TRM actions required due to the SGTS Exhaust Radiation Monitor failure. Document your conclusions below. Procedural Requirement(s):

Technical Requirement Manual: Tech Specs: THIS JPM IS COMPLETE WHEN YOUR CONCLUSIONS ARE DOCUMENTED ABOVE. FORM NTP-QA-31.8-1, Rev. 0 PPL SUSQUEHANNA, JOB PERFORMANCE APPROVAL AND ADMINISTRATIVE DATA SRO 00.EP.001.087 o 11/3/10 Generic 2.4.44 4.0 Appl. JPM !\lumber Rev. No. Date NUREG 1123 KIA No. KIA Imp. To Sys. No. Task Classify A Site Area Emergency Under Shutdown Conditions And Complete The Emergency Notification Report; Upgrade To A General Emergency And Make Protective Action Recommendations Completed Validated Tracy North 11/3/10 M. Jacopetti 11/27/10 Writer Date Instructor/Writer Date Approval:

Date Time Critical #1: 15 Time Critical #1: __ Time Critical #2: 15 Time Critical #2: __ Time Critical #3: 15 Time Critical #3: Date of Validation Time (Min.) Time Taken (Min.) JPM Performed By: Candidate Name: Last First M.1. Employee # / S.S. # Performance Satisfactory ) Unsatisfactory Evaluation:

Evaluator Name: Signature Typed or Printed Comments:

FORM NTP-QA-31.8-1, Rev. 0 REQUIRED TASK JOB PERFORMANCE SRO I. SAFETY 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. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. 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. 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. 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. REFERENCES EP-PS-100, Revision 26 EP-PS-100, Tab E, Revision 28 Emergency Plan -Units 1 and 2 EP-TP-001, Emergency Classification Level Manual, Revision 3 EP-TP-001, Section C, Revision 3 OPERATIONAL ACTIVITIES None TASK CONDITIONS Unit 1 in Mode 4. "A" RHR Pump is in service for Shutdown Cooling. A rigging incident inside the Containment resulted in damage to Recirc Loop 'A' suction piping causing a rapid reduction in RPV level. Division 2 Core Spray and LPCI are injecting full flow. Primary Containment was evacuated and the personnel hatch is closed with interlocks maintained prior to and during the transient. RPV level has been stabilized at -168 inches Fuel Zone. Secondary Containment pressure is -0.28 inches WG with Standby Gas Treatment in service. FORM NTP-QA-31.8-1, Rev. 0 INITIATING CUE Classify the Event, and implement the Emergency Plan as the Control Room Emergency Director in accordance with EP-PS-100. TASK STATEMENT Declaration of a Site Area Emergency based on classification CS4 within 15 minutes. Declaration of a General Emergency based on classification CG4 within 15 minutes of second set of conditions. Make Protective Action Recommendation (PAR) [evacuate 0 to 2 miles, shelter 2 to 10 miles, and advise citizens take KI per state plans] within 15 minutes of declaring a General Emergency. TASK SAFETY SIGNIFICANCE Proper Emergency Plan implementation is required to provide reasonable assurance that public health and safety is not endangered by operation of the facility, and that adequate protective measures can and will be taken in the event of an emergency.

[1 OCFR50.47(c){1

)(iii)] FORM NTP-QA-31.8-1, Rev. 0

---

---

Page 3 of 8 PERFORMANCE CHECKLIST Appl. To/JPM No.: SRO Candidate Name: Step Standard Eval Comments EVALUATOR CUE: To begin this JPM provide the with CUE SHEET#1 When the candidate is ready begin the JPM, inform candidate that this is a CRITICAL Record START TIME ------. *1. Classify the emergency as Evaluate updated information.

conditions indicate.

Review Emergency Classification Level Manual, EP-TP-001. EVALUATOR CUE: If asked, conditions have not Declare a SITE AREA changed. EMERGENCY in accordance with Classification CS4 << -161" with EVALUATOR NOTE: Secondary When candidate declares initial EAL Record Time to determine correct must be within 15 minutes FORM NTP-QA-31.8-1, Rev. 0

---

Page 4 of 8 Step Standard Eval Comments

• Refer to EP-PS-100, "Emergency Obtain a copy of EP-PS-100 and Director, Control Room; Emergency-refer to tab D, Manage the SITE Plan Position Specific Instruction" AREA EMERGENCY. Document and communicate the Announce to Control Room emergency classification.

personnel Assuming duties of Emergency Director Emergency Classification Time and Date of Classification Appoint E-Plan Communicator.

Appoint E-Plan Communicator.

Instruct E-Plan Communicator to immediately perform EVALUATOR CUE: EP-PS-126.

Acknowledge the appointment of the Plan Communicator, when given the form indicate that the Communicator will transmit the Appoint NRC Communicator.

Appoint NRC Communicator.

Instruct NRC Communicator to perform EP-PS-135, NRC EVALUATOR CUE: Communicator.

Acknowledge the appointment of the FORM NTP-QA-31.8-1, Rev. 0 I Page 5 of 8 Step Standard Eval Comments Generate and approve ENR Form for Fill out ENR Form from Tab 9 and transmittal.

authorizes Form for transmittal.

Review ENR Form with E-Plan EVALUATOR Communicator prior If JPM is not performed in the simulator, transmittal.

when requested, inform the student that: Wind Direction is 210 degrees

• Wind Speed is 5 If performed in the Simulator, should use current PICSY EVALUATOR CUE: Inform the student that no further PS-100 actions are required respect to the previous Provide candidate with CUE Record START TIME Refer to EP-TP-001 and evaluate the Refer to EP-TP-001 Category C, impact of new and determine that the blowout panel failure Secondary Containment EVALUATOR established and water level When candidate identifies the been < -161 inches for >30 mins, upgrade EAL classification AND an escalation to GENERAL Record TIME EMERGENCY CG4 is now required;Time to determine correct EAL must within 15 minutes of START TIME EP-PS-100 tab E must now be in 3., above. implemented.

FORM NTP-QA-31.8-1, Rev. 0

---

---

Page 6 of 8 Step Standard Eval Comments Generate and approve ENR Form for Fill out ENR Form from Tab 9 and transmittal.

authorizes Form for transmittal.

Review ENR Form with E-Plan EVALUATOR CUE: Communicator prior to If JPM is not performed in the simulator, transmittal.

when requested, inform the student that:

• Wind Direction is 205 degrees

• Wind Speed is 7 If performed in the Simulator, should use current PICSY Refer to EP-PS-100 tab E and Refer to determine that a PAR must also performed in accordance with EVALUATOR CUE: After the candidate determines a PAR required, direct the candidate to the correct PAR for current FORM NTP-QA-31.8-1, Rev. 0 Page 7 of 8 Refer to EP-PS-100 Tab 5 and Perform EP-PS-100 Tab 5, Emergency Dose Assessment and Protective Action Recommendation (PAR)

• PA-2: Has a GE been declared?

YES Guide" PA-3: Release via EVALUATOR CUE: controlled direct When asked, inform student that a valid containment vent < 1 hr? offsite dose projection is NOT available NO yet. PA-6: Valid Dose projection?

NO EVALUATOR

• Per PA-7: When candidate completes

• Evacuate 0-2 miles and indicates need to transmit it

• Shelter 2-10 miles the Senior State

• Citizens take KI per Record state plans Time to determine PAR must be within Notify Senior State Official, using 15 minutes of General Emergency PAR State Notification Form, at declaration time noted in Step 7. 717-651-2148.

EVALUATOR CUE: When student indicates need to transmit PAR to Senior State OffiCial, inform student "This completes the JPM." EVALUATOR:

Do you have ALL your JPM exam materials?

Task Cue Sheets? Procedures?

"'Critical Step #Critical Sequence FORM NTP-QA-31.8-1, Rev. 0 CUE SHEET #1: TASK CONDITIONS Unit 1 in Mode 4. "A" RHR Pump is in service for Shutdown Cooling. A rigging incident inside the Containment resulted in damage to Recirc Loop 'A' suction piping causing a rapid reduction in RPV level. Division 2 Core Spray and LPCI are injecting full flow. Primary Containment was evacuated and the personnel hatch is closed with interlocks maintained prior to and during the transient. RPV level has been stabilized at -168 inches Fuel Zone. Secondary Containment pressure is -0.28 inches WG with Standby Gas Treatment in service. INITIATING CUE Classify the Event, and implement the Emergency Plan as the Control Room Emergency Director in accordance with EP-PS-100.

Page 1 of 2 CUE SHEET #1: TASK CONDITIONS Unit 1 in Mode 4. "A" RHR Pump is in service for Shutdown Cooling. A rigging incident inside the Containment resulted in damage to Recirc Loop 'A' suction piping causing a rapid reduction in RPV level. Division 2 Core Spray and LPCI are injecting full flow. Primary Containment was evacuated and the personnel hatch is closed with interlocks maintained prior to and during the transient. RPV level has been stabilized at -168 inches Fuel Zone. Secondary Containment pressure is -0.28 inches WG with Standby Gas Treatment in service. INITIATING CUE Classify the Event, and implement the Emergency Plan as the Control Room Emergency Director in accordance with EP-PS-100.

Page 2 of 2 CUE SHEET #2: (Do not provide until directed to by JPM.) At time T =40 minutes, It has just been discovered by an NPO that the Unit 1 HPCI blowout panel has been dislodged and the HPCI room is open to outside atmosphere. The Standby Gas Treatment system is now maintaining Secondary Containment at -0.16 inchesWG. Assuming the other initial conditions are still valid, determine if this new condition will affect the current EAL classification, AND if so perform any other additional actions that may be required.

Page 1 of 2 CUE SHEET #2: (Do not provide until directed by JPM) At time T =40 minutes. It has just been discovered by an NPO that the Unit 1 HPCI blowout panel has been dislodged and the HPCI room is open to outside atmosphere. The Standby Gas Treatment system is now maintaining Secondary Containment at -0.16 inchesWG. Assuming the other initial conditions are still valid. determine if this new condition will affect the current EAL classification, AND if so perform any other additional actions that may be required.

Page 1 of 2 PPL SUSQUEHANNA, JOB PERFORMANCE APPROVAL AND ADMINISTRATIVE DATA S/RO 00.AD.3246.052 o 8/3/10 Generic 2.1.5 2.9/3.9 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task Title: Evaluate Overtime Request With Respect to Work Hour Limits per Completed By:

Tracy North 8/3/10 P. Moran Writer Date I nstructorlW riter Date Approval: ,'Ii'"'£, 1>1. 10./6 lear rng. SUpv. Date of Performance:

Validation Time (Min.) Time Taken JPM Performed By: Last First M.1. Employee # / S.S. Performance Evaluation: ( ) Satisfactory

}

Evaluator Signature Typed or FORM NTP-QA-31.8-1, Rev. 0 Page 1 of 7 REQUIRED TASK JOB PERFORMANCE SIRO I. SAFETY 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. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. 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. 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. 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. REFERENCES NDAP-QA-0025, Work Hour Limits for Station Staff, rev 8 10CFR26.205, Work Hours OPERA1*IONAL ACTIVITIES None TASK CONDITIONS Shift Supervision has called you at home on Sunday, 9/12 (a scheduled day off), to report to the control room to work a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> overtime shift from 0600-1800. Your work history for the previous week is as follows: Sunday Monday Tuesday Wednesday

°rhursday Friday Saturday 9/5 9/6 9n 9/8 9/9 9110 9/11 Worked Worked OFF Worked Worked Worked Worked 0600-1800 0600-1800 0600-1800 0600-1800 0800-1600 0600-2100 C. Prior to Sunday 9/5 you were on two weeks of vacation.

FORM NTP-QA-31.8-1, Rev. Page 2 of 7 V. INITIATING CUE Using the work history provided, determine whether or not you are able to cover the requested shift and state the reason. Document your conclusion on the Task Condition sheet provided.

VI. TASK STANDARD The candidate determines that they are unable to work the requested shift without an approved waiver because they will not have had a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> break prior to the work start and/or will exceed 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> worked within a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period. VI. TASK SAFETY SIGNIFICANCE Federal requirements stated in 10CFR26.205 provide limitations on work hours for "covered workers" such as licensed operators in order to manage fatigue and prevent fatigue-related operator errors from threatening the health and safety of the public. FORM NTP-QA-31.8-1, Rev. 0 Page 3 of 7 PERFORMANCE CHECKLIST Appl. To: SIRO JPM No.: 00.AD.3246.052 Student Name: Step Standard Eval Comments EVALUATOR NOTE: This JPM should be performed in the classroom (or similar Ensure a copy of the current revision of 0025 is available for candidate use if EVALUATOR CUE: To begin this JPM provide the conditionsllnitiating cue sheet to the , 1. The candidate may review NDAP-QA-0025, Work Student refers to NDAP-QA-0025.

I Hour Limits for Station Staff. EVALUATOR CUE: If asked, provide procedure.

I Refer to work history and analyze for additional Refer to and analyze work hours I requested work hours FORM NTP-QA-31.8-1, Rev. Page 4 of 7 PERFORMANCE Appl. To: JPM No.: 00.AD.3246.052 Student Name: Step Standard Eval Comments

• Determine that working the requested shift will Determine that the required 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> break 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Sunday 9/12 + ; result in exceeding between work periods will not be met. 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> Saturday 9/11 = Andlor that the additional hours will result in 27 hour3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> exceeding 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> worked within a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period. 2100 to 0600 = 9 period hours vs. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Report to Shift Supervision that the overtime Makes report to shift request CANNOT be honored due to the 10 break between work periods will not be met exceeding 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if the hours were to be EVALUATOR CUE: When candidate reports results, report that this is EVALUATOR NOTE: Do you have ALL your JPM exam materials?

Task Cue Sheets? Procedures?

FORM NTP-QA-31.8-1, Rev. Page 5 of 7 TASK CONDITIONS Shift Supervision has called you at home on Sunday, 9/12 (a scheduled day off), to report to the control room to work a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> overtime shift from 0600-1800, as the Unit 1 PCOM. Your work history for the previous week is as follows: Sunday Monday Tuesday Wednesday Thursday Friday Saturday 9/5 9/6 9n 9/8 9/9 9/10 9/11 Worked Worked OFF Worked Worked Worked Worked 0600-0600-0600-1800 0600-1800 0800-0600-2100 1800 1800 1600 Prior to Sunday 9/5 you were on two weeks of vacation.

INITIATING CUE Using the work history provided, determine whether or not you are able to cover the requested shift and state the reason .. Document your conclusion on the Task Condition sheet provided.

Circle One: CAN I CANNOT work the requested shift. Reason: ______________________

.____________

__ FORM NTP-QA-31.8-1, Rev. 0

---

3.2 PPL SUSQUEHANNA, JOB PERFORMANCE ) APPROVAL AND ADMINISTRATIVE DATA SHEET RD 00. EP.1135.081 o 11/3/10 Generic 2.4.43 Appl. JPM Number Rev. No. Date NUREG 1123 KIA No. KIA Imp. To Sys. No. Task Title: Control Room Communicator Emergency Notification Completed By: Validated:

T.North 11/3/10 (/-2.'2. -/0 Writer Date InstructortWriter Date Approval:

NCJarrng: Supv. Date Time Critical 15 Minutes Date of Performance:

Validated Time (Min.) Time Taken JPM Performed Student Name: _________---:=-____Last First M.1. Employee # 1 S.S. Performance ( Satisfactory ( )

Evaluator Signature Typed or FORM NTP-QA-31.8-1, Rev. 0 REQUIRED TASK JOB PERFORMANCE RO SAFETY CONSIDERATIONS All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with Standards for Shift Operations. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required andlor posted as being necessary. 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. 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. REFERENCES "Emergency Director, Control Room: Emergency-Plan-Position Specific Instruction" (Rev. 26) EP-PS-126, "Emergency Plan Communicator:

Emergency Plan-Position Specific Instruction" (Rev. 27 EP-TP-003, "Communication Process" (Rev. 5) EP-AD-OOO-301, "Emergency Notification Reporf' (Rev. 12) III. REACTIVITY MANIPULATIONS This JPM satisfies the following Operational IV. TASK CONDITIONS A General Emergency has been declared due to "Loss of RPV Inventory Affecting Fuel Clad Integrity with Containment Challenged with Irradiated Fuel in the RPV" (CG4). An airborne release is in progress. INITIATING CUE You have been assigned as the Control Room Transmit initial information about the Emergency Condition to required organizations, lAW appropriate A TASK STANDARD "!,,, Identify the ENR form is incorrectly completed; Contact the offsite agencies within 15 minutes from "time of declaration";

Communicate the Emergency Classification, Unit, Declaration Time and Date to the offsite agencies.

FORM NTP-QA-31.8-1, Rev. 0 B. Task Safety Significance Proper notification of state and local agencies is essential to ensure the health and safety of the general public. FORM NTP-QA-31.8-1, Rev. 0

.,"') ..) PERFORMANCE Page 3 of 9 Appl. To/JPM No.: RO OO.EP.1135.081 Student Name' Step Action Standard Eval Comments EVALUATOR NOTE: This is a time critical JPM. Ensure a copy of EP-PS-100, EP-TP-003, EP-PS-126 are available to performance of this Have current, filled-out copy of ENR available with the INCORRECT line 4 attached. (a table C label CS5 should Ensure an ENR form with the correct CG4 is EVALUATOR NOTE: To begin this JPM, provide the candidate with the Conditions and Initiating Cue Role playas Control Room ED and give filled-out ENR Time ENR form is given: Start time is above time MINUS 5 (declaration Enter time of declaration(start The TIME CRITICAL portion of the JPM *Critical Step #Critical Sequence FORM NTP-QA-31.8-1, Rev. a

, .....J PERFORMANC)CHECKUST Page 4 of 9 Appl. To/JPM No.: ROOO.EP.1135.081 Student Name' Step Action Standard Eval Comments *1. Obtain and review Event Notification Report (ENR) Review ENR form to verify Lines 1, 3, 4, 5, 6, and 7 form with the Shift Manager/ED.

are all filled out. Determine that the line 4 label is NOT the correct label for CG4. Report to ED that line 4 is incorrect

2. EVALUATOR CUE: Reviews the ENR from with the correct CG4 label in block on line 4. Role Playas ED and provide the ENR form with the correct CG4 label to the candidate.

EVALUATOR NOTE: If the JIC does not answer, do not wait. Transmit the ENR form information to the emergency agencies.

Do not communicate the control number to offsite agencies.

This block is gray shaded on the ENRform. __ *Critical Step #Critical Sequence FORM NTP-QA-31.8-1, Rev. 0

--)

Page 5 of 9 ......,J Appl. To/JPM No.: RO Student Name' Step Standard Eval Comments Within 15 minutes of declaration, using the purple Dial "191" on the purple colored colored phone button, dial "191" to transmit the form to the (Dialing 191 will simultaneously connect the Verify the following agencies are on the agencies in a conference (1) Penna. Emergency Management EVALUATOR (2) Columbia County If candidate is concerned about the button not CLEARL Y purple, Inform the candidate that the CTN (3) Luzerne County 4915 button is (4) Joint Information EV ALUATORIBOOTH Role-play the receiving agencies and confirm agency is on the line and you are "Ready to EVALUATOR NOTE: After contact with the FIRST offsite agency has been confirmed, the Time Critical Portion of the JPM ends. Within 15 minutes of "time of Record stop Time previously EVALUATOR NOTE: When you communicate your phone number to the offsite agencies, the prefix for 4XXX numbers is (570) 759. (The 191 call originates from a 4XXX number, if the purple button is used.) _ .....-*Critical Step #Critical Sequence FORM NTP-QA-31.8-1, Rev. 0

... ":, PERFORMANCE CHECKLIST Page6of9 V AppL To/JPM No.: RO OO.EP.1135.081 Student Name' Step Action Standard Eval Comments 3. Communicate ENR Form: Communicate the following for line1 Call status: Line This is a 4. Communicate Line 2 Communicate the following for line 2: This is: Candidate's Name at Susquehanna Steam Electric Station. My telephone number is: 570-759-4915 Notification time is: Current Time *Critical Step #Critical Sequence FORM NTP-QA-31.8-1, Rev. 0

---

PERFORMANC-IcHECKUST Page 7 of 9 ..""J Appl. To/JPM No.: RO OO.EP.1135.081 Student Name* Step Action Standard Eval Comments *5. Communicate Line 3 Communicate the following for line 3: EMERGENCY CLASSIFICATION:

EVALUATOR NOTE: GENERAL EMERGENCY "Initial Declaration" statement is not critical UNIT: ONE Declaration Time: FROM ENR FORM DATE: <TODAY'S DATE> THIS REPRESENTS AlAN: INITIAL DECLARATION

• 6. Communicate Line 4 Communicate the following for line 4: The Classification Designation is: CG4 BRIEF NON-TECHNICAL DESCRIPTION OF THE EVENT: "The water level inside the Unit 1 reactor has dropped and does not completely cover the uranium fuel. The unit had been shut down prior to the event and remains shut down. Protective actions will be made for the public" _....--... -_._.... -....-.._.-_ ..-.... -.... -.... _ ..-.... _---_.. _...... *Critical Step #Critical Sequence FORM NTP-QA-31.8-1, Rev. 0 i.*1 , , ) PERFORMANCE CHECKLIST pageBof9....J Appl. To/JPM No.: RO OO.EP.1135.0B1 Step Action *7. Communicate Line 5 B. Communicate Line 6 9. Communicate Line 7 EV ALUATORIBOOTH CUE: Candidate may request one of the offsite agencies "REPEAT" back the communicated information.

If necessary, role-play the offsite agency and "Repeaf back the information.

Student Name' Standard Eval Comments Communicate the following for line 5: THERE IS: AN AIRBORNE RADIOLOGICAL RELEASE IN PROGRESS Communicate the following for line 6: WIND DIRECTION IS FROM: 2n° WIND SPEED IS: 5 mph Communicate the following for line 7: THIS IS A DRILL

---........ ........-.--........-..---.. -..--

• Critical Step #Critical Sequence FORM NTP-QA-31.B-1, Rev. 0 I

<C'j PERFORMANC/cHECKlIST Page 9 of 9 Appl. To/JPM No.: RO OO.EP.1135.081 Student Name' Step Action Standard Eva I Comments EVALUATOR CUE: This completes the JPM EV ALUATOR NOTE: In order for the candidate to pass the Time Critical element of this JPM, they must complete step 2 of this JPM within 15 minutes. EVALUATOR:

Do you have ALL your JPM exam materials? Cue Sheets?

---

'

I *Critical Step #Critical Sequence FORM NTP*QA*31.8*1, Rev. 0 TASK ) A General Emergency has been declared due to "Loss of RPV Inventory Affecting Fuel Clad Integrity with Containment Challenged with Irradiated Fuel in the RPV" (CG4). An airborne release is in progress.

INITIATING ClIE You have been assigned as the Control Room Transmit initial information about the Emergency Condition to required lAW the appropriate

,:;,."""" { Page 1 of 2 TASK ) A General Emergency has been declared due to "Loss of RPV Inventory Affecting Fuel Clad Integrity with Containment Challenged with Irradiated Fuel in the RPV" (CG4). An airborne release is in progress.

INITIATING CUE You have been assigned as the Control Room Transmit initial information about the Emergency Condition to required lAW the appropriate Page 2 of 2 PPL SUSQUEHANNA, JOB PERFORMANCE APPROVAL AND ADMINISTRATIVE DATA SIRO Appl. To 44.0N.1792.101 JPM Number o Rev. No. 11/22110 Date 256000 NUREG 1123 Sys. No. A4.0S KIA No. 3.7/3.7 KIA Imp. Task Title: Emergency Operation of Condensate System Completed By: Bob Pudish Writer 11/22110 Date Validated:

Approval: "l.'D,I!!.

N I r Trng. Supv. Date Date of Performance:

20 Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name:

Last First M.1. Employee # I S.S. # Performance Evaluation: ( ) Satisfactory ( ) Unsatisfactory Evaluator Name: Signature Typed or Printed Comments:

FORM NTP-QA-31.S-1, Rev. 0 REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 44.0N.1792.1 01 I. SAFETY CONSIDERATIONS 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. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: 1 Whenever any electrical panel is opened for inspection during JPM performance. 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. 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. 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. REFERENCES A . ON-144-001, Emergency Operation of Condensate System (Rev. 10) .OP-AD-001, Operations Standards for System and Equipment Operation (Rev. 44) OPERATIONAL TASK CONDITIONS Unit 1 has experienced a loss of coolant accident. No injection sources are currently injecting into the Vessel. RPV pressure has been between 700-800 psig for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. RPV level is approximately

-180 inches, steady on Compensated Fuel Zone Indicator. TBCCW is unavailable Instrument Air has been cross tied to U2. INITIATING CUE Restore and maintain RPV level> -161 inches on Compensated Fuel Zone Indicator, via LV -10641, using the Condensate system, in accordance with ON-144-001 (Emergency Operation of Condensate System). TASK STANDARD RPV pressure is lowered below the shutoff head of the Condensate Pump to allow restoration of RPV level. Condensate is injected into the Vessel to raise Level. :tr" VII. TASK SAFETY SIGNIFICANCE r, Restoring and maintaining RPV level> -161 inches assures Adequate Core Cooling which will prevent Cladding Damage. FORM NTP-QA-31.8-1, Rev. 0

--, PERFORMJE Page 30t ';J Appl. Tal JPM No 44.0N.1792.l0l Student Name Step Action Eval Comments This JPM must be performed in the Setup was snapped to IC-39G for LOC-23 NRC Setup the simulator to Insert the following IMF mfHP152015 HPCI IMF RCIC IMF ADS IMF cmfPM03_1 CS IMF cmfPM03_1 " " IMF cmfPM03_1 P206B " " IMF cmfPM03_1 P206D .. " IMF cmfPM02_1 P1 CRD IMF cmfPM02_1 P1 O3B .. " IMF IMF cmfPM03_1P132B IRF rf1AOl9001 f:100 IA cross tied to Recirc Leak 2% to obtain -1BO" on Camp Consider snapping an IC for multiple performances then modify to of this JPM. DW has been sprayed once to lower MSIVs When student is ready to begin JPM, place the FV-i OG04A(B)(C) in simulator in RUN. Shut off all Condensate Pumps after The simulator booth operator should role playas the Start 'C' Condensate Pump immediately NPO when required.

beginning Ensure FIC-l050B in RPV pressure approx 700 *Critical Step #Critical Sequence FORM NTP-QA-3l.B-2, Rev. 0

PERFORMAdcE CHECKLIST Appl. Tol JPM No 44.0N.1792.101 Student Name Step Standard Eval Comments Obtain ON-144-001.

Student obtains procedure. Reviews Notes Determines Section 4.3 is applicable based on Plant conditions Ensure a Rx Scram has been initiated.

Student recognizes the Unit is scrammed. Mode Switch in Shutdown All Rods In If the Rx is Shutdown and any Rx Feed Pump is still in service If the injection flow path is through any RFP Discharge Isolation Valve Ensure all Rx Feed Pumps are tripped. Student confirms RFPs are tripped on HMI

• Pump Icon states Tripped

• Pump Icon Gray Ensure all RFP Recirc valves FV-10604A,B,C Student observes RFP Recirc valves controller FIC-1 0604A,B,C are in Manual and FV-10604A,B,C are in Student closes the valves B Opens the overlay for FV-10604A,B,C Touches the Manual button Observes controller output 0 C *Critical Step #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0 PERFORMA-JCE page50f;-i Appl. SIRO JPM No 44.0N.1792.101 Student Name Step Standard Eval Comments 7. If RPV pressure is < 650 psig N/A If RPV pressure>

650 psig: Student observes Control Room and recognizes only one Cond Pump Shutdown all but one Condensate running. (1 Red light on: 3 Amber lights *9. Place the Condensate Recirc Flow controller Student touches FV08 on HMI. FIC-10508 in Manual with a controller output

• Touches MAN of 0% (FW Startup/shutdown HMI screen) Sets % CTLR OUTPUT to 0 by depressing DEC button *10. Shutdown the last remaining in-service Student depresses the Stop pushbutton.

Condensate pumps.

• Red light off, Amber light on , *11.

• Then lower RPV Pressure using Bypass Student lowers RPV pressure by either: , Valves and/or SRVs.

• Opening Bypass valves (not an option due to MSIVs being closed) or Opens SRV(s): Switch to Open Student observes RPV pressure lowering.

_.... _.... _ .... _---.... -.... _.. _._... _ .. _.__... _.... _... _.... _--_ .... *Critical Step #Critical Sequence FORM NTP-QA-31.B-2, Rev. 0

" ) PERFORMANCE Appl. Tol JPM No 44.0N.1792.101 Student Name Step Standard Eval Comments *12.

• After RPV Pressure is < 650 psig and RPV Student depresses Start pushbutton for one Level is at the lower range of the assigned Condensate Pump after RPV Pressure is < 650 band, Start a Condensate Pump. psig and Level is at the lower range of band. RPV pressure < 650 psig RPV level -180" on Camp FZWL One Condensate Pump "Start" pushbutton depressed (Red light on, Amber light off) Maintain RPV Pressure between 450-650 psig using Student reduces RPV pressure to 45(}650 psig Bypass Valves andlor SRVs. by opening SRV(s). If feeding through LV-10641 , Manually Throttle LV-Student manually throttles L V-10641 by: 10641 FW LOW LOAD VALVE to maximize Injection

• Touches 641 on Flow and minimize time above 143 amps on Touches INC I DEC as necessary service Condensate Pump. Monitors Cond Pump amps (minimize time above 143 amps) Ensure Condensate Recirc Flow controller FIC-Student recognizes FIC-10508 already in 10508 in Manual with a controller output of 0%. manual from previous manipulation Dispatch Field Operators to Isolate the Condensate Student contacts Field Operator to isolate Recirc & Rx Feedpump Recirc Flow paths in and RFP Recirc Flow accordance with Attachment *Critical #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0

) PERFORMANCE Page 7 of 9 """ Appl. Tal JPM No 44.0N.1792.101 Student Name Step Standard Eval Comments EVALUATOR CUE Role playas Field Operator and inform Student you will isolate Condensate and Feedpump Flow Operate Condensate Pumps one at a time, Student monitors Cond Pump bearing temp sequentially, to maintain bearing temp below 265°F PICSY display (PICSY display If the RPV injection is lost due to the degraded Instrument Air Header Pressure prior to of Attachment F If reactor is not shutdown, maintain level per EO-100-113 _.... _.... _._-_ .. --*Critical Step #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0

) PERFORMANCE Page 8 of 9"wt1 Appl. Tol SIRO JPM 44.0N.1792.101 Student Name Step Standard Eval Comments If reactor is shutdown, to minimize condensate Student raises RPV level above -161" by*20. starts, Maintain a maximum level band of -129" to throttling LV-10641.

+54". RPV level> -161" on Compensated Shutdown condensate pump prior to Fuel Zone Level reaching a bearing temperature of 265°F when level reaches +54" (EVALUATOR:

SEE CUE ON NEXT FOR TERMINATION CRITERIA) Start next sequential pump when RPV drops to -129" Student monitors Cond Pump bearing Repeat the previous Steps 4.3.15.a and b as Student monitors RPV necessary until there are no Pumps available for use or TSCCW has Student shuts down Condensate Pump prior been restored.

bearing temp reaching Stop pushbutton depressed (Red light off, Amber light on) Student shuts down Condensate Pump when RPV level reaches +54". Stop pushbutton depressed (Red light off, Amber light on) 21. Request TSC to pursue providing alternate means of Student contacts TSC to pursue providing cooling for TSCCW and/or Condensate alternate means of cooling for TSCCW Condensate EVALUATOR CUE Role Playas TSC that alternate means of are being , _.. _.. __ .... _ .... _ .... _.... _.. _-.... _ .... -, --....-.... _.... _ ..__ .... _ .... _ .... _.. _._._..*Critical #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0 PERFORMAJcE CHECKLIST page90f:J Appl. Tol S/RO JPM No 44.0N.1792.101 Student Name Step Action Standard Eval Comments EVALUATOR CUE Once RPV level has been restored>

-161 inches on Compensated Fuel Zone Level indicator and showing a rising trend, inform the Candidate this completes the JPM. EVALUATOR Do you have ALL your JPM exam Task Cue Sheets? , *Critical Step #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0 I TASK

} Unit 1 has experienced a loss of coolant accident. No injection sources are currently injecting into the Vessel. RPV pressure has been between 700-800 psig for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. RPV level is approximately

-180 inches, steady on Compensated Fuel Zone Indicator. TBCCW is unavailable Instrument Air has been cross tied to U2. INITIATING CUE Restore and maintain RPV level> -161 inches on Compensated Fuel Zone Indicator, via LV-10641 , using the Condensate system, in accordance with ON-144-001 (Emergency Operation of Condensate System). Page 1 of 2 PPL SUSQUEHANNA, JOB PERFORMANCE APPROVAL AND ADMINISTRATIVE DATA 8/RO 64.0P.4841.101 o 11/22110 202001 A4.01 3.7/3.7 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task Title: Post SCRAM Recovery of "A" Reactor Recirculation Pump Completed By: Bob Pudish 11/22/10 Writer Date Date / Date 25 Date of Performance:

Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name: Employee # I 8.S. # Performance ) Satisfactory Unsatisfactory Evaluation:

Evaluator Name: Signature Typed or Printed Comments:

Form NTP-QA-31.8-1, Rev. 0, Page 1 of 2 REQUIRED TASK JOB PERFORMANCE SIRO 64.0P.4841.101 I. SAFETY 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. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hard hats , etc., is required and/or posted as being necessary. 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. 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. REFERENCES OP-164-001, Reactor Recirculation System (Rev. 56) OPERATIONAL ACTIVITIES None TASK CONDITIONS A Reactor SCRAM has occurred and all control rods inserted. Both Reactor Recirculation Pumps have tripped due to -38 inches Reactor Water Level being reached during the scram. The "A" MG Set Generator and Drive Motor Lockout Relays have been reset. INITIATING CUE Restore the "A" Reactor Recirculation Pump to service in accordance with the 001 Hard Card. TASK STANDARD The "A" Reactor Recirculation Pump is placed in service in accordance with 001. TASK SAFETY SIGNIFICANCE Restoring the reactor recirculation pump to service provides forced circulation preventing thermal stratification in the reactor vessel. Form NTP-QA-31.8-1, Rev. 0, Page 2 of 2

PERFORMAJCE CHECKLIST Appl. Tol S/RO JPMNo 64.0P.4841.1 Student Name Step Action Standard Eval Comments This JPM must be performed in the simulator.

Setup the simulator to a full power IC. Insert a manual scram and perform the immediate operator actions. RRPs will trip on -38". Reset containment isolations to get cooling back to RRPs. Press and release the STOP pushbutton for 14001A, MG SET A DRV MTR BKA. Resets 1C063A LlO relay. Setup was snapped to 394 for LOC-23 NRC Exam. Insert the following commands:

IRF rfRR164011 f:TRIP _RESET IRF rfRR164011 f:NORM Assign the following Keys: {Key[1]} IRF rfRP158035 f:CL_CB3A

{Key[2]} IRF rfRP158036 f:CL_CB4A Resets 1A101-10 LlO relay. Resets RPT Breaker at 1 C609 (URR) Resets RPT Breaker at 1C611 (LRR) Consider snapping an IC for multiple performances of this JPM. The simulator booth operator should role playas the NPO when required.

When student is ready to begin JPM, place the simulator in RUN. 1. Obtains OP-164-001, Attachment D, Hard Card. Student obtains OP-164-001, Attachment D Hard Card. 2. Procedure section shall only be used to Startup the First Recire Pump Post Scram. Student determines that no other Recire Pump has been started post SCRAM. *Critical Step #Critieal Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1

') ...".; PERFORMANCE Page 4 of 9 Appl. Tol JPM No 64.0P.4841.101 Student Name Step Standard Eval Comments Recirculation pump trip is understood and trip Student determines from task conditions condition has cleared and all control rods are fully state of the plant that the pump trip inserted.

understood, the trip condition has and that all control rods are fully inserted. MG Set Generator and Drive Motor Lockout Relays Student determines from task conditions that . the MG Set Generator and Drive Lockout Relays are This section shall not be used when at power (mode Student confirms that the plant is not 1 or 2). mode 1 or Ensure MG Set Ventilation System in operation.

Student confirms MG Set Ventilation Ensure Reactor Recirc Pump motor winding cooling Student confirms on 1 C681 water is aligned to "A" pump as follows:

• HV-18791 A1/A2 RRP A Clg Wtr DB Iso Valves HV-18791 HV-18792 B1/B2 OPEN*A1/A2 OPEN RRP A Clg Wtr IB Iso Valves B1/B2 Ensure Reactor Recirc Pump Seal Package cooling Student confirms on 1 water is aligned to "A" pump as RBCCW OB CONTN ISO MOVS RBCCW OB CONTN ISO MOVS HV-11313/14 11313114 RBCCW IB CONTN ISO MOVS RBCCW IB CONTN ISO MOVS HV-11345/46 11345/46 *Critical #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 i

.J PERFORMANCE Page 5 of 9 """ Appl. Tol JPM No 64.0P.4841.101 Student Name Step Standard Eval Comments Ensure Reactor Recirc Pump RPT breakers at Student contacts an NPO for 1C609 (URR) 1A20501 and 1C611 (LRR) 1A20502 that Reactor Recirc Pump RPT breakers are closed by observing the RED indicating light 1C609 (URR) 1A20501 and 1C611 illuminated.

1 A20502 are BOOTH OPERATOR Press {Key[1]} and {Key[2]} to ensure breakers are closed at 1C609 (URR) and EVALUATOR CUE Role playas NPO and report that RRP breakers at 1 C609 (URR) and 1 C611 (LRR) Ensure Reactor Recirc Pump A Speed SY-B31-At HMI student confirms / 1 R621A Controller in MANUAL with a speed

• SY -831-1 R621 A Controller of approximately MANUAL with a controller output setting of approximately 0% Comply with TRO 3.8.2.1. Student informs Shift Supervision to with TRO EVALUATOR CUE Role playas Shift Supervision indicating that TRO 3.8.2.1 will be taken for action that will be in the next ......*Critical #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1

......; PERFORMAdcE Page 6 of 9 Appl. Tal JPM No 64.OP .4841.101 Student Name Step Standard Eval Comments Place Recirc A MOV OL BYPS HV-143-F031A I Student places Recirc A MOV OL BYPS F032A switch to TEST position.

143-F031A I F032A switch to TEST Student confirms Recirc Loop "A" Valves In Test annunciator Ensure Recirc Pump "An Suet HV-143-F023A Student ensures Recirc Pump "A" Suet OPEN. 143-F023A Ensure Recirc Pump 'W' Dsch Byps HV-143-F032A Student ensures Recirc Pump" A" OPEN. Byps HV-143-F032A Ensure CLOSED or CLOSE Recirc Pump "Au Dsch Student ensures CLOSED or HV-143-F031A.

Recirc Pump "A" Dsch Depress Scoop Tube "A" Lock or Reset HS-B31-Student depresses Scoop Tube "A" Lock 1 S03A Reset pushbutton -4 to 5 seconds (to allow Reset HS-B31-1S03A Reset pushbutton -position amplifier timer to clear and reset logic to to 5 seal IObserve Recirc MG "A" Scoop Tube Drive Lock Confirms Recirc MG "Au Scoop Tube Annunciator NOT ALARMING.

Lock Annunciator NOT NOTE (1) (PICSY format: GD I Utilize steam dome temperature, Camp. Pt. NFA05 or Steam Tables. NOTE (2) RPV Bottom Head Drain temperature is valid even RWCU is

• Critical #Critical Sequence Form NTP-QA-31.8-2.

Rev. 0, Page 1 of 1 PERFORMA,jCE Page 70f;-' Appl. Tol JPM No 64.0P.4841.101 Student Name Step Standard Eval Comments In Mode 3 or 4, within 15 minutes prior to Student records and confirms AT's within recirculation pump start (SR 3.4.10.3 & SR limits specified.

3.4.10.4): Record AT between bottom head temperature and reactor pressure coolant temperatures in Unit 1 Ensure AT between bottom head temperature and reactor vessel temperature s 145 Record AT between reactor temperature in recirculation loop to started and reactor pressure vessel temperature in Unit 1 Ensure AT between reactor temperature in recirculation loop to started and reactor pressure vessel temperature s 50 EVALUATOR Ensure the student SIMULATES announcement over the Announce twice over Plant PA System: "Attention Student SIMULATES making the aI/ personnel, a recirc pump start is about to take place causing a potential loss of lighting, should take precautions with work in

• Critical #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1

\wi PERFORMANCE Page 8 of 9 Appl. Tol JPM No 64.0P.4841.101 Student Name Step Standard Eval Comments START Reactor Recirc Pump 1P401A by Student depresses MG SET A DRV MTR DEPRESSING MG SET A DRV MTR BKR HS-BKR HS-14001A START pushbutton for 14001A START pushbutton

-one (1) second (to approximately one second. allow start sequence relay to seal in). Observe the following:

Student confirms the following actions occur: MG SET A DRIVE MTR BKR CLOSES

• MG SET A DRIVE MTR G EN 1 A SPEED indication INCREASES

• GEN 1A SPEED After 11 seconds, GENERATOR A FIELD

• After 11 seconds, GENERATOR FIELD BREAKER closed BREAKER closed indicator light light ILLUMINATES RECIRC A DRIVE FLOW

• RECIRC A DRIVE FLOW

• INCREASES INCREASES WHEN GEN 1A SPEED indication and RECIRC A When RECIRC A DRIVE FLOW indication DRIVE FLOW indication reached a settled state, reaches a settled state, student OPENS approximately 40-60 seconds, OPEN RECIRC RECIRC PUMP A DSCH HV-143-F031A.

PUMP A DSCH HV-143-F031A. Slowly ADJUST REACTOR RECIRC PUMP A At HMI, student slowly adjusts SPEED SY-B31-1 R621A controller to achieve RECIRC PUMP A SPEED approximately 30% generator speed as indicated on controller to achieve -30% generator SI-14032A.

as indicated on After 2 minutes, place RECIRC A MOV OL BYPS After 2 minutes, student places RECIRC A HV-143-F031A I F032A switch to NORM position.

MOV OL BYPS HV-143-F031A I switch to NORM

• Critical #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 PERFORMAFiCE Page 90t 9 Appl. Tol JPM No 64.0P.4841.101 Student Name Step Standard Eval Comments Clear TRO 3.8.2.1. Student informs Shift Supervision that may clear TRO EVALUATOR CUE Role playas Shift Supervision indicating that TRO 3.8.2.1 will be cleared. EVALUATOR CUE This completes the JPM. I EVALUATOR Do you have ALL your JPM exam materials? Cue Sheets?

I ------I *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 TASK A A Reactor SCRAM has occurred and all control rods inserted.

B Both Reactor Recirculation Pumps have tripped due to inches reached during the scram. C The "A" MG Set Generator and Drive Motor Lockout Relays have been reset. INITIATING CUE Restore the "At! Reactor Recirculation Pump to service in accordance with the 001 Hard Card. Page 1 of 2 PPL SUSQUEHANNA, JOB PERFORMANCE APPROVAL AND ADMINISTRATIVE DATA S/RO Appl. To 34.EO.1619.151 JPM Number o 11/22110 Rev. Date No. 400000 NUREG 1123 Sys. No. A4.01 3.1/3.0 KIA No. KIA Imp. Task Reset Drywell Cooling Isolation and Restore Drywell Cooling lAW ES-134-001 (Control Room Actions) Alternate Path Completed Validated:

Bob Pudish Writer Date Approval: m,1)"e;; armg. SUpv. Date of Performance:

Validation Time (Min.) Time Taken ..IPM Performed By: Student Name: ____________________Last First M.1. Employee # I S.S. Performance ( ) Satisfactory )

Evaluator Signature Typed or Comments:

Form NTP-QA-31.8-1, Rev. 0 REQUIRED TASK JOB PERFORMANCE SIRO SAFETY CONSIDERATIONS 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. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: 1 Whenever any electrical panel is opened for inspection during JPM performance. 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. 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. 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. REFERENCES ES-134-001, Restoring Drywell Cooling With A LOCA Signal Present (Rev. 17) III. OPERATIONAL ACTIVITIES This JPM satisfies the requirements of Operational IV. TASK CONDITIONS An A TWS has occurred coincident with a loss of drywell cooling. EO-1 00-113 is being implemented for leveVpower control. EO-1 00-1 03 is being executed for primary containment control. ES-134-001 is being implemented and is complete through Step 4.2. CIG 90 # header has been restored. MSIVs have been opened lAW ES-184-002, REOPENING MSIVS BYPASSING ISOLATIONS. INITIATING CUE Reset Drywell Cooling LogiC isolations and restore Drywell Cooling in accordance VI. TASK STANDARD Drywell Cooling Logic isolations reset and Drywell cooling restored.

VII. TASK SAFETY SIGNIFICANCE Re-establish containment cooling. Form NTP-QA-31.S-1, Rev. 0

.",,) ) 'III PERFORMANCE CHECKLIST Page 3 of 9 Appl. To/JPM No.: SIRO 34.EO.1619.151 Student Name: __________ Step Action EVALUATOR NOTE

• This JPM must be performed on the simulator.

• Load a Mode 1 IC.

• Set up simulator according to the task conditions.

• Place the simulator in Freeze. Standard Eval Comments Setup was snapped to IC-392 for LOC-23 NRC Exam. Consider snapping an IC for multiple performances of this JPM. When student is ready to begin JPM, place the simulator in RUN. The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. Fill out and approve for use a blank copy of 134-001 up to step 4.3; Initial as SS, steps 4.1: the three bullets and 4.3. Check off Section 4.2 as complete.

PROVIDE THIS TO THE STUDENT FOR USE IN COMPLETING THE TASK. 1. Obtain a controlled copy of ES-134-001, RESTORING DRYWELL COOLING WITH A LOCA SIGNAL PRESENT. Student obtains Controlled copy. 2. Review Sections 1.0 through 3.0.

• Section 1,2,3 reviewed . Student review Sections 1.0 through 3.0. *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0

---

, ) PERFORMANCE CHECKLIST Page 4 of 9 App\. To/JPM No.: SIRO 34.EO.1619.1S1 Student Name: __________ Step Action 3. Check for approval in Section 4.1.

• Approval verified.

4. Verify step 4.2 is marked as complete

• Step 4.2 verified completed.

5. Selects the correct section to perform.

• Goes to Section 4.3. NOTE Steps 4.3.1.a through d are performed at Panel 1 C681. Heat and Ventilation Control Panel. FAULT STATEMENT B CLRS CLG WTR OB ISO VLVS HV-18781B1 and HV-18781B2 did not automatically close. Student should recognize this condition and place the Control Switch for B CLRS CLG WTR OB ISO VLVS HV-18781B1 and HV-18781B2 to Close. (this will close the valves). Student may elect to place the control switches to "CLOSE" for all the valves listed in step 6 below. If the student places these switches to "CLOSE", then it will be "Critical" that they place all of the control switches back to "OPEN" in step 17 of this JPM. At a minimum, the Control Switch for B CLRS CLG WTR OB ISO VLVS HV-18781B1 and HV-18781B2 must be taken to Open in step 17. Standard Eval Comments Student verifies Shift Manager approval at step 4.1. Student verifies step 4.2 is marked as complete.

Student selects section 4.3. *Critical Step #Critical Sequence Form Rev. 0 J PERFORMANCE Page 5 of 9 Appl. To/JPM No.: S/RO 34.EO.1619.151 Action Ensure the following valves are closed prior resetting isolation A ClRS ClG WTR DB ISO VlVS HV-18781A1 and HV-18781A2.

• Amber light LIT and red light NOT LIT A ClRS ClG WTR IB ISO VlVS HV-18782B1 and HV*18782B2.

• Amber light LIT and red light NOT LIT *B ClRS ClG WTR DB ISO VlVS HV-18781B1 and HV-18781B2. Initially:

Amber light NOT LIT and red light LIT Switch to Close : Amber light LIT and red light NOT LIT 8 ClRS ClG WTR 18 ISO VlVS HV-18782A1 and HV-18782A2.

• Amber light LIT and red light NOT LIT If Containment Instrument Gas has not been restored by ES-1B4-002.

Ensure the following are closed at Panel 1 C601 prior to resetting isolation logic: INSTR GAS TO CONTN ISO SV-12651.

INSTR GAS CMP IB SUCT ISO HV-12603.

INSTR GAS CMP OB SUCT ISO SV-12605. N/A Student Name: __________

_

Eval Student verifies position of the following valves: A ClRS ClG WTR DB ISO Vl VS HV-18781A1 and HV-18781A2.

A ClRS ClG WTR IB ISO Vl VS HV-18782B1 and HV-18782B2.

B ClRS ClG WTR DB ISO Vl VS HV-1878181 and HV-18781B2. (Recognizes valves Initially Open, manually closes the valves) B ClRS ClG WTR 18 ISO Vl VS HV-18782A1 and HV-18782A2.

Based on initial conditions:

Student determines that CIG 90# header has been restored.

Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0

" " J .",j PERFORMANCE CHECKLIST Page 6 of 9 Appl. To/JPM No.: SIRO 34.EO.1619.151 Student Name: __________ Action Reset Drywell Cooling (HVAC LOCA Trip 1A and On 1 C601 momentarily Depress CHAN A DRWL CLG HS-14141A RESET pushbutton. CHAN A DRWL CLG HS-14141A RESET push button depressed. Observe CHAN A DRWL CLG RESET green ISO light extinguishes. Green light above the pushbutton NOT LIT. On 1 C601 momentarily Depress CHAN B DRWL CLG HS-14141B RESET pushbutton. CHAN B DRWL CLG HS-14141B RESET push button depressed. Observe CHAN B DRWL CLG RESET green ISO light extinguishes. Green light above the pushbutton NOT LIT. On 1 C681 Heat and Ventilation Control Panel momentarily Depress Chan A RBCW ISO VALVE POS RESET HS-14140A pushbutton. Chan A RBCW ISO VALVE POS RESET HS-14140A pushbutton depressed.

Eval Student resets A Isolation.

Student observes A Isolation reset. Student resets B Isolation.

Student observes B Isolation reset. Student resets CHAN A RBCW ISO VALVE POS HS-14140A.

Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0

, PERFORMANCE Page 7 of 9 Appl. To/JPM No.: SIRO 34.EO.1619.151 Action ObseNe Chan A RBCW ISO VALVE POS RESET white Iso light extinguishes.

• White light NOT LIT. On 1C681 Heat and Ventilation Control momentarily Depress Chan B RBCW ISO pas RESET HS-1414DB push ObseNe Chan B RBCW ISO VALVE POS RESET white Iso light extinguishes.

• White light NOT LIT. If Containment Instrument Gas has not been restored by ES-184-002, Restore CIG in accordance with section 4.4 of this procedure.

• NIA NOTE Following valves may not open if CIG header pressure is low. Drywell cooling will occur after the following steps if RBCCW is in seNice and the drywell cooling swap valves have re-aligned.

Student Name:,__________

Eval Comments Student obseNes A RBCW Isolation valve reset. Student resets CHAN B RBCW ISO VALVE POS HS-14140B.

Student obseNes B RBCW Isolation valve reset. Based on initial conditions:

Determines that CIG 90# header has been restored.

• Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 "1, ..J Page 8 of 9 Appl. To/JPM No.: S/RO Student Name: __________ Step Standard Eval Comments EVALUATOR NOTE Previously, in step 6 of this JPM, the Student may have placed the control switches to "CLOSE" for the valves listed in step 17 below. If the student placed these switches to "CLOSE", then it is "Critical" that they place the same control switches back to "OPEN" in step 17 below. At a minimum, the Control Switch for 8 CLRS CLG WTR 08 ISO VLVS HV-1878181 and HV-1878182 must be taken to Open. On 1C681 Heat and Ventilation Control Panel, Ensure Student verifies position of the following , following valves open: valves: A CLRS CLG WTR 08 ISO VLVS HV-18781A1 and A CLRS CLG WTR 08 ISO HV-18781A2.

HV-18781A1 and

• Amber light NOT LIT and red light LIT. A CLRS CLG WTR 18 ISO VLVS HV-1878281 and A CLRS CLG WTR 18 ISO HV-1878282.

HV-1878281 and

• Amber light NOT LIT and red light LIT. *8 CLRS CLG WTR 08 ISO VLVS HV-1878181 and 8 CLRS CLG WTR 08 ISO HV-18781B2.

HV-18781B1 and

• Control Switch to Open

• Amber light NOT LIT and red light LIT. 8 CLRS CLG WTR IB ISO VLVS 8 CLRS CLG WTR IB ISO VLVS HV-18782A1 HV-18782A2.

HV-18782A1 and

• Amber light NOT LIT and red light LIT. -_.... _---.... -.... -.... _.... __.. _ .... __._._._.. __ .... _ .... *Critical #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 I

..j Page 9 of 9 Appl. To/JPM No.: S/RO 34.EO.1619.151 Student Name: __________ Step Action Standard Eval Comments EV ALUATOR CUE This completes the JPM. EVALUATOR Do you have ALL your JPM exam materials?

Task Cue Sheets? Procedures?

• Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 TASK CONDITIONS An ATWS has occurred coincident with a loss of drywell cooling. EO-100-113 is being implemented for level/power control. EO-1 00-1 03 is being executed for primary containment control. ES-134-001 is being implemented and is complete through Step 4.2. CIG 90 # header has been restored. MSIVs have been opened lAW ES-184-002, REOPENING MSIVS BYPASSING ISOLA liONS. INITIATING CUE Reset Drywell Cooling Logic isolations and restore Drywell Cooling in accordance with 134-001. 1 of 2 TASK CONDITIONS An ATWS has occurred coincident with a loss of drywell cooling. EO-1 00-113 is being implemented for level/power control. EO-1 00-1 03 is being executed for primary containment control. ES-134-001 is being implemented and is complete through Step 4.2. CIG 90 # header has been restored. MSIVs have been opened lAW ES-184-002, REOPENING MSIVS BYPASSING ISOLATIONS.

INITIATING CUE Reset Drywell Cooling Logic isolations and restore Drywell Cooling in accordance with 134-001. 2 of 2 SIRO 04.0N.1203.251 Appl. JPM Number To JOB PERFORMANCE APPROVAL AND ADMINISTRATIVE DATA o 11/22110 262001 Rev. Date NUREG 1123 No. Sys. No. Task Title: Energize "Dead" 4KV ESS Bus '20' (Alternate Path) Completed By: Bob Pudish Writer 11/22110 Date Approval:

A2.07 KIA No. 3.0/3.2 KIA Imp.

/ 15 Date of Performance:

Validation Time (Min.) Time Taken (Min.) ..IPM Performed By: Student Name:

Last First M.1. Employee # I S.S. # Performance ( Satisfactory (

Evaluator Signature Typed or Printed Comments:

FORM NTP-QA-31.8-1, Rev. 0 REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SIRO 04.0N.1203.251 I. SAFETY 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. All applicable safety precautions shall be taken in accordance with established PPL safety pOlicies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. 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. 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. 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. REFERENCES ON-004-002, Energizing Dead 4KV ESS Bus (Rev. 20) OP-024-001, Diesel Generators (Rev. 56) OP-AD-001, Operations Standards for System and Equipment Operation (Rev. 44) OPERATIONAL ACTIVrnES None TASK CONDITIONS Unit 2 is in a Shutdown Condition. An Electrical transient has occurred on the 20 ESS bus. DG 0 has failed to auto start and is in standby alignment. No electrical Bus fault is present. You are the On-Shift U2 PCOP. INITIATING CUE Implement ON-004-002 to re-energize the 20 ESS bus. TASK STANDARD ESS Bus 20 is re-energized from DG '0' iaw ON-004-002 (Energizing Dead 4KV ESS Bus) recognizing that the DG Output breaker fails to automatically close and ESW cooling water for the DG did not start. TASK SAFETY SIGNIFICANCE ESS Busses are the power supply to ECCS components necessary to mitigate Core Damage. ESW is the cooling medium for the DG to prevent component damage. FORM NTP-QA-31.8-1, Rev. 0

(

CHECKLIST Page Appl. Tol S/RO JPM No 04.0N.1203.251 Student Name Step Action This JPM must be performed in the simulator.

Setup the simulator to IC-1B. Insert the following IMF IMF IMF IMF IMF This JPM uses the following Event Trigger: aet 040N1203151 Which consists of conditions:

diHSOOO51 D.CurrValue=#OR.diHSOO051 O.RESET And linked commands:

OMF mfOG0240010 Consider snapping an IC for multiple performances of this JPM. When student is ready to begin JPM, place the simulator in RUN. The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. The simulator booth operator should role playas the NPO when required.

• Critical Step #Critical Sequence Standard DG D Fails to Start Bkr 01 Fails Asls Bkr 04 Auto Logic Fails Bkr OB Overcurrent Trip ESW Pump D Auto Logic Fails DG D Start Pushbutton Delete DG D Fails to Start Eval Comments Setup was snapped to IC-394 for LOC-23 NRC Exam. FORM NTP-QA-31.B-2, Rev. 0

---

( PERFORMANCE Page 4 of 8 Appl. Tol JPMNo 04.0N.1203.251 Student Name Action Select the correct section to perform. Confirm the normal, alternate and breakers for the dead 4KV ESS bus are Check status of following lockout relays: Determine if any relays Tripped. Do Not reset any tripped relays. If any relays Tripped: Perform Att B, Exit Att A. EVALUATOR CUE Role Playas NPO and report no lockout relays are tripped. 4.16 KV bus will shed all loads except 480 volt load centers (feeder breaker remains closed).

Eval Comments Student selects Attachment A Step 1.3. Student confirms the following breakers open:

• 2A20408 (Red light off-Amber light on)

• 2A20401 (Red light off-Amber light on)

• 2A20404 (Red light off-Amber light on) Student contacts an NPO to check the following Lockout relays not tripped: 86A-204 86A1-204 86A2-204 -*Critical Step #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0 Page 5 of 8 CHECKLIST Appl. Tol JPM No 04.0N.1203.251 Student Name Step Action 4. Ensure appropriate breakers supplied from 4.16 KV ESS Bus 20 listed on Attachment 0 are open. EVALUATOR CUE Role Playas NPO and report all breakers listed on Attachment 0 are open. Ensure OG '0' aligned for Standby operation iaw EVALUATOR CUE If necessary, role playas the Unit Supervisor and report that the OG '0' is available for manual operation. If OG failure has occurred, if possible substitute OG E for affected OG iaw OP-024-004. NlA *7. To start diesel at OC653, perform the following: Place HS-00055D DG D Gov Mode Sel switch to ISOCH. *Critical #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0 Eval Comments Student contacts an NPO to check the following breakers open: 2A20405 (Red light off-Amber light on) 2A20402 (Red light off-Amber light on) 2A20403 (Red light off-Amber light 2A20409 (Red light off-Amber light

• Student recalls from Task Conditions that OG '0' is aligned for standby operation.

NI A, DG failure has not occurred.

I Student places HS-000550 OG D Gov Mode i Sel switch in ISOCH position.

--PERFORMANCE Page 6 of 8 Appl. Tol JPM No 04.0N.1203.251 Student Name Step Standard Eval Comments To start diesel at OC653, perform the following Student ensures HS-000560 OG 0 Volt (continued):

Mode Sel switch is in Ensure HS-000560 OG 0 Volt Reg Mode switch to To start diesel at OC653, perform the following Student depresses HS-00051 0 OG 0 Start (continued):

pushbutton. Depress HS-000510 OG 0 Start pushbutton . FAULT STATEMENT THE NEXT STEP HAS THE DG OUTPUT BREAKER FAILING TO AUTO CLOSE, STUDENT SHOULD RECOGNIZE FAILURE AND MANUALLY CLOSE BREAKER. Observe OG 0 starts and OG 0 to Bus 20 Bkr Student 2A20404 automatically OG 0 volts and Hz rise to 4160V and 60 I Hz. Bkr 2A20404 did NOT close (Red light off-Amber light on). Observe white ESS Bus available light Illuminated Student observes white ESS Bus available light on mimic bus on Panel OC653. NOT Illuminated on mimic bus on _ ... _ .... _.. _ .....__ .... _ .... _.. -

_ .............

_._.............*Critical Step #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0

CHECKLIST Appl. SIRO JPM No 04.0N.1203.251 Student Name Step Standard Eval If OG 0 to Bus 20 Bkr 2A20404 did not close Student recognizes Bkr 2A20404 did NOT automatically, manually close OG 0 Output Breaker close automatically.

2A20404 onto dead 4.16KV Bus 20 as follows:

• Student ensures all synchroscope

• Ensure all synchroscope switches off on switches off on OC653. OC653. *14. Place HS-00042B OG 0 to Bus 20 Synch Student places HS-00042B OG 0 to Bus 20 Sel keyswitch to On. Synch Sel keyswitch to On. *15.

• Close OG 0 to Bus 20 Bkr Student closes OG 0 to Bus 20 Bkr 2A20404 (Red light on-amber light off). 16. Observe voltage on 4.16KV Bus 20. Student observes voltage on 4.16KV Bus 20.

• Observe white ESS Bus available light Student observes white ESS Bus available Illuminated on mimic bus on Panel OC653. Illuminated on mimic bus on Panel *18. Place HS-00042B OG 0 to Bus 20 Synch Student places HS-00042B OG 0 to Bus 20 Sel keyswitch to Off. Synch Sel keyswitch to Off. Ensure ESW supplying adequate cooling to OG iaw Student recognizes ESW Pump 0 not May inform SRO. _.-....-.... ....-.... -.... .. -.... .. -.... -...-....-.-...----_ .._._ .... Comments _ .... _._._ .... _.__.... _ ...__... *Critical Step #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0 i v

( Page 8 of 8 CHECKLIST Appl. Tol JPM No 04.0N.1203.2S1 Student Name Step Standard Eval Comments Select correct procedure I section. Student selects OP-OS4-001 Section Student may start ESW Pumps referring to OP due to auto action failing to occur. Place ESW Loop B in service by depressing ESW Student depresses ESW Pump D or B Run *22. Pump D or B Run pushbutton.

pushbutton (Red light on-Amber light off). Place ESW Loop A in service by depressing ESW Student depresses ESW Pump A or C Pump A or C Run pushbutton.

pushbutton (Red light on-Amber light As soon as possible, station Operator at DG to Student dispatches NPO to monitor monitor conditions that would cause normal shutdown of EVALUATOR CUE Role playas NPO and report conditions normal EV AlUATOR CUE This completes the JPM. EVAlUATOR Do you have ALL your JPM exam Task Cue Sheets?

J *Critical Step #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0 I TASK CONDITIONS

• Unit 2 is in a Shutdown Condition.

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

• DG D has failed to auto start and is in standby alignment.

• No electrical Bus fault is present.

• You are the On-Shift U2 PCOP. INITIATING CUE Implement ON-004-002 to re-energize the 2D ESS bus. Page 1 of 2 TASK CONDITIONS

• Unit 2 is in a Shutdown Condition.

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

• DG D has failed to auto start and is in standby alignment.

• No electrical Bus fault is present.

• You are the On-Shift U2 PCOP. INITIATING CUE Implement ON-004-002 to re-energize the 2D ESS bus. Page 2 of 2

---

PPL SUSQUEHANNA, JOB PERFORMANCE ) APPROVAL AND ADMINISTRATIVE DATA S/RO 35.0N.1662.101 o 11/22110 233000 A2.02 3.1/3.3 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task Title: Add Water to Fuel Pool via RHRSW lAW Completed By:

Bob Pudish Writer Date Instructor . er Approval:

NuT(g. Supv. Date Date of Performance:

Validation Time (Min.) Time Taken JPM Performed By: Student Last First M.1. Employee # I S.S. Performance ( ) Satisfactory Evaluator Name:

Signature Typed or Form NTP-QA-31.8-1, Rev. 0 REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SIRO 35.0N.1662.1 01 ) I. SAFETY CONSIDERATIONS All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AO-002, Standards for Shift Operations. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. 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. 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. 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 ON-135-001, Loss Fuel Pool Cooling / Coolant Inventory (Rev. 30) III. OPERATIONAL ACTIVITIES This JPM satisfies the requirements of Operational IV. TASK CONDITIONS A Seismic event has occurred. Unit 1 is in Mode 3 Unit 1 Fuel Pool inventory is lowering due to a system breach. Normal Fuel Pool makeup is unavailable. A system walkdown was unable to locate the leak, however the rate of inventory loss is not severe. The Unit 1 Fuel Pool Cooling System has been shutdown. The Cask Storage Pit Gate is closed The Unit 1 Fuel Pool has been isolated from Non-Q piping by another operator. Adding water to the fuel pool was attempted using the ESW System, but was unsuccessful. Current Unit 1 Pool level is 21' 11" down slow. V. INITIATING CUE Add water to the Unit 1 Fuel Pool via RHRSW through RHR Loop 'A' lAW ON-135-001.

VI. TASK STANDARD Water is added to Fuel Pool using the RHRSW system. VII. TASK SAFETY SIGNIFICANCE t: Maintaining Fuel Pool inventory will prevent fuel element overheating and cladding damage. Form NTP-QA-31.8-1, Rev. 0

( L PERFORMANCE Page 3 of 10 Appl. To/JPM No.: SIRO Student Name: ___Action EVALUATOR NOTE This JPM must be performed on the simulator. Insert the following malfunctions:

IMF annAR016G06 f:ALARM_ON IMF annAR016H14 f:ALARM_ON IMF annAR016H16 f:ALARM_ON IMF annAR106A17 f:ALARM_ON Insert the following remote function:

IRF rfFPl35007 f:RHR_BACKUP Insert the following lOR aoLRTRl5347 A This JPM uses the following Event Trigger: aet 350N16621 01 Which consists of conditions:

diHS11275A.CurrValue

=#OR.diHSl1275A.OPEN And linked commands:

DOR aoLRTR15347 A

• Assign the following Keys: {Key[l]} MOR aoLRTR15347A r:30:00 i:Asls f:815.75 {Key[2]} IRF rfRH149026 f:100 Place the simulator in Run, take the MIS to SID, override HPCI and RCIC, perform immediate operator actions following a scram to control FW. Place the simulator in Freeze. Consider snapping an IC for multiple performances of this JPM. When student is ready to begin JPM, place the simulator in RUN. Press {Key[l]} to begin lowering the level in the fuel pool. Standard Eval Comments Setup was snapped to IC*393 for LOC-23 NRC Exam. Turns on the annunciator for seismic. Turns on the annunciator for OC211. Turns on the annunciator for OC207. Turns on the annunciator for 1 C206. Closes suction valve to trip FPC Pps. Sets fuel pool level at 21'11". Delete FP lowering when HV112F075A is open. Start lowering level in the fuel pool. Open manual valve151070.

• Critical Step #Critical Sequence Form NTp*QA*31.8*2, Rev. 0 Page 4 of 10 CHECKLIST Appl. To/JPM No.: SIRO 35.0N.1662.101 Student Name: __________ Step Action Standard Eval Comments 1. Obtain a controlled copy of ON-135-001, Loss of Fuel Student obtains Controlled copy. Pool Cooling I Coolant Inventory.

2. Review Sections 1.0 through 3.0. Student review Sections 1 through 3.

• Sections 1 through 3 reviewed . EVALUATOR CUE If asked about Step 3.2, inform Candidate that Unit 1 is in Mode 3. If asked about Step 3.3.2, inform Candidate that TS are being complied with. I I 3. Selects the correct section to perform. Student selects section 3.6.

• Goes to Section 3.6 . *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 PERFORMANCE CHECKLIST Page 5 of 10 Appl. To/JPM No.: S/RO 35.0N.1662.101 Step Action 4. Ensure the following valves are Closed: (a) HV-151 F023 RHR Rx Head Spray Flow Cntrl Vlv.

• Amber light On, Red light Off (b) HV-151 F015A RHR Loop A Inj OB Iso Vlv.

• Amber light On, Red light Off (c) HV-151F010A RHR Loop A Cross-tie.

• Amber light Off, Red light Off (d) HV-151F010B RHR Loop B Cross-tie.

• Amber light Off, Red light Off (e) HV-11210A U1 RHRSW Hx A Inlet.

• Amber light On, Red light Off (f) HV-21210A U2 RHRSW Hx A Inlet.

• Amber light On, Red light Off EV ALUATOR CUE Role Playas Unit 2 PCOP and report valve HV-21210A is Closed. 5. Momentarily place HS-E11-1S17A LOCA Isolation Manual Override Keylock Switch to override.

• Key inserted

• Switch turned to Override *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 Student Name: __________ Standard Eval Comments Student checks valve positions.

This valve is normally closed and de-energized.

This valve is normally closed and de-energized.

Student contacts Unit 2 PCOP and asks for the position of HV-21210A.

Student overrides LOCA Iso logic.

( Page 6 of 10 Appl. To/JPM No.: SIRO 35.0N.1662.101 Student Name:,__________ Step Action 6. Observe the following: (a) LOCA Isolation Manual Override White Indicating Light Illuminated.

• White light momentarily LIT (b) LOCA Iso Switch Loop A Manual Override Annunciator Alarmed.

• Annunciator AR-109-C05 LIT (n\a) Close the following valves: *7. (a) HV-151 F048A RHR Hx Shell Side Bypass Vlv.

• Switch to Close

• Amber light LIT, Red light NOT LIT (b) HV-151 F017A RHR Loop A Injection Flow Cntrl Vlv.

• Switch to Close

• Amber light LIT, Red light NOT LIT (c) HV-151 F003A RHR Hx A Shell Side Outlet Vlv.

• Switch to Close

• Amber light LIT, Red light NOT LIT 8. Ensure the following valves Closed: (a) HV-151F016A RHR Loop A Drwl Spray OB Iso Vlv.

• Amber light LIT, Red light Not Lit (b) HV-151 F028A RHR Loop A Supp Cbr Spray Test Shutoff Vlv.

• Amber light LIT, Red light Not Lit Standard Eval Comments Student observes override condition.

No LOCA signal is present Student begins lineup. Student verifies lineup. *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0

( PERFORMANCE Page 7 of 10 Appl. To/JPM No.: S/RO Student Name: __________

_ Step Standard Eval Comments EV ALUATOR NOTE The following valves are located In-Plant.

Student will contact In-Plant Operator and direct these valves opened. Open the following valves: Student directs an In-Plant Operator open these (a) 151070 -RHR to Refuel Pool Clg and Clnup Return (RB 683' in 'B' RHR pipeway) (b) 153070A -Fuel Pool Fill Vlv from (RB 749' in FP pump & Hx room) (c) 153070B -Fuel Pool Fill Vlv from (RB 749' in FP pump & Hx room) BOOTH OPERATOR CUE Press {Key[2]} to open manual valve 151070. on P&ID Valves 153070AlB are already open. (Found on EVALUATOR CUE Role Playas In-Plant Operator and report the are If necessary, Momentarily Place HS-11202A3 RHRSW Student does not need to reset Pump A LOCA-Trip to Reset. trip logic to RHRSW

• Switch to Reset not necessary ...--.......-.......-*Critical #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 L Page 8 of 10 CHECKLIST Appl. To/JPM No.: S/RO Student Name: __________

_ Action EVALUATOR NOTE AR-109-H03 and H04 will come in when 1 P506A is started. *11. Start 1 P506A RHRSW Pump A.

• Control Switch to Start.

• Red light LIT, Amber light Not LIT *12. Open HV112F073A RHRSW Crosstie.

• Switch to Open

• Red light LIT, Amber light Not LIT *13. Open HV112F075A RHRSW Crosstie.

• Switch to Open

• Red light LIT, Amber light Not LIT Ensure HV-112F074A RHRSW/RHR Loop A Crosstie Drain Vlv Closes (Rm 1-10429-645').

EVALUATOR CUE As In-Plant operator, when asked about valve, report valve is closed.

Eval Student starts pump. Student opens HV112F073A RHRSW Crosstie.

Student opens HV112F075A RHRSW Crosstie.

Student contacts an NPO to ensure that HV-112F074A Closes. Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0

( PERFORMANCE Page 9 of 10 Appl. To/JPM No.: SIRO 35.0N.1662.101 Action NOTE The pump and valves in the next step may be cycled to maintain fuel pool level. EVALUATOR CUE Role Playas In-Plant Operator that Fuel Pool level is at the Weir overflow level. When desired fuel pool level reached, Stop adding water to fuel pool as follows: (a) Stop 1P506A RHRSW Pump A.

• Control Switch to Stop

• Amber light LIT, Red light Not LIT (b) Close HV112F075A RHRSW Crosstie.

• Switch to Close

• Amber light LIT, Red light Not LIT (c) Close HV112F073A RHRSW Crosstie.

• Switch to Close

• Amber light LIT. Red light Not LIT EVALUATOR CUE This completes the JPM. *Critical #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 Student Name: __________

Eval Comments Student secures makeup based on reports I direction.

f l PERFORMANCE CHECKLIST Page 10 of 10 Appl. To/JPM No.: S/RO 35.0N.1662.101 Student Name: __________

_ Step Action Standard Eval Comments EVALUATOR Do you have ALL your JPM exam materials? Cue Sheets?

. *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 TASK CONDITIONS A Seismic event has occurred. Unit 1 Fuel Pool inventory is lowering due to a system breach. Normal Fuel Pool makeup is unavailable. A system walkdown was unable to locate the leak, however the rate of inventory loss is not severe. The Unit 1 Fuel Pool Cooling System has been shutdown. The Cask Storage Pit Gate is closed. The Unit 1 Fuel Pool has been isolated from Non-Q piping by another operator. Adding water to the fuel pool was attempted using the ESW System, but Current Unit 1 Pool level is 21' 11" down slow. INITIATING CUE Add water to the Unit 1 Fuel Pool via RHRSW through RHR Loop 'A' lAW ON-135-001.

1 of 2 TASK CONDITIONS A Seismic event has occurred. Unit 1 Fuel Pool inventory is lowering due to a system breach. Normal Fuel Pool makeup is unavailable. A system walkdown was unable to locate the leak, however the rate of inventory loss is not severe. The Unit 1 Fuel Pool Cooling System has been shutdown. The Cask Storage Pit Gate is closed. The Unit 1 Fuel Pool has been isolated from Non*Q piping by another operator. Adding water to the fuel pool was attempted using the ESW System, but Current Unit 1 Pool level is 21' 11 U down slow. INITIATING CUE Add water to the Unit 1 Fuel Pool via RHRSW through RHR Loop 'A' lAW ON*135-001.

2 of 2 PPL SUSQUEHANNA, .) JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO Appl. To 55.0N.2000.152 JPM Number 2 Rev. No. 11/22110 Date 201003 NUREG 1123 Sys. No. A2.01 KIA No. 3.4/3.6 KIA Imp. Task Title: Completed By: Bob Pudish Writer Respond to a Stuck Control Rod lAW ON-155-001 Validated:

11/22110 Date Approval:

Date Date of Performance:

JPM Performed By: 30 Validation Time (Min.) Time Taken (Min.) Student Name:

Last First M.1. Employee # 1 S.S. # Performance Evaluation: ) Satisfactory ) Unsatisfactory Evaluator Name: Comments:

Signature Typed or Printed Form NTP-QA-31.8-1, Rev. 0 REQUIRED TASK INFORMATION ) JOB PERFORMANCE MEASURE SIRO 55.0N.2000.152 SAFETY CONSIDERATIONS 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. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. 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. 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. 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. REFERENCES ON-155-001, CONTROL ROD PROBLEMS (Rev. 34) OPERATIONAL ACTIVITIES This JPM satisfies the requirements of Operational Activity(s):

None TASK CONDITIONS Unit 1 is at 90% power. A rod pattern adjustment is scheduled. INITIATING CUE The Unit Supervisor directs you to perform the rod pattern adjustment by SINGLE NOTCH Withdrawing Rods in accordance with the reactivity manipulation request form and control rod movement sheet. The reactivity briefing for this power change has been completed. TASK STANDARD Rods 22-39 withdrawn to notch 12; Rod 3S-39 withdrawn to notch OS. TASK SAFETY SIGNIFICANCE Ability to safely add positive Reactivity with control rod motion . . Form NTP-QA-31.S-1, Rev. 0 Page 3 of 11 Appl. To/JPM No.: S/RO Student Name: __________

_ Step Action Standard Eval Comments Setup was snapped to IC-Simulator Setup for LOC-23 NRC Load MODE 1 IC-20. Exam. Place Simulator in RUN, lower power to with rods and Insert the following IMF mfRD1550063839 Ensure FWFE is on LEFM. Ensure PICYS screen is on CRDA. Clear I acknowledge all RWM alarms. Place the simulator in Freeze. Have a reactivity manipulation request form and control rod movement sheet ready. Consider snapping an IC for multiple of this The FAULTED step in this JPM is preceded by fault statement in BOLD TYPE WITH CAPITAL When student is ready to begin JPM, place the simulator in RUN . ... Critical Step # Critical Sequence Form NTP-QA-31.8-2, Rev. 0 L Page 4 of 11 Appl. To/JPM No.: SIRO Student Name: __________ Step Standard Eval Comments *1. Selects Rod for Depresses 22 -Verifies 22 and White lights -Four rod display reads notch *2. Withdraws Rod 22-39 to notch 12. Depresses WID RAW ROD Four rod display changes to notch Depresses WID RAW ROD Four rod display changes to notch Depresses W/DRAW ROD Four rod display changes to notch ! *3. Selects Rod 38-39 for Depresses Verifies 38 and White lights -Four rod display reads notch

• Critical Step # Critical Sequence Form NTP-QA-31.8-2, Rev. 0 L Page 5 of 11 f CHECKLIST Appl. To/JPM No.: S/RO 55.0N.2000.152 Step Action FAULT STATEMENT ROD 38-39 WILL NOT MOVE IN THE NEXT STEP. 4. I Withdraws Rod 38-39 to notch 12. EVALUATOR CUE Student may request permission to attempt to move rod ONE MORE time before proceeding to the Normal procedure.

IF necessary, Role-play Unit Supervisor and grant permission to attempt ONE MORE withdrawal sequence.

If necessary, Play unit supervisor and direct entry into 001. 5. Proceed to applicable section of OFF-Normal procedure ON-155-001, Control Rod Problems as indicated.

• Stuck Control Rod Step 4.3

• Rod Drift or Rod Scram Step 4.4

• Rod Overtravel Step 4.5

• Mispositioned Rod Step 4.6

• Multiple Rod Notching Step 4.7

• Slow to Settle Rod Step 4.8 Student Name: __________ Standard Eval Comments Depresses WID RAW ROD pushbutton.

Verifies:

Four rod display DID NOT CHANGE to notch 08. Determines step 4.3 is applicable based on initial conditions.

• Critical Step # Critical Sequence Form NTP-QA-31.8-2, Rev. 0 V

Page 6 of 11 Appl. To/JPM No.: S/RO 55.0N.2000.152 Action 6. IF rod position indication does not change when valid withdraw OR insert signal applied, Perform the following:

Confirm control rod position using any 3 of the available rod position indication as follows:

• CRT and SIP 4 ROD DISPLAY.

• FULL IN/FULL OUT DISPLAY push button. .007

• Alarm logging printer, System Event Display Message

• RWM Main Display when below Low Power Alarm Point. CAUTION Scramming a stuck control rod will cause damage to CRD mechanism.

7. IF rod failed to move, Attempt to move control as Complete rod data on Attachment .,. Critical Step # Critical Sequence Form NTP-QA*31.8*2, Rev. 0 Student Name: __________

Eval Comments : Uses any 3 of the following to Rod 38-39 is STILL AT NOTCH CRT and SIP 4 ROD DISPLAY. FULL INIFULL OUT DISPLAY 007 Alarm logging printer, System Display RWM Main Display when Low Power Alarm Records the following on Attachment A Date Time Rod 38-39 Reactor Pressure "S" for Stuck Position 06 -_...... __.... _------_....... _-_.-....... ....... .......-.-...... .......-.-......-.-....

Page 7 of 11 Appl. To/JPM No.: SIRO 55.0N.2000.152 Student Name:,__________ Step Action Standard Eval Comments *8. In -50 psid increments, Increase drive water Places DRIVE WTR PRESS THLTG pressure 146F003 to AND UNTIL Perform following at each increment until 350 psid DRIVE WATER DIFF PRESSURE reached: INCREASES FROM -250 TO -300 PSID. CAUTION Elevated drive pressure increases the risk multiple notch

9. Attempt to operate drive one notch in intended Depresses WIDRAW ROD pushbutton direction, authorized by procedure governing Verifies: original Control Rod motion, while observing water flows (4 gpm insertl2.5 gpm withdraw).

Full core display FOR ROD 38-39 DID CHANGE to notch AND Verifies:

DRIVE WATER FLOW FI-C12-1R604 RAISE to -2.5 gpm EVALUATOR CUE Normally, another operator would be assigned to observe drive water flows. If necessary, inform student that drive water flow was 2.5 gpm during the withdrawal attempt. ,-.....-.... ---....-.-.......-.......-....... ....

• Critical Step # Critical Sequence Form NTP-QA-31.8-2, Rev. 0 L Page 8 of 11 CHECKLIST Appl. To/JPM No.: SIRO 55.0N.2000.152 Step Action

10. If rod position does not change on 4-rod display, confirm control rod position using available rod position indications.

• 11. In -50 psid increments, Increase drive water pressure AND Perform following at each increment until $ 350 psid reached: BOOTH OPERATOR CUE Remove ROD 38-39 Stuck Rod malfunction by deleting the malfunction:

DMF mfRD1550063839 CAUTION Elevated drive pressure increases the risk of multiple notch movement.

Student Name: __________ Standard Eval Comments Uses any other available rod position indication to confirm rod 38-39 is STILL AT NOTCH 06. Places DRIVE WTR PRESS THl TG 146F003 to CLOSE UNTil DRIVE WATER DIFF PRESSURE 1R602 INCREASES FROM -300 TO 350 PSID.

• Critical Step # Critical Sequence Form NTP-QA-31.8-2, Rev. 0 I

( ( PERFORMANCE CHECKLIST Page 9 of 11 Appl. To/JPM No.: SIRO 55.0N.2000.152 Student Name:.__________ Step Action Standard Eval Comments *12. Attempt to operate drive one notch in intended Depresses WIDRAW ROD direction, authorized by procedure Verifies: original Control Rod motion, while observing water flows (4 gpm insert/2.5 gpm withdraw).

Full core display FOR ROD CHANGES to notch 08 AND Verifies:

DRIVE WATER FLOW FI-C12-1 R604 RAISE to -2.5 gpm Reports ROD 38-39 is at NOTCH OS to Unit Supervisor.

EVALUATOR CUE Normally, another operator would be assigned to observe drive water flows. If necessary, inform student that drive water flow was 2.5 gpm during the withdrawal attempt. EVALUATOR CUE Role-play Unit Supervisor and acknowledge the report and direct student to complete the ON procedure.

13. Proceeds to step 4.3.1.f. IF rod moves one notch in intended direction, to step

__ ..... -...

• Critical Step # Critical Sequence Form NTP-QA-31.S-2, Rev. 0

( PERFORMANCE CHECKLIST Page 10 of 11 Appl. To/JPM No.: SIRO 55.0N.2000.152 Student Name:.__________ Step Action Standard Eva I Comments 14. Record drive water pressure required to move Records the following on Attachment control rod on Attachment A. 350 psid drive water pressure required move control 15. Record drive water flow that is indicated while Records the following on Attachment attempting to move stuck control rod Indicated drive water flow required to move Attachment A. control rod. NOTE (1): IF control rod testing is being performed lAW TP-055-001 or TP-055-006, multiple control rod notch movement is allowed at elevated drive water pressure.

Drive water pressure must be returned to 250 psid prior to testing next control rod. NOTE (2): Multiple notch movement is permitted for control rods with identified friction (except during startup Single notch restraint).

If excessive control rod speed is observed, control rod movement must be stopped and drive pressure returned to 250 psid.

• Critical Step # Critical Sequence Form NTP-QA-31.8-2, Rev. 0 L Page 11 of 11 CHECKLIST Appl. To/JPM No.: SIRO 55.0N.2000.152 Student Name: __________ Step Action Standard Eval Comments *16. Return drive water pressure to -250 psid, for each Places DRIVE WTR PRESS THLTG PV-subsequent rod notch. Document on Attachment A. 146F003 to OPEN UNTIL DRIVE WATER DIFF PRESSURE 1R602 DECREASES TO -250 PSID AND Records the following on Attachment A: 250 psid J EVALUATOR CUE I This completes the JPM. J EVALUATOR I Do you have ALL your JPM exam materials?

Task Cue Sheets? Procedures?

... Critical Step # Critical Sequence Form NTP-QA-31.8-2, Rev. 0 TASK CONDITIONS ) A. Unit 1 is at 90% power B. A control rod pattern adjustment is scheduled.

INITIATING CUE The Unit Supervisor directs you to perform the control rod pattern adjustment by SINGLE NOTCH Withdrawing Rods in accordance with the reactivity manipulation request form and control rod movement sheet. The reactivity briefing for this power change has been completed.

Page 1 of 2

---

PPL SUSQUEHANNA, JOB PERFORMANCE APPROVAL AND ADMINISTRATIVE DATA S/RO 78.0P.3680.101 o 11/22110 215005 A2.04 3.8/3.9 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task Title: Inserting APRM Rod Block and Scram Setpoints for Single Loop Ops lAW OP-178-002 Completed By: Validated:

Bob Pudish 11/22110 Writer Date Approval:

"/o/)ko Date 10 Date of Performance:

Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name: Last First M.1. Employee # I S.S. # Performance ( ) Satisfactory Unsatisfactory Evaluation:

Evaluator Name: Signature Typed or Printed Comments:

Form NTP-QA-31.8-1, Rev. 0 REQUIRED TASK JOB PERFORMANCE SIRO I. SAFETY 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. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. 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. 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. 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. REFERENCES OP-178-002, PRNMS (Rev. 2) III. OPERATIONAL ACTIVITIES This JPM satisfies the requirements of Operational IV. TASK CONDITIONS Unit 1 has entered Single Loop Operation (SLO) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago. Condition C of TS LCO 3.4.1 is to be performed. INITIATING CUE Insert APRM Rod block and Scram Setpoints for Single Loop Operation for APRM 3 accordance with VI. TASK STANDARD SLO setpoints are inserted for APRM 3. VII. TASK SAFETY SIGNIFICANCE Correct ARPM Rod Block and Scram setpoints are required for Single Loop operation.

Form NTP-QA-31.8-1, Rev. 0

.'. ".Ii} .,J!I PERFORMANCE Page 3 of 8 Appl. To/JPM No.: S/RO Student Name: __________

_ Step Standard Eval Comments Setup was snapped to IC-393 EVALUATOR NOTE: for LOC-23 NRC Exam. This JPM must be performed on the simulator. Reset to Single Loop IC with SLO setpoints inserted Due to Simulator modeling, APRM 3 is the Module that is Place the simulator in Freeze. When student is ready to begin JPM, place simulator in 1. Obtain a controlled copy of OP-178-002, Student obtains Controlled copy. Review Pre-reqs, Precautions, Notes. Student reviews Pre-reqs, Pre-reqs, Precautions, Notes reviewed 3. Selects the correct section to Student selects section 2.5.3. Goes to Section 2.5.3 NOTE This section revises APRM trip and alarm setpoints required by Tech. Spec. for single loop operation accordance with LCO *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0

} PERFORMANCE Page 4 of 8 Appl. To/JPM No.: S/RO 78.0P.3680.101 Step Action 4. Insert APRM setpoints for SLO: (a) Establish communication with PCO. EVALUATOR CUE Role Playas PCO and inform Student coms are established.

• 5. (b) Request PCO bypass APRM to be adjusted.

• APRM Bypass Joystick to 3 position EV ALUATOR CUE Inform Student that for this JPM, he/she is responsible for bypassing the APRM. (c) Confirm at All four 214 Voters, Bypassed LEOs for bypassed APRM Illuminated.

EVALUATOR CUE Inform Student that All four 214 Voters, Bypassed LEOs for APRM 3 are Illuminated.

• Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 Student Name: __________

Eval Comments Student establishes coms with pca. Student bypasses APRM. Student acknowledges cue.

---

." PERFORMANCE Page 5 of 8 Appl. To/JPM No.: S/RO Student Name: __________

_ Step Standard Eval Comments (d) Press ETC soft key as required until Enter Set Student presses ETC soft key Mode is shown above soft key pushbutton across required until Enter Set Mode bottom of display.

• Enter Set Mode is displayed NOTE The password for entry into OPER-SET mode of the NUMAC must be entered within approximately 10 seconds or the screen will revert to the main bargraph display. *8. (e) Press Enter Set Mode soft Student presses Enter Set Mode

• Enter Set Mode soft key pressed

• Password entry display screen appears *9. (f) Enter Password "1234" and Press Student enters Password "1234" Press

• 1 2 3 4 depressed

• Ent depressed (g) Confirm Oper-Set mode indicated at APRM or Student confirms Oper-Set ODA. indicated at APRM or

• Oper-Set confirmed at either APRM or ODA --*Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 I

{.\'1i;fl f "11" ..,j PERFORMANCE Page 6 of 8 Appl. To/JPM No.: SIRO Student Name: __________ Step Standard Eval Comments (h) Select Single Loop Operation using (i U Cursor Student selects Single Loop keys to scroll. using (i.1.) Cursor Single Loop Operation selected.

• 12. (i) Press Set Parameters soft Student presses Set Parameters Set Parameter pressed m Ensure APRM indicates Set Parameters:

Single Student ensures APRM indicates Loop Operation.

Parameters:

Single Loop Set Parameters:

Single Loop (k) Change the Desired: Enabled field to YES using Student changes the Desired: the (i L) Cursor keys. field to YES using the (i L) Cursor YES displayed (I) Press Accept soft key. Student presses Accept soft key. Accept soft key pressed (m) Confirm Present Enabled field changed to YES. Student confirms Present Enabled changed to Yes displayed

-*Critical #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 I K<i:' PERFORMANCE Page 7 of 8 Appl. To/JPM No.: S/RO Student Name: __________

_ Step Standard Eval Comments 17. (n) Press Exit soft Student presses Exit soft key.

• Exit depressed (0) Press Exit Set Mode soft key. Student presses Exit Set Mode

• Exit Set Mode depressed

19. (p) Press Yes soft Student presses Yes soft key.

• Yes soft key depressed (q) Confirm the APRM display header indicated Student confirms the APRM Operate. header indicates

• Operate displayed I I (r) Confirm the APRM display header indicates SLO. Student confirms the APRM header indicates

• SLO displayed EVALUATOR CUE Steps (s), (t) and (u) have been satisfactorily by another

• 22. (v) Remove applicable APRM from Bypass. Student unbypasses APRM.

• APRM 3 Bypass Joystick taken out of Bypass *Critical #Critical Sequence Form NTP-QA-31.8-2.

Rev. 0

[;) Page 8 of 8 Appl. To/JPM No.: S/RO 78.0P.3680.101 Student Name: __________

_ Step Action Standard Eval Comments EVALUATOR CUE This completes the JPM. EVALUATOR Do you have ALL your JPM materials?

Task Cue Sheets? Procedures?

• Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 TASK CONDITIONS A. Unit 1 has entered Single Loop Operation (SLO) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago. B. Condition C of TS LCO 3.4.1 is to be performed.

INITIATING CUE Insert APRM Rod block and Scram Setpoints for Single Loop Operation for APRM 3 in accordance with OP-178-002.

Page 1 of 2 PPL SUSQUEHANNA, JOB PERFORMANCE APPROVAL AND ADMINISTRAnVE DATA SIRO 59.0N.2084.151 o 11/22110 223002 A3.02 3.5/3.5 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task Title: -38 Inch Primary Containment Isolation Verification per ON-159-002 (Alt Completed By:

Bob Pudish Writer Date Date' 7Approval: Ncar mg. SUpv. Date 15 Date of Performance:

Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name: """""'L::-a-s-t

---

=F:::-ir-st-----=M:-::-:".I.-

Employee # I S.S. # Performance Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name: Signature Typed or Printed Comments:

Form NTP-QA-31.8-1, Rev. 0 REQUIRED TASK JOB PERFORMANCE SIRO SAFETY CONSIDERATIONS All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, OPERATIONS STANDARDS FOR SHIFT OPERATIONS. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. 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. If, in the judgment of the Evaluator, any safety issue occurs during JPM performance, the JPM will be terminated until the issue is resolved. 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. REFERENCES A. ON-159-002 Containment Isolation (Rev. 29) III. OPERATIONAL ACTIVITIES This JPM satisfies the requirements of Operational TASK CONDITIONS A. The Rx is in Mode 3. B. The Safety Parameter Display System (SPDS) is out of service for maintenance.

C. A Level 2 isolation signal has been processed by the Primary Containment Isolation System. INITIATING CUE Perform Containment Isolation verification for -38 inch RPV level isolation signal in accordance with ON-159-002, Containment Isolation.

VI. TASK STANDARD Recirculation System dampers and the SGTS fan OV109A do not actuate. The dampers must be opened and the fan started. VII. TASK SAFETY SIGNIFICANCE Incomplete Containment Isolation could lead to a loss of the ability to maintain secondary containment. Form NTP-QA-31.8-1, Rev. 0 l 1 PERFORMANCE CHECKLIST Page 3 of 13 Appl. Tol JPM No 59.0N.2084.151 Student Name Action Standard Eval Comments The simulator should be set up for the Setup was snapped to IC-395 following conditions:

for LOC-23 NRC Exam. Insert the following IMF cmfAV03_HD17657A Auto Logic Fails for IMF cmfAV03_HD17602A Auto Logic Fails for IMF cmfAV03_HD17601A Auto Logic Fails for IMF cmfAV03_HD07543A Auto Logic Fails for IMF cmfPM04_0V109A Auto Logic Fails for This JPM uses the following 3 Event aet Which consists of diHS17657(02)(01 )A.CurrValue OR.diHS17657(02)(01 And linked DMF Place MIS to SID, perform immediate operator actions, stabilize plant, snap When student is ready to begin JPM, the simulator in The FAULTED step in this JPM is by a fault statement in BOLD TYPE ALL CAPITAL

1. Obtains Student executes ON-159-002. Reviews Symptoms, Alarms, Automatic

Actions,

• Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0

, V PERFORMANCE Page 4 of 13 Appl. Tol JPM No 59.0N.2084.151 Student Name Step Standard Eva I Comments As time permits, record date and time of Student records Name, date, Enters Shift Supervision name, EVALUATOR CUE If Student requests name, date, time: "John Doe, current date, current J Immediately evaluate status of Containment Student recalls SPDS Isolation using Student recalls SPDS is from Task EVALUATOR CUE If Student reports unable to perform Step 3.2, Role Playas Shift Manager and direct Student to visually ensure component by component isolation status. If -38" RPV level &!!Q 1.72# isolation signals Student recognizes

• 38" are received, Perform ... signals not NI A (both signals not received) Notify SM to refer to EP-PS-100 to determine Student informs SM to refer to if any E-Plan entry is

• Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 PERFORMANCE Page 5 of 13 Appl. Tol JPM No 59.0N.2084.151 Student Name Step Standard Eval Comments EVALUATOR CUE E-Plan will be referred to by the SM. Perform one of the following Attachments for Student selects Attachment lowest level isolation signal If -38" RPV water level isolation received, perform Attachment Student performs Attachment B EVALUATOR CUE ONCE THE STUDENT HAS ATTACHMENT B, HAND THE THE MARKED-UP COPY ATTACHMENT B IN THIS Ensure component in required isolation Student ensures component position per the following:

per Attachment Student ensures component per Attachment EVALUATOR CUE INFORM THE STUDENT ATTACHMENT B STEPS 1.1 1.48 HAVE BEEN COMPLETED, COMPONENTS WERE IN THE

• Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0

\",I PERFORMANd CHECKLIST Page 6 of 13 Appl. Tol SIRO JPM No 59.0N.2084.151 Student Name Step 8. Action Att B 1.49 TIP System Ball Valves are closed.

• 4 Green lights LIT Standard Student observes TI P System Ball Valves position.

Eval Comments FAULT STATEMENT NEXT STEP, STUDENT RECOGNIZES HD17657A FAILED TO AUTO OPEN AND MANUALLY OPENS HD17657 A. STUDENT MAY INFORM SRO AND/OR ASK FOR DIRECTION.

EVALUATOR CUE If student asks for direction, inform student to proceed using any/all station policies for observed condition.

• 9. Att B 1.50 Recirc Sys to Zone 1 Sup Sys Dmp HD17657A is open.

• Red light NOT LIT

• Amber light LIT Student recognizes HD17657A failed to auto open, places switch to OPEN position.

Student observes HD17657 A OPENS. I FAULT STATEMENT NEXT STEP, STUDENT RECOGNIZES HD17602A FAILED TO AUTO OPEN AND MANUALLY OPENS HD17602A.

STUDENT MAY INFORM SRO ANDIOR ASK FOR DIRECTION.

• Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 PERFORMANCE Page 7 of 13 Appl. Tol JPM No 59.0N.20B4.151 Student Name Action Standard Eva I EVALUATOR If student asks for direction, inform student to proceed using anylall station policies for observed condition.

• 10. Att B 1.51 Zone 1 Exh Sys to Recirc Sys Student recognizes HD17602A failed Dmp HD17602A is open. auto open, places switch to position.

Student observes

• Red light NOT LIT OPENS.

• Amber light LIT FAULT STATEMENT NEXT STEP, STUDENT HD17601 A FAILED TO AUTO OPEN MANUALLY OPENS HD17601 A. MAY INFORM SRO ANDIOR ASK EVALUATOR CUE If student asks for direction, inform student to proceed using anylall station policies for observed condition.

• 11. Att B 1.52 Zone 1 Filt Exh to Recirc Sys Dmp Student recognizes HD17601A failed HD17601A is open. auto open, places switch to position.

Student observes

• Red light NOT LIT OPENS.

• Amber light LIT ----..

• Critical Step #Critical Sequence Form Rev. 0

!!,'{" '-./ \.; PERFORMANCE Page 8 of 13 Appl. Tol JPM No 59.0N.2084.151 Student Name Step Standard Eval Comments Att B 1.53 SGTS Unit 1 Contn Burp & Purge Student observes HD17508A Iso Dmp HD17508A is

• Red light NOT LIT

• Amber light LIT Att B 1.54 RRP A Clg Wtr OB Iso Vlvs HV-Student observes HV-18791A1

& 18791A1 & HV-18791A2 are closed. 18791A2

• Red light NOT LIT

• Amber light LIT Att B 1.55 Zone 1 Exh Sys Isolation Dmp Student observes HD17576A HD17576A is

• Red light NOT LIT

• Amber light LIT Att B 1.56 Zone 1 Equip Compt Exh Sys Student observes HD17524A Dmp HD17524A is

• Red light NOT LIT

• Amber light LIT Att B 1.57 Zone 1 Sup Sys Isolation Dmp Student observes HD17586A HD17586A is

• Red light NOT LIT

• Amber light LIT Att A 1.58 Zone 3 Exh Sys Isolation Dmp Student observes HD17502A HD17502A is

• Red light NOT LIT

• Amber light LIT *Critical #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 Appl. To/ JPM No Step Action Att B 1.59 Zone 3 Filt Exh Sys Dmp HD17514A is closed.

• Red light NOT LIT

• Amber light LIT Att B 1.60 Zone 3 Sup Sys Isolation Dmp HD17564A is closed.

• Red light NOT LIT

• Amber light LIT Att B 1.61 RRP B Clg Wtr IB Iso Vlvs 18792A 1 &HV-18792A2 are closed.

• Red light NOT LIT

• Amber light LIT Att B 1.62 Recirc Sys to Zone 1 Sup Sys Dmp HD17657B is open.

• Red light LIT

• Amber light NOT LIT Att B 1.63 Zone 1 Exh Sys to Recirc Sys Dmp HD17602B is open.

• Red light LIT

• Amber light NOT LIT Att B 1.64 Zone 1 Filt Exh to Recirc Sys Dmp HD17601B is open.

• Red light LIT

• Amber light NOT LIT *Critical #Critical Sequence PERFORMANCE CHECKLIST Page 9 of 13 59.0N.2084.151 Student Name Eval Comments Student observes HD17514A position.

Student observes HD17564A position.

Student observes

&18792A2 position.

Student observes HD17657B position.

Student observes HD17602B position.

Student observes HD17601B position.

Form NTP-QA-31.8-2, Rev. 0

'; \..f PERFORMANCE Page 10 of 13 Appl. Tol JPM No 59.0N.20B4.151 Student Name Step Standard Eval Comments Att 8 1 .65 RRP 8 Clg Wtr 08 Iso Vlvs HV-Student observes HV-1879181

& 1879181 & HV-18791B2 are closed. 1879182

• Red light NOT LIT

• Amber light LIT Att B 1.66 SGTS Unit 1 Contn Burp & Purge Student observes HD17508B Iso Dmp HD17508B is

• Red light NOT LIT

• Amber light LIT Att B 1.67 Zone 1 Exh Sys Isolation Dmp Student observes HD17576B HD175768 is

• Red light NOT LIT

• Amber light LIT Att B 1.68 Zone 1 Equip Compt Exh Sys Student observes HD17524B Dmp HD17524B is

• Red light NOT LIT

• Amber light LIT Att B 1.69 Zone 1 Sup Sys Isolation Dmp Student observes HD17586B HD17586B is

• Red light NOT LIT

• Amber light LIT Att B 1.70 Zone 3 Exh Sys Isolation Dmp Student observes HD17502B HD17502B is

• Red light NOT LIT

• Amber light LIT *Critical #Critical Sequence Form NTP-QA-31.8-2.

Rev. 0 I PERFORMANCE Page 11 of 13 Appl. Tol JPM No 59.0N.2084.151 Student Name Step Standard Eval Comments Att B 1.71 Zone 3 Filt Exh Sys Dmp Student observes HD17514B HD17514B is

• Red light NOT LIT

• Amber light LIT Att B 1.72 Zone 3 Sup Sys Isolation Dmp Student observes HD17564B HD17564B is

• Red light NOT LIT

• Amber light LIT Att B 1.73 RRP A Gig Wtr IB Iso Vlvs HV-Student observes HV-18792B1

& 18792B1 & HV-18792B2 are closed. 18792B2

• Red light NOT LIT

• Amber light LIT EVALUATOR CUE INFORM STUDENT THAT ATIACHMENT B STEPS 1.74 THROUGH 1.81 ARE COMPLETED, WITH ALL COMPONENTS IN THE PROPER POSITION.

FAULT STATEMENT NEXT STEP, STUDENT HD07543A FAILED TO AUTO OPEN MANUALLY OPENS HD07543A. MAY INFORM SRO ANDIOR ASK

• Gritical #Gritical Sequence Form NTP-QA-31.8-2, Rev. 0

.J ..., PERFORMANCE Page 12 of 13 Appl. Tol JPM No 59.0N.2084.151 Student Name Step Standard Eval Comments EVALUATOR CUE If student asks for direction, inform student to proceed using any/all station policies for observed condition.

• 32. Att B 1.82 RB Recirc Sys to SGTS Dmp Student recognizes HD07543A failed HD07543A is open. auto open, places switch to position.

Student observes

• Red light NOT LIT OPENS.

• Amber light LIT FAULT STATEMENT NEXT STEP, STUDENT RECOGNIZES OV109A FAILED TO AUTO START AND MANUALLY STARTS OV109A. STUDENT MAY INFORM SRO AND/OR ASK FOR DIRECTION.

EVALUATOR CUE If student asks for direction, inform student proceed using any/all station policies observed

• 33. Att B 1.83 SGTS Fan OV109A is Student determines OV109A status incorrect and STARTS the OV109A

• Red light NOT LIT

• Amber light LIT *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0

\wi PERFORMANci Page 13 of 13 Appl. Tol JPM No 59.0N.2084.151 Student Name Action Standard Eval Comments EVALUATOR CUE This completes the JPM. EVALUATOR Do you have ALL your JPM exam Task Cue Sheets?

• Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0 TASK The Rx is in Mode 3. The Safety Parameter Display System (SPDS) is out of service for maintenance. A Level 2 isolation signal has been processed by the Primary Containment Isolation System. INITIATING CUE Perform Containment Isolation verification for -38 inch RPV level isolation signal in accordance with ON-159-002, Containment Isolation . . . " \ Page 1 of 2 PPL SUSQUEHANNA, LLC) JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIRO 24.0P.1443.051 o 11/24/10 264000 A4.04 3.7/3.7 AppL JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task Title: Manual Emergency Shutdown of Diesel Generator

'A' from Panel OC521 A (Alt Completed By:

Bob Pudish Writer Date Approval: /VI ,0./'5 (I /3 () I(i) -NU@;TlfIg,sUpv.-D-a 20 Date of Performance:

Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name: ________________________Last First M.1. Employee # I S.S. # Performance Evaluation: ( ) Satisfactory ( )

Evaluator Signature Typed or Form NTP-QA-31.8-1.

Rev. 0 REQUIRED TASK INFORMATION) JOB PERFORMANCE MEASURE SIRO 24.0P.1443.051 SAFETY CONSIDERATIONS All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP*AD-002, OPERATIONS STANDARDS FOR SHIFT OPERATIONS. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. 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. If, in the judgment of the Evaluator, any safety issue occurs during JPM performance, the JPM will be terminated until the issue is resolved. 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. REFERENCES A. OP-024-001 Diesel Generators (Rev. 56) OPERATIONAL ACTIVITIES IV* TASK A. The Rx has experienced a small Loss of Coolant Accident.

B. Drywell pressure is 2.1 psig up slow. C. All Emergency Diesel Generators (EDG) have started in Emergency Mode. D. EDG 'A' output breaker failed to close and cannot be closed. E. There is no Emergency Service Water (ESW) cooling being supplied to EDG 'A'. INITIATING CUE Perform Manual Emergency Shutdown of Diesel Generator

'A' in accordance with OP-024-001. TASK STANDARD EDG 'A' is shutdown using the Overspeed Fuel Shutdown Valve and Fuel Quadrant Lever due to Emergency Stop pushbutton failing to stop EDG 'A'. VII. TASK SAFETY SIGNIFICANCE tfP" EDG operation without cooling would lead to catastrophic failure of engine. Form NTP-QA-31.8-1, Rev. 0

) V PERFORMANCE CHECKLIST Page 3 of 9 Appl. Tol SIRO JPM No 24.0P.1443.051 Student Name Step Action Standard Eval NOTE All steps of this JPM are to be simulated.

No component manipulations are to be made. 1. Obtains OP-024-001.

Reviews Notes, Prerequisites,

• Precautions, Caution sections.

Student executes OP-024-001, Section 2.7. CAUTION LOCA auto start signal is bypassed in local mode. 2. If diesel generator running in Emergency Mode, place DG 'A' 43CM Control Mode Select Switch in Local.

• 43CM simulated in Local position Student simulates pOSitioning 43CM switch clockwise to Local. EVALUATOR CUE 43CM switch "clicks" and is simulated in the Local position.

3. At Diesel engine Control Panel OC521 A 5ES, Depress Emergency Stop pushbutton.

• Emergency Stop pushbutton simulated depressed Student simulates depressing the Emergency Stop pushbutton.

Comments *=Critical Step # =Critical Sequence Form NTP-QA-31.8-2, Rev. 0 J \wi PERFORMANCE CHECKLIST Page 4 of 9 Appl. Tol SIRO JPM No 24.0P.1443.051 Student Name Step Standard Eval Comments EVALUATOR CUE Spring resistance is felt as Emergency Stop pushbutton is depressed. Emergency Stop pushbutton "bottoms out" or stops inward motion. Emergency Stop pushbutton spring returns to full out I normal position.

FAULT STATEMENT THE NEXT STEP HAS THE STUDENT OBSERVE THE EDG STOPS. THE EVALUATOR Will CUE THE STUDENT THAT THE EOG CONTINUES TO RUN. THE STUDENT Will TAKE FURTHER ACTIONS TO SHUTDOWN THE EDG. 4. At Diesel Engine Control Panel OC521 A, Student monitors for EDG shutdown.

Observe Student determines, from

a. Master Trip Circuit Tripped Green light Cue, that EDG is still running and Illuminates continues in procedure.

b. Running Idle light Extinguishes At 280 rpm, DG 'A' Pre-Lube OP532A *= Critical Step # = Critical Sequence Form NTP-QA-31.S-2, Rev. 0

""') \wi PERFORMANCE CHECKLIST Page 5 of 9 Appl. Tal S/RO JPM No 24.0P.1443.051 Student Name Action Standard Eval EVALUATOR a. Master Trip Circuit Tripped Green light I NOT LIT I b. Running Idle light LIT c. Engine speed 600 rpm CAUnON Personnel safety must be considered proceeding with this step. Do not perform area is not EVALUATOR CUE Inform student that Maintenance is present assist in the following If the diesel engine fails to stop as expected, Student simulates pulling Obtain maintenance assistance and the Pull the black knob labeled Overspeed Fuel shutdown Vlv This knob is located on top of engine the right side by the overspeed

• SX-03483A simulated pulled * = Critical Step # = Critical Sequence Form NTP-QA-31.8-2, Rev. 0 C'l, V PERFORMANCE CHECKLIST Page 6 of 9 Appl. Tol SIRO JPM No 24.0P.1443.051 Student Name Step Standard Eval Comments EVALUATOR CUE SX-03483A is simulated pulled to end NOTE This action may cause engine overspeed alarms, similar to an actual overspeed trip of the engine. This action will NOT trip the combustion butterfly valve as it does not move the linkage. *6. b. Pull the fuel quadrant lever down and Student simulates pulling and hold until the engine comes to a Fuel quadrant complete stop. The fuel quadrant is located on the engine left side the turning gear Fuel quadrant lever simulated down and EVALUATOR CUE Fuel quadrant lever is simulated pulled to end of travel and is being held in

---

_L.-*=Critical Step # =Critical Sequence Form NTP-QA-31.8-2, Rev. 0

-) V PERFORMANCE Page 7 of 9 Appl. Tol JPM No 24.0P.1443.051 Student Name Step Action When diesel generator comes to stop, Depress Emergency Stop Reset pushbutton Emergency Stop Reset pushbutton simulated depressed EVALUATOR CUE Spring resistance felt while depressing Emergency Stop Reset pushbutton.

Pushbutton "bottomed out" and stays latched when released. Depress Reset pushbutton for Annunciator and System Reset to reset emergency trip. Reset pushbutton simulated depressed EVALUATOR CUE Spring resistance felt while depressing Reset pushbutton.

Pushbutton "bottomed out" and returned to normal when released. Observe DG A Master Trip Circuit Amber light

• Amber light simulated LIT Standard Student simulates depressing Emergency Stop Reset pushbutton.

Student simulates depressing Reset pushbutton.

Student simulates observing DG A Master Trip Circuit Reset Amber light Illuminated.

Eval Comments * =Critical Step # =Critical Sequence Form NTP-QA-31.8-2, Rev. 0

) V PERFORMANCE CHECKLIST Page 8 of 9 Appl. Tal SIRO JPM No 24.0P.1443.051 Student Name Action Standard Eval EVALUATOR Amber light is lit. 10. Observe OG A Master Trip Circuit Tripped Student simulates observing OG A Green light Master Trip Circuit Tripped Green

• Green light simulated NOT LIT I I EVALUATOR CUE Green light is not lit. 11. Comply with TS 3.8.1 for Unit 1 and Unit 2. Student simulates informing SRO of TS.

• SRO simulated informed of TS LCO I EVALUATOR CUE SRO has been informed.

12. Ensure auto initiation signal Reset. Student inquires about OW I EVALUATOR CUE High OW pressure condition still No further EOG manipulations

• = Critical Step # =Critical Sequence Form NTP-QA-31.8-2, Rev. 0 V PERFORMANCE Page 9 of 9 Appl. Tol JPM No 24.0P.1443.051 Student Name Action Standard Eval Comments EVALUATOR CUE This completes the JPM. EVALUATOR Do you have ALL your JPM exam Task Cue Sheets? *=Critical Step # =Critical Sequence Form NTP-QA-31.8-2, Rev. 0

) TASK CONDITIONS A. The Rx has experienced a small Loss of Coolant Accident.

B. Drywell pressure is 2.1 psig up slow. C. All Emergency Diesel Generators (EDG) have started in Emergency Mode. D. EDG 'A' output breaker failed to close and cannot be closed. E. There is no Emergency Service Water (ESW) cooling being supplied to EDG 'A'. INITIATING CUE Perform Manual Emergency Shutdown of Diesel Generator

'A' in accordance with OP-024-001.

Page 1 of 2 PPl SUSQUEHANNA, JOB PERFORMANCE APPROVAL AND ADMINISTRATIVE DATA S/RO 55.EO.1995.101 1 11/24/10 201003 A2.01 3.4/3.6 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task Title: Venting CRD to Insert Control Completed By:

Bob Pudish Writer Date Date ' Approval:

Nu e r ng. SUpv. Date ) Date of Performance:

Validation Time (Min.) Time Taken JPM Performed Student Name:

Last First M.1. Employee # I S.S. # Performance ) Satisfactory ( )

Evaluator Name: --::,-:____________________Signature Typed or Form NTP-QA-31.8-1, Rev. 0

) I. II. III. IV. V. VI. VII. REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 55.EO.1995.1 01 SAFETY CONSIDERATIONS 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. All applicable safety precautions shall be taken in accordance with established PPL safety poliCies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required andlor posted as being necessary. 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. 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.

REFERENCES ES-155-001 Venting CRD to Insert Control Rods (Rev. 13) EO-000-113-1, Sheet 2 (Rev. 10) OPERATIONAL ACTIVITIES NONE. T ASK CONDITIONS Unit 1 was at 100 percent power when a transient occurred. A hydraulic ATWS is in progress. All but the following seven Control Rods have been fully inserted. 1C2227; 1C2231; 1C2631; 1C2635;1C2643; 1C3031;1C3035 The CRD Hydraulic system main supply header ruptured and has been shutdown. All scram valves are open. Power to RPS bus A and B is unavailable.

G. The Unit Supervisor has authorized performance of ES-155-001.

INITIATING CUE Insert Control Rods in accordance with ES-155-001.

TASK STANDARD Control rods correctly grouped on Attachment A of ES-155-001, one control rod fully inserted lAW ES-155-001.

TASK SAFETY SIGNIFICANCE ES-155-001 provides a method of inserting the control rods using the differential pressure available between the reactor and the reactor building atmosphere.

This method is used only when all other methods for inserting control rods are unsuccessful because it is difficult, time consuming, dangerous or could cause the spread of contamination.

Form NTP-QA-31.8-1, Rev. 0 L. PERFORMANCE CHECKLIST

\., Page 3 of 12 Appl. To/JPM No.: SIRO 55.EO.1995.101 Student Name:,__________ Step EV ALUATOR NOTE Action Standard Eval Comments This JPM must be performed in the Plant. Consider signing out an HCU ES Tool Box key in advance to permit ready access during the JPM. Have a copy of ES-155-001 available for the student. 1. Obtain a controlled copy of Controlled copy obtained Obtains keys to HCU ES Tool Box. Obtains HCU ES Tool Box key from Shift Manager's office or FUS office key locker.

• Informs Evaluator how to obtain EVALUATOR NOTE Have student demonstrate ability to obtain proper key. It is not necessary to sign out the key. 3. Review the precautions and Follows all precautions as applicable.

Notes US authorization to perform procedure from Cue Sheet. * =Critical Step #:; Critical Sequence Form NTP-QA-31.8-1, Rev. 0 J PERFORMANCE Page 4 of 12 Appl. To/JPM No.: S/RO Student Name:.__________

_ Step Standard Eval Comments 4. Check Off I on Attachment A, HCU's to be Student fills out Attachment A of ES-155-001. Marks Attachment A to reflect the 7 to be 1C2227 -Group A 1C2231 -Group B 1C2631 -Group C 1C2635 -Group 0 1C2643 -Group B 1 C3031 -Group A 1 C3035 -Group B Confirmed By ... Contacts a second operator to confirm the HCU's have been identified on Attachment EVALUATOR CUE Role-play the second operator, and inform student that you confirm the HCU's to be Do not agree or disagree with Student marks. Notify HP that CROs will be vented. Uses plant page or telephone to contact HP report that CROs will be EVALUATOR CUE Role-play HP and acknowledge the report. *=Critical Step # = Critical Sequence Form NTP-QA-31.8-1, Rev. 0

) V PERFORMANCE CHECKLIST Page 5 of 12 Appl. To/JPM No.: SIRO 55.EO.1995.101 Student Name: __________ Step Action Standard Eval Comments *7. Install floor drain plug with quick disconnect fitting Locates Floor Drain. (located in ES tool Box):

• Locate Floor Drain Removes floor drain cover.

• Remove floor drain cover Removes drain plug and obstructions, if any.

• Remove drain plug and obstructions, if any

• Install threaded floor drain plug with quick disconnect fitting into floor drain. Installs threaded floor drain plug with quick disconnect fitting into floor drain.

• Connect Stainless Steel hose to floor drain quick disconnect Connects Stainless Steel hose to floor drain quick disconnect.

EVALUATOR CUE Stainless Steel hose to floor drain connected with quick disconnect, and drain plug installed with no obstructions.

8. Perform following for all HCU's checked off on Contacts control room, using plant radio, and Attachment A: reports that the first HCU is about to be vented.

• Establish AND Maintain communication with the Control Room Operator.

I EVALUATOR CUE Role-play PCO in Control Room and acknowledge communications. .......-.......-.-...............*::;: Critical Step # ::;: Critical Sequence Form NTP-QA-31.8-1, Rev. 0 PERFORMANCE CHECKLIST V Page 6 of 12 Appl. To/JPM No.: SIRO 55.EO.1995.101 Student Name: __________ Step EVALUATOR NOTE Action Standard Eval Comments 147F102 is located at top right of upper platform area above the valve bank on the line connecting to the 102 valve. 9. Refer to Attachment B for HCU's location on Reactor Building elevation 719'.

• Select the correct HCU for rod to be inserted.

Physically locates in the plant first HCUin group to be inserted.

EV ALUATOR NOTE Student should select group B for insertion first since there are three rods in the group. CAUTION Student reviews CAUTION. Potential Exists For Possible Personnel Contamination And Unisolable Primary System Leak When Removing Threaded Vent Plug (A). Ensure Proper PPE Is Worn. 10. Don appropriate PPE. At a minimum, Dons: Rubber gloves and Face Shield. -_....._ .... * = Critical Step # = Critical Sequence Form NTP-QA-31.8-1, Rev. 0

\...,-.PERFORMANCE CHECKLIST Page 7 of 12 Appl. To/JPM No.: SIRO 55.EO.1995.101 Student Name: __________ Step Action Standard Eval Comments EVALUATOR CUE After Student states PPE minimum requirement, inform Student that PPE is donned. *11. Referring to Attachment D, Remove threaded vent Attaches adjustable wrench to threaded vent plug plug (A) from top of HCU's Withdraw Line High (A) AND SLOWLY turns wrench in the counter Point Vent Valve 1 F102, to gain access to Needle clockwise (CCW) direction.

Valve operator.

Verifies NO leakage present while removing threaded vent plug (A). Removes threaded vent plug (A). EVALUATOR CUE As Student simulates removing plug, inform Student that plug is twisting in the CCW direction, NO leakage observed.

Threaded vent plug (A) is removed. 12. IF leakage is present during removal of vent plugs, N/A. Determines venting may proceed. Perform Step 4.4.7 to restore plugs. 13. Ensure Needle Valve closed. Installs high Point Vent Operator onto Needle valve I AND turns high Point Vent Operator in the Clockwise (CW) direction.

• = Critical Step # =Critical Sequence Form NTP-QA-31.8-1, Rev. 0

---

,-,.J PERFORMANCE Page 8 of 12 Appl. To/JPM No.: SIRO Student Name: __________ Step Standard Eval Comments EV ALUATOR CUE High Point Vent Operator fully clockwise and resistance is now Student reviews CAUTION. Potential Exists For Possible Personnel Contamination And Unisolable Primary System Leak When Removing Threaded Vent Plug (A). Ensure Proper PPE Is Worn. Referring to Attachment D, Cautiously Remove Attaches adjustable wrench to threaded vent plug threaded vent plug (8) from Withdraw Une High (6) AND SLOWLY turns wrench in the counter Point Vent Valve 1 F1 02. clockwise (CCW) direction.

Verifies NO leakage present while removing threaded vent plug (8). Removes threaded vent plug (6). EVALUATOR CUE Vent plug B is moving in the CCW direction.

NO leakage observed.

Threaded vent plug (8) is removed. * = Critical Step # = Critical Sequence Form NTP-QA-31.8-1, Rev. 0 L,'-..I PERFORMANCE Page 9 of 12 Appl. To/JPM No.: SIRO Student Name: __________ Step Standard Eval Comments 15. If any leakage is present, Perform following:

NlA. Determines venting may proceed. Immediately Retighten threaded vent to stop On Attachment A, Record location of with leaking 1F102 Notify following of a leak location: Health Physics. Mechanical Maintenance. IF required, Replace threaded vent plug in top of HCU Withdraw Line High Vent Valve Install quick disconnect fitting to Vent Plug (8) at Attaches quick disconnect fitting to Vent Plug (8) at Withdraw Line High Point Vent Valve 1 F1 02 Withdraw Line High Point Vent Valve 1 F1 02. (Attachment D). I EVALUATOR CUE Quick disconnect fitting A IT ACHED to Vent Plug (8) at Withdraw Line High Point Vent Valve 1 F1 02. I Connect Stainless Steel Hose to quick disconnect Attaches stainless Steel Hose to quick disconnect at Withdraw Line High Point Vent Valve 1 F1 02. at Withdraw Line High POint Vent Valve 1 F1 02. EVALUATOR CUE Stainless Steel Hose A IT ACHED to quick disconnect at Withdraw Line High Point Vent Valve 1F102. *= Critical Step # =Critical Sequence Form NTP-QA-31.8-1, Rev. 0

--PERFORMANCE Page 10 of 12 Appl. To/JPM No.: SIRO 55.EO.1995.101 Action CAUnON Fully Opening Withdraw Une High Point Vent Valve 1 F1 02 With Locking Ring Not Installed May Result In Following:

• Primary System Unisolable Leak

• Valve Damage

• Eject Needle Valve Operator Using High Point Vent Lock Ring Operator, Ensure Withdraw Une High Paint Vent Valve 1F102 locking ring installed and remains stationary.

EVALUATOR CUE Withdraw Une High Point Vent Valve 1F102 locking ring is installed and did not move. Notify Control Room Operator to observe motion and reactor power response, EVALUATOR CUE Role-play PCO in Control Room and acknowledge the request. * = Critical Step # = Critical Sequence Form NTP-QA-31.8-1 t Rev. 0 Student Name:__________

Eval Comments Student reviews CAUTION. High Point Vent Lock Ring Operator is used to ensure Withdraw Une High Point Vent Valve 1 F1 02 locking ring installed and remains stationary . Contacts control room, using plant radio, and requests PCO to observe rod motion and reactor power response.

PERFORMANCE Page 11 of 12 Appl. To/JPM No.: SIRO Student Name:__________

_ Step Standard Eval Comments Using High Point Vent Operator, Crack Open Installs High Point Vent Operator onto Needle Withdraw Line High Point Vent Valve 1 F1 valve AND SLOWLY turns High Point Operator in the Counter Clockwise EVALUATOR CUE 1 F1 02 is "cracked" open. -EVALUATOR CUE Role-play PCO in Control Room and report slow inward rod motion, THEN report rod fully inserted, rod motion stopped. When Control Room Operator communicates Installs High Point Vent Operator onto Needle inward rod motion has stopped, Close Withdraw valve AND SLOWLY turns High Point Vent Line High Point Vent Valve 1 F102 with High Point Operator in the Clockwise (CW) direction.

Vent Operator.

EVALUATOR CUE High Point Vent Operator fully clockwise. Confirm HCU vented by recording initials in Initials venting completed column on Attachment applicable space on Attachment A. for the vented

• Initials Att A * = Critical Step # = Critical Sequence Form NTP-QA-31.8-1, Rev. 0 PERFORMANCE Page 12 of 12 Appl. To/JPM No.: S/RO Student Name:,__________ Step Standard Eval Comments Remove Stainless Steel Hose from quick Removes Stainless Steel Hose from disconnect at Withdraw Line High Point Vent Valve disconnect at Withdraw Line High Point Vent 1F102. EVALUATOR CUE Stainless Steel Hose from quick disconnect at Withdraw Line High Point Vent Valve 1F102 is removed. EVALUATOR CUE This completes the JPM. EVALUATOR Do you have ALL your JPM exam materials? Cue Sheets?

-_ .... , -*=Critical Step # =Critical Sequence Form NTP-QA-31.8-1, Rev. 0 V TASK CONDITIONS A. Unit 1 was at 100 percent power when a transient occurred.

B. A hydraulic A TWS is in progress.

C. All but the following seven Control Rods have been fully inserted.

• 1C2227

• 1C2231

• 1C2631

• 1C2635

• 1C2643

• 1C3031

• 1C3035 D. The CRD Hydraulic system main supply header ruptured and has been shutdown.

E. All scram valves are open. F. Power to RPS bus A and B is unavailable.

G. The Unit Supervisor has authorized performance of ES-155-001.

INITIATING CUE Insert Control Rods in accordance with ES-155-001.

Page 1 of 2 PPL SUSQUEHANNA, JOB PERFORMANCE APPROVAL AND ADMINISTRATIVE DATA SIRO Appl. To 73.0P.2289.103 JPM Number o Rev. No. 11/24/10 Date 223001 NUREG 1123 Sys. No. A2.01 KIA No. 4.3/4.4 KIA Imp. Task Title: Completed By: Bob Pudish Writer Start a Containment H2 Recombiner in Manual lAW OP-173-001 Validated:

11/24/10 Date Date' Approval: '1Yni'i:?PI .'lUt!, N cl ar rng. Supv. Date Date of Performance:

JPM Performed By: 20 Validation Time (Min.) Time Taken (Min.) Student Name:

Last First M.1. Employee # 1 S.S. # Performance Evaluation:

Evaluator Name: Comments:

Satisfactory

-=-----------------------------.

Signature ) Unsatisfactory Typed or Printed Form NTP-QA-31.8-1, Rev. 0 REQUIRED TASK JOB PERFORMANCE SIRO 73.0P.2289.103 SAFETY CONSIDERATIONS 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. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: Whenever any electrical panel is opened for inspection during JPM performance. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required andlor posted as being necessary. 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. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check wi" be provided and Self-Checking is required. REFERENCES A. OP-173-001, CONTAINMENT ATMOSPHERE CONTROL SYSTEM (Rev. 38) OPERATIONAL TASK CONDITIONS The plant is in a post-LOCA condition 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after an event. Containment pressure is 7.0 psig, steady. Containment temperature was 135°F before the LOCA. Hi02 concentrations are below combustible limits. INITIATING Start Containment Hydrogen Recombiner 1 E440A in TASK Selected Recombiner operating manually lAW TASK SAFETY SIGNIFICANCE Recombiners are the primary means or hydrogen reduction in containment post-LOCA.

Failure to place the Recombiner(s) in service post-LOCA may result in excessive hydrogen concentrations in containment and raise the risk of containment damage due to hydrogen detonation deflagration.

Form NTP-QA-31.8-1, Rev. 0

---

)

Page 30t 10 V Appl. To/JPM No.: SIRO Student Name:,__________ Step Standard Eval Comments This JPM must be performed in the Plant. EVALUATOR NOTE Recombiner A is in the Upper Relay Room. 1. Obtain a controlled copy ot OP-173-00Controlled copy obtained.

2. Select the correct procedure section to Selects Section 2.10. Review the prerequisites I precautions.

Ensures all prerequisites have been Reviews EVALUATOR CUE Inform student that all prerequisites have 4. Ensure H2 Recombiner aligned as follows prior Student turning H2 Rcb A Heater Power Adj Control HC-15796A in counter clockwise until potentiometer Turn H2 Rcb A Heater Power Adj HC-15796A in counter clockwise until potentiometer .,. = Critical Step # = Critical Sequence Form NTP-QA-31.8-2, Rev. 0 I Page 4 of 10 L, PERFORMAN"ce"CHECKLIST Appl. To/JPM No.: SIRO Student Name: __________ Step Action Standard Eval Comments EVALUATOR CUE Control turned counter clockwise potentiometer Set H2 Rcb A Heater Power Adj Control Student sets H2 Rcb A Heater Power Adj Control

• HC-15796A to ZERO HC-15796A to ZERO (000). EVALUATOR CUE Control set to ZERO (000).

• Observe H2 RCB A Power In Available Student observes H2 RCB A Power In White light illuminated indicating MCC White light illuminated indicating MCC feeder closed EVALUATOR CUE White light illuminated indicating MCC feeder *7. To start H2 Recombiner in Manual: Student simulates placing H2 Rcb A Temp Select HSS-15796A to a) Place H2 Rcb A Temp Ctl Select to H2 Rcb A Temp Ctl Select placed to * = Critical Step # = Critical Sequence Form NTP-QA-31.8-2, Rev. 0 PERFORMANcr{HECKLIST Page50f 10 V Appl. To/JPM No.: SIRO 73.0P.2289.103 Student Name: __________ Step Action Standard Eval Comments EVALUATOR CUE Switch clicks and is in Man position. b) Place H2 Rcb A Power Out Switch HS-15796A Student simulates placing H2 Rcb A Power to ON. Switch HS-15796A placed to H2 Reb A Power Out Switch placed to EVALUATOR CUE Switch clicks and is in ON position.

Red light Determine required power setting from Student determines required power setting Attachment A. ATT A to be 56KW based on Initial 56KW is determined to be power setting -* = Critical Step # =Critical Sequence Form NTP-QA-31.8-2, Rev. 0

--)PERFORMANCE CHECKLIST Page60f 10 V Appl. To/JPM No.: S/RO 73.0P.2289.103 Student Name:,__________ Step Standard Eval Comments Student reviews NOTE. Potentiometer settings vary from recombiner to recombiner.

Initial power increase may occur at settings as low as 70 and as high as 170. The actual setting value is not important as long as proper power level is observed on the "Power Out to Heater" Wattmeter. Student reviews CAUTION. Turn H2 RCB Power Adj Control Slowly because there is a lag between Power Out Indication and potentiomenter adjustment.

Power out indication must be continuously monitored when power level is being changed. *10. Increase power out to heater as Students simulates slowly adjusting H2 RCB A Heater Power Adj Control HC-15796A until H2 Rcb 1) Adjust H2 RCB A Heater Power Adj Control A Power Out to Heater XI-15796A indicates 5 HC-15796A until H2 Rcb A Power Out Heater XI-15796A indicates 5 H2 RCB A Heater Power Adj Control 15796A slowly adjusted in the CW until H2 Rcb A Power Out to Heater 15796A indicates 5 --------L-. * =Critical Step # =Critical Sequence Form NTP-QA-31.8-2, Rev. 0

'-) PERFORMANCt Page 7 of 10 \...t Appl. To/JPM No.: SIRO Student Name:,__________ Step Standard Eval Comments I I EVALUATOR CUE Inform Student HC-15796A is slowly turning in the CW direction.

KW indication is rising. KW indication reads 5KW. *11. 2) After 10 minutes, Adjust HC-15796A until Student simulates waiting 10 min based on XI-15796A indicates 10 Evaluator Cue then simulates slowly adjusting RCB A Heater Power Adj Control HC-15796A H2 Rcb A Power Out to Heater indicates 10 EVALUATOR CUE 10 minutes has elapsed. After Evaluator Cue, 15796A is slowly adjusted CW until XI-15796A indicates 10 KW. EVALUATOR CUE Inform Student HC-15796A is slowly turning in CW direction.

KW indication is riSing. indication reads *12. 3) After 10 minutes, Adjust HC-15796A until Student simulates waiting 10 min based on XI-15796A indicates 20 Evaluator Cue then simulates slowly adjusting RCB A Heater Power Adj Control HC-15796A H2 Rcb A Power Out to Heater indicates 20 * =Critical Step # = Critical Sequence Form NTP-QA-31.8-2, Rev. 0

CHECKLIST Page8of10 L Appl. To/JPM No.: SIRO 73.0P.2289.103 Student Name:,__________ Step Action Standard Eval Comments -EVALUATOR CUE 10 minutes has elapsed. After Evaluator Cue, 15796A is slowly adjusted CW until XI-15796A indicates 20 KW. EVALUATOR CUE Inform Student HC-15796A is slowly turning in the CW direction.

KW indication is rising. KW indication reads 20KW. *13. 4) After 5 minutes, Adjust HC-15796A until Student simulates waiting 5 min based on required power setting determined in 2.10.5.c of Evaluator Cue then simulates slowly adjusting H2 this procedure observed on XI-15796A.

RCB A Heater Power Adj Control HC-15796A until H2 Rcb A Power Out to Heater XI-15796A indicates 56 KW. EVALUATOR CUE 5 minutes has elapsed. After Evaluator Cue, 15796A is slowly adjusted CW until XI-15796A indicates 56 KW. * =Critical Step # = Critical Sequence Form NTP-QA-31.8-2, Rev. 0 L

Page 90f 10 Appl. To/JPM No.: S/RO 73.0P.2289.103 Student Name: __________ Step Action Standard Eval Comments EV ALUATOR CUE Inform Student HC-15796A is slowly turning in the CW direction.

KW indication is rising. KW indication reads 56KW. 14. Monitor temperature periodically placing H2 Rcb A Student simulates placing TSS-15796A in Temp Chan Select TSS-15796A in following while Positions

1. 1, #2, and #3. observing temperature:

(1 ) Position #1 (2) Position #2 (3) Position #3 I EVALUATOR CUE Temp Chan Select TSS-15796A clicks into position 1, temperature is rising. Temp Chan Select TSS-15796A clicks into position 2, temperature is rising. Temp Chan Select TSS-15796A clicks into position 3, temperature is rising. * =Critical Step # =Critical Sequence Form NTP-QA-31.8-2, Rev. 0

---

Page 10 of 10 l.,... Appl. To/JPM No.: SIRO Student Name: __________

_ Step Standard Eval Comments Adjust HC-15796A between 0 KW and calculated Student verifies TIC-15796A temperature is required power setting to maintain following:

towards 1250°F not to exceed H2 Recombiner temp -1250°F not to b) Required power setting on H2 Rcb A Power to Heater XI-15796A not to exceed EVALUATOR CUE Temperature is 1250°F steady. Inform the Student that they are relieved another Operator to monitor Rcb EVALUATOR CUE This completes the JPM. EVALUATOR Do you have ALL your JPM exam materials? Cue Sheets?

• = Critical Step # = Critical Sequence Form NTP-QA-31.8-2, Rev. 0 TASK CONDITIONS )

• The plant is in a post-LOCA condition 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after an event.

• Containment pressure is 7.0 psig, steady.

• Containment temperature was 135°F before the LOCA.

• H 2/0 2 concentrations are below combustible limits. INlrIA-nNG CUE Start Containment Hydrogen Recombiner 1 E440A in Manual. Page 1 of 2 TASK

• The plant is in a post*LOCA condition 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after an event.

• Containment pressure is 7.0 psig, steady.

• Containment temperature was 135°F before the LOCA.

• H 2/0 2 concentrations are below combustible limits. INITIATING CUE Start Containment Hydrogen Recombiner 1 E440A in Manual. Page 2 of 2 NRC Scenario Kt£Mlj;VAM The Crew takes the shift with the Rx operating at approximately 75%. Activities for the shift are to secure RHR Suppression Pool cooling and return the Rx to Full Power. After the Suppression Pool cooling lineup is secured, the Crew will begin raising Rx Power. During the power ascension the Crew will recognize that the Control Valves begin to oscillate.

The Crew will enter ON-193-001 (Turbine EHC System Malfunction).

The Off Normal procedure directs Rx power to be lowered and Load Limit Set reduced to transfer the oscillations to the Bypass Valves. '\ Once plant parameters have stabilized, Reactor Building Closed Cooling Water (RBCCW) pump 'A' trips and RBCCW pump :B' fails to automatically start. The Crew will enter ON-114-001 (Loss ofRBCCW) and manually start the 'B' pump. -After RBCCW is restored and system parameters are stable, the Standby Liquid Control Injection Valve, HV -148-F006, comes "off' its Full Open seat. This will result in the SRO determining that two SBLC subsystems are Inoperable and enter TS 3.1.7. Once the SRO has determined TS 3.1.7 is applicable, the High Pressure Coolant Injection (HPCI) pump inadvertently starts and injects into the RPV. The Crew will enter ON-156-00l (Unanticipated Reactivity Change) and secure the HPCI pump. The SRO will consult TS 3.5.1. As the HPCI transient is being mitigated, the crew will receive a report that there is a vacuum leak coming from the Main Turbine area. The crew will enter ON-143-001 (Main Condenser Vacuum and Offgas System Off-Normal Operation) and begin a power reduction in an attempt to maintain Turbine Exhaust Pressure within limits. They will receive another report that the leak is un-isolable and perform Scram-Scram Imminent actions and attempt to Scram the Rx prior to the Main Turbine Low Vacuum trip, however, the Reactor fails to scram when the Mode Switch is placed in Shutdown .. Immediate Operator Actions ofON-lOO-101 (Scram-Scram Imminent) directs the Operator to Arm and Depress the Manual Scram pushbuttons, which also fails to Scram the Reactor, and initiate Alternate Rod Insertion (ARI). ARI results in all Rods fully inserting. 000-102 (RPV Control) will be entered and executed.

Following the Reactor Scram the Condenser Vacuum leak increases significantly, causing the Reactor Feed Pumps to trip and the Turbine Bypass Valves and Main Steam Isolation valves closing. This will force the Crew to use Safety Relief Valves (SRV) for RPV pressure control. When the first SRV is manually opened, its Tailpipe will rupture and the SRV will not close. This results in Suppression Chamber pressure, then DryweU pressure rising fairly fast (the SRV sticks open). EO-000-103 (Primary Containment Control) will be executed and the SRO will monitor the PSL Curve. The crew will initiate Suppression Chamber Sprays, then when Suppression Chamber exceeds 13 psig, they will initiate DryweU Sprays. Once Drywell Sprays are placed in service, an ESS Bus Lockout occurs, forcing the crew to utilize the other division of RHR to resume sprays. The Scenario will be terminated when DW pressure is being controlled and RPV level is in assigned band.

NRC Scenario #Spare Summary Critical Tasks Overrides HPCI and prevents uncontrolled injection. (BOP) Manually initiate ARI. (ATC) Spray the Drywell when Suppression Chamber pressure exceeds 13 psig. (BOP) Limits Drywell Spray flow to between 1000 and 2800 gpm for the first 30 seconds. (BOP) Qualitative Attributes Total Malfs (5*8): Malf> EOP (1-2): ABN Events (2-4): MAJ Events (1-2): EOPs entered (1-2): EOP Contingencies (0-2): Critical Tasks (2-3): 9 (ERC osc, RBCCW pump trip, SBLC valve, HPCI inadvertent start, Loss Condenser Vacuum, Failure Auto Scram, Failure of Scram pushbuttons, SRV tailpipe break, ESS bus Lockout) 2 (SRV tailpipe break, ESS bus 4 (ERC Malf, Loss RBCCW, HPCI start, Main Cond 1 (SRV Tailpipe rupture-PC 2 (RPV Control, PC o (None) 4 (Overrides HPCI and prevents uncontrolled injection, Manually initiate ARI, Spray the DryweU when Suppression Chamber pressure exceeds 13 psig, Limits Drywell Spray flow to between 1000 and 2800 gpm for the first 30 seconds)

NRC Scenario #Spare Summary Description Event Type Who Secure Supp Pool cool N BOP 2 Raise Rx power N SRO,ATC 3 EHC oscillation C R SRO, BOP ATC 4 RBCCW pump trip C SRO, BOP 5 SBLC inj valve C SRO 6 HPCI inadvertent start C SRO, BOP 7 Loss of Main Cond Vac R SRO,ATC 8 Failure to Scram I ATC 9 SRV tailpipe rupture \ stuck open M All 10 ESS bus Lockout C BOP Scenario # Spare Applicant "Event count" Position RX NOR IIC MAJ TS SRO 7 2 3,4,6 9 5,6 ATC 3,7 2 8 9 BOP 3,4,6,10 9 SRO (U) needs minimum total for all Scenarios of: RX: NOR: lie: MAl: TS: 0 I 2 I 2 SRO (I) needs minimum total for all Scenarios of: RX: NOR: lie: MAl: TS: 4 2 2 RO needs minimum total for all Scenarios of: RX: NOR: lie: MAl: TS: I I 4 2 0 PPL-SUSQUEHANNA,LLC LEARNING CENTER SIMULATOR SCENARIO Scenario Title: LOC23 NRC SCENARIO SPARE Scenario Duration:

90 Minutes Scenario Number: LOC23 NRC-Spare Revision/Date:

Rev. 0, 11/19/2010 Course:

......,' """,',..*...;.......'

",..,......:,: """' '.'_.__

..-....,.;.

...... :.''':

.......... ,:(,</:.'_':,'='

'_""""'.'1-,.".,....,......

',';;'<.;...;' '-'--"', ....;.......

..............

..*. ,::_:,\_,'

........... , ..............."""'}"""'.>

';:...... .*.;\1<>, :'-"""'_'

....__ *..*'."""'>..... :'-"""'/_'

11 I Prepared By: D. KellY 1 M. Jacopetti 11/19/10 Instructor Date Reviewed By: ( , Operations Training Supervisor Approved By: I SupefYising Manager/Shift Manager Form NTP-QA-31.7-1, Rev. 0, Page 1 of 15 Page 2 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 THIS PAGE IS INTENTIONALLY LEFT BLANK Form NTP-QA-31.7-1, Rev. 0, Page 2 of 15 I Page 3 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 SCENARIO The Crew takes the shift with the Rx operating at approximately 75%. Activities for the shift are to secure RHR Suppression Pool cooling and return the Rx to Full Power. After the Suppression Pool cooling lineup is secured, the Crew will begin raising Rx Power. During the power ascension the Crew will recognize that the Control Valves begin to oscillate.

The Crew will enter ON-193-001 (Turbine EHC System Malfunction).

The Off Normal procedure directs Rx power to be lowered and load Limit Set reduced to transfer the oscillations to the Bypass Valves. Once plant parameters have stabilized, Reactor Building Closed Cooling Water (RBCCW) pump 'A' trips and RBCCW pump 'B' fails to automatically start. The Crew will enter ON-114-QQ1 (loss of RBCCW) and manually start the 'B' pump. After RBCCW is restored and system parameters are stable, the Standby Liquid Control Injection Valve, HV-148-FOQ6, comes "off" its Full Open seat. This will result in the SRO determining that two SBlC subsystems are Inoperable and enter TS 3.1.7. Once the SRO has determined TS 3.1.7 is applicable, the High Pressure Coolant Injection (HPCI) pump inadvertently starts and injects into the RPV. The Crew will enter ON-156-0Q1 (Unanticipated Reactivity Change) and secure the HPCI pump. The SRO will consult TS 3.5.1. As the HPCI transient is being mitigated, the crew will receive a report that there is a vacuum leak coming from the Main Turbine area. The crew will enter ON-143-001 (Main Condenser Vacuum and Offgas System Off-Normal Operation) and begin a power reduction in an attempt to maintain Turbine Exhaust Pressure within limits. They will receive another report that the leak is un-isolable and perform Scram-Scram Imminent actions and attempt to Scram the Rx prior to the Main Turbine low Vacuum trip. however, the Reactor fails to scram when the Mode Switch is placed in Shutdown.

Immediate Operator Actions of ON-100-1Q1 (Scram-Scram Imminent) directs the Operator to Arm and Depress the Manual Scram pushbuttons, which also fails to Scram the Reactor, and initiate Alternate Rod Insertion (ARI). ARI results in all Rods fully inserting.

EO-QOO-102 (RPV Control) will be entered and executed.

Following the Reactor Scram the Condenser Vacuum leak increases significantly, causing the Reactor Feed Pumps to trip and the Turbine Bypass Valves and Main Steam Isolation valves closing. This will force the Crew to use Safety Relief Valves (SRV) for RPV pressure control. When the first SRV is manually opened, its Tailpipe will rupture and the SRV will not close. This results in Suppression Chamber pressure, then Drywell pressure rising fairly fast (the SRV sticks open). EO-OOO-1 Q3 (Primary Containment Control) will be executed and the SRO will monitor the PSl Curve. The crew will initiate Suppression Chamber Sprays, then when Suppression Chamber exceeds 13 psig, they will initiate Drywell Sprays. Once Drywell Sprays are placed in service, an ESS Bus lockout occurs, forcing the crew to utilize the other division of RHR to resume sprays. The Scenario will be terminated when OW pressure is being controlled and RPV level is in aSSigned band. Form NTP-QA-31.7-1, Rev. Q, Page 3 of 15 Page 4 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 . THIS PAGE IS INTENTIONALLY LEFT Form NTP-QA-31.7-1, Rev. 0, Page 4 of 15 Page 5 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 SCENARIO OBJECTIVES The objective of this scenario is to evaluate the Licensed Operator Candidate's ability to respond to the scenario events. These events will require each candidate to demonstrate the following:

• Knowledge of integrated plant operations

• Ability to diagnose abnormal plant conditions

• Ability to work together as a team

• Ability to mitigate plant transients that exercise their knowledge and use of ONs and EOPs

• Ability to utilize Technical Specifications (SRO Only) To meet this objective, the Licensed Operator Candidates must demonstrate proficiency in the Reactor Operator Candidates:

1. Interpret/diagnose events and conditions based on alarms, signals, and readings.

2. Comply with and use procedures, references, and Technical Specifications.

3. Operate the control boards. 4. Communicate and interact with other crew members. Senior Reactor Operator Candidates:

1. Interpret/diagnose events and conditions based on alarms, signals, and readings.

2. Comply with and use procedures and references.

3. Operate the control boards (N/A to upgrade candidates).

4. Communicate and interact with the crew and other personnel.

5. Direct shift operations.

Comply with and use Technical Specifications.

Form NTP-QA-31.7-1, Rev. 0, Page40f 15 PageS Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 THIS PAGE IS INTENTIONALLY LEFT Form NTP-QA-31.7-1.

Rev. 0, Page 5 of 15 Page 7 Scenario LOC23-NRC-Spare Rev.O.11i19/2010 CRITICAL TASKS

• Overrides HPCI and prevents uncontrolled Injection.

Safety Significance Uncontrolled HPCI injection to a critical reactor will increase core inlet subcooling resulting in a positive reactivity excursion.

Consequences of Failure to Perform the Task If injection is not stopped, reactor power will increase dramatically which could result in fuel failure. Timely response in recognizing and preventing the cold water injection will minimize the reactivity event. SSES Procedure Basis for: OP-AD-001, Operations Standards for System and Equipment Operation. STANDARDS FOR FAILURES OF PROTECTIVE FEA TURES FAILURE OF EQUIPMENT PROTECTIVE FEA TURES TO PERFORM THEIR FUNCTION 7.4. 1 Should a situation occur that requires actuation of an equipment protective feature and the protective feature has not automatically actuated, then the operator shall manually initiate the protective feature. Should a situation occur that an equipment protective feature is found disabled, then the operator shall take prompt action to either: Restore the protective feature OR b. Remove the equipment from service. STANDARDS FOR OVERRIDING SYSTEM FEA TURES 8.1 OVERRIDING EMERGENCY CORE COOLING SYSTEMS (ECCS) One of the predominant overlying causes which may result in severe damage and worsening of an event is personnel prematurely overriding automatically actuated EGCS based on erroneous plant indications.

To preclude premature shutdown of an automatically actuated ECCS function when it is still required to mitigate an incident, the following guidelines shall be used: 8. 1. 1 ECCS actuations may be throttled, stopped, prevented or inhibited under the cognizance of a Unit Supervisor or Shift Manager if any of following:

a. Directed to do so per Emergency Operating Procedure.

Form NTP-QA-31.7-1, Rev. 0, Page 5 of 15 Page 8 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010

b. Misoperation in automatic mode confirmed by at least two (2) independent indications.

c. Adequate core cooling assured by at least two (2) independent indications.

Indications/Cues for the Event Reguiring Critical Task HPCI system injecting with the reactor in Mode 1 at normal RPV level and normal Drywell pressures.

Performance Criteria Take manual control of the HPCI system and stop injection.

Performance Feedback HPCI system f/owrate decreases to zero gpm. Form NTP-QA-31.7-1, Rev. 0, Page 5 of 15 Page 9 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010 CRITICAL TASKS

• Manually initiate ARI. Safety Sianificance Control rod insertion initiates power reduction immediately Consequences for Failure to Perform Task Failure to insert control rods allows power to remain elevated with resultant power oscillations and potential core damage. Indications/Cues for Event Reauirinq Critical Task Exceeding a RPS scram setting with NO reactor scram signal, or RPS/ARI fail to fully insert all control rods. Performance Criteria Insert Control Rods by one or more of the following Maximize CRD to drift control Drive control rods after bypassing Reset and Scram again by performing ES-158-002 Bypass RPS logic De-energizing RPS solenoids by performing Local venting of Scram Air Performance Feedback Successful insertion of control rods will be indicated by: Rod position full in indication for manual insertion of control rods, venting scram air header or de-energizing RPS solenoids.

Rod position full in after resetting scram, draining scram discharge volume and re-scram.

Form NTP-QA-31.7-1, Rev. 0, Page 5 of 15 Page 10 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010

• Spray the Drywell when Suppression Chamber pressure exceeds 13 psig. Safety Significance Maintenance of primary containment integrity.

Actions are taken to spray the Drywell during a LOCA when the Suppression Chamber pressure exceeds 13 psig. From the Susquehanna Emergency Operating Procedures basis document, EO-OOO-103, "The value of 13 psig is the lowest suppression chamber pressure which can occur when 95% of the non-condensables (Nitrogen) in the drywell have been transferred to the suppression chamber." At 13 psig suppression chamber pressure, 5% of the non-condensables remain in the drywell. This 5% value is the limit established to preclude "chugging" -the cyclic condensation of steam at the downcomer openings of the drywell vents. Values in excess of 13 psig are indicative of more non-condensables in the drywell, meaning chugging is more probable.

Chugging (steam bubble collapse at the downcomer exit resulting in a water in-rush to fill the voided areas) induces stresses at the junction of the downcomers and the drywell floor. Repeated such stresses may result in failure of these joints, creating a direct bypass from drywell to suppression chamber. Bypassing the suppression pool will directly pressurize the primary containment during a LOCA may result in failure. By requiring drywell sprays at 13 psig in the suppression chamber (5% non-condensables in the drywell), a drywell non-condensable value of >1% will be maintained and chugging should not occur. From Appendix D of NUREG-1021, Draft Revision 9, the critical task listed above has essential safety action that correctly completed, will prevent "degradation of any barrier to fission product release" and the crew will take action to "effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition describe in the previous paragraph." Conseguences of Failure to Perform the Task Potential failure of primary containment.

SSES EOP Basis for: WHEN SUPP CHMBR PRESS> 13

[Directions to initiate drywell Drywell spray operation may affect the allai/ability of electrical equipment located in the drywell. Therefore, suppression chamber sprays are given the maximum time allowable to reduce primary containment pressure before operation of drywell sprays is required.

The allowable time is determined by the suppression chamber pressure which is equated to the amount of non-condensables remaining in the drywell. The value of 13 psig is the lowest suppression chamber pressure which can occur when 95% of the non-condensables (N2J in the drywell have been transferred to the suppression chamber. That is, at least 5% non-condensables remain in the drywell when suppression chamber pressure reaches 13 psig. This non-condensable concentration limit is established to preclude chugging -the cyclic condensation of steam at the downcomer openings of the drywell vents. A suppression chamber pressure greater than 13 psig could be indicative of Form NTP-QA-31.7-1, Rev. 0, Page50f 15 Page 11 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 a lower concentration of non-condensables in the drywell, thereby meaning that chugging is more probable.

Chugging occurs when a steam bubble collapses at the exit of the downcomers, the rush of water drawn into the downcomers to fill the void induces stresses at the junction of the downcomers and the drywell floor. Repeated occurrence of such stresses could cause fatigue failure of these joints, thereby creating a direct path between the drywell and suppression chamber. Steam discharged through the downcomers could then bypass the suppression pool and directly pressurize the primary containment.

Scale model tests have demonstrated that chugging will not occur so long as the drywell contains at least 1% non-condensables.

To preclude conditions under which chugging may occur, drywell sprays are conservatively required when at least 5% non-condensables remain in the drywelJ, i.e., suppression chamber pressure reaches 13 psig. Both wide range and narrow range suppression chamber pressure indication is available in the control room. Wide range suppression chamber pressure indication is available locally on Containment H2102 Analyzer Panel if analyzer is selected to suppression chamber. Indications/Cues for the Event Reguirlng Critical Task Multiple control board and control room indications of suppression chamber and drywell pressures.

Performance Criteria Start an operable RHR Perform a valve alignment to provide a flowpath for Performance Feedback RHR pump, valve and system flow indications are available.

Multiple indications of Drywell pressure dropping Form NTP-QA-31.7-1, Rev. 0, Page 5 of 15 Page 12 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010

• Limits Drywell Spray flow to between 1000 and 2800 gpm for the first 30 seconds. Safety Significance Maintenance of primary containment integrity.

Actions are taken to limit the system flowrates when first initiating drywell sprays (1000 to 2800 gpm for the first 30 seconds).

The reason for this restriction is to limit the magnitude of the drywell pressure reduction such that it will not go less than atmospheric (prevents air from being drawn in to containment) and ensures a margin to the negative design pressure of the containment.

The BWR Owners Group Emergency Operating Procedures Basis document discusses drywell spray limitations utilizing a Drywell Spray Initiation limit Curve to protect against containment damage from exceeding the design drywell to suppression chamber differential pressure.

From the Susquehanna Emergency Operating Procedures basis document, EO-OOO-103, II A drywell spray initiation limit has been developed by PPL" which provides the same protection guarantees without necessitating the use of an additional curve on the EOP flowcharts. "By limiting drywell spray flow to between 1000 and 2800 gpm for the first 30 seconds of drywell spray operation, drywell sprays can be initiated without concern" in all regions of the BWR Owners Group curve. "After 30 seconds of operation, the drywell atmosphere contains sufficient vapor to allow full drywell sprays flow." In other words, spraying the drywell within these limits will not result in a drywell pressure rapid reduction such that the differential pressure limit would be challenged.

From Appendix 0 of NUREG-1021 , Draft Revision 9, the critical task listed above has essential safety action that correctly completed, will prevent "degradation of any barrier to fission product release" and the crew will take action to "effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition describe in the previous paragraph." Consequences of Failure to Perform the Task Potential failure of primary containment.

SSES EOP Basis for: SHUT DOWN OW SHUT DOWN RECIRC INITIATE OW UNLESS PUMPS CONTINUOUSLY FOR ADEQUATE CORE LIMITING FLOW TO BETWEEN 1000 AND 2800 FOR FIRST 30 A DWSIL (Drywell Spray Initiation Limit) has been developed by PPL which provides protection against containment damage from exceeding the design differential pressure, yet does not restrict operation of the drywell sprays. By limiting drywell spray flow to between 1000 and 2800 gpm for the first 30 seconds of drywell spray operation, drywell sprays can be initiated without concern in all regions of this curve. After 30 seconds, the drywell atmosphere contains sufficient vapor to allow full drywell sprays flow. For this reason, the curve is not included.

Form NTP-QA-31.7-1, Rev. 0, Page 5 of 15 Page 13 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010 Indications/Cues for the Event Requiring Critical Task The Unit Supervisor will direct drywell sprays be initiated, limiting flow to between 1000 and 2800 gpm for the first 30 seconds. The pca will initiate drywell sprays monitoring the flowrate on available digital and analog indications on 1 C601, limiting flow to between 1000 and 2800 gpm for at least the first 30 seconds of operation before increasing flow. Performance Criteria Manually throttle HV151-F016A and B and monitor drywell spray Use clock to determine 30 seconds has elapsed Performance Feedback Monitor Drywell spray flow indications during first 30 seconds of drywell spray operation Form NTP-QA-31.7-1, Rev. 0, Page 5 of 15 Page 14 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010 , c

• THfSPAGEISINTENTIONALLY LEFT BLANK Form NTP-QA-31.7-1, Rev. 0, Page60f 15

1. OP-149-00S

2. GO-100-012

3. ON-193-001

4. ON-114-001

5. AR107-001 (003) 6. TS 3.1.7 7. ON-156-001

8. OP-152-001

9. TS 3.S.1 10. AR-121-001 (F02) 11. ON-143-001

12. ON-156-001

13. EO-100-102

14. EO-100-103 1S.0P-149-004

16. ON-183-001 Page 15 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 SCENARIO REFERENCES RHR Suppression Pool Cooling Power Maneuvers Turbine EHC System Malfunction Loss of RBCCW SBLC Injection HV-148-F006 not fully open Standby Liquid Control System Unanticipated Reactivity Change HPCI System ECCS Operating SJAE Condenser Discharge Hi Press Main Condenser Vacuum and Offgas Sys Off-Normal Operation Unanticipated Reactivity Change RPVControl Primary Containment Control RHR Containment Cooling Stuck Open Safety Relief Valve Form NTP-QA-31.7-1, Rev. 0, Page 9 of 15

Page 16 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010

! * .',0' _'. ' THIS PAGE IS INTENTIONALLY LEFT Form NTP-QA-31.7-1, Rev. 0, Page 10 of 15 Page 17 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 SCENARIO SPECIAL INSTRUC"rlONS Initialize the simulator to IC-376: Unit 1 at 75 percent power EOl, Unit 2 in Startup. load SCN file LOC23 NRC Scenario Spare Place simulator in RUN and verify the following pre-inserts and Key assignments MF RF 2:2 2:2 IMF mfRP158003 lOR diHSC72A1S03AA f:NORM lOR diHSC72A1S03BB f:DISARM lOR diHSC72A1S03CB f:DISARM lOR diHSC72A1S03DA f:NORM IMF cmfPM04_1 P21 OB OR 4:4 SCN o ET 0:0 RPS Fails To Auto Actuate RPS Manual Scram Fails " " " " " " RBCCW Pump 'B' Auto logic Fails Key[1]} IMF cmfMV08_HV151 F028A f:.0001 leak by to simulate loop Key[1]} IMF cmfMV08_HV151 F024A r:60 f:.00000001 leak by to simulate loop Key[2]} MMF cmfMV08_HV151 F028A f:O Key[2]} IMMF cmfMV08_HV151 F024A f:O Key[3]} MMF cmfMV08_HV151 F028A Key[3]} IMMF cmfMV08_HV151 F024A {Key[4]} IMF mfTC193026 f:10.0 {Key[5]} IMF mfRW114003A

{Key[6]} IMF cmfMV07_HV148F006 f:10 {Key[7]} IMF mfHP152004

{Key[8]} IMF mfMC143001 f:0.2 {Key[9]} MMF mfMC143001 1:10 f:50 {Key[10]}

IMF mfMS183010A f:100 {Key[10]}

IMF mfMS183013A f:25 {Key[11]}

IMF mfHP152015

{Key[12]}

IMF cmfRV06_PSV141F13A

{Key[13]}

IMF cmfEB01_1A201

{Key[14]}

IMF cmfEB01_1A202

{Key[15]}

IMF cmfEB01_1A203

{Key[16]}

IMF cmfEB01_1A204 Remove leak by Remove leak by Delete leak by Delete leak by EHC Steam Flow Gain Unit RBCCW Pump 'A' Trip SBel Inj Vlv Off Open Seat HPCI Inadvertent Start Main Condenser Air In leakage Increase Main Cond Air In leakage SRV 'A' Stuck Open SRV 'A' Tail Pipe Rupture HPCI Turbine trip Pull "A" SRV fuses F019 & F020 'A' Bus lockout 'B' Bus lockout 'C' Bus lockout '0' Bus Lockout ENSURE Eccentricity recorder, XR-10116, on 1C652 is displaying BPV POS and CV POS trends. Prepare a turnover sheet indicating: Unit 1 is at 75% power, following a Rod Pattern Adjustment.

Unit 2 in Startup -1 hour from synchronizing yo the grid Supp Pool Cooling is in service with RHR loop 'A' with OP-149-005 is complete up to Step 2.1.20. Shutdown Suppression Pool cooling and leave RHRSW and ESW in service per WWM's request. Once Suppression Pool Cooling is secured, commence returning Rx Power to 100% using Recirc RE directions:

raise Power iaw Form OP-AD-338-1 (1% I min from 75% to 85%, then Hold until RE verifications completed)

Form NTP-QA-31.7-1, Rev. 0, Page 11 of 15 Page 18 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010 Form NTP-QA-31.7-1, Rev. 0, Page 12 of 15 Page 19 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 SCENARIO EVENT DESCRIPTION FORM Initial Conditions:

Initialize the simulator to IC-376 Ensure the SCN File is executed per the Special Instructions Sheet. Assign Shift positions.

Direct the Crew to begin a five**minute panel walk down. EVENT TIME DESCRIPTION 1 1 min Secure Supp Pool cooling (Normal, 2 10 min I Raise Rx power (Normal, SRO, 3 20 min kc (Component, SRO, II (Reactivity, 4 35 min RBCCW pump trip (Component, SRO, 5 40 min SBlC inj valve (Component, 6 50 min HPCI inadvertent start (Component, SRO, 7 60 min loss of Main Cond Vac (Reactivity, SRO, 8 70 min Failure to Scram (Instrument, 9 75 min SRV tailpipe rupture \ stuck open (Major, 10 85 min ESS bus lockout (Component, Form NTP-QA-31.7-1, Rev. 0, Page 13 of 15 Page 20 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 SCENARIO EVENT FORM Event No: ______

______________________________________

__ Brief

Description:

Secure Suppression Pool cooling POSITION STUDENT ACTIVITIES Direct Suppression Pool cooling secured per OP-149-00S Section Direct not to secure RHRSW and ESW after RHR pump shutdown due subsequent support of scheduled RHR Surveillance Steps up to Step 2.1.20 are Enters TRO 3.8.2.1 for Motor Overload Remove Div 1 RHR from Suppression Pooling Cooling, as follows: Obtains OP-149-00S. Reviews procedure Begin at Step 2.1 .20 Informs SRO to enter TRO 3.8.2.1 Place HS-E11-1S62A to Test, Confirm BIS light Illuminates and Confirm Annunciator RHR Loop A Out of Service alarms AR109-001 (B09) Close HV-1S1-F024A by holding control switch in Close for at least 10 seconds after Amber Closed illuminates Observe HV-1S1-FOO7A opens -30 sec after 3000 gpm flow reached Stops RHR Pump 1 P202A Closes HV*151*F028A Ensures HV-151-F017A open Opens HV-151-F048A Observes RHR Pump Room Cooler stops Directs NPO to fill and vent RHR iaw OP-149-001 After 2 minutes, places HS-E11-1 S62A to Normal Confirms BIS light extinguishes Confirms Annunciator RHR Loop A Out of Service clears Directs SRO to exit TRO 3.8.2.1

• Denotes Critical Task NOTES: I Note: Special logs not maintained in Simulator Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15 Page 21 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 INSTRUCTOR ACTIVn'IES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No: __________________________________________

__ Brief

Description:

Secure Suppression Pool cooling INSTRUCTOR ACTIVITY:

When directed to fill and vent Div 1 RHR, take fallowing actions::

1. On PNOV PaneL601 A insert, monitor INLET PRESS TO HX A PI-E11-1 R606A 1. 2. Depress soft Key #1 : Key 1 IMF cmfMV08_HV151 F028A f:,OOOl Leak by to simulate loop venting Key 1 IMF cmfMV08_HV151 F024A r:60 f:.00000001 Leak by to simulate loop venting 3. When pressure drops to 150 psig, depress soft Key #2, then Key#3: Key 2 MMF cmfMV08_HV151 F028A f:O Simulate venting Key 2 MMF cmfMV08_HV151 F024A f:O Simulate venting Key 3 DMF cmfMV08_HV151 F028A Simulate venting Key 3 DMF cmfMV08.:...HV151 F024A Simulate venting ROLE PLAY: If directed as RB NPO to fill and vent RHR iaw OP-149-001 Step 2.5.3, acknowledge directions and once above actions are taken, informs control room that Div 1 RHR is filled and vented. As necessary.

Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 Page 22 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010 SCENARIO EVENT FORM Event No: 2, Brief

Description:

-'-"Ra;;;;;I;.;;;.S8.;;...;;..;R""x..;;.P...;;o-'-'w...;;e.;;.zr,...;;E;;.;;.H.;...;C'-o-'-'s;;;..;c...;.;II""la:.:;ti;.;;;.o.:..;.n

____________________POSITION STUDENT ACTIVITIES Performs Crew Brief for Rx Manip on U1 Prepares to raise Rx Power using Recirc flow. Conduct Reactivity Brief (overview, actual Brief occurred prior to Shift) Directs power raised per RE instructions and GO-1 00-012, beginning at Step 5.4 Raises Rx power by increasing Recirc flow iaw OP-164-002 (approx 1%/min), as follows: On Recirc HMI, ensure Manual Mode Selected and Manual buttons are yellow for and "B" Recirc Pumps Slowly adjust RRP 'A' and 'B' Speed Controller Demand with the (Double Chevron) INC pushbuttons as required. Observes % indications increase Observe Rx power rises Monitor Plant response. Plots position on the Power to Flow Map. Provide Peer Check of Recirc HMI operation Monitors Plant response.

Maintain Load Set at approximately 100 MWe above actual generator output by depressing Load Selector Dec:rease pushbutton and watching Load Set meter. Balance the Main Generator Manual Voltage Regulator with the auto regulator by adjusting Man Volt Reg Adjust HC-10002, as necessary

• Denotes Critical Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15 Page 23 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 INS'rRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No:

____________________________________________

__ Brief

Description:

Raise Rx Power, EHC oscillation INSTRUCTOR ACTIVITY:

None ROLE PLAY: 1. As necessary Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 Page 24 Scenario LOC23-NRC-Spare Rev. O. 11/19/2010 SCENARIO EVENT FORM Event No: __________________________________________________________

__ Brief

Description:

_E=H:.,:.C=...=o.=.sc=-:i:.:.;.lIa::.;t;;,.;io;.,;:.n=---

________________________________________

__ POSITION STUDENT ACTIVITIES Reports oscillating reactor power, level, and Reports oscillating generator Reports oscillating Turbine Control Valve Ceases raising Rx Depresses TRA Init Button on PCO desk to initiate Acknowledges ATC reports Ensures Rx power raise halted Enters ON-193-001 (Turbine EHC System Malfunction) and directs BOP to perform the ON. Contacts Work Week Manager \ I&C concerning EHC problem Enters ON-156-001 Unanticipated Reactivity Change Implements ON-193-001 Section 3.4 Reduces Reactor Power with Recirc flow by 5% with RRP "A" and "B" (Double Chevron) DEC buttons Once power is reduced 5%, adjusts EHC to transfer oscillations from the Control Valves to the Bypass Valves, by: Noting initial Load Limit Setpoint value. Decreases Load Limit Setpoint, by slowly turning it counter clockwise, until the Load Limit Limiting Light illuminates. Continues to slowly lower Load Limit Setpoint to open bypass valves enough to stop the control valve oscillations. (Note 1) Check Control Valve oscillations Stop (Note 2) Contacts WWM to have FIN investigate the cause of Control Valve oscillations and to notify the Duty Manager. (Note 3)

• Denotes Critical Task NOTES: I #1: The off-normal directs reducing load limit setpoint until one BPV is 50% open. This is not enough stop the control valve

1. 2: Crew may contact I & C to have the backup pressure regulator placed in service due to control indications showing pressure regulator oscillations.

This is caused by the scenario's EHC

1. 3: The SRO may refer to TS 3.7.8, Main Turbine Pressure Regulation System, if the crew believes ; cause of the oscillations is due to the in-service regulator.

Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15 Page 25 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No: ________________________________________________________

_ Brief

Description:

_E;;:.:H:...:.,C=-.;=.os.::.;c:;.;.iI;.;.;;18;;;.;;;tl;.;;;o,:..:n

___________________________________________

_ INSTRUCTOR ACTIVITY:

After Rx power has been raised by 3% and at Lead Instructors cue, then insert the EHC Steam Flow Fain Unit oscillations by activating soft Key 4: {Key[4]} IMF mfTC193026 f:10.0 EHC Steam Flow Gain Unit ROLE PLAY: As necessary.

When contacted as WWM concerning EHC malfunction, report "FIN has been notified and are in route to investigate." Five minutes after the above call, contact the Control Room via the PA as I&C (Delroy Artman) and say, "The Unit 1 EHC problem appears to be with the EHC Steam Flow Gain Unit, not the inservice pressure regulator.

We need to develop a work package and should be able to repair it within the hour." Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 Page 26 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010 SCENARIO EVENT FORM Event No: 4 Brief

Description:

RBCCW Pump trip POSITION TIME STUDENT ACTIVITIES BOP Report running RBCCW pump tripped and refers to AR*123-001 (E01) Report standby RBCCW pump failed to auto start Execute ON*114-001 Section 3.5 Start standby RBCCW pump ATC Report Recirc Pump 'A' Seal Clg Water La Flow AR-102-001 (F03) &(F06) Report RWCU Iso/ation Filter Inlet High Temp AR-101-001 (A01) Ensure RWCU FOO4 Isolation closes Check PICSY point NBA01 to ensure Core Thermal Power is unaffected Enter ON-114-001 Ensure standby RBCCW pump started Contact Work Week Manager concerning the trip of the "A" RBCCW Pump and failure of the standby pump to auto start. Report CIG bottle swap (AR-107-001 (C06>> Dispatch NPO to restore CIG and Crosstie Instrument Air

• Denotes Critical Task NOTES: I Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15 Page 27 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No: 4 Brief

Description:

RBCCW Pump trip INSTRUCTOR ACTIVITY:

When Pressure Regulator oscillation is complete, on Lead Evaluator cue, insert RBCCW Pump trip by activating Key #5: {Key[5]} IMF mfRW114003A RBCCW Pump 'A' Trip When contacted as the RB NPO to restore CIG and I or cross tie Instrument Air and CIG wait three minutes, and: For CIG Compressors, pull up 1 C239 PNOV and:

• Depress 1 PBCMPA\B Logic Reset pushbutton

• Depress the Flasher Reset Pushbutton To cross tie CIG and lA, Pull up P&ID pe3 on the instructor station and open 126172 (which also opens 126167) ROLE PLAY: As necessary.

When contacted as RB NPO to investigate 1 A RBCCW pump, wait three minutes and report "The Unit 1 A RBCCW Pump outboard pump bearing is extremely hot and If directed to check 18216-103, wait two minutes and report "1 B216-1 03 is If directed to check status of RWCU panel, wait two minutes and report "Both RWCU Filters are in At CIG Panel on 1 C239, report that the "Low cooling water pressure alarms are in for both (LA-1239-001, windows A04 and B04) and "I am attempting a reset at my panel" To crosstie CIG and IA: IRF rfPC125001 Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 Page 28 Scenario lOC23-NRC-Spare Rev. 0,11/19/2010 SCENARIO EVENT FORM Event No: 5 Brief

Description:

SBlC Injection Valve off open seat POSITION TIME STUDENT ACTIVITIES BOP Report Annunciator AR107-001 (003) SBLC Injection HV-148-FOO6 not fully open. SRO Acknowledge report Enter LCO 3.1.7 Condition C (Two SLC subsystems inoperable)

Required action C.1, restore one system to operable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.) Contact Work Week Manager concerning status of HV-148-FOO6

• Denotes Critical Task NOTES: I Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15 Page 29 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 INSTRUCTOR ACTIVITIES, ROLE AND INS"rRUCTOR'S PERSONAL Event No: 5 Brief

Description:

SBlC Injection Valve off open seat INSTRUCTOR ACTIVITY:

When the crew has stabilized the Plant following the RBCCW pump trip and CIG restored and on Lead Evaluator cue, insert SBLC injection valve off open seat by activating Key #6: {Key[6]} IMF cmfMV07_HV148F006 1:10 SBLC Inj Vlv Off Open Seat ROLE PLAY: When contacted as RB NPO to determine status of SLC HV-148-F006, wait two minutes, call the room via radio and state "HV-148-F006 appears to be about 10% If directed to manually open it, report "I can not engage the When contacted as the Work Week Manager concerning the SLC valve, state "I will contact Electrical and Mechanical to investigate." As necessary.

Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 Page 30 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010 SCENARIO EVENT FORM Event No: 6 Brief

Description:

HPCI inadvertent start POSITION STUDENT ACTIVITIES Reports HPCI start. Verifies adequate core cooling by two independent means and ensures Drywell pressure is < 1.72 psig Obtains SRO permission to Override HPCI Verifies no valid initiation signal Direct HPCI overridden per

• Directs BOP to enter Declares Enter TS LCO 3.5.1 Condition 0, Required Action 0.1: Verify RCIC immediately and Required Action 0.2: restore HPCI to Operable within 14 Contacts Work Week Manger concerning the HPCI injection, requests support, and notification of the Duty Executes OP-152-001 Section 2.16 or Hard Overrides HPCI and prevents uncontrolled

• Places HPCI Aux Oil Pump switch to Start Places HPCI Turbine Flow Control FC-E41-1R600 in Manual Depresses Close button to reduce discharge pressure less than RPV pressure. Ensures HPCI Min Flow to Supp Pool opens when flow < 500 gpm and discharge pressure>

125 psig Directs BOP to enter Declares HPCI

• Enter TS LCO 3.5.1 Condition 0, Required Action 0.1: Verify RCIC Operable immediately and Required Action 0.2: restore HPCI to Operable within 14 days, Contacts Work Week Manger concerning the HPCI injection, requests FIN support, and notification of the Duty Manager. Refers to ON-156-001 and determines no other reactivity control systems were responsible for the power increase.

• Denotes Critical Task NOTES: I Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15 Page 31 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No: 6 Brief

Description:

HPCllnadvertent INSTRUCTOR When SBLC issue is complete, on Lead Instructors cue, insert HPCI inadvertent start by activating Key {Key[7]} IMF mfHP152004 HPCI Inadvertent Start ROLE PLAY: When contacted as the Work Week Manager, state "I will contact FIN to investigate and notify the Duty Manager (if directed to do so)". As necessary.

Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 Page 32 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010 SCENARIO EVENT FORM Event No: 7, Brief

Description:

_L::;o::.;ss=-.;M;;.;;.;8::.;I;;.;;.;n...;;C;.;::o.::..;n,;:;,de;;;;.;;n.:;.;;s;..=e..:...r

_____________POSITION TIME STUDENT ACTIVITIES ATC/BOP Responds to page and informs crew. Dispatch NPO / FUS to investigate noise. Contacts Work Week Manager to have FIN investigate. Recognize MWe lowering, elevated Offgas Flow, and lowering Main Condenser vacuum. (Note 1) Enter ON-143-001 Main Condenser Vacuum and Offgas Sys Off-Normal, and direct BOP to perform the ON. Brief Crew on plant system response to loss of vacuum and informs them they will Scram prior to 7.5" Turbine Trip Direct Rx Power reduced iaw GO-l 00-012 to maintain Turbine Exhaust Pressure within limits of Attachment E or PICSY Display VAC Refer to ON-143-001 Att A Reduces Rx Power by depressing RRP /1:' and "B" DEC buttons on Recirc HMI in attempt to maintain Turbine Exhaust Pressure limits. On report of un-isolable vacuum leak directs Scram Imminent Actions, updates crew on Pressure \ Level strategy after MSIV closure, and directs ATC to Scram the reactor. Initiates a Manual Rx Recirc Limiter #2 Runback by touching Manual Flow Reduction Initiation, Limiter #2 48%, and then Initiate RRP Flow Reduction When directed, places Mode Switch to Shutdown Reports Failure to Scram Arms and depresses Manual Scram Pushbuttons Reports Failure to Scram Inserts SRMs and IRMs BOP Manually initiate AAI

• Arms and Depresses Div 1 and 2 HS-147103A1 and 81

• Reports ARI went to completion .

• Denotes Critical Task NOTES: J #1: Initially, the loss of vacuum will be difficult to see on PR-10502 HP/IP/LP Condenser or PI-10502 CDSA C Vacuum indications.

Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15 Page 33 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No: Brief

Description:

____________INSTRUCTOR ACTIVITY:

When HPCI injection has been addressed and TS reviewed and on Lead Instructor's cue, insert Loss of Main Condenser Vacuum by activating soft Key #8: {Key[8]} IMF mfMC143001 f:0.2 Main Condenser Air In Leakage Then, call Control Room as John Smith via the PA, and say: "I am on the U1 Turbine deck and I hear a very loud whistling noise coming from somewhere inside the area where the LP turbines are." If asked if you can see steam report that you can not. After all rods are in, increase Condenser Air Leak by activating Key #9: {Key[9]} MMF mfMC143001 i:10 f:50 Increase Main Cond Air In Leakage ROLE PLAY: When contacted as the Work Week Manager concerning the noise, state "I am dispatching FIN to investigate." Five minutes after the call to the WWM, contact the control room via the PA as Jim Paisley FIN, and report "There is a tear in the boot between the Unit 1 LP Turbine and Condenser and it is getting worse. I am leaving the area." If WWM is not contacted, then five minutes after being contacted as NPO I FUS to investigate, use the radio and make the report as noted above. As necessary.

Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 Page 34 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 SCENARIO EVENT FORM Event No:

__________________________________________________

___ Brief

Description:

Failure to Scram, SRV Tailpipe rupture-Stuck Open ,

".......,111""... STUDENT ACTIVITIES Reports all Rods Executes ON-1 00-1 Enters EO-1 00-1 02 Directs A TC to place Feedwater I Condensate in Startup Level Control. May direct BOP to close MSIVs due to lowering Condenser vacuum Directs BOP to control RPV pressure between 800-1,087 psig using SRVs. Directs BOP to reset the Main Generator Lockouts Opens "A" SRV to maintain RPV pressure in band. Recognizes and reports rapid DW pressure rise and SC pressure leading DW. Attempts to close "An SRV and reports it failed to close ers ON-183-oo1, Stuck Open SRV, and directs BOP to perform the ON. Executes ON-183-001 as follows: Places "A" SRV hand switch to Off and notes acoustic monitor light still on. With SRO permission, places N' SRV handswitch to open, then to off. Determines SRV still open Directs NPO to pull Fuses B21 C-F019 and F020 for 'A' SRV iaw ON-183-001 Att A in the URR Align FW for SULC per OP-145-001 Att A, as follows: Stop two Condensate Pumps by depressing 1 P1 02C(D)(A)(B) Ensure the "Alf RFPT realigns to Discharge Pressure Mode and "B" and C align to Idle Mode. (Note 1) Trip one of the Idle RFPTs by depressing its Trip pushbutton. (Note 1) Using the HMI display, Reset Setpoint Setdown. (Note 1) Slowly raise LlC-C32-1 R602 setpoint to 35"

• Denotes Critical Task NOTES: I #1: Due to RAPs tripping and BPVs opening, RPV level may swell to 54" and this action will not apply. Ian classification:

MA3 A TWS and ARI reduces power to < 5% Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15 Page 35 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No:

________________________________________Brief

Description:

SRV Tailpipe rupture-Stuck INSTRUCTOR When SRV 'A' is opened, fail the tailpipe and stick it open by activating Key {Key[10]}

IMF mfMS183010A f:100 SRV 'A' Stuck {Key[10]}

IMF mfMS183013A f:25 SRV 'A' Tail Pipe When \ if Operator attempts to place HPCI in Pressure Control Mode, trip HPCI by activating Key #11: {Key[11]}

IMF mfHP152015 HPCI Turbine trip When directed to pull SRV fuses, wait one minute then call the Control Room on the page and tell them you are ready to pull the fuses, then activate following Key #12: {Key[12]}

IMF cmfRV06_PSV141F13A SRV fuse F019 {Key[12]}

SRV fuse F020 ROLE PLAY: As necessary.

Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15 Page 36 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010 SCENARIO EVENT FORM Event No:

______________________________________________

__ Brief

Description:

SRV Tailpipe rupture \ stuck open -ESS Bus Lockout POSITION STUDENT ACTIVITIES Enters EO-1 00-1 03 (Primary Containment Directs BOP to initiate Suppression Chamber Directs BOP to monitor for 13 psig Supp Chamber Monitors PSL BOP Sprays Suppression Chamber iaw OP-149-OO4 Att. A, as Places HS-El1-1S17A(B) to

• Opens HV-151-F028A(B) Closes HV -15l-F017 A(B) Starts RHR Pump A or C (B or D) Throttles open HV-151-F027A(B) to maintain s500 gpm on FI-15120A(B) Places RHRSW in service iaw OP-149-004 Att A, section 4.0, as time permits. When Supp Chamber pressure>

13 psig, directs: ATC to shut down the DW Coolers and Fans ATC to shut down Reactor Recirc Pumps BOP to initiate OW Sprays, limiting flow between 1,000 and 2,800 gpm for first 30 seconds. Shutdown Recirc Pumps by depressing HSOl4001 A and Places all Drywell Cooler I Fan handswitches on 1 C68l to BOP Spray the Using OP149-004, Att Opens HV-1S1-F021A(B) Ensures both RRPs are shutdown Ensures DW Coolers and Fans are shutdown

• Throttles HV-1S1-F016A(B) to establish between 1,000 and 2,800 gpm for the first 30 seconds. [indicated on FI-15120A(B)] After 30 sec, throttles open HV-151-F016A(B) to between 9,500 and 10,000gpm Reports loss of in-service RHR Pump. Recognize loss of ESS Bus

• Denotes Critical Task NOTES: I STA SPDS is lost if 1 BESS is de-energized.

PICSY is lost if 1 CESS Bus is de-energized.

Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15 Page 37 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No:

_____________________________________________________

___ Brief

Description:

ESS Bus Lockout INSTRUCTOR ACTIVITY:

Once OW spray flow rate is -9,500 gpm, Lockout the ESS bus that supplies the RHR pump being used for OW Sprays by activating the associated Key listed below: {Key[13]}

IMF cmfEB01_1 A201; 'A' Bus Lockout if RHR pump 'A' {Key[14]}

IMF cmfEB01_1A202;

'B' Bus Lockout if RHR pump 'B' {Key[ 15]} I MF cmfEB01_1 A203; 'e' Bus Lockout If RHR pump 'C' {Key[16]}

IMF cmfEB01_1A204;

'0' Bus Lockout if RHR pump '0' ROLE PLAY: As necessary.

Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15

---

Page 38 Scenario LOC23-NRC-Spare Rev. 0, 11/19/2010 SCENARIO EVENT FORM Event No:

__Brief

Description:

SRV Tailpipe rupture \ stuck open -ESS bus Lockout continued POSITION STUDENT ACTIVITIES BOP / ATC Assesses electrical Reports 1 A(l B)(l C)(l D) ESS Bus is de-energized due to a bus

• References AR-015-oo1 (008 if "A"), (011 if "B"), (014 if "C"), or 001 (001 if "0") Dispatches NPO to check ESS Bus.* Directs BOP to restore Suppression Chamber and Drywell Sprays using the other division of RHR. (Note 1) Enters ON-1 04-201 (202)(203)(204)

• BOP Sprays Suppression Chamber iaw OP-149-004 Att. A, as Place HS-E11-1S17B(A) to

• Open HV-151-F028B(A) Close HV-151-F017B(A) Start RHR Pump B or 0 (A or C) Throttle open HV-151-F027B(A) to maintain s500 gpm on FI-15120B(A) Spray the Opens

• Throttles open HV-151-F016B(A) to between 9,500 and 10,000 gpm (Note 2) Reports OW pressure and temperature lowering.

Places RHRSW in service iaw OP-149-004 Att A, section 4.0, as time permits Secures OW spray before OW pressure drops to zero pSig by closing 151 F016B(A). Directs RPV level restored and maintained

+13 inches to +54 inches Monitors operation of LV-10641 using HMI display. Takes manual control, as necessary.

• Denotes Critical Task NOTES: I #1: US may direct initiating OW Sprays first, since Suppression Chamber Sprays were ineffective.

1. 2: It is not necessary to limit OW Spray flow during the first 30 seconds, since that was done the first time OW II Sprays were initiated.

Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15

__,_""m _______...._'_Siili._._iI>.t;."

_______

Page 39 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No: 9, Brief

Description:

c.;..;o.;..;":..;;;tl;.;.;n.;::.ue::;..:d::...-.

_______INSTRUCTOR ACTIVITY:

ROLE PLAY: As necessary.

TERMINATION CUE: The Scenario will be terminated when OW pressure is being controlled and RPV level is in assigned band. Post-scenario Instructor Activity:

After the scenario is terminated and students exit the simulator, perform the following action, as required:: If 1 BESS was de-energized, once the simulator is reset and placed in Run, restore the two selected SPOS screens. If 1 CESS Bus is de-energized, causing loss of PICSY, the simulator must be placed in Run and the remote function must be run to restore power to PICSY, PRIOR to resetting the simulator.

This remote function is located on P & 10 D816. Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 NRC Scenario #2 Summary The Crew takes the Shift with Rx power at approximately 100%. Scheduled activities for the shift are to place the Standby Turbine Building Closed Cooling Water (TBCCW) pump in service and the secure the running pump. Once TBCCW pumps are swapped, a Drywell Cooling Fan trips. The Crew will respond to the trip in accordance with the Alarm Response Procedure and consult Tech Spec 3.6.3.2. After Station Management has been infoltTIled of the DW Cooler issue, the Crew will be notified by Generation Control Center that a Minimum Generation Emergency has been declared and that a 100 MWe reduction for Unit One is requested ASAP. The Crew will reduce power iaw OI-AD-029 (Emergency Load Control) and GO-100-0l2 (Power Maneuvers).

Coincident with Min Gen Emergency, Control Power to Control Room Emergency Outside Air Supply System (CREOASS)

Fan 'A' is lost. This will result in the SRO declaring one train of CREOASS inoperable and enter TS 3.7.3. Following the Load reduction, the Hydraulic Fluid Temperature Controller for Reactor Recirc Pump 4A' Motor Generator set will fail to automatically control temperature.

This failure results in a high temperature condition and the Crew will manually restore temperature of the hydraulic fluid to the RRP MG set. Once RRP MG temps are stabilized, a loss of Extraction Steam to 4B Feedwater Heater occurs. The Crew will enter ON-147 -00 1, Loss of Feedwater Heater Extraction Steam. The Crew will lower Rx power to approximately 70% and consult MCPR LCO 3.2.2. Following the power reduction, four Control Rods will drift into the Core. This condition requires an Immediate Operator Action to Scram the Rx per OP-AD-055 and ON-15S-00l (Control Rod Problems).

The attempt to scram the Rx fails, resulting in a high power Anticipated Transient Without Scram (A TWS). The Crew will enter 000-113 (LevellPower Control).

A malfunction with the Electro-Hydraulic Control (EHC) system occurs, resulting in a Turbine Trip and a failure of the Turbine Bypass Valves to open. This will force the Crew to utilize SRVs for pressure control. Suppression Pool temperature will eventually exceed 90°F and EO-OOO-103, Primary Containment Control, will be entered. As the Crew is taking actions to mitigate the A TWS, the first Standby Liquid Control (SBLC) pump started, will trip. The Crew should recognize the pump trip and start the other SBLC pump. Additionally, the Reactor Water Cleanup (RWCU) system fails to automatically isolate when the SBLC pump is started. RWCU can be manually isolated.

Crew actions will involve lowering RPV water level and Control Rod insertion.

Actions for Control Rod insertion will be iaw EO-OOO-l13 Sheet 2. An order for Venting the Scram Air Header should be directed and when the Scram Air Header is vented, all NRC Scenario #2 Summary Control Rods fully insert. The Crew will exit EO-OOO-l13.

enter EO-OOO-1 02. RPV Control. and restore RPV water level to +13 to +54 inches. The Scenario will be terminated once all Rods are in, direction is given to restore RPV level to between 13" and 54" with Feedwater, and Suppression Pool cooling is in service. Critical Tasks Inhibits ADS (BOP) Inject SLC (BOP) Takes Action to Lower RPV level to <-60" but >-161" (ATC) Inserts control rods IA W EO-OOO-l13 Sh. 2. (ATC) Qualitative Attributes Total Malfs (5-8): 9 (DW Fan trip. CREOASS inop. RRP MG controller, loss FW heat. 4 Rods Drift, ATWS, EHC malfunction, SBLC pump trip. RWCU fails to auto isolate) Malf> EOP (1-2): 2 (SBLC pump trip, RWCU fails to auto ABN Events (2-4): 2 (Loss FW Heating, Control Rod MAl Events (1-2): EOPs entered (1-2): (Primary Containment EOP Contingencies (0-2): (Level Power

• "\ . NRC Scenario #2 Summary Critical Tasks (2-3): 4 (Inhibits ADS, Inject SLC, Takes Action to Lower RPV level to < -60" but> -161 ", Inserts control rods IA W EO-1 00-113 Sht. 2)

• NRC Scenario #2 Summary Description SwapTBCCW N SRO, BOP 2 DW Cool Fan trip C SRO 3 Min Gen Emerg N SRO,ATC 4 CREOASS inop C SRO, BOP 5 RRP MG hi temp C SRO, BOP 6 Loss FW Heating R SRO,ATC 7 4 Rods Drift C ATC 8 ATWS M All 9 EHC malfunction C 10 SBLC pump trip C BOP II RWCU fail to isolate C BOP Scenario #2 Applicant "Event count" Position RX NOR IIC MAJ TS SRO 6 1,3 2,4,5 8 2,4 ATC 6 3 7 8 BOP 4,5.10,11 8 SRO (U) needs minimum total for all Scenarios of: RX: NOR: lie: MAl: TS: 0 I 2 I 2 SRO (I) needs minimum total for all Scenarios of: RO needs minimum total for all Scenarios of: RX: NOR: lie: MAl: TS: RX: NOR: lie: MAl: TS: I I 4 2 2 I I 4 2 0

..!'Q.; ;/-""'X""" :. \/)' ". j n "1 ," ,

,... **Scenario Title: Scenario Duration:

Scenario Number: Revision/Date:

Course: . i .'Fc " Prepared By: Reviewed By: Approved By:

LEARNING SIMULATOR SCENARIO LOC23 NRC SCENARIO 2 90 Minutes LOC23 NRC-2 Rev. 0,11/1812010

... :,,:>. : .' ...*.... J .*....,. .', *... : .. .. Don Kelly 1 Mike Jacopetti 11/18/2010 Instructor Date rA ..... -C-fl'l.'"U. "/'hr:Jh 0 ( , Operations Training Supervisor Date '7.f"JUJk

! Sup#rvising Manager/Shift Manager Date Form NTP-QA-31.7-1, Rev. 0, Page 1 of 15 Page Scenario LOC23 Rev. 0, THIS PAGE IS INTENTIONALLY LEfT Form NTP-QA-31.7-1, Rev. 0, Page 2 of Page 3 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 SCENARIO

SUMMARY

The Crew takes the Shift with Rx power at approximately 100%. Scheduled activities for the shift are to place the Standby Turbine Building Closed Cooling Water (TBCCW) pump in service and the secure the running pump. Once TBCCW pumps are swapped, a Drywell Cooling Fan trips. The Crew will respond to the trip in accordance with the Alarm Response Procedure and consult Tech Spec 3.6.3.2. After Station Management has been informed of the OW Cooler issue, the Crew will be n . ledBy \ Generation Control Center that a Minimum Generation Emergency has been declared and that 100 MWe 1 reduction for Unit One is requested ASAP. The Crew will reduce power iaw OI*AD-029 (Emer ncy Load Control) and GO-100-012 (Power Maneuvers).

Coincident with Min Gen Emergency, Control Po Control Room Emergency Outside Air Supply System (CREOASS)

Fan 'A' is lost. This will result in the SRO declaring one train of CREOASS inoperable and enter TS 3.7.3. Following the load reduction, the Hydraulic Fluid Temperature Controller for Reactor Recirc Pump 'A' Motor Generator set will fail to automatically control temperature.

This failure results in a high temperature condition and the Crew will manually restore temperature of the hydraulic fluid to the RRP MG set. Once RRP MG temps are stabilized, a loss of Extraction Steam to 4B Feedwater Heater occurs. The Crew will enter ON-147-001, loss of Feedwater Heater Extraction Steam. The Crew will lower Rx power to approximately 70% and consult MCPR lCO 3.2.2. Following the power reduction, four Control Rods will drift into the Core. This condition requires an Immediate Operator Action to Scram the Rx per OP-AD-055 and ON-155-001 (Control Rod Problems).

The attempt to scram the Rx fails, resulting in a high power Anticipated Transient Without Scram (A TWS). The Crew will enter EO-OOO-113 (level/Power Control).

A malfunction with the Electro-Hydraulic Control (EHC) system occurs, resulting in a Turbine Trip and a failure of the Turbine Bypass Valves to open. This will force the Crew to utilize SRVs for pressure control. Suppression Pool temperature will eventually exceed 90°F and EO-000-103, Primary Containment Control, will be entered. As the Crew is taking actions to mitigate the ATWS, the first Standby Liquid Control (SBlC) pump started, will trip. The Crew should recognize the pump trip and start the other SBlC pump. Additionally, the Reactor Water Cleanup (RWCU) system fails to automatically isolate when the SBlC pump is started. RWCU can be manually isolated.

Crew actions will involve lowering RPV water level and Control Rod insertion.

Actions for Control Rod insertion will be iaw EO-000-113 Sheet 2. An order for Venting the Scram Air Header should be directed and when the Scram Air Header is vented, all Control Rods fully insert. The Crew will exit 000-113, enter EO-OOO-102, RPV Control, and restore RPV water level to +13 to +54 inches. The Scenario will be terminated once all Rods are in, direction is given to restore RPV level to between 13" and 54" with Feedwater, and Suppression Pool cooling is in service. Form NTP-QA-31.

7 -1, Rev. 0, Page 3 of 15 Page Scenario LOC23 Rev. 0, THIS PAGE IS INTENTIONALLY LEFT Form NTP-QA-31.7-1, Rev. 0, Page 4 of Page 5 Scenario LOC23 NRC-2 Rev. 0,11/18/2010 SCENARIO OBJECTIVES The objective of this scenario is to evaluate the Licensed Operator Candidate's ability to respond to the scenario events. These events will require each candidate to demonstrate the following:

• Knowledge of integrated plant operations

• Ability to diagnose abnormal plant conditions

• Ability to work together as a team

• Ability to mitigate plant transients that exercise their knowledge and use of ONs and EOPs

• Ability to utilize Technical Specifications (SRO Only) To meet this objective, the Licensed Operator Candidates must demonstrate proficiency in the following competencies:

Reactor Operator Candidates:

1. Interpret/diagnose events and conditions based on alarms, signals, and readings.

2. Comply with and use procedures, references, and Technical Specifications.

3. Operate the control boards. 4. Communicate and interact with other crew members. Senior Reactor Operator Candidates:

1. Interpret/diagnose events and conditions based on alarms, signals, and readings.

2. Comply with and use procedures and references.

3. Operate the control boards (N/A to upgrade candidates).

4. Communicate and interact with the crew and other personnel.

5. Direct shift operations.

6. Comply with and use Technical Specifications.

Form NTP-QA-31.7-1, Rev. 0, Page 5 of 15 Page Scenario LOC23 Rev. , .", 'j THIS PAGE IS INTENTIONALLY lEFT BLANK Form NTP-QA-31.7-1, Rev. 0, Page 6 of Page? Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 CRITICAL TASKS I

• Inlect SLC

• Inhibits ADS Safety Significance Early boron injection has the following Stop or prevent large magnitude Limit Cycle Oscillations which can lead to core Limit fuel damage from uneven flux patterns that could result from partial rod Inhibiting ADS prevents uncontrolled injection of large amounts of relatively cold, unborated low ECCS water when the reactor is not shutdown with control Conseguences for Failure to Perform Task Failure to inject Boron can result Cycle Oscillations which can lead to core Fuel damage from uneven flux patterns that could result from partial rod Failure to inhibit ADS can result in large amounts of positive reactivity addition due to boron dilution cold water SSES EOP Basis for: IF INITIAL ATWS PWR > OR CANNOT BE DETERMINED INJECT SLC AND INHIBIT When scram and ARI have fai/ed, reactor power must be considered to determine if immediate boron injection is required.

If initial A TWS power was greater than 5%, then a relatively large number of control rods have failed to insert. The seriousness of this condition requires immediate injection of boron to positively terminate the A TWS event. ADS initiation may result in the injection of large amounts of relatively cold, unborated water from low pressure injection systems. With the reactor either critical or shutdown on boron, the positive reactivity addition due to boron dilution and temperature reduction through the injection of cold water may result in a reactor power excursion large enough to cause substantial core damage. Preventing ADS is therefore appropriate whenever boron injection is required.

Indications/Cues for Event Requiring Critical Task ATWS with initial reactor power level greater than 5% APRM power. Performance Criteria Inject SLC by inserting key into keylock switch and turning to start selected SLC pump, fire the valves and close the Reactor Water Cleanup isolation Alternate SLC injection using RCIC Inhibit ADS by placing 1C601 keylock switches to Performance Feedback Successful SLC injection would be indicated by a lowering SLC tank level and a corresponding power Successful ADS inhibiting is indicated by Green Indicating Light at switch Form NTP-QA-31.7-1, Rev. 0, Page 7 of 15 Page 8 Scenario LOC23 NRC-2 Rev. 0,11/18/2010 Takes Action to Lower RPV level to <-60" but >-161" Safety Significance Core damage due to unstable operation can be prevented or at least mitigated by promptly reducing feedwater flow so that level is lowered below the feedwater spargers.

Consequences for Failure to Perform Task A General Electric Company study (NEDO-32047) indicates that the major threat to fuel integrity from ATWS is caused by large-amplitude power/flow instabilities.

The power oscillations can become large enough to cause melting of fuel in high-power bundles. SSES EOP Basis for: MAINTAIN LVL BETWEEN -60" AND USING TABLE 15 BYPASSING INTERLOCKS AS NECESSARY lAW This step identifies the widest, acceptable water level control band. Although level fluctuations within this band are safe, it is very desirable to maintain level within the more restrictive target area of -110" to -60". The target area and expanded band are shown in Figure 8, Water Level Operation Guidance.

The intent of this step is to remain within the target band at aI/ times unless prohibited by system perturbations, and remain within the expanded band at a/l times. Operation outside the target area has the following disadvantages:

The basis for an upper level of -60" is given in LQ/L-6. A lower level of -110" is specified for the following reasons: Provides a margin for core coverage. Avoids operation near TAF where core power is more responsive to RPV pressure fluctuations. Makes level control easier by maintaining level above the narrow region of the downcomer.

Below -110" the downcomer free area reduces from 300 if to 88 if resulting in increased magnitude of indicated level oscillations.

Form NTP-QA-31.7-1, Rev. 0, Page 7 of 15

. Page 9 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 Maintains sufficient core flow to carry liquid boron from lower plenum upward into the core. As level is decreased below -110", boron mixing efficiency is reduced because the natural circulation flow rate through the jet pumps is reduced and not as efficient at carrying the injected boron from the lower plenum upward into the core. At very low downcomer water levels near or below top of active fuel, there is little water available in the region above the jet pump throat for mixing with boron injected via RCIC. In this situation, there is concern that boron may accumulate in the stagnant region of the downcomer which is below the jet pump throat. Water level can be determined from wide range level instrumentation. Avoids MSIV isolation setpoint of -129". RPV level below TAF is not, by itself, a determination of whether or not level can be maintained>

-161". The determination that level cannot be maintained>

-161" must be made based upon:

• availability of high pressure injection systems, and.

• present level trend This decision must not be made prematurely since depressurization of a critical core results in destabilizing affects and has a potential to cause core damage. Controlling reactor pressure, power and level with condensate and SRVs at 500 psig is difficult because al/ 3 parameters affect each other. Therefore, rapid depressurization is recommended when high pressure injection cannot be obtained.

The initial influence of reactor depressurization is stabilizing since the additional flashing of liquid phase required for depressurization introduces excess voids in the reactor core which can essentially terminate the fission process if the rate of depressurization is high enough. Once the depressurization is complete, however, the result is the immediate initiation of power 19xcursions.

Core damage is expected to occur from high clad stresses induced by: temperature excursions above the rewet temperature, PCI, cyclic fatigue, burnout or having the fuel enthalpy exceed the cladding failure threshold.

Indications/Cues for Event Requirinq Critical Task ATWS with initial reactor power level greater than 5% APRM power. Performance Criteria Lower reactor water level by manually controlling injection rate from Feedwater, HPCI and/or RCIC. Form NTP-QA-31.7-1, Rev. 0, Page 7 of 15 Page 10 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010

• Inserts control rods lAW EO-100-113 Sht. 2. Safety Significance Control rod insertion initiates power reduction immediately Conseguences for Failure to Perform Task Failure to insert control rods allows power to remain elevated with resultant power oscillations and potential core damage. Indications/Cues for Event Regulring Critical Task Exceeding a RPS scram setting with NO reactor scram signal, or RPS/ARI fail to fully insert all control rods. Performance Criteria Insert Control Rods by one or more of the following Maximize CRD to drift control Drive control rods after bypassing Reset and Scram again by performing ES-158-002 Bypass RPS logic De-energizing RPS solenoids by performing Local venting of Scram Air Performance Feedback Successful insertion of control rods will be indicated by: Rod position full in indication for manual insertion of control rods, venting scram air header or de-energizing RPS solenoids.

Rod position full in after resetting scram, draining scram discharge volume and re-scram.

Form NTP-QA-31.7-1, Rev. 0, Page 7 of 15 Page 11 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 SCENARIO REFERENCES

1.

TBCCW 2. AR-128-001 DRWL FAN 1V414B FAILED 3. TS CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM 4.

EMERGENCY LOAD CONTROL 5.

POWER MANEUVERS

6. AR-029-001 CS EMER OA SUP FAN FAILED TS 3.7.3 PLANT SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY SYSTEM (CREOASS)

8. AR-102-001 RECIRC MG 'A' FLUID DRIVE OIL HI-LO TEMP 9. ON-147-001 LOSS FW HEATING EXTRACTION STEAM 10.0N-164-002 LOSS RECIRC FLOW 11.

CONTROL ROD PROBLEMS 12. EO-1 00-1 RPV CONTROL 13.

LEVEUPOWER CONTROL 14.

RHR CONTAINMENT COOLING 15.

RFP AND RFP LUBE OIL SYSTEM OP-183-001 AUTOMATIC DEPRESSURIZATION SYSTEM AND SAFETY RELIEF VALVES 17. OP-184-001, ATT EO HARD CARD-BYPASS MSIV AND CIG INTERLOCKS

18. OP-150-001, ATT EO HARD CARD-OVERRIDING RCIC INJECTION

19. OP-152-001, ATT EO HARD CARD-OVERRIDING HPCIINJECTION

20. OP-145-001, A TT EO HARD CARD-A TWS POWER\LEVEL REDUCTION STRATEGY 21. OP-149-004, ATT EO HARD CARD-INITIATE CONTAINMENT COOLING Form NTP-QA-31.7-1, Rev. 0, Page 9 of 15 Page Scenario LOC23 Rev.

THIS PAGE IS INTENTIONALLY LEFT Form NTP-QA-31.7-1, Rev. 0, Page 10 of Page 13 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 SCENARIO SPECIAL INSTRUCTIONS

1. Initialize the simulator to IC-20: Unit 1 at 100 percent power EOl, Unit 2 in MODE 1. 2. load SCN file LOC23 NRC Scenario 2; verify the 'following pre*inserts and Key assignments:

MF RF OR SCN ET Conditions 4:4 0:0 4:4 o 0:0 17 IMF mfRP158003 RPS FAilS TO AUTO ACTUATE lOR diHSC72A 1 S03AA f:NORM RPS MANUAL SCRAM FAilS lOR diHSC72A 1 S03BB f:DISARM II " lOR diHSC72A 1 S03CB f:DISARM u " lOR diHSC72A 1 S03DA f:NORM II " IMF cmfRl03_63X114725D1 ARI FAilS TO ACTUATE IMF cmfRl03_63X214725D1 " " IMF cmfMV06_HV144F004 RWCU Valve F004 Fails to Auto Isolate {Key[1]} IMF cmfPM02_1V414B DW Cooling Fan Trip {Key[2]} IMF cmfPM01_0V101A CREOASS loss Control Pwr {Key[3]} IMF cmfCN02_ TIC11 016A f:O RRP MG Hyd Fluid Temp Controller

{Key[4]} IMF cmfMV05_HV10241B loss FW Heat to 4B {Key[5]} IMF mfRD1550041839 f:100 Rod Drift {Key[5]} IMF mfRD1550041835 1:100 Rod Drift {Key[5]} IMF mfRD1550041807 f:1 00 Rod Drift {Key[5]} IMF mfRD1550041031 f:100 Rod Drift {Key[5]} IMF cmfMV07 _PV146F003 d:60 f:4.72 Prevents Opening CRD PCV (can't drift rods) {Key[6]} IMF cmfPM02_1 P208A SBle 'A' Thermal Overload {Key[7]} IMF cmfPM02_1 P208B SBle 'B' Thermal Overload {Key[8]} IMF mfTC193001 Turbine Trip {Key[8]} IMF mfTC193025 TBVs Fail Closed {Key[9]} IRF rfRD155025 r:1 1:0 Vents Scram Air Header {Key[9]} IRF rfRD155016 r:5 f:1oo " " {Key[10]} IRF rfRD155025 f:100 Restores Scram Air Header {Key[10]}

IRF rfRD155016 f:O " .. 3. Prepare a turnover sheet indicating the following:

a. U1 at 100%, U2 at full power b. Scheduled activity for the shift is to swap TBCCW pumps c. Maintain full power operation

4. Make a copy of shift aSSignments.

5. Place the Simulator in RUN. Form NTP*QA-31.

7*1, Rev. 0, Page 11 of 15 Page Scenario LOC23 Rev.

THIS PAGElS INTENTIONALLY LEFT BLANK Form NTP-QA-31.7-1, Rev. 0, Page 12 of Page 15 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 SCENARIO EVENT DESCRIP"nON FORM Initial Conditions:

Initialize the simulator to IC-20 Ensure the SCN File is executed per the Special Instructions Sheet. Assign Shift positions.

Direct the Crew to begin a five-minute panel walk down. EVENT TIME 2 min SwapTBCCW (Normal: SRO, 2 10min DW Cool Fan trip (Component: 3 20 min Min Gen Emerg (Normal: SRO, 4 30 min CREOASS inop (Component:

SRO, 5 40 min RRP MG hi temp (Component:

SRO, 6 45 min loss FW Heating (Reactivity:

SRO, 7 60 min 3 Rods Drift (Component: 8 60 min ATWS (Major: 9 65 min EHC malfunction 10 65 min SBlC pump trip (Component: 60 min RWCU fail to isolate (Component:

BOP) 90 min Termination Form NTP-QA-31.7-1, Rev. 0, Page 130f 15 Page 16 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 SCENARIO EVENT FORM Event No: Brief

Description:

________________________POSITION TIME STUDENT ACTIVITIES SRO Direct TBCCW Pump swap iaw OP-115-001.

BOP Swap TBCCW Pumps:

• Obtain OP-115-001, review procedure, and begin at Section 2.2

• Start TBCCW PP 1 P1 038 by depressing Run pushbutton

• Directs TB1 NPO to slowly close TBCCW PP 'A' discharge valve 114011

• Have NPO check pump discharge pressure between 86 and1 00 psig

• Stop TBCCW PP 1 P1 03A by depressing Stop pushbutton

• Check HX outlet temp 92-98F

• Check system pressure stabilizes at approx 64 psig

• Directs TB1 NPO to open TBCCW PP 'A' discharge valve 114011

• Refer to Attachment A as necessaJY to verify proper flowrates I temps

• Denotes Critical Task I NOTES: Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15 I Page 17 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INS'rRUCTOR'S PERSONAL NOTES Event No: ________________________________________________________

_ Brief

Description:

Swap TBCCW pumps INSTRUCTOR ACTIVITY:

Select P & 10 TW1, then close and open "A" TBCCW Pump Discharge Valve 114011, as directed.

ROLE PLAY: As NPO at TBCCW, when requested, report 1 B TBCCW Pump is ready for a start." When directed to close, then open 114011, report dOing so after taking actions as directed above. When directed to report "B" TBCCW Pump Discharge pressure, report "B" rBCCW pump discharge pressure is 98 psig, steady." Form NTP-QA-31.7-1, Rev. 0, Page 15of 15 I -Page 18 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 SCENARIO EVENT FORM Event No:

______________________________________________

_ Brief

Description:

DW cooling Fan trip POSITION STUDENT ACTIVITIES Report 1 C681 Panel Trouble alarm and refer to AR-1 06-001 (B16) Report DW Cooling Fan 1 V414B Refer to AR-128-001 Verifies lV414A is Dispatch NPO to check 1 B246061 (Note Monitor D!ywell Refer to TS 3.6.3.2 and Bases. Enter Condition A, Required Action A.l, restore to operable within 30 days. Contact Work Week Manager to investigate 1V414B trip and to inform the Duty Manager.

• Denotes Critical Task NOTES: I #1: Crew may place 1 V414B fan hand switch to Stop prior to directing NPO to attempt overload reset. Form NTP-QA-31.7-1, Rev. 0, Page 140f 15 Page 19 Scenario LOC23 NRC*2 Rev. 0, 11/18/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No: ________________________________________________________

_ Brief

Description:

OW cooling Fan trip INSTRUCTOR ACTIVITY:

When the TBCCW pump swap is complete and on Lead Evaluators cue, insert OW Cooling Fan trip by activating Key 1 {Key[1]} IMF cmfPM02_1V414B OW Cooling Fan Trip ROLE PLAY: As RB1 NPO: three minutes after being directed to check 1 B246061, report: "1 B246-061 is not tripped, should I check the thermal overloads?" If directed to reset the thermal overloads, report: "1 B246-061 thermal overloads will not reset." When contacted as the Work Week Manager concerning 1 V414B, report: "I will contact FIN to investigate

." Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 Page 20 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 SCENARIO EVENT FORM Event No:

________________

____________________

__ Brief

Description:

Min Generation Emergency, Loss of CREOASS Fan 'A' Control Power POSITION TIME STUDENT ATC Report Min Gen Emergency request from GCC to lower output by 50 Brief Crew on Power Reduction plan Refer to OI-AD-029 Att. D, and CRC Book Direct ATC to reduce power with Recirc at a rate of 1% I minute until MWe is lowered by 50. (Note 1) Refer to GO-1oo-012 Provide Reactivity oversight Contact the Work Week Manager to notify the Duty Manager and Reactor EngineerinJj. Reduce power as directed by the SRO: Using the RRP Dual Screen HMI, lower "A" and "B" Recirc speeds by depressing the double chevron DEC buttons, as necessary, to reduce power at approximately 1 % I minute. Observe Controller Output, Gen Demand, and Scoop Tube Position lowers Monitor Plant response \ MWe. Plot power reduction on Power to Flow Map. Provide peer check of RRP speed reduction.

Maintain Load Set at approximately 100 MWe above actual generator output by depressing Load Selector Decrease pushbutton and watching Load Set meter. Balance the Main Generator Manual Voltage Regulator with the auto regulator by adjusting Man Volt Reg Adjust HC-1oo02, as necessary. Report HVAC Div 1 Control Panel OC681 System Trouble alarm, and:. Report CREOASS Fan 'N alarm Refer to AR-029-oo1 (A01), CS EMER OA SUP FAN FAILED, amber light out Dispatch Operator to Investigate OB136-063 Places OV101 B fan hand switch in Auto Lead and informs SRO. Enter TS 3.7.3 Condition A, Required Action A.1, restore to operable wi in 7 days (for both Units) Contact Work Week Manager to inform him of 'A' CREOASS status and to run EOOS.

• Denotes Critical Task NOTES: I #1; Crew may use insert rods iaw CRC book until below 98% rod line. then reduce Recirc flow. Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15

__________________________________________________

_ Page 21 Scenario LOC23 NRC-2 Rev. 0.11/18/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No: 3 Brief

Description:

INSTRUCTOR ACTIVITY:

When actions are complete for DW Fan trip, and on Lead Instructors cue, contact the U-1 Control Room via the GCC direct line and state, This is John Smith. A Minimum Generation Emergency is required and we need Unit 1 Susquehanna to reduce output by 50 MWe as quickly as possible." When MWe has been reduced by approximately 30 MWe (-1280 MWe), and on Lead Instructors cue, insert CREOASS control power loss by activating Key 2: {Key[2]} IMF cmfPM01_0V1 01 A CREOASS Loss Control Pwr ROLE PLAY: As Operator dispatched to investigate CREOASS Fan, wait three minutes and report: "Breaker OB136-063 is closed and still/ooks good." As Work Week Manager-when contacted concerning CREOASS state, "I will contact FIN to investigate," As FIN wait five minutes and report: "It appears that the OB136-063 Control Power Fuse is blown", Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 Page 22 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 SCENARIO EVENT FORM Event No: _______________________________________________________

_ Brief

Description:

_______________________________________

_ POSITION STUDENT ACTIVITIES Report RRP MG set high temp alarm and refer to:

• AR-102-001 (C05), Recirc MG 'A\B' Brg or Fluid Drive Oil Hi Temp

• AR-102-001 (C03, Recirc MG 'A' Fluid Drive Oil Hi-Lo Temp Check MG Set A Hyd Fluid Clr Temp TIC11016A and report that demand is a 0 and temperature is rising based on controller indication and "A" MG Set Hydraulic Fluid Temperature on TI-14020A.

Place TIC11 016A in Manual and depress the Open button to restore demand to approximately the original value. Adjust controller as necessary to restore temperature to normal of approximately 125°F. Direct BOP to take manual control of "A" RR MG Set Hydraulic Oil temperature controller.

Inform Work Week Manager of the controller malfunction Monitor "A" Recirc Pump operation using Recirc HMI screen / PICSY display. Take manual control of TIC11016A by placing it in Manual and depressing the Open button to restore demand to approximate pre-failure value. Adjust controller as necessary to restore temperature to normal of approximately 125°F.

• Denotes Critical Task NOTES: I Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15 Page 23 Scenario LOC23 NRC-2 Rev. 0, 11118/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No: Brief

Description:

_R;;..;;.R;.....P"-""M.;..;G;;;...;H;.....i'--T;....;;e..;.;;m""p

________________________INSTRUCTOR ACTIVITY:

Once the CREOASS Fan failure is addressed, and on Lead Instructor cue, insert Recirc MG 'A' Fluid Drive Oil automatic Controller failure by activating:

{Key[3]} IMF cmfCN02_TIC11 016A f:O RRP MG Hyd Fluid Temp Controller ROLE PLAY: If contacted as TB1 NPO to investigate the 'A' MG Set Lube Oil temperature controller, report the valve is closed (if PCO has not taken manual control yet) (Monitor temperatures on P&ID SW3) Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 Page 24 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 SCENARIO EVENT FORM Event No: __________________________________________________________

_ Brief

Description:

___________________________________

_ POSITION STUDENT ACTIVITIES Reports FW Loop 8 Panel1C102 Trouble Alarm AR120-001 (H07) then (007) Reports 4B Heater, HV-1024'lB, is closed and dispatches NPO to 1C102. Reports RPV power, pressure, and level. Enter ON-147-001 (Loss FW Heating Extraction Steam) Direct immediate Power reduction iaw RE Instructions in CRC Book to $71 % (NOTE 1) Enter ON-156-001 (Unanticipated Reactivity Change) and ON-164-002 (Loss Recirc Flow) Reduces power to s 71 % power, based on SRO's direction, as follows: If directed to reduce Recire first, per the CRC book, then performs one of the following using the Recirc HMI screen: Initiates a Manual Rx Recirc Limiter #2 Runback by touching Manual Flow Reduction Initiation, then Limiter #2 48%, and then Initiate RRP Flow Reduction.

or Touches the double chevron DEC buttons on the RRP A &8 Speed controllers as required to establish the final Core Flow value stated in CRC Book If directed to insert rods first to get < 98% rod line, then selects control rods beginning with the first one in the CRC book (30-31), depresses the Insert Rod pushbutton, monitors rod position, and releases the button after 00 is observed.

Documents move in CRC, then proceeds with in sequence rods. Insert additional Rods iaw CRC to reduce \ maintain < 71 % power. Plots position on Power to Flow Map usin-.9 Core Flow and APRM power. Provides peer check of Recirc I Control Rod manipulations.

Per ON-147-001, once s 71% power, closes HV-10242B Extraction Steam to 58 FW Heater (coordinates with ATC due to power increase) Maintain Rx power s 71 % by inserting Control Rods iaw the CRC Book. Refer to MCPR LCO 3.2.2. Determine extraction steam must be restored within two hours or the string must be isolated.

Contact Reactor Engineering and WWM

• Denotes Critical Task NOTES: I #1: SRO may direct ATe to insert control rods first per ON-147-001 guidance, then reduce power using Recire. Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15 Page 25 Scenario LOC23 NRC-2 Rev. 0,11/18/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No: 6 Brief

Description:

.....;L::.;O:::.;:88=-:;.F...,:.W.:.....:...:He.;:;;8::.;:t;:.;in.9

____________________________________

_ INSTRUCTOR ACTIVITY:

When the RRP MG temp is returned to normal, and on Lead Instructor cue, insert Loss of FW Heating by activating Key 4: {Key[4]} IMF cmfMV05_HV10241B Loss FW Heat to 4B ROLE PLAY: When contacted as the TB NPO to investigate 1 C1 02 panel alarm, wait three minutes, then select the 1 C1 02 PNOV display. Report alarms currently in. Do not report the closed indication for 10241 B unless the crew has already identified it has closed. When contacted as the WWM concerning isolation of U1 4B Extraction Steam, reply "I will contact FIN to investigate. As FIN, wait five minutes after WWM was contacted and call the U-1 Control Room via the PA. State, "This is Bill Brown, FIN. I am not sure why HV-10241B closed. I will inform you as soon as I find anything." Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 Page 26 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 Event No: Brief

Description:

_______________________STUDENT ACTIVITIES POSITION TIME ATe Reports Rod Drift alarm AR-104-001 (G05) Depresses Display Rods Drifting pushbutton Reports three control rods are drifting Perform immediate operator action per OP-AD-055 or ON-155-001 by placing Mode Switch to Shutdown.

Reports failure to Scram, and takes immediate operator actions: Arms and Depresses the four Manual Scram Push buttons Report failure to Scram Inserts SRMs and IRMs by selecting each detector, depressing Power On and the Drive In pushbuttons. Initiates ARI by arming and depressing Manual pushbuttons HS-1471 03A 1 and B1 and observes vent and block valve positions.

Reports failure of ARI to insert Rods Enters EO-100-102 (RPV CONTROL), and exit to EO-100-113 (LEVEUPOWER CONTROL).

and: Ensures Mode Switch in S\D and ARI initiated. Requests and record Initial ATWS power. Direct SBlC injected and ADS inhibited (BOP)* BOP Injects SlC:

• Turns SlC Man Initiation key lock switch to Start A (Start BOP

• Recognize the first SBlC pump started BOP

• Start the other SBlC Turns SlC Man Initiation key lock switch to Start B (Start A) Verifies SBlC Pump Dsch Press PI-C41-1 R600 is greater than Rx pressure. Verifies SBlC flow is -42 gpm and SlC Tank level is lowering on 14806. Recognizes RWCU HV*144-FOO4 failed to close and closes it, or has ATC close it.

• Denotes Critical Task NOTES: Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 I Page 27 Scenario LOC23 NRC-2 Rev. 0,11/18/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No:

_______________ . ________________________________

______ Brief

Description:

Rods Drift, ATWS INSTRUCTOR ACl1VITY:

When FW Heating issue has been stabilized, and on lead Instructor cue, drift four Control Rods and disable the Drive Water Pressure Control Valve by activating Key 5: {Key[5]} IMF mfRD1550041839 f:100 Rod Drift {Key[5]} IMF mfRD1550041835 f:1oo Rod Drift {Key[5]} IMF mfRD1550041807 f:100 Rod Drift {Key[5]} IMF mfRD1550041031 f:1oo Rod Drift {Key[5]} IMF cmfMV07_PV146F003 d:60 f:4.72 Prevents Opening CRD PCV (can't drift rods) When the SBlC pump is started, insert motor overload by activating appropriate key as noted below: If 'A' SLC Pump is injecting, activate Key 6 {Key[6]} IMF cmfPM02_1 P208A ; SBlC 'A' Motor Overload If 'B' SLC Pump is injecting, activate Key 7 {Key[7]} IMF cmfPM02_1 P208B ; SBlC 'B' Motor Overload ROLE PLAY: If contacted as the RB NPO to investigate the "A"{B) SlC Pump trip, wait two minutes and report "The SlC pump is extremely hot and the breaker is tripped." As necessary Form NTP-QA-31.

7-1, Rev. 0, Page 15 of 15 Page 29 Scenario LOC23 NRC-2 Rev. 0,11/18/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No:

______

________________ Brief

Description:

ATWS, EHC Malfunction, SBlC pump trip, RWCU fails to auto isolate continued INSTRUCTOR When both ARPs are tripped, insert Turbine Trip and TSVs to fail closed by activating Key {Key[8]} IMF mfTC193001 Turbine {Key[8]} IMF mfTC193025 TSVs Fail ROLE PLAY: As AS NPO directed to investigate CAD Drive Water Pressure Control Valve, PV-146-FOO3, wait four minutes and report via the radio, "I am unable to turn the handwheel on the U-1 CRD Drive Water PCV and am going to get help." As necessary Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 Page 30 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 Event No:

____________________________________

__ Brief

Description:

ATWS, EHC Malfunction, SBlC pump trip. RWCU falls to auto isolate continued POSITION STUDENT ACTIVITIES SRO Directs Throttle injection and Prevent injection until Level between -60" and -110": Directs BOP to override RCIC and HPCI

• Directs ATC to lower RPV level to between -60" and -110" using Feedwater.

Directs BOP to bypass MSIV and CIG interlocks.

BOP Overrides RCIC and HPCI to prevent injection: For RCIC, closes HV-1S012 For HPCI, places FC-E41-1R600 in Manual and reduces demand to 0% ATC Throttle and Prevent Injection until Level is between -60" and -110" (Note 1) Lowers RPV level to Target Band iaw OP-145-001 Att C Hard Card as follows: Places LV-10641 controller UC-10641 to manual and reduces controller demand to 0%. (If OP-14S-OQ1 Att C was used to reduce Recirc Speeds, this is already done) Places LIC-C32-1 R600 (Master) in Manual USing L1C-C32-1R600, lowers Feedwater flow to < 1Mlbm\hr less than Steam Flow. For the RFP that will control level (most likely A), touches the RFPT Man Vlv Ctl button, touches the Pump Icon, touches Man on 1 R601 A(B)(C). For remaining RFPs (most likely B & C), touches RFP button, and touches RFPT Idle Mode. (Note 2) Depresses the DEC button on SIC-C32-1 R601 A(B)(C) to reduce feed flow and monitors approach to directed level band. Bypass MSIV and CIG interlocks iaw OP-184-001 Att A Hard Card, as follows: At 1 C645 places HS-B21-S38A and C, HS-12694 &95 to Bypass.

• At 1C644 places HS-12696 to Bypass. Informs SRO MSIV and CIG interlocks are bypassed. Enters EO-1 00-1 03 when Suppression Pool temperature is > Directs ATC to maximize Suppression Pool *Denotes Critical Task NOTES: I #1 Due to the effectiveness of SBlC the time to reach -60 inches even with feedwater flow may be

1. 2: If, due to reduce power level, ICS initiates alignment to SUlC and "8" and "C" RFPTs are in Mode when ATC reaches applicable step, then ATC will need to verify are in Form NTP-QA-31.7-1, Rev. 0, Page 140f 15 Page 31 Scenario LOC23 NRC*2 Rev. 0, 11/18/2010 Event No:

______________

__________________ Brief

Description:

ATWS, EHC Malfunction, SBlC pump trip, RWCU fails to auto Isolate continued POSITION STUDENT ACTIVITIES Maximizes Suppression Pool cooling iaw OP-149-004, Att A., as follows: Open HV-151-F028A(B) Close HV-151-F017A(B) Start RHR Pump A or C (B or D) Throttle open HV-151-F024A(B) to establish total loop flow of 9,500 to 10,000 gpm on FI-E11-1 R603A(B). Places RHRSW in service iaw OP-149-004 Att A, section 4.0. Direct Control Rod insertion per Sh 2: Directs A TC to insert control rods in accordance with directions on EO-113 Sheet 2. Directs BOP to have Scram Air Header Vented Contacts FUS to perform ES-158-oo1.

ATC Insert Control Rods per EO-OOO-113 Sh2 Bypasses RWM by placing Normal \ bypass keylock to Bypass Establish approx 63 gpm Cooling Water flow and approx 350 psid Drive Water pressure, as necessary Starting with Intermediate, then Full Out Rods, select Rods in rotating quadrants Depress Continuous Insert until Rod is Full In Directs NPO to vent Unit 1 Scram Air Header Reports NPO venting Scram Air Monitors for Low Scram Air Pressure Monitors for drifting Reports all control rods full in. Directs BOP to have Scram Air Header restored and to stop SLC Contacts the FUS to stop performance of Exits Enters Directs ATC to slowly restore RPV level to 13" to 54" using Restores RPV level +13" to +54" by depressing INC button on 1 R601 A(B)(C), then adjusts using the INC/DEC button to maintain the band.

• Denotes Critical Task I_N_OTE_S:

---

1 Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15 Page 32 Scenario LOC23 NRC-2 Rev. 0,11/18/2010 INSTRUCTOR ACTIVITIES, ROLE AND INSTRUCTOR'S PERSONAL Event No:

Brief

Description:

....;A;.,.;;.TW,;...;.;;..;;:.S'-'.

E;;;.;H..;..C::..=M;;.;;;;8",,"If.::.un;.;;..c;;.,;t;:.::lo..:..;n

....

___INSTRUCTOR ACTIVITY:

Once actions are complete to lower RPV level into the ATWS target band of -60" to -110", several rods have been inserted to position 00, and on the Lead Evaluator's cue, contact Control room via the radio and report that you are ready to vent the U1 Scram Air Header iaw Posted Instructions.

Once directed to vent the Scram Air Header, activate Key 9: {Key[9]} IRF rfRD155025 r:1 f:O Vents Scram Air {Key[9]} IRF rfRD155016 r:5 f:100 " Once Key 9 is activated, contact the control room and report, "I vented the Unit 1 Scram Air Header and no longer hear any air." When directed to restore U1 Scram Air Header, activate Key 10: {Key[10]}

IRF rfRD155025 f:100 Restores Scram Air Header {Key[10]}

IRF rfRD155016 f:O " " Once Key 10 is activated, contact the control room and report, "I restored the Unit 1 Scram Air Header." ROLE See above for specific As TERMINATION CUE: All Rods are in, direction is given to restore RPV level to between 13" and 54" with Feedwater, and Suppression Pool cooling in service. Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15