ML110200558
| ML110200558 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/26/2010 |
| From: | Susquehanna |
| To: | Caruso J Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML102180025 | List: |
| References | |
| TAC U01793 | |
| Download: ML110200558 (276) | |
Text
{{#Wiki_filter:PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SRO 00.AD.1021.101 o 8/2/10 215002 2.1.37 4.6 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task
Title:
Authorize Bypassing the Rod Block Monitor In Accordance With NDAP-QA-0338, "Reactivity Management and Controls Program" Completed By: 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: Last 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 INFORMATION JOB PERFORMANCE MEASURE SRO OO.AD.1021.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self-Checking is required. II. REFERENCES A. NDAP-QA-0338, "Reactivity Management and Controls Program", Rev. 14 B. AR-103-001 (C04), "RBM UPSCALE OR INOP ROD BLOCK", Rev 15 C. TS 3.3.2.1, "Control Rod Block Instrumentation", Amendment 242 D. TRM 3.2.1, "Core Operating Limits Report", Rev 11 III. OPERATIONAL ACTIVITIES None IV. TASK CONDITIONS A. A plant startup is in progress on Unit 1:
- Reactor Power is 30%
- Total Core flow is 50 Mlbm/Hr.
B. 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. C. The PCOM verified the correct rod was selected per the pull sheet. D. It has been determined that Rod Block Monitor A has a Critical Self Test Fault. E. 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 . G. Reactor Engineering determined that MCPR is 1.5. FORM NTP-QA-31.8-1, Rev. 0
) V. 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. 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 Action Standard Eval Comments EVALUATOR NOTE: Ensure the following material is available to support performance of this JPM:
- A copy of NDAP-QA-0338
- A blank copy of NDAP-QA-0338, Attachment A
- Unit 1 Technical Specifications
- Unit 1 TRM (COLR)
- AR-l03-001 (C04), "RBM UPSCALE OR INOP ROD BLOCK" EVALUATOR CUE:
To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.
- 1. Obtain a controlled copy of Controlled copy obtained.
NDAP-QA-0338. EVALUATOR CUE When the candidate indicates NDAP-QA-0338, Attachment A, must be completed, give him/her the blank form. If asked, provide AR-103-001 (C04) FORM NTP-QA-31.8-1 , Rev. 0 Page 3 of 10
) ) ....)
Step Action Standard Eval Comments
- 2. Complete NDAP-QA-0338, Review NDAP-QA-0338, Section Attachment A. 6.4 and/or Attachment A.
- 3. Enter initiating condition data. Enter the following data for Initiating Condition:
- Rod 10 10-43
- Notch 04
- Unit 1
- Circle RBM Channel A
- Power Level 30 percent
- DatefTime
- 4. Determine if power is <28%. Place checkmark in "NO" Box, from Task Conditions Reactor Power is 30%.
- 5. Determine if Rod Block Monitor A is Refers to Table 7.2-1 and cue providing a valid rod block per TRM 3.2 sheet. Determines Rod Block is Table 7.2-1. being generated due to the Critical Self Test Fault, not as a EVALUATOR CUE: result of exceeding a Table 7.2-1 If asked, provide student with a Unit 1 setpoint.
TRM. Place a checkmark in the "NO" Box. i FORM NTP-QA-31.8-1, Rev. 0 Page 4 of 10
) ) ~
Step Action Standard Eval Comments
- 6. Determine if inputs to the Rod Block Refer to provided task conditions, Monitor A are valid. and place a checkmark in the "NO" Box.
- 7. Contact I&C to repair the Rod Block Contact I&C to investigate and Monitor A. 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 7.2 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 Action 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 hours.
*9. Determine that it is allowable to bypass Determine that Rod Block Rod Block Monitor A. Monitor A can be bypassed.
*10. Authorize bypassing Rod Block Monitor Sign, date, and enter time on A. 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 NOTE:
~
\,
(
\
If student indicates need to address TS
~
/TRM for MCPR not within limits, tell them it is not required for this JPM.
~
EVALUATUtt Vl '-. This completes the JPM. L/ FORM NTP-QA-31.8-1, Rev. 0 Page 6 of 10
)
J v Step Action Standard Eval Comments 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 Page 7 of 10
TASK CONDITIONS A. A plant startup is in progress on Unit 1:
- Reactor power is 30%.
- Total Core flow is 50 Mlbm/hr.
A. 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. B. The PCOM verified the correct rod was selected per the pull sheet. C. It has been determined that Rod Block Monitor Pl.' has a Critical Self Test Fault. D. All external inputs to Rod Block Monitor A have been determined to be valid. E. The PCOM has suggested bypassing Rod Block Monitor A and continuing with the rod withdrawals and reactor startup. F. 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, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET 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
Title:
Implement ON-145-004, "Reactor Water Level Anomaly", Determine Cause For Erroneous RPV Water Level Indications, And Identify Required Tech Spec Actions Completed By: Validated: Tracy North 11/1/10 Writer Date Date Approval: ~~mJ)'11J, uc ea Trng. Supv. 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. 0 Page 1 of 10
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 45.0N.1829.1 01 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. ON-145-001, "RPV Water Level Anomaly" (Rev 18) B. ON-117-001, "Loss Of Instrument Bus" (Rev 31) C. Tech Spec 3.3.3.1, PAM Instrumentation (Rev 2), and Bases (Rev 8) III. OPERATIONAL ACTIVITIES None IV. TASK CONDITIONS A. Unit 1 is in MODE 1 at full power. B. The following 1C601 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. 0 Page 2 of 10
C. The following 1C651 RPV Water Level indicators are ENERGIZED, but indicate FULL DOWNSCALE:
- U-14201B1 Extended Range
- U-14201 B1 Wide Range D. UR-14201 B is ENERGIZED, but ALL THREE (3) parameters are indicating FULL DOWNSCALE.
E. 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. 0 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 environment. Ensure a copy of ON-145-004, "RPV Water Level Anomaly" (rev 18), and Unit 1 Tech Specs & Bases are available for candidate use. 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 CHECKLIST Appl. To: SIRO JPM No.: 45.0N.1829.101 Student Name: Step Action Standard Eval Comments
- 5. Refer to Attachment B per step 3.5.1. Determine step 3.5 is applicable, and refer to Attachment B to perform step 3.5.1.
*6. Check for instruments with common REFERENCE Evaluate failed water level instruments leg condensing chambers or excess flow check against Attachment B page 1 and 2 to valves (3.5.1.a). determine if the instruments share a common REFERENCE leg or excess flow check valve.
Determine that these instruments DO NOT share these components. i i
*7. Check for instruments with common VARIABLE leg Evaluate failed water level instruments supplies or excess flow check valves (3.5.1.b) against Attachment B page 1 and 2 to determine if the instruments share a common VARIABLE leg or excess flow check valve.
Determine that these instruments DO NOT share these components. FORM NTP-QA-31.8-1, Rev. 0 Page 5 of 10
PERFORMANCE CHECKLIST Appl. To: SIRO JPM No.: 45.0N.1829.101 Student Name: Step Action Standard Eval Comments I
-8. Check for instruments with common POWER Evaluate failed water level instruments SUPPLIES (3.5.1.c) against Attachment B page 1 and 2 to determine if the instruments share a EVALUATOR NOTE: common POWER SUPPLIES.
Although the indicators themselves a/l share a common power supply, 1Y125-01, the i~ Determine that ALL the erroneous RPV conditions state that the indicator~i~I;;?~d so Water Level indicators are provided signals candidates must determine that thi is NOT tN by transmitters LT -14201 B, LT -14202B and cause. LT -14203B and ALL are powered by 1Y125 Additionally, the wide range pressure indication on breaker 05. UR-14201B is also downscale since its signal comes from a transmitter powered by 1Y125-05. Recognition of this helps ensure the candidate determines the correct cause.
- 9. Check for automatic actions and alarms. Evaluate Attachment B and determine that there are NO automatic actions or alarms associated with these instruments.
- 10. Evaluate level, if level cannot be determined to be Determine that level can be determined to 2! + 13", Enter EO-1 00-1 02. be ~ + 13" by referring to task conditions provided.
- 11. 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 Technical 3.3.5.1, 3.3.4.2, 3.3.5.2 Specifications for the failed instruments.
FORM NTP-QA-31.8-1, Rev. 0 Page 6 of 10
PERFORMANCE CHECKLIST Appl. To: SIRO JPM No.: 45.0N.1829.101 Student Name: Step Action 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.
- 12. SRO Candidates ONL Y: Evaluate Tech Spec 3.3.3.1, "PAM Obtain and evaluate Tech Specs Instrumentation", and determine that Condition A is applicable since there are less than the required number of operable channels of Wide Range Level, Extended Range Level, and Fuel Zone Level in accordance with Table 3.3.3.1-1 Functions 2a, 2b and 2c; and the following action is required:
Restore required channels to OPERABLE status within 30 days. EVALUATOR CUE:. This completes the JPM; ensure results are entered on task condition sheet. FORM NTP-QA-31.8-1, Rev. 0 Page 7 of 10
PERFORMANCE CHECKLIST Appl. To: S/RO JPM No.: 45.0N.1829.101 Student Name: Step Action Standard Eval Comments EVALUATOR: Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures? FORM NTP-QA-31.8-1, Rev. 0 Page 8 of 10
TASK CONDITIONS A. Unit 1 is in MODE 1 at full power. B. The following 1C601 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 C. The following 1C651 RPV Water Level indicators are ENERGIZED, but indicate FULL DOWNSCALE:
- U-14201B1 Extended Range
- U-14201B1 Wide Range D. UR-14201B is ENERGIZED, but ALL THREE (3) parameters are indicating FULL DOWNSCALE.
E. 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, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET 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
Title:
Perform LPRM Upscale Alarm Operability Tracking In Accordance With 01-078-001 and Determine Reguired Actions. Completed By: 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 INFORMATION JOB PERFORMANCE MEASURE SIRO 78.AD.2319.102 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. 01-078-001 LPRM STATUS CONTROL, (Rev. 11) B. TRM 3.3.9. rev 3 C. LCO 3.3.1.1 rev 3 III. OPERATIONAL ACTIVITIES This JPM satisfies the requirements of Operational Activity(s): None IV. TASK CONDITIONS A. Unit 1 is in MODE 1 at 80% power. B. ALL OPRM channels are OPERABLE C. APRM Gain Calibration was last performed 30 days ago. D. LPRM detector 40-57A caused a downscale alarm, 1& C determined the detector failed, and Reactor Engineering requested bypassing the detector. E. The PCOP has just bypassed LPRM detector 40-57A in the lower relay room. V. INITIATING CUE Perform LPRM Upscale Alarm operability tracking for LPRM detector 40-57A in accordance with 01-078-001. FORM NTP-QA-31.8-1, Rev. 0 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 CHECKLIST Appl. To/JPM No.: SIRO 78.AO.2319.102 Student Name: _ _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments EVALUATOR NOTE: Ensure the following material is available to support performance of this JPM:
- A working copy of rev 11 of 01-078-001.
CAUTION: Ensure the answer key, which precedes the two Cue Sheet pages in the JPM package, is NOT given to the student.
- Previously filled out Attachments A -0 (with zone 8 having exactly 50%
operable LPRM upscale alarms.)
- 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 blank attachments A - 0
- Previously filled out attachments A - 0
- 1. Obtain a controlled copy of procedure. Controlled copy of 01-078-001 obtained.
(Provided with initiating cue)
- Critical Step #Critical Sequence Page 3 of 7 FORM NTP-QA-31.8-1, Rev. 0
PERFORMANCE CHECKLIST Appl. To/JPM No.: SIRO 78.AD.2319.102 Student Name: _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
- 2. Refer to correct section. Refer to section 4.
- 3. Determine current LPRM status. Refer to the previously completed copy of Attachments A & B.
- 4. Complete new Attachment A. Enter 1 for Unit.
Transfer the previous LPRM data to the new Attachment A
- 5. Enter a check (--1) in column (2) for LPRM Place a checkmark in column 2 adjacent to alarms determined inoperable or bypassed for LPRM detector 40-57A in Zone 8.
all other reasons.
*6. Determine if ;?:50% of LPRM Upscale alarms in Consider all LPRM Upscale Alarms with a check each zone are operable. 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.
- 7. Notify Reactor Engineering of all LPRM upscale N/A alarms determined inoperable.
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 Student Name:_ _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments B. Evaluate the need to place placard to 1C651 Determine that placard is NOT required since indicating < required # of LPRM Upscale ALL OPRM channels are OPERABLE. Alarms. {reguires com(2letion of Attachments C & 0 1 which a(2(2ears in Ste(2 111 below.}
*9. Complete an LPRM vs. APRM/LPRM Group Transfer the previous LPRM data to the new Status Control Log (Attachment B) each time Attachment B.
LPRM operability status is changed. Circle LPRM detector 40-57A for APRM 1, under Circle all inoperable LPRM's on LPRM vs. the column 'A' Level, and enter today's date. APRM/LPRM Group Status Control Log (Attachment B).
*10. Refer to weekly surveillance SO-100-00B to Compare the following criteria to current confirm APRM operability requirements APRMlLPRM operability status:
maintained.
- 2: 20 total operable LPRMs per APRM channel
- 2: 3 LPRM inputs per level (A, B, C, or D)
- s 9 LPRMs inop since last APRM gain calibration (after date provided in task conditions)
Determine that APRM channel 1 does NOT meet operability requirements due to LESS THAN 3 operable level "A" LPRMs. (The only operable Level A LPRMs in APRM 1 are 40-17A and OB-49A)
- Critical Step #Critical Sequence Page 5 of 7 FORM NTP-QA-31.B-1, Rev. 0
PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 78.AD.2319.102 Student Name: _ _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments I 11 Identifies Inoperable OPRM cells. Transfers the previous LPRM data to the new Attachment C and circles "A LEVEL" for LPRM 40-57. Determines it inputs to APRM1 Cell 03 Transfers the previous LPRM data to the new Attachment D and circles LPRM 40-57A in the Cell 03 row, in the LPRM#2 column. Determines OPRM cell remains operable due to at least three operable LPRMs. 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 Refer to Tech Spec 3.3.1.1 and determine that a minimum of 3 operable APRM channels are Instrumentation and TR 3.1.3 for Control Rod required in MODE 1 per table 3.3.1.1-1, therefore Block Instrumentation NO TS actions are required. EVALUATOR NOTE: Refer to TRM 3.1.3 and determine that a LCO 3.3.1.1 and TRM 3.1.3 Condition A is met minimum of 3 operable APRM channels are and action A.1 is NOT required since only one required in MODE 1 per table 3.1.3-1, therefore APRM channel is inoperable. NO TRM actions are required.
- Critical Step #Critical Sequence Page 6 of 7 FORM NTP-QA-31.8-1, Rev. 0
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. EVALUATOR: Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?
- Critical Step #Critical Sequence Page 7 of 7 FORM NTP-QA-31.8-1, Rev. 0
JPM Key (next 11 pages) Do Not Provide To Student (They are given the 11 pages that follow the 2nd 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 _ _1 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 -L 16-418 24-498 24-418 @NO 16-49C 16-41C
-"- 24-49C
-" 24-41C Zone 2 40-49A -L 40-41 A -L 48-49A 48-41 A 40-49B 40-49C 40-418 40-41C 48-498 48-49C -"- 48-418 48-41C -" @NO Zone 3 16-17A 16-25A 24-17A 24-25A 16-17B 16-258 24-176 24-258 @NO 16-17C 16-25C -L 24-17C 24-25C Zone 4 4O-17A 40-17B 40-25A 40-258 " 48-17A 48-178 48-25A 48*256 @NO 40-17C 4O-25C 48-17C 48-25C Zone 5 24-33A 24-33B -"-
32-25A 32-256 32-33A 32*336 32-41 A 32-418 40-33A 40-33B @NO Zone 6 24-33C 16-09A
-" 32-25C 24-09A 32-33C 32*09A 32-41C 4O-09A 4O-33C 32-17A 16-09B 24-098 32-098 -L 40-09B 32-178 @No l6-09C 24-09C
-" 32-09C 40-09C 32-17C Zone 7 08-17A -L 08-25A -L 08-33A 08-41 A 16-33A 08-178 08-256 08-336 08-416 16-336 @NO 08-17C 08-25C 08-33C -L 08-41C 16*33C Zone 8 24-57A 24-578 32-57A 32-578 4O-57A 40-57B -"-
-L 32-49A 32-496
..L
-L YE@
24-57C -L 32-57C 4O-57C 32-49C Zone 9 48-33A 48-338 48-33C 56-25A 56-258 56-25C 56-33A 56-338 56-33C
-"- 56-41 A 56-41B 56-41C
-"- @NO 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 LPRM LOCATIONS A 8 Date C Date D Date APRM CHANNEL LEVEL Date inop. LEVEL inop. LEVEL inop LEVEL inop. APRM1 C56-3~ 04/05/10 G2-096> 06/15/10 W8-33C) 11/02/19 32-57D GO-49~
~
96/19/19 16-258 40-33C (16-41 D) 40-17A 16-578 24-17C 48-09D
~4-33Y 07/98/19 48-258 (g4-499 93/19/19 32 (Q8-17N 99/19/10 G2-416) .7/87/19 ~ 16
~
08-49A 32-338 48-410 (08-25A) 95/29/19 16-178 95/96/10 ~2-49rD (40-57 TO/DAlY (j6-49ij) 99/16/19 24-25C 32-17D (24-41 /19 48-178 (24-57(!) 12/01/19 48-33D
<24-09 /19 ~8-49§) 19/31/10 08-41C 16-33D (56-41/y 07/11/19 (40-09C) 10/25/10 (40-25~ 09/99/19 APRM2 32-57A 56-338 32-09C 08-330 I 16-41A 40-178 32-41C 24-170 48-41A 08-498 <i6-25C) 05/91/19 56-170 32-25A 40-498 16-57C (40-330) 97/99/10 16-09A ~4-33ED 98/08/19 ~8-25C) 04/11/19 24-490
~8-09~ 05/19/19 08-178 ~41C 32-330 08-41 A 32-178 -25C 48-490
~
<32-496> 05/97/10 24-09C 48-17D 16-338 24-41C 16-17D I
'/I.
48-338 40-57C (J6-49q) 09/10/10 56-25A 08-25C 40-41 A APRM3 08-33A 1(32-576) 96/05/10 (56-33C> 08/29/19 32-090 24-49A 48-418 ~4-33Q) 08/08/19 48-250 24-17A 16-418 40-49C <i6-25W 08/12/19 40-33A 48-098 08-17C 16-570
~6-17A;> 94/01/10 32-258 08-49C 32-410 32-33A 40-17C (08-25W 09/95/19 16-17A 56-258 (32-49C) 05/97/19 24-410 48-17A 40-418 32-17C 24-09D 48-49A 24-578 48-33C 56-41 D 16-49A 24-258 16-33C 40-570 08-418 40-25D 40-098 FORM 01-078-001-2, Rev. 2, Page 1 of 2
JPM 78.AD.2319.1 02 KEY Attachment B 01-078-001 LPRM vs. APRM Status Control Log Revision 11 (Inoperable LPRM's are circled) Page 8 of 16 UNIT(1"kr 2 (Circle Unit) I LPRM LOCATIONS APRM4 32-09A 08-338 32-57C 56-33D 16-25A 24-498 32-25C 40-49D 48-25A 24-178 16-41C 08-17W 08/11/10 32-41A (56-176> 04/01/10 48-41C 24-33D 16-57A 40-338 16-09C 08-49D 32-17A 56-418 48-09C 40-17D
~2-4W 05/07/10 40-258 32-33C 08-41 D 16-33A 24-418 16-49C (40-09W 04/12/10 48-33A 08-258 48-49C 24-25D (40-578) 05/30/10 16-17C 56-25D 24-098 48-17C (z4-57J>> 05/06/10 40-41 D LPRM Operability Assessment Complete Only SROs sign here ##1##1## ####
Shift Supervision Date Time FORM 01-078-001-2, Rev. 2, Page 2 of 2
JPM 78.AD.2319.102 KEY Attachment C 01-078-001 Revision 11 Page 9 of 16 LPRM VB. OPRM Status I LPRM OPRM Cells (APRMlOPRM - Cell) i 08-17 C~ LEVEL ::> B LEVEL C LEVEL D LEVEL APRM1-Cell 21 2-21 3-21 4-21 I 08-25 C ALEVEL~ B LEVEL C LEVEL o LEVEL 1-15 4-15 2-15 3-15 1-21 4-21 2-21 3-21 08-33 A LEVEL B LEVEL C C LEVE[""':) D LEVEL 3-09 4-09 '-09 2-09 3-15 4-15 1-15 2-15 08-41 A LEVEL B LEVEL C LEVEL D LEVEL 2-04 3-04 1-04 4-04 2-09 3-09 1-09 4-09 08-49 A LEVEL B LEVEL C LEVEL D LEVEL 1-04 2-04 3-04 4-04 16-09 A LEVEL BLEVEL C LEVEL D LEVEL 2-27 3-27 4-27 1-27 16-17 A LEVEL B LEVEL C LEVEL D LEVEL 3-21 1-21 4-21 2-21 3-22 1-22 4-22 2-22 3-27 1-27 4-27 2-27 16-25 A LEVEL B LEVEL C:CLEVED D LEVEL 4-15 1-15 2-15 3-15 4-16 1-16 2-16 3-16 4-21 1-21 2-21 3-21 4-22 1-22 2-22 3-22 16-33 A LEVEL B LEVEL C LEVEL D LEVEL 4-09 2-09 3-09 1-09 4-10 2-10 3-10 1-10 4-15 2*15 3-15 1-15 4-16 2-16 3*16 1-16 16-41 A LEVEL B LEVEL c: .c LEVEL ::::> D LEVEL 2-04 3-04 4-04 1-04 2-05 3-05 4-05 1-05 2-09 3-09 4-09 1-09 2-10 3-10 4-10 1*10 16-49 A LEVEL CJ3LEVEL ~ C LEVEL D LEVEL 3-01 1-01 4-01 2-01 3-04 1*04 4*04 2-04 3-05 1-05 4-05 2-05 16-57 A LEVEL B LEVEL C LEVEL D LEVEL I 4-01 1-01 2-01 3-01 24*09 A LEVEL B LEVEL <: C LEVEL~ D LEVEL
'*27 4-27 2-27 3-27 i
'-28 4-28 2-28 3-28 24-17 A LEVEL B LEVEL C LEVEL D LEVEL 3-22 4-22 1-22 2-22 3-23 4-23 1-23 2-23 3-27 4-27 1-27 2-27 3-28 4-28 1*28 2-28 Page 1 of 4
JPM 78.AD.2319.102 KEY Attachment C 01-078-001 Revision 11 Page 10 of 16 LPRM vs. OPRM Status LPRM OPRM Cells (APRM/OPRM - Cell) 24-25 A LEVEL B LEVEL C LEVEL D LEVEL APRM2-CeIl16 3-16 1-16 4-16 2-17 3-17 1-17 4-17 2-22 3-22 1-22 4-22 2-23 3-23 1-23 4-23 24-33 CALEVEL") CBLEVEl) ('C LEVEL) D LEVEL 1-10 2~10 " .. I' 4-10 1*11 2-11 3-11 4-11 1-16 2-16 3-16 4-16 1-17 2-17 3-17 4-17 24-41 lALEVELJ B LEVEL C LEVEL D LEVEL
.:00 4-05 2-05 3-05 1-06 4-06 2-06 3-06 1-10 4-10 2-10 3-10 1-11 4-11 2-11 3-11 24-49 A LEVEL B LEVEL cCLEVEL) D LEVEL 3-01 4-01 2-01 3-02 4-02 1-02 2-02 3-05 4-05 1-05 2-05 3-06 4-06 1-06 2-06 24-57 A LEVEL B LEVEL ("'C LEVEL) D LEVEL 2-01 3-01 r-v 4-01 2-02 3-02 1-02 4-02 32-09 A LEVEL cBLEVEC) C LEVEL D LEVEL 4-28 -'::0 2-28 3-28 4-29 1-29 2-29 3-29 32-17 A LEVEL B LEVEL C LEVEL D LEVEL 4-23 2-23 3-23 1-23 4-24 2-24 3-24 1-24 4-28 2-28 3-28 1-28 4-29 2-29 3-29 1-29 32-25 A LEVEL B LEVEL C LEVEL D LEVEL 2-17 3-17 4-17 1-17 2-18 3-18 4-18 1-18 2-23 3-23 4-23 1-23 2-24 3-24 4-24 1-24 32-33 A LEVEL B LEVEL C LEVEL D LEVEL 3-11 1-11 4-11 2-11 3-12 1-12 4-12 2-12 3-17 1-17 4-17 2-17 3-18 1-18 4-18 2-18 32-41 A LEVEL CBLEVEL) C LEVEL D LEVEL 4-06 I-U6 2-06 3-06 4-07 1-07 2-07 3-07 4-11 1-11 2-11 3-11 4-12 1-12 2-12 3-12 32-49 CALEVEl) (' B LEVEl:) CCLEVEl) D LEVEL
--.<f-UZ -z;v.::: ~.
1-02 4-03 2-03 3-03 1-03 4-06 2-06 3-06 1-06 4-07 2-07 3-07 1-07 Page 2 of 4
JPM 78.AD.2319.102 KEY Attachment C 01-078-001 Revision 11 Page 11 of 16 lPRM vs. OPRM Status LPRM OPRM Cells (APRMlOPRM - Cell) 32-57 A LEVEL C.B LEVEL:> C LEVEL D LEVEL APRM2-Cell 02 3-02 4-02 1-02 2-03 3-03 4-03 1-03 40-09 A LEVEL B LEVEL ( C LEVEL:::> D LEVEL 2-29 3-29 1=29 4-29 2-30 3-30 1-30 4-30 40-17 A LEVEL B LEVEL C LEVEL D LEVEL 1-24 2-24 3-24 4-24 1-25 2-25 3-25 4-25 1-29 2-29 3-29 4-29 1-30 2-30 3-30 4-30 40-25 C ALEVED BLEVEL C LEVEL n LEVEL 1-18 4-18 2-18 3-18 1-19 4-19 2-19 3-19 1-24 4-24 2-24 3-24 1-25 4-25 2-25 3-25 40-33 A LEVEL BLEVEL C LEVEL D LEVEL 3-12 4-12 1-12 2-12 3-13 4-13 ",3 2-13 3-18 4-18 1-18 2-18 3-19 4-19 1-19 2-19 40-41 CA LEVEL :::> B LEVEL ~LEVE0 D LEVEL 2-07 3-07 1-07 4-07 2-08 3-08 1-08 4-08 2-12 3-12 1-12 4-12 2-13 3-13 1-13 4-13 40-49 C A LEVEL"::> B LEVEL C CLEVEi) D LEVEL 1-03 2-03 3-03 4-03 ! 1-07 2-07 3-07 4-07 1-08 2-08 3-08 4-08 40-57 CA LEVEL-=> CBLEVED C LEVEL D LEVEL 1~O3 4-03 2-03 3-03 48-09 A LEVEL B LEVEL C LEVEL D LEVEL I 2-30 3-30 4-30 1-30 48-17 A LEVEL B LEVEL C LEVEL D LEVEL 3-25 1-25 4-25 2-25 3-26 1-26 4-26 2-26 3-30 1-30 4-30 2-30 48-25 A LEVEL BLEVEL C CLEVED D LEVEL 4-19 1-19 ~-19 3-19 4-20 1-20 2-20 3-20 4-25 1-25 2-25 3-25 4-26 1-26 2-26 3-26 48-33 A LEVEL B LEVEL C LEVEL D LEVEL 4-13 2-13 3-13 1-13 4-14 2-14 3-14 1-14 4-19 2-19 3-19 ",9 4-20 2-20 3-20 1-20 Page 3 of 4
JPM 78.AD.2319.1 02 KEY Attachment C 01-078-001 Revision 11 Page 12 of 16 LPRM vs. OPRM Status LPRM OPRM Cells (APRM/OPRM - Cell) 48-41 A LEVEL C B LEVEL~ C LEVEL D LEVEL APRM2-Cell 08 ;;s-ut$ 4-08 1-08 2-13 3-13 4-13 1-13 2-14 3-14 4-14 1-14 48-49 A LEVEL c BLEVEL ' ) C LEVEL D LEVEL 3-08 ..-=mY 4-08 2-08 56-17 A LEVEL B LEVEL C LEVEL D LEVEL 3-26 4-26 1-26 2-26 56-25 A LEVEL B LEVEL C LEVEL D LEVEL 2-20 3-20 1-20 4-20 2-26 3-26 1-26 4-26 56-33 cALEVEL) B LEVEL cCLEVEL) D LEVEL
- I q. 2-14 3'-~ 4-14 1-20 2-20 3-20 4-20 56-41 C ALEVEL~ B LEVEL C LEVEL D LEVEL T-~ 4-14 2-14 3-14 Page 4 of 4
JPM 78.AD.2319:f 02 KEY Attachment C 01-078-001 Revision 11 Page 13 of 16 OPRM Status Control Log OPRM Cell Assignments for APRM 1 LPRM(s): 4()"'57A (to be bypassed) Impacted Cell(s): 3 (from Attachment C) Operable Cells: 24 (from OOA ST A81L1TY display) Circle LPRMs inoperable in cell with LPRM(s) to be bypassed (already and one to be bypassed). CELL 10: LPRM #1 LPRM #2 LPRM#3 LPRM #4 01 16-578 (24-57~ C24-49(;) (16-49ED 02 (24-570 32-570 32-490 (24-490 03 32-570 (4(),.57A) 40-49A 32-490 04 OS-49A (16-49fD 16-410 08-41C 05 (16-498:) (24-49C:) C24-41/f) 16-410 06 (24-49<:;) 32-490 C32-41 a) (24-41~ 07 32-490 (40-49A:) (40-41G) (32-41fD OS (40-49~ ( 48-49ID 48-410 (40-41C:) 09 OS-41C 16-410 16-330 (OS-33C) 10 16-410 ("24-41/!:) (24-3311:) 16-330 11 12 13 C24-41A:) ("32-418) C40-41C) 32-41B:> C40-41C) 48-410
= 32-338 40-33C 4S-330 C24-33,lt;)
32-338 40-33C 14 48-410 ~6-41A) C"A-33A) 48-330 15 c...oa-33cJ 16-330 16-258 Co8-25A) 16 16-330 (z4-33P 24-25C 16-258 17 I (.24-3W 32-338 32-250 24-25C 18 32-338 40-33C C4.0-25A) 32-250 19 40-33C 48-330 48-258 ~0-25V 20 4~P (5.6-33A) 56-25C 48-258 21 <..oB-2SAJ 16-258 16-178 (J)8-17A) 22 16-258 24-25C 24-17C 16-178 23 24-25C 32-250 32-170 24-17C 24 32-250 ~0-2W 40-17A 32-170 25 (40-25A) 48-258 48-178 40-17A 26 4S-258 56-25C 56-17C 48-178 27 16-178 24-17C 24-09A I 16-090 28 24-17C 32-170 '-...32-0gs) 24-09A 29 32-170 40-17A C40-09C> C32::0913) 30 40-17A 48-178 48-090 \....4.0-0gc) 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: 24 (following bypass of LPRM(s>> If <22 cells remain operable, the OPRM will become inoperable following bypass of LPRM(s). 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 bypassed) Impacted Cell(s): None (from Attachment C) Operable Cells: 30 (from aOA STABILITY display) Circle LPRMs inoperable in cell with LPRM(s) to be bypassed (already and one to be bypassed). 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 (16-2~ 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 (16-25~ 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 Attachment C 01-078-001 Revision 11 Page 15 of 16 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) Circle LPRMs inoperable in cell with LPRM(s) to be bypassed (already and one to be bypassed). CELL ID: LPRM #1 LPRM#2 LPRM#3 LPRM#4 1 16-57D 24-57B I 2~ 16-49A 2 2..!:.QlB (32-57B) (32-49C) 24-49A 3 (32-57B) 4cr-57D ( 40-49C) (32-49Cj 4 08-49C 16-49A 16-4"1 B OF1B 5 16-49A 2~A 24-41D 16-418 6 24-49A (32-49C) 32-41D 24*41D 7 (~?-d~r,) (40-49C) 40-41B 32-41D 8 (,40-49G) 48"::4§"A (48-418) 40-418 9 08-418 16-418 ~C 08-33A 10 16-418 24-41D (24-33C) 16-33C 11 24-41D 32-41D 32-33A (24-33Cj 12 32-41 D 40-418 40-33A 3~J.\ 13 40-41B ( 48-418) 48-33C 40-33A 14 (1i8-418") 56-41D ~56-33C) 48-33C 15 0B=3'3'A 16-33C lo-~oU 08-25D 16 16:.a3C (24-33C) 24-258 16-25D 17 (24-33C) 3~A 32-25B 24-25B 18 32=33A 40-33A 40-25D 32-258 19 40-33A 48-33C 48-25D 40-25D 20 48-33C (b6-33C) 56-258 48-25D 21 08-25D lO"Z!)U 16-17A 08-17C 22 16-25D 24-258 24-17A 16-17A 23 24-25B 32-25B 32-17C 24-17A 24 32-25B 40-25D 40-17C 32-17C 25 otv-25D 48-25D 48-17A 40-17C 26 48-25D 56-25B 56-17A 48-17A 27 16-17A 24-17A 24-09D 16-09B 28 24-17A 32*17C 32-09D 24-09D 29 32-17C 40-17C 40-098 32-09D 30 40-17C 48-17A 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
JPM 78.AD.2319.1 02 KEY Attachment C 01-078-001 Revision 11 Page 16 of 16 OPRM Cell Assignments for APRM 4 LPRM(s}: 40-57 A (to be bypassed) Impacted Cell(s): None (from Attachment C) Operable Cells: 30 (from ODA STA81L1TY display) Circle LPRMs inoperable in cell with LPRM(s) to be bypassed (already and one to be bypassed). CELL ID: LPRM #1 LPRM #2 LPRM #3 LPRM #4 1 16-57A 24-57D 24-498 16-49C 2 24-57D 3WC (32-49~ 24-498 3 32-57C (40-57EV 40-49D C32-49~ 4 08-49D 16-49C (16-41C) 08-41D 5 16-49C 24-498 24-418 (16-41 C) 6 24*498 (32-49A) 32-41 A 24-418 7 (32-49A) 40-49D 40-41D 32-41 A 8 I 40-49D 48-49C 48-41C 40-41D 9 08-41D ( 16-41C) 16-33A 08-338 10 (J6-41~ 24-418 24-33D 16-33A 11 24-418 I 32-41 A 32-33C 24-33D 12 32-41 A 40-41 D 40-338 32-33C 13 40-41D 48-41C 48-33A 40-338 14 48-41C 56-418 56-33D 48-33A 15 08-338 16-33A 16-25A 08-258 16 16-33A 24-33D I 24-25D 16-25A 17 24-33D 32-33C 32-25C 24-25D 18 32-33C 40-338 I 40-258 32-25C 19 40-338 48-33A 48-25A 40-258 20 48-33A 56-33D 56-25D 48-25A 21 08-258 16-25A 16-17C 08-17D 22 16-25A 24-25D 24-178 16-17C 23 24-25D 32-25C 32-17A 24-178 24 32-25C 40-258 40-17D 32-17A 25 40-258 48-25A 48-17C 40-17D 26 27 28 48-25A 16-17C 24-178 56-250 24-178 32-17A
= 56-178 24-098 32-09A 48-17C 16-09C 24-098 29 32-17A 40-170 40-090 32-09A 30 40-17D 48-17C 48-09C 40-090 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): 0 . Operable Cells: 30 (following bypass of LPRM(s>> If <22 cells remain operable, the OPRM will become inoperable following bypass of LPRM(s). 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, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET 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
Title:
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. 0 Page 1 of 7
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SRO 00.AD.1 018.001 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required andlor posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. NDAP-QA-0309, Primary Containment Access and Control, rev 26 B. Tech Spec 3.3.6.1, Primary Containment Isolation Instrumentation. rev 4 C. TRM 3.6.1, Containment Venting and Purging, rev 0 D. OP-173-001. Containment Atmosphere Control System, rev 37 E. AR-015-001, 13.8/4 KV Switchgear Distribution And Diesel Generators A, B, & C OC653, rev 36 III. OPERATIONAL ACTIVITIES None IV. TASK CONDITIONS A. Unit 1 is in Mode 3. B. 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. C. 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. 0 Page 2 of 7
V. 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 hours.
- 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. 0 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 the Task Conditionsllnitiating Cue sheet. The steps of this JPM may be performed in any order.
- 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: SRO JPM No.: OO.AD.1018.051 Student Name: Step Action Standard Eval Comments
*2. Determine that BOTH SGTS Exhaust Radiation Review step 6.2.3 and determine that High trips are required to be operable for insufficient SGTS Exhaust Rad Monitors are containment purge in Mode 3. available to continue containment purge, and TRM 3.6.1 should be evaluated.
Document on Task Condition sheet.
*3. Evaluate TRM 3.6.1 Refer to TRM 3.6.1, and determine that action A.1 is required with less than the minimum number of SGTS Exhaust High Radiation isolation channels operable, and primary containment purging must be immediately suspended.
Document on Task Condition sheet.
*4. Evaluate Tech Spec 3.3.6.1 Refer to TS 3.3.6.1 and determine that action A.1 is required since less than the required number of channels is operable, and the failed channel must be placed in EVALUATOR CUE:
TRIP within 24 hours (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. 0 Page 5 of 7
TASK CONDITIONS A. Unit 1 is in Mode 3. B. 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. C. 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-D12-0N017A) 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 A. Unit 1 is in Mode 3. B. 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. C. 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, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET 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
Title:
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 By: 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 Performance: 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 INFORMATION JOB PERFORMANCE MEASURE SRO 00.EP.001.087 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self-Checking is required. II. REFERENCES A. EP-PS-100, Revision 26 B. EP-PS-100, Tab E, Revision 28 C. Emergency Plan - Units 1 and 2 D. EP-TP-001, Emergency Classification Level Manual, Revision 3 E. EP-TP-001, Section C, Revision 3 III. OPERATIONAL ACTIVITIES None IV. TASK CONDITIONS A. Unit 1 in Mode 4. B. "A" RHR Pump is in service for Shutdown Cooling. C. A rigging incident inside the Containment resulted in damage to Recirc Loop 'A' suction piping causing a rapid reduction in RPV level. D. Division 2 Core Spray and LPCI are injecting full flow. E. Primary Containment was evacuated and the personnel hatch is closed with interlocks maintained prior to and during the transient. F. RPV level has been stabilized at -168 inches Fuel Zone. G. Secondary Containment pressure is -0.28 inches WG with Standby Gas Treatment in service. FORM NTP-QA-31.8-1, Rev. 0
V. INITIATING CUE Classify the Event, and implement the Emergency Plan as the Control Room Emergency Director in accordance with EP-PS-100. VI. TASK STATEMENT A. Declaration of a Site Area Emergency based on classification CS4 within 15 minutes. B. Declaration of a General Emergency based on classification CG4 within 15 minutes of second set of conditions. C. 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. VII. 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 OO.EP.001.086 Candidate Name: Step Action Standard Eval Comments EVALUATOR CUE: To begin this JPM provide the candidate with CUE SHEET#1 :
- When the candidate is ready to begin the JPM, inform the candidate that this is a TIME CRITICAL JPM.
Record START TIME - - - - - - ~- . ----
*1. Classify the emergency as Evaluate updated information.
conditions indicate. Review Emergency Classification EVALUATOR CUE: Level Manual, EP-TP-001. If asked, conditions have not Declare a SITE AREA changed. EMERGENCY in accordance with Classification CS4 << -161" with EVALUATOR NOTE: Secondary Containment) When candidate declares the initial EAL classification, Record TIME Time to determine correct EAL must be within 15 minutes of
~TARTTIME FORM NTP-QA-31.8-1, Rev. 0
Page 4 of 8 Step Action Standard Eval Comments
- 2. 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.
- 3. Document and communicate the Announce to Control Room emergency classification. personnel 1} Assuming duties of Emergency Director
- 2) Emergency Classification
- 3) Time and Date of Classification
- 4. Appoint E-Plan Communicator. Appoint E-Plan Communicator.
Instruct E-Plan Communicator to EVALUATOR CUE: immediately perform EP-PS-126. Acknowledge the appointment of the E-Plan Communicator, when given the ENR form indicate that the E-Plan Communicator will transmit the form.
- 5. Appoint NRC Communicator. Appoint NRC Communicator.
Instruct NRC Communicator to EVALUATOR CUE: perform EP-PS-135, NRC Communicator. Acknowledge the appointment of the NRC Communicator. I FORM NTP-QA-31.8-1, Rev. 0
Page 5 of 8 Step Action Standard Eval Comments
- 6. Generate and approve ENR Form for Fill out ENR Form from Tab 9 and transmittal. authorizes Form for transmittal.
EVALUATOR CUE: Review ENR Form with E-Plan Communicator prior to If JPM is not performed in the simulator, transmittal. when requested, inform the student that:
- Wind Direction is 210 degrees
- Wind Speed is 5 mph If performed in the Simulator, student should use current PICSY data.
EVALUATOR CUE:
- 1. Inform the student that no further EP PS-100 actions are required with respect to the previous classification.
- 2. Provide candidate with CUE SHEET
#2.
- 3. Record START TIME
- 7. Refer to EP-TP-001 and evaluate the Refer to EP-TP-001 Category C, impact of new conditions. and determine that the HPCI blowout panel failure renders EVALUATOR NOTE: Secondary Containment NOT established and water level has 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 be within 15 minutes of START TIME noted 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 Action Standard Eval Comments
- 8. Generate and approve ENR Form for Fill out ENR Form from Tab 9 and transmittal. authorizes Form for transmittal.
EVALUATOR CUE: Review ENR Form with E-Plan 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 mph If performed in the Simulator, student should use current PICSY data.
- 9. Refer to EP-PS-100 Refer to EP-PS-100 tab E and determine that a PAR must also be performed in accordance with EP PS-100-6 EVALUATOR CUE:
After the candidate determines a PAR is required, direct the candidate to determine the correct PAR for current plant conditions FORM NTP-QA-31.8-1, Rev. 0
Page 7 of 8
- 10. Perform EP-PS-100 Tab 5, "PPL Refer to EP-PS-100 Tab 5 and Emergency Dose Assessment and determine:
Protective Action Recommendation (PAR)
- PA-2: Has a GE been Guide" declared? YES EVALUATOR CUE:
- PA-3: Release via 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 NOTE:
- Per PA-7:
When candidate completes PAR
- Evacuate 0-2 miles and indicates need to transmit it to
- Shelter 2-10 miles the Senior State Official:
- Citizens take KI per Record TIME 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 A. Unit 1 in Mode 4. B. "A" RHR Pump is in service for Shutdown Cooling. C. A rigging incident inside the Containment resulted in damage to Recirc Loop 'A' suction piping causing a rapid reduction in RPV level. D. Division 2 Core Spray and LPCI are injecting full flow. E. Primary Containment was evacuated and the personnel hatch is closed with interlocks maintained prior to and during the transient. F. RPV level has been stabilized at -168 inches Fuel Zone. G. 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 A. Unit 1 in Mode 4. B. "A" RHR Pump is in service for Shutdown Cooling. C. A rigging incident inside the Containment resulted in damage to Recirc Loop 'A' suction piping causing a rapid reduction in RPV level. D. Division 2 Core Spray and LPCI are injecting full flow. E. Primary Containment was evacuated and the personnel hatch is closed with interlocks maintained prior to and during the transient. F. RPV level has been stabilized at -168 inches Fuel Zone. G. 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.)
- 1. 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.
- 2. 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)
=
- 1. 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.
- 2. 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, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET 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 NDAP-QA-0025 Completed By: Validated: Tracy North 8/3/10 P. Moran 11/29/10 Writer Date InstructorlW riter Date Approval: ~.lear,'Ii'"' £, 1>1. 10./6 rng. SUpv. 15 Date of Performance: Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name: Last First M.1. Employee # / S.S. # Performance Evaluation: ( ) Satisfactory } Unsatisfactory Evaluator Name: Signature Typed or Printed Comments: FORM NTP-QA-31.8-1, Rev. 0 Page 1 of 7
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SIRO 00.AD.3246.052 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. NDAP-QA-0025, Work Hour Limits for Station Staff, rev 8 B. 10CFR26.205, Work Hours III. OPERA1*IONAL ACTIVITIES None IV. TASK CONDITIONS A. 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 hour overtime shift from 0600-1800. B. 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. 0 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 hour break prior to the work start and/or will exceed 26 hours worked within a 48 hour 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 Action Standard Eval Comments EVALUATOR NOTE: This JPM should be performed in the classroom (or similar environment). Ensure a copy of the current revision of NDAP-QA 0025 is available for candidate use if requested. EVALUATOR CUE: To begin this JPM provide the task conditionsllnitiating cue sheet to the candidate.
- 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 I
*2. Refer to work history and analyze for additional Refer to and analyze work hours requested work hours FORM NTP-QA-31.8-1, Rev. 0 Page 4 of 7
PERFORMANCE CHECKLIST Appl. To: SIRO JPM No.: 00.AD.3246.052 Student Name: Step Action Standard Eval Comments
*3. Determine that working the requested shift will Determine that the required 10 hour break 12 hours Sunday 9/12 +
result in exceeding limits. between work periods will not be met. 15 hours Saturday 9/11 = Andlor that the additional hours will result in 27 hour in a 48 hour exceeding 26 hours worked within a 48 hour period. 2100 to 0600 = 9 period hours vs. 10 hours.
- 4. Report to Shift Supervision that the overtime Makes report to shift supervision.
request CANNOT be honored due to the 10 hour break between work periods will not be met and/or exceeding 26 hours within 48 hours if the requested hours were to be worked. EVALUATOR CUE: When candidate reports results, report that this JPM is complete. EVALUATOR NOTE: Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures? FORM NTP-QA-31.8-1, Rev. 0 Page 5 of 7
TASK CONDITIONS A. 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 hour overtime shift from 0600-1800, as the Unit 1 PCOM. B. 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 C. 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
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE ) APPROVAL AND ADMINISTRATIVE DATA SHEET RD 00. EP.1135.081 o 11/3/10 Generic 2.4.43 3.2 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:
~~M.1>.I!3 NCJarrng:Supv. Date Time Critical 15 Minutes Date of Performance: Validated Time (Min.) Time Taken (Min.)
JPM Performed By: Student Name: _ _ _ _ _ _ _ _ _---:=-_ _ _ __ Last First M.1. Employee # 1 S.S. # Performance ( Satisfactory ( ) Unsatisfactory Evaluation: Evaluator Name: Signature Typed or Printed Comments: FORM NTP-QA-31.8-1, Rev. 0
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE RO OO.EP.1135.081 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD~OO2, Standards for Shift Operations. B. 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.
- 2. 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.
C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. EP~PS-100 "Emergency Director, Control Room: Emergency-Plan-Position Specific Instruction" (Rev. 26) B. EP-PS-126, "Emergency Plan Communicator: Emergency Plan-Position Specific Instruction" (Rev. 27 C. EP-TP-003, "Communication Process" (Rev. 5) D. EP-AD-OOO-301, "Emergency Notification Reporf' (Rev. 12) III. REACTIVITY MANIPULATIONS This JPM satisfies the following Operational Activity(s): None IV. TASK CONDITIONS A. 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). B. An airborne release is in progress. V. INITIATING CUE You have been assigned as the Control Room Communicator. Transmit initial information about the Emergency Condition to required organizations, lAW the appropriate procedure. 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 CHECKLIST 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, and EP-PS-126 are available to support performance of this JPM.
- Have current, filled-out copy of ENR Form available with the INCORRECT line 4 label attached. (a table C label CS5 should be used)
- Ensure an ENR form with the correct CG4 label is available EVALUATOR NOTE:
To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet. Role playas Control Room ED and give student filled-out ENR Form. Time ENR form is given: Start time is above time MINUS 5 MINUTES (declaration time). Enter time of declaration(start time): The TIME CRITICAL portion of the JPM begins.
*Critical Step #Critical Sequence FORM NTP-QA-31.8-1, Rev. a
PERFORMANC)CHECKUST Page 4 of 9
.....J 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. L __
*Critical Step #Critical Sequence FORM NTP-QA-31.8-1, Rev. 0
)
PERFORMANClcHECKLIST Page 5 of 9 ......,J Appl. To/JPM No.: RO OO.EP.1135.081 Student Name' Step Action Standard Eval Comments
- 3. Within 15 minutes of declaration, using the purple Dial "191" on the purple colored button colored phone button, dial "191" to transmit the ENR form to the following:
(Dialing 191 will simultaneously connect the listed Verify the following agencies are on the line: agencies in a conference call.) (1) Penna. Emergency Management Agency EVALUATOR CUE: (2) Columbia County EMA If candidate is concerned about the button not being CLEARLY purple, Inform the candidate that the CTN (3) Luzerne County EMA 4915 button is PURPLE! (4) Joint Information Center EVALUATORIBOOTH CUE: Role-play the receiving agencies and confirm each agency is on the line and you are "Ready to Copy" 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 declaration" Record stop Time previously recorded. 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 1 This is a Drill
- 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 Student Name' Step Action Standard Eval Comments
- 7. Communicate Line 5 Communicate the following for line 5:
THERE IS: AN AIRBORNE RADIOLOGICAL RELEASE IN PROGRESS B. Communicate Line 6 Communicate the following for line 6: WIND DIRECTION IS FROM: 2n° WIND SPEED IS: 5 mph I
- 9. Communicate Line 7 Communicate the following for line 7:
THIS IS A DRILL EVALUATORIBOOTH 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.
- - -........ -.-~ ........- . - - --~ ........ -..- - - -- -
.. .. ......... -~---~
*Critical Step #Critical Sequence FORM NTP-QA-31.B-1, Rev. 0
<C'j Page 9 of 9
~
PERFORMANC/cHECKlIST 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? Task Cue Sheets? Procedures?
------ ---- --- - - - - --~- --------------' I *Critical Step #Critical Sequence FORM NTP*QA*31.8*1, Rev. 0
TASK CONDITIONS
) A. 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).
B. An airborne release is in progress. INITIATING ClIE You have been assigned as the Control Room Communicator. Transmit initial information about the Emergency Condition to required organizations, lAW the appropriate procedure. { Page 1 of 2
TASK CONDITIONS ) A. 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). B. An airborne release is in progress. INITIATING CUE You have been assigned as the Control Room Communicator. Transmit initial information about the Emergency Condition to required organizations, lAW the appropriate procedure. Page 2 of 2
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASlIRE APPROVAL AND ADMINISTRATIVE DATA SHEET SIRO 44.0N.1792.101 o 11/22110 256000 A4.0S 3.7/3.7 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task
Title:
Emergency Operation of Condensate System Completed By: Validated: Bob Pudish Writer 11/22110 Date Instru~ Approval: ~~ "l.'D,I!!. N I r Trng. Supv. Date 20 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.S-1, Rev. 0
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 44.0N.1792.1 01 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. ON-144-001, Emergency Operation of Condensate System (Rev. 10) .~ B. OP-AD-001, Operations Standards for System and Equipment Operation (Rev. 44) III. OPERATIONAL ACTIVITIES None IV. TASK CONDITIONS A. Unit 1 has experienced a loss of coolant accident. B. No injection sources are currently injecting into the Vessel. C. RPV pressure has been between 700-800 psig for 1 hour. D. RPV level is approximately -180 inches, steady on Compensated Fuel Zone Indicator. E. TBCCW is unavailable F. Instrument Air has been cross tied to U2. V. 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). VI. 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" r, VII. TASK SAFETY SIGNIFICANCE 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 CHECKLIST Page 30t ';J Appl. Tal SIRO JPM No 44.0N.1792.l0l Student Name Step Action Standard Eval Comments This JPM must be performed in the simulator. Setup was snapped to Setup the simulator to IC-l1. IC-39G for LOC-23 NRC Exam.
Insert the following malfunctions: IMF mfHP152015 HPCI trip IMF mfRC150011 RCIC trip IMF mfAD183001 ADS failed IMF cmfPM03_1 P206A CS tripped IMF cmfPM03_1 P206C IMF cmfPM03_1 P206B IMF cmfPM03_1 P206D .. " IMF cmfPM02_1 P1 O3A IMF cmfPM02_1 P1 O3B CRD trip IMF cmfPM03_1P132A IMF cmfPM03_1P132B TBCCWtrip IRF rf1AOl9001 f:100 IA cross tied to U2 Recirc Leak 2% to obtain -1BO" on Camp FZWL Consider snapping an IC for multiple performances then modify to 0%. of this JPM. DW has been sprayed once to lower pressure. MSIVs closed. When student is ready to begin JPM, place the FV- i OG04A(B)(C) in Auto. simulator in RUN. Shut off all Condensate Pumps immediately after Scram. The simulator booth operator should role playas the Start 'C' Condensate Pump immediately before NPO when required. beginning JPM. Ensure FIC-l050B in Auto. RPV pressure approx 700 psig
- Critical Step #Critical Sequence FORM NTP-QA-3l.B-2, Rev. 0
PERFORMAdcE CHECKLIST page40f~ Appl. Tol S/RO JPM No 44.0N.1792.101 Student Name Step Action Standard Eval Comments
- 1. Obtain ON-144-001. Student obtains procedure.
- Reviews Notes
- Determines Section 4.3 is applicable based on Plant conditions
- 2. Ensure a Rx Scram has been initiated. Student recognizes the Unit is scrammed.
- Mode Switch in Shutdown
- All Rods In
- 3. If the Rx is Shutdown and any Rx Feed Pump is still N/A in service ...
- 4. If the injection flow path is through any RFP N/A Discharge Isolation Valve ...
- 5. Ensure all Rx Feed Pumps are tripped. Student confirms RFPs are tripped on HMI
- Pump Icon states Tripped
- Pump Icon Gray
*6. Ensure all RFP Recirc valves FV-10604A,B,C Student observes RFP Recirc valves A controller FIC-1 0604A,B,C are in Manual and FV-10604A,B,C are in Auto Closed.
Student closes the valves by: 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 CHECKLIST page50f;-i Appl. Tol SIRO JPM No 44.0N.1792.101 Student Name Step Action Standard Eval Comments
- 7. If RPV pressure is < 650 psig ... N/A B. If RPV pressure> 650 psig: Student observes Control Room indications and recognizes only one Cond Pump is
- Shutdown all but one Condensate Pump running. (1 Red light on: 3 Amber lights on)
*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
;,r'
)
PERFORMANCE CHECKLIST page60f9~ Appl. Tol S/RO JPM No 44.0N.1792.101 Student Name Step Action Standard Eval Comments
- 12.
- After RPV Pressure is < 650 psig and RPV Student depresses Start pushbutton for one Condensate Pump after RPV Pressure is < 650 Level is at the lower range of the assigned 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)
- 13. Maintain RPV Pressure between 450-650 psig using Student reduces RPV pressure to 45(}650 psig Bypass Valves andlor SRVs. by opening SRV(s).
- 14. If feeding through LV-10641 , Manually Throttle LV- Student manually throttles LV-10641 by:
10641 FW LOW LOAD VALVE to maximize Injection Flow and minimize time above 143 amps on in
- Touches 641 on HMI service Condensate Pump.
- Touches INC I DEC as necessary
- Monitors Cond Pump amps (minimize time above 143 amps)
- 15. 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 in procedure.
- 16. Dispatch Field Operators to Isolate the Condensate Student contacts Field Operator to isolate Cond Recirc & Rx Feedpump Recirc Flow paths in and RFP Recirc Flow paths.
accordance with Attachment F.
- Critical Step #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0
'1 )
Appl. Tal SIRO JPM No PERFORMANCE CHECKLIST 44.0N.1792.101 Student Name Page 7 of 9 Step Action Standard Eval Comments EVALUATOR CUE Role playas Field Operator and inform Student that you will isolate Condensate and Feedpump Recirc Flow paths.
- 17. Operate Condensate Pumps one at a time, Student monitors Cond Pump bearing temp on sequentially, to maintain bearing temp below 265°F PICSY display CNDPP.
(PICSY display CNDPP)
- 18. If the RPV injection is lost due to the degraded N/A Instrument Air Header Pressure prior to completion of Attachment F ...
- 19. If reactor is not shutdown, maintain level per EO- N/A 100-113 ...
- Critical Step #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0
)
PERFORMANCE CHECKLIST Page 8 of 9"wt1 Appl. Tol SIRO JPM No 44.0N.1792.101 Student Name Step Action Standard Eval Comments
- 20. If reactor is shutdown, to minimize condensate pump Student raises RPV level above -161" by 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 instrument reaching a bearing temperature of 265°F or when level reaches +54" (EVALUATOR: SEE CUE ON NEXT PAGE FOR TERMINATION CRITERIA)
- Start next sequential pump when RPV level drops to -129" Student monitors Cond Pump bearing temp.
- Repeat the previous Steps 4.3.15.a and b as Student monitors RPV level.
necessary until there are no Condensate Pumps available for use or TSCCW has Student shuts down Condensate Pump prior to been restored. bearing temp reaching 265°F.
- 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 Pumps. alternate means of cooling for TSCCW andlor Condensate Pumps.
EVALUATOR CUE Role Playas TSC that alternate means of cooling are being pursued.
- Critical Step #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 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 }
- 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 hour.
- 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, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET 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:
~L~a-s~t----------------=Fi~rs~t------~M~.~I.-
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 INFORMATION JOB PERFORMANCE MEASURE SIRO 64.0P.4841.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats , etc., is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. OP-164-001, Reactor Recirculation System (Rev. 56) III. OPERATIONAL ACTIVITIES None IV. TASK CONDITIONS A. A Reactor SCRAM has occurred and all control rods inserted. B. Both Reactor Recirculation Pumps have tripped due to -38 inches Reactor Water Level being reached during the scram. C. The "A" MG Set Generator and Drive Motor Lockout Relays have been reset. V. INITIATING CUE Restore the "A" Reactor Recirculation Pump to service in accordance with the OP-164 001 Hard Card. VI. TASK STANDARD The "A" Reactor Recirculation Pump is placed in service in accordance with OP-164 001. VII. 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 page30f~ 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 was snapped to IC Setup the simulator to a full power IC. 394 for LOC-23 NRC Exam. 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 HS Resets 1C063A LlO relay. 14001A, MG SET A DRV MTR BKA. Insert the following commands: IRF rfRR164011 f:TRIP_RESET Resets 1A101-10 LlO relay. IRF rfRR164011 f:NORM Assign the following Keys: {Key[1]} IRF rfRP158035 f:CL_CB3A Resets RPT Breaker at 1C609 (URR) {Key[2]} IRF rfRP158036 f:CL_CB4A 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 Student determines that no other Recire First Recire Pump Post Scram. Pump has been started post SCRAM.
- Critical Step #Critieal Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1
')
.J ...".;
PERFORMANCE CHECKLIST Page 4 of 9 Appl. Tol SIRO JPM No 64.0P.4841.101 Student Name Step Action Standard Eval Comments
- 3. Recirculation pump trip is understood and trip Student determines from task conditions and condition has cleared and all control rods are fully state of the plant that the pump trip is inserted. understood, the trip condition has cleared and that all control rods are fully inserted.
i
- 4. MG Set Generator and Drive Motor Lockout Relays Student determines from task conditions that reset. the MG Set Generator and Drive Motor Lockout Relays are reset.
- 5. This section shall not be used when at power (mode Student confirms that the plant is not in 1 or 2). mode 1 or 2.
- 6. Ensure MG Set Ventilation System in operation. Student confirms MG Set Ventilation in operation.
- 7. Ensure Reactor Recirc Pump motor winding cooling Student confirms on 1C681 :
water is aligned to "A" pump as follows:
- HV-18791 A1/A2 OPEN
- RRP A Clg Wtr DB Iso Valves HV-18791
- HV-18792 B1/B2 OPEN A1/A2 OPEN
- RRP A Clg Wtr IB Iso Valves HV-18792 B1/B2 OPEN
- 8. Ensure Reactor Recirc Pump Seal Package cooling Student confirms on 1C668:
water is aligned to "A" pump as follows:
- RBCCW OB CONTN ISO MOVS HV
- RBCCW OB CONTN ISO MOVS HV- 11313/14 OPEN 11313114 OPEN
- RBCCW IB CONTN ISO MOVS HV
- RBCCW IB CONTN ISO MOVS HV- 11345/46 OPEN 11345/46 OPEN
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1
.J Appl. Tol S/RO JPM No PERFORMANCE CHECKLIST 64.0P.4841.101 Student Name Page 5 of 9 Step Action Standard Eval Comments
- 9. Ensure Reactor Recirc Pump RPT breakers at Student contacts an NPO for confirmation 1C609 (URR) 1A20501 and 1C611 (LRR) 1A20502 that Reactor Recirc Pump RPT breakers at are closed by observing the RED indicating light 1C609 (URR) 1A20501 and 1C611 (LRR) illuminated. 1A20502 are closed.
BOOTH OPERATOR CUE Press {Key[1]} and {Key[2]} to ensure RPT breakers are closed at 1C609 (URR) and 1C611 (LRR). EVALUATOR CUE Role playas NPO and report that RRP RPT breakers at 1C609 (URR) and 1C611 (LRR) are closed.
- 10. Ensure Reactor Recirc Pump A Speed SY-B31- At HMI student confirms / adjust:
1R621A Controller in MANUAL with a speed setting
- SY-831-1 R621 A Controller in of approximately 0%. MANUAL with a controller output setting of approximately 0%
- 11. Comply with TRO 3.8.2.1. Student informs Shift Supervision to comply with TRO 3.8.2.1.
EVALUATOR CUE Role playas Shift Supervision indicating that TRO 3.8.2.1 will be taken for action that will be occurring in the next step.
~ ...... - .
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1
PERFORMAdcE CHECKLIST Page 6 of 9 Appl. Tal SIRO JPM No 64. OP .4841.101 Student Name Step Action Standard Eval Comments
-~-
- 12. Place Recirc A MOV OL BYPS HV-143-F031A I Student places Recirc A MOV OL BYPS HV F032A switch to TEST position. 143-F031A I F032A switch to TEST position.
Student confirms Recirc Loop "A" Discharge Valves In Test annunciator ALARMS.
- 13. Ensure Recirc Pump "An Suet HV-143-F023A Student ensures Recirc Pump "A" Suet HV OPEN. 143-F023A OPEN.
- 14. Ensure Recirc Pump 'W' Dsch Byps HV-143-F032A Student ensures Recirc Pump"A" Dsch OPEN. Byps HV-143-F032A OPEN.
*15. Ensure CLOSED or CLOSE Recirc Pump "Au Dsch Student ensures CLOSED or CLOSES HV-143-F031A. Recirc Pump "A" Dsch HV-143-F031A.
I
- 16. Depress Scoop Tube "A" Lock or Reset HS-B31- Student depresses Scoop Tube "A" Lock or 1S03A Reset pushbutton - 4 to 5 seconds (to allow Reset HS-B31-1S03A Reset pushbutton - 4 position amplifier timer to clear and reset logic to to 5 seconds.
seal in).
- 17. Observe Recirc MG "A" Scoop Tube Drive Lock Confirms Recirc MG "Au Scoop Tube Drive I Annunciator NOT ALARMING. Lock Annunciator NOT ALARMING.
I NOTE (1) (PICSY format: GD HUCD) Utilize steam dome temperature, Camp. Pt. NFA05 or Steam Tables. NOTE (2) RPV Bottom Head Drain temperature is valid even if RWCU is isolated.
*Critical Step #Critical Sequence Form NTP-QA-31.8-2. Rev. 0, Page 1 of 1
PERFORMA,jCE CHECKLIST Page 70f;-' Appl. Tol SIRO JPM No 64.0P.4841.101 Student Name Step Action Standard Eval Comments
- 18. 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 coolant temperature and reactor pressure vessel coolant temperatures in Unit 1 log.
- Ensure AT between bottom head coolant temperature and reactor vessel coolant temperature s 145 OF.
- Record AT between reactor coolant temperature in recirculation loop to be started and reactor pressure vessel coolant temperature in Unit 1 log.
- Ensure AT between reactor coolant temperature in recirculation loop to be started and reactor pressure vessel coolant temperature s 50 OF.
EVALUATOR CUE Ensure the student SIMULATES the announcement over the page.
- 19. Announce twice over Plant PA System: "Attention Student SIMULATES making the PA aI/ personnel, a recirc pump start is about to take announcement.
place causing a potential loss of lighting, personnel should take precautions with work in progress".
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1
J \wi PERFORMANCE CHECKLIST Page 8 of 9 Appl. Tol SIRO JPM No 64.0P.4841.101 Student Name Step Action Standard Eval Comments
- 20. 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).
- 21. Observe the following: Student confirms the following actions occur:
- MG SET A DRIVE MTR BKR CLOSES
- MG SET A DRIVE MTR BKR CLOSES
- G EN 1A SPEED indication INCREASES
- GEN 1A SPEED indication INCREASES
- After 11 seconds, GENERATOR A FIELD
- After 11 seconds, GENERATOR A BREAKER closed indicator light FIELD BREAKER closed indicator ILLUMINATES light ILLUMINATES
- RECIRC A DRIVE FLOW indication
- RECIRC A DRIVE FLOW indication INCREASES INCREASES
- 22. 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.
- 23. Slowly ADJUST REACTOR RECIRC PUMP A At HMI, student slowly adjusts REACTOR SPEED SY-B31-1 R621A controller to achieve RECIRC PUMP A SPEED SY-B31-1R621A approximately 30% generator speed as indicated on controller to achieve - 30% generator speed SI-14032A. as indicated on SI-14032A.
- 24. 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 F032A switch to NORM position.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1
-~\
PERFORMAFiCE CHECKLIST '-' Page 90t 9 Appl. Tol SIRO JPM No 64.0P.4841.101 Student Name Step Action Standard Eval Comments
- 25. Clear TRO 3.8.2.1. Student informs Shift Supervision that they may clear TRO 3.8.2.1.
EVALUATOR CUE Role playas Shift Supervision indicating that TRO 3.8.2.1 will be cleared. EVALUATOR CUE This completes the JPM. EVALUATOR I Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures? I --- --- I
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1
TASK CONDITIONS A A Reactor SCRAM has occurred and all control rods inserted. B Both Reactor Recirculation Pumps have tripped due to ~38 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 OP-164 001 Hard Card. Page 1 of 2
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 34.EO.1619.151 o 11/22110 400000 A4.01 3.1/3.0 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task
Title:
Reset Drywell Cooling Isolation and Restore Drywell Cooling lAW ES-134-001 (Control Room Actions) Alternate Path Completed By: Validated: Bob Pudish Writer 11/22110 Date Inst~ Dat~1 Approval: ~'r ;; armg.~ m,1)"e SUpv. 10 Date of Performance: Validation Time (Min.) Time Taken (Min.) ..IPM 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 INFORMATION JOB PERFORMANCE MEASURE SIRO 34.EO.1619.151 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES ES-134-001, Restoring Drywell Cooling With A LOCA Signal Present (Rev. 17) III. OPERATIONAL ACTIVITIES This JPM satisfies the requirements of Operational Activity{s): NONE IV. TASK CONDITIONS A. An ATWS has occurred coincident with a loss of drywell cooling. B. EO-1 00-113 is being implemented for leveVpower control. C. EO-1 00-1 03 is being executed for primary containment control. D. ES-134-001 is being implemented and is complete through Step 4.2. E. CIG 90 # header has been restored. F. MSIVs have been opened lAW ES-184-002, REOPENING MSIVS BYPASSING ISOLATIONS. V. INITIATING CUE Reset Drywell Cooling LogiC isolations and restore Drywell Cooling in accordance with ES-134-001. 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
.",,) )
PERFORMANCE CHECKLIST
'III Page 3 of 9 Appl. To/JPM No.: SIRO 34.EO.1619.151 Student Name: _ _ _ _ _ _ _ _ __
Step Action Standard Eval Comments EVALUATOR NOTE Setup was snapped to IC-392 for LOC-23 NRC Exam.
- 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.
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 ES 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 Student obtains Controlled copy.
DRYWELL COOLING WITH A LOCA SIGNAL PRESENT.
- 2. Review Sections 1.0 through 3.0. Student review Sections 1.0 through 3.0.
- Section 1,2,3 reviewed .
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
, )
PERFORMANCE CHECKLIST
.,j Page 4 of 9 App\. To/JPM No.: SIRO 34.EO.1619.1S1 Student Name: _ _ _ _ _ _ _ _ __
Step Action Standard Eval Comments
- 3. Check for approval in Section 4.1. Student verifies Shift Manager approval at step 4.1.
- Approval verified.
- 4. Verify step 4.2 is marked as complete Student verifies step 4.2 is marked as complete.
- Step 4.2 verified completed.
- 5. Selects the correct section to perform. Student selects section 4.3.
- Goes to Section 4.3.
NOTE Steps 4.3.1.a through d are performed at Panel 1C681. 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.
- Critical Step #Critical Sequence Form NTP~QA~31.8~2, Rev. 0
') J PERFORMANCE CHECKLIST Page 5 of 9 Appl. To/JPM No.: S/RO 34.EO.1619.151 Student Name:_ _ _ _ _ _ _ _ _ __
Step Action Standard Eval Comments
*6. Ensure the following valves are closed prior to Student verifies position of the following resetting isolation logic: valves:
A ClRS ClG WTR DB ISO VlVS HV-18781A1 and A ClRS ClG WTR DB ISO VlVS HV-18781A2. HV-18781A1 and HV-18781A2.
- Amber light LIT and red light NOT LIT A ClRS ClG WTR IB ISO VlVS HV-18782B1 and A ClRS ClG WTR IB ISO VlVS HV*18782B2. HV-18782B1 and HV-18782B2.
- Amber light LIT and red light NOT LIT
*B ClRS ClG WTR DB ISO VlVS HV-18781B1 and B ClRS ClG WTR DB ISO VlVS HV-18781B2. HV-1878181 and HV-18781B2.
- Initially: Amber light NOT LIT and red light LIT (Recognizes valves Initially Open, manually closes the valves)
- Switch to Close : Amber light LIT and red light NOT LIT 8 ClRS ClG WTR 18 ISO VlVS HV-18782A1 and B ClRS ClG WTR 18 ISO VlVS HV-18782A2. HV-18782A1 and HV-18782A2.
- Amber light LIT and red light NOT LIT
- 7. If Containment Instrument Gas has not been restored Based on initial conditions: Student by ES-1B4-002. Ensure the following are closed at determines that CIG 90# header has Panel 1C601 prior to resetting isolation logic: been restored.
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
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
"', J PERFORMANCE CHECKLIST
.",j Page 6 of 9 Appl. To/JPM No.: SIRO 34.EO.1619.151 Student Name:_ _ _ _ _ _ _ _ __
Step Action Standard Eval Comments
*8. Reset Drywell Cooling (HVAC LOCA Trip 1A and 1B) Student resets A Isolation.
Logic: On 1C601 momentarily Depress CHAN A DRWL CLG HS-14141A RESET pushbutton.
- CHAN A DRWL CLG HS-14141A RESET push button depressed.
- 9. Observe CHAN A DRWL CLG RESET green ISO light Student observes A Isolation reset.
extinguishes.
- Green light above the pushbutton NOT LIT.
*10. On 1C601 momentarily Depress CHAN B DRWL CLG Student resets B Isolation.
HS-14141B RESET pushbutton.
- CHAN B DRWL CLG HS-14141B RESET push button depressed.
- 11. Observe CHAN B DRWL CLG RESET green ISO light Student observes B Isolation reset.
extinguishes.
- Green light above the pushbutton NOT LIT.
*12. On 1C681 Heat and Ventilation Control Panel Student resets CHAN A RBCW ISO momentarily Depress Chan A RBCW ISO VALVE VALVE POS HS-14140A.
POS RESET HS-14140A pushbutton.
- Chan A RBCW ISO VALVE POS RESET HS-14140A pushbutton depressed.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
, )
PERFORMANCE CHECKLIST Page 7 of 9 Appl. To/JPM No.: SIRO 34.EO.1619.151 Student Name:,_ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
- 13. ObseNe Chan A RBCW ISO VALVE POS RESET Student obseNes A RBCW Isolation white Iso light extinguishes. valve reset.
- White light NOT LIT.
*14. On 1C681 Heat and Ventilation Control Panel Student resets CHAN B RBCW ISO momentarily Depress Chan B RBCW ISO VALVE VALVE POS HS-14140B.
pas RESET HS-1414DB push button.
- 15. ObseNe Chan B RBCW ISO VALVE POS RESET Student obseNes B RBCW Isolation white Iso light extinguishes. valve reset.
- White light NOT LIT.
- 16. If Containment Instrument Gas has not been restored Based on initial conditions:
by ES-184-002, Restore CIG in accordance with Determines that CIG 90# header has section 4.4 of this procedure. been restored.
- 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.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
"1, ..J PERFORMANCJHECKLIST Page 8 of 9 Appl. To/JPM No.: S/RO 34.EO.1619.151 Student Name: _ _ _ _ _ _ _ _ __
Step Action 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. I
*17. 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 VLVS HV-18781A2. HV-18781A1 and HV-18781A2.
- Amber light NOT LIT and red light LIT.
A CLRS CLG WTR 18 ISO VLVS HV-1878281 and A CLRS CLG WTR 18 ISO VLVS HV-1878282. HV-1878281 and HV-1878282.
- Amber light NOT LIT and red light LIT.
*8 CLRS CLG WTR 08 ISO VLVS HV-1878181 and 8 CLRS CLG WTR 08 ISO VLVS HV-18781B2. HV-18781B1 and HV-18781B2.
- Control Switch to Open
- Amber light NOT LIT and red light LIT.
8 CLRS CLG WTR IB ISO VLVS HV-18782A1 and 8 CLRS CLG WTR IB ISO VLVS HV-18782A2. HV-18782A1 and HV-18782A2.
- Amber light NOT LIT and red light LIT.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
PERFORMANC~HECKUST ..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 A. An ATWS has occurred coincident with a loss of drywell cooling. B. EO-100-113 is being implemented for level/power control. C. EO-1 00-1 03 is being executed for primary containment control. D. ES-134-001 is being implemented and is complete through Step 4.2. E. CIG 90 # header has been restored. F. MSIVs have been opened lAW ES-184-002, REOPENING MSIVS BYPASSING ISOLAliONS. INITIATING CUE Reset Drywell Cooling Logic isolations and restore Drywell Cooling in accordance with ES 134-001. 1 of 2
TASK CONDITIONS A. An ATWS has occurred coincident with a loss of drywell cooling. B. EO-1 00-113 is being implemented for level/power control. C. EO-1 00-1 03 is being executed for primary containment control. D. ES-134-001 is being implemented and is complete through Step 4.2. E. CIG 90 # header has been restored. F. 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 ES 134-001. 2 of 2
PPLSUSQUEHANNA,LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIRO 04.0N.1203.251 o 11/22110 262001 A2.07 3.0/3.2 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task
Title:
Energize "Dead" 4KV ESS Bus '20' (Alternate Path) Completed By: Bob Pudish 11/22110 /{/';':?/lo Date~ / Writer Date Approval: 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 ( Unsatisfactory Evaluation: Evaluator Name:
-=---------------------
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 CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety pOlicies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection. safety shoes, hardhats, etc., is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. ON-004-002, Energizing Dead 4KV ESS Bus (Rev. 20) B. OP-024-001, Diesel Generators (Rev. 56) C. OP-AD-001, Operations Standards for System and Equipment Operation (Rev. 44) III. OPERATIONAL ACTIVrnES None IV. TASK CONDITIONS A. Unit 2 is in a Shutdown Condition. B. An Electrical transient has occurred on the 20 ESS bus. C. DG 0 has failed to auto start and is in standby alignment. D. No electrical Bus fault is present. E. You are the On-Shift U2 PCOP. V. INITIATING CUE Implement ON-004-002 to re-energize the 20 ESS bus. VI. 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. VII. 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
PERFORM~CE 30f~ ( CHECKLIST Page Appl. Tol S/RO JPM No 04.0N.1203.251 Student Name Step Action Standard Eval Comments This JPM must be performed in the simulator. Setup was snapped to IC-394 for LOC-23 NRC Exam. Setup the simulator to IC-1B. Insert the following malfunctions: IMF mfDG0240010 DG D Fails to Start IMF cmfBR05_2A20401 Bkr 01 Fails Asls IMF cmfBR04_2A20404 Bkr 04 Auto Logic Fails IMF cmfBR03_2A20408 Bkr OB Overcurrent Trip IMF cmfPM04_0P5040 ESW Pump D Auto Logic Fails This JPM uses the following Event Trigger: aet 040N1203151 Which consists of conditions: DG D Start Pushbutton diHSOOO51 D.CurrValue=#OR.diHSOO051 O.RESET And linked commands: Delete DG D Fails to Start 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 FORM NTP-QA-31.B-2, Rev. 0
( ( PERFORMANCE CHECKLIST
~
Page 4 of 8 Appl. Tol S/RO JPMNo 04.0N.1203.251 Student Name Step Action Standard Eval Comments
- 1. Select the correct section to perform. Student selects Attachment A Step 1.3.
- 2. Confirm the normal, alternate and DG Student confirms the following breakers open:
breakers for the dead 4KV ESS bus are open.
- 2A20408 (Red light off-Amber light on)
- 2A20401 (Red light off-Amber light on)
- 2A20404 (Red light off-Amber light on)
- 3. Check status of following lockout relays: Student contacts an NPO to check the
- Determine if any relays Tripped. following Lockout relays not tripped:
- Do Not reset any tripped relays.
- 86A-204
- If any relays Tripped: Perform Att B,
- 86A1-204 Exit Att A.
- 86A2-204 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).
- Critical Step #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0
(' PERFORM~CE CHECKLIST
~
Page 5 of 8 Appl. Tol SIRO JPM No 04.0N.1203.251 Student Name Step Action Standard Eval Comments
- 4. Ensure appropriate breakers supplied from 4.16 KV Student contacts an NPO to check the ESS Bus 20 listed on Attachment 0 are open. following breakers open:
- 2A20405 (Red light off-Amber light on)
- 2A20402 (Red light off-Amber light on)
- 2A20403 (Red light off-Amber light on)
- 2A20409 (Red light off-Amber light on)
EVALUATOR CUE Role Playas NPO and report all breakers listed on Attachment 0 are open.
- 5. Ensure OG '0' aligned for Standby Automatic Student recalls from Task Conditions that OG operation iaw OP-024-001. '0' is aligned for standby operation.
EVALUATOR CUE If necessary, role playas the Unit Supervisor and report that the OG '0' is available for manual operation.
- 6. If OG failure has occurred, if possible substitute OG NIA, DG failure has not occurred.
E for affected OG iaw OP-024-004.
- NlA I
i
*7. To start diesel at OC653, perform the following: Student places HS-000550 OG D Gov Mode
- Place HS-00055D DG D Gov Mode Sel Sel switch in ISOCH position.
switch to ISOCH.
- Critical Step #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0
( L PERFORMANCE CHECKLIST Page 6 of 8 Appl. Tol SIRO JPM No 04.0N.1203.251 Student Name Step Action Standard Eval Comments
- 8. To start diesel at OC653, perform the following Student ensures HS-000560 OG 0 Volt Reg (continued): Mode Sel switch is in Auto.
- Ensure HS-000560 OG 0 Volt Reg Mode Sel switch to Auto.
*9. 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.
- 11. Observe OG 0 starts and OG 0 to Bus 20 Bkr Student observes:
2A20404 automatically closes.
- OG 0 volts and Hz rise to 4160V and 60 I Hz.
- Bkr 2A20404 did NOT close (Red light off-Amber light on).
- 12. 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 Panel OC653.
-~-L...- -- _ ............. _._ ............. _
- Critical Step #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0
PERFORM~CE page7of~ ( CHECKLIST Appl. Tal SIRO JPM No 04.0N.1203.251 Student Name Step Action Standard Eval Comments
- 13. 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 2A20404. Student closes OG 0 to Bus 20 Bkr 2A20404 (Red light on-amber light off).
i
- 16.
- Observe voltage on 4.16KV Bus 20. Student observes voltage on 4.16KV Bus 20.
- 17.
- Observe white ESS Bus available light Student observes white ESS Bus available light Illuminated on mimic bus on Panel OC653. Illuminated on mimic bus on Panel OC653.
- 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.
- 20. Ensure ESW supplying adequate cooling to OG iaw Student recognizes ESW Pump 0 not running.
OP-054-001. May inform SRO.
.... .... .... - .... - .... ~ .. - .... ~ .. - .... - ... - .... - . -...- - - - _ .. _._ .... _ .... _._._ _.__ _ __ _._
- Critical Step #Critical Sequence v FORM NTP-QA-31.8-2, Rev. 0
( PERFORM~CE CHECKLIST ~ Page 8 of 8 Appl. Tol S/RO JPM No 04.0N.1203.2S1 Student Name Step Action Standard Eval Comments
- 21. Select correct procedure I section. Student selects OP-OS4-001 Section 2.2.
Student may start ESW Pumps without referring to OP due to auto action failing to occur.
- 22. Place ESW Loop B in service by depressing ESW Student depresses ESW Pump D or B Run Pump D or B Run pushbutton. pushbutton (Red light on-Amber light off).
- 23. Place ESW Loop A in service by depressing ESW Student depresses ESW Pump A or C Run Pump A or C Run pushbutton. pushbutton (Red light on-Amber light off).
- 24. As soon as possible, station Operator at DG to Student dispatches NPO to monitor DG monitor conditions that would cause normal parameters.
shutdown of DG. EVALUATOR CUE Role playas NPO and report conditions normal for DGD. EVAlUATOR CUE This completes the JPM. EVAlUATOR I Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures? J
- Critical Step #Critical Sequence FORM NTP-QA-31.8-2, Rev. 0
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, LLC JOB PERFORMANCE MEASURE ) APPROVAL AND ADMINISTRATIVE DATA SHEET 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 ON-135-001 Completed By: Validated: Bob Pudish Writer 11/22110 Date ~ Instructor . er Approval:
"YY'~~--..(;,f1.Q).lb NuT(g. Supv. Date 20 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 INFORMATION JOB PERFORMANCE MEASURE SIRO 35.0N.1662.1 01
) I. SAFETY CONSIDERATIONS A. 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.
B. 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.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. O. 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 Activity(s): NONE IV. TASK CONDITIONS A. A Seismic event has occurred. B. Unit 1 is in Mode 3 C. Unit 1 Fuel Pool inventory is lowering due to a system breach. O. Normal Fuel Pool makeup is unavailable. E. A system walkdown was unable to locate the leak, however the rate of inventory loss is not severe. F. The Unit 1 Fuel Pool Cooling System has been shutdown. G. The Cask Storage Pit Gate is closed H. The Unit 1 Fuel Pool has been isolated from Non-Q piping by another operator. I. Adding water to the fuel pool was attempted using the ESW System, but was unsuccessful. J. 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 CHECKLIST L Page 3 of 10 Appl. To/JPM No.: SIRO 35.0N.1662.101 Student Name: _ _ _c - - - - - - - Step Action Standard Eval Comments EVALUATOR NOTE Setup was snapped to IC*393
- This JPM must be performed on the simulator. for LOC-23 NRC Exam.
- Insert the following malfunctions:
IMF annAR016G06 f:ALARM_ON Turns on the annunciator for seismic. IMF annAR016H14 f:ALARM_ON Turns on the annunciator for OC211. IMF annAR016H16 f:ALARM_ON Turns on the annunciator for OC207. IMF annAR106A17 f:ALARM_ON Turns on the annunciator for 1C206.
- Insert the following remote function:
IRF rfFPl35007 f:RHR_BACKUP Closes suction valve to trip FPC Pps.
- Insert the following over*ride:
lOR aoLRTRl5347A f:815.92 Sets fuel pool level at 21'11".
- This JPM uses the following Event Trigger:
aet 350N16621 01 Which consists of conditions:
=
diHS11275A.CurrValue #OR.diHSl1275A.OPEN Delete FP lowering when HV112F075A is open. And linked commands: DOR aoLRTR15347A
- Assign the following Keys:
Start lowering level in the fuel pool. {Key[l]} MOR aoLRTR15347A r:30:00 i:Asls f:815.75 {Key[2]} IRF rfRH149026 f:100 Open manual valve151070.
- 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.
- Critical Step #Critical Sequence Form NTp*QA*31.8*2, Rev. 0
PERFORMAN~ CHECKLIST
~
Page 4 of 10 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 Student Name: _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
- 4. Ensure the following valves are Closed: Student checks valve positions.
(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. This valve is normally closed and de-energized.
- Amber light Off, Red light Off This valve is normally closed and de-(d) HV-151F010B RHR Loop B Cross-tie. energized.
- 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. Student contacts Unit 2 PCOP and asks for the position of HV-21210A.
- Amber light On, Red light Off EVALUATOR CUE Role Playas Unit 2 PCOP and report valve HV-21210A is Closed.
- 5. Momentarily place HS-E11-1S17A LOCA Isolation Student overrides LOCA Iso logic.
Manual Override Keylock Switch to override.
- Key inserted
- Switch turned to Override
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
( PERFORMAN~CHECKLIST ~ Page 6 of 10 Appl. To/JPM No.: SIRO 35.0N.1662.101 Student Name:,_ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
- 6. Observe the following: Student observes override condition.
(a) LOCA Isolation Manual Override White Indicating Light Illuminated.
- White light momentarily LIT No LOCA signal is present (b) LOCA Iso Switch Loop A Manual Override Annunciator Alarmed.
- Annunciator AR-109-C05 LIT (n\a)
*7. Close the following valves: Student begins lineup.
(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: Student verifies lineup.
(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
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
f ( L PERFORMANCE CHECKLIST Page 7 of 10 Appl. To/JPM No.: S/RO 35.0N.1662.101 Student Name: _ _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments EV ALUATOR NOTE The following valves are located In-Plant. Student will contact In-Plant Operator and direct these valves opened.
- 9. Open the following valves: Student directs an In-Plant Operator to open these valves.
(a) 151070 - RHR to Refuel Pool Clg and Clnup Return (RB 683' in 'B' RHR pipeway) (b) 153070A - Fuel Pool Fill Vlv from RHR (RB 749' in FP pump & Hx room) (c) 153070B - Fuel Pool Fill Vlv from RHR (RB 749' in FP pump & Hx room) BOOTH OPERATOR CUE Press {Key[2]} to open manual valve 151070. (Found on P&ID RH1) Valves 153070AlB are already open. (Found on P&ID FP1) EVALUATOR CUE Role Playas In-Plant Operator and report the valves are Open.
- 10. If necessary, Momentarily Place HS-11202A3 RHRSW Student does not need to reset LOCA-Pump A LOCA-Trip to Reset. trip logic to RHRSW Pump.
- Switch to Reset not necessary
~.-- ... -- -
....... ....... - .... -~
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
r PERFORMAN~ CHECKLIST L Page 8 of 10 Appl. To/JPM No.: S/RO 35.0N.1662.101 Student Name:_ _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments EVALUATOR NOTE AR-109-H03 and H04 will come in when 1P506A is started.
*11. Start 1P506A RHRSW Pump A. Student starts pump.
- Control Switch to Start.
- Red light LIT, Amber light Not LIT
*12. Open HV112F073A RHRSW Crosstie. Student opens HV112F073A RHRSW Crosstie.
- Switch to Open
- Red light LIT, Amber light Not LIT
*13. Open HV112F075A RHRSW Crosstie. Student opens HV112F075A RHRSW Crosstie.
- Switch to Open
- Red light LIT, Amber light Not LIT
- 14. Ensure HV-112F074A RHRSW/RHR Loop A Crosstie Student contacts an NPO to ensure Drain Vlv Closes (Rm 1-10429-645'). that HV-112F074A Closes.
EVALUATOR CUE As In-Plant operator, when asked about valve, report valve is closed.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
t ( L PERFORMANCE CHECKLIST Page 9 of 10 Appl. To/JPM No.: SIRO 35.0N.1662.101 Student Name: _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments 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.
- 15. When desired fuel pool level reached, Stop adding Student secures makeup based on water to fuel pool as follows: reports I direction.
(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 Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
f l PERFORMANCE CHECKLIST L 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? Task Cue Sheets? Procedures?
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
TASK CONDITIONS A. A Seismic event has occurred. B. Unit 1 Fuel Pool inventory is lowering due to a system breach. C. Normal Fuel Pool makeup is unavailable. D. A system walkdown was unable to locate the leak, however the rate of inventory loss is not severe. E. The Unit 1 Fuel Pool Cooling System has been shutdown. F. The Cask Storage Pit Gate is closed. G. The Unit 1 Fuel Pool has been isolated from Non-Q piping by another operator. H. 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.
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. A Seismic event has occurred. B. Unit 1 Fuel Pool inventory is lowering due to a system breach. C. Normal Fuel Pool makeup is unavailable. D. A system walkdown was unable to locate the leak, however the rate of inventory loss is not severe. E. The Unit 1 Fuel Pool Cooling System has been shutdown. F. The Cask Storage Pit Gate is closed. G. The Unit 1 Fuel Pool has been isolated from Non*Q piping by another operator. H. Adding water to the fuel pool was attempted using the ESW System, but was unsuccessful. I. 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, LLC .) JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 55.0N.2000.152 2 11/22110 201003 A2.01 3.4/3.6 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task
Title:
Respond to a Stuck Control Rod lAW ON-155-001 Completed By: Validated: Bob Pudish Writer 11/22110 Date Inslru~ Approval: Date 30 Date of Performance: Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name: Last First M.1. Employee # 1 S.S. # Performance ) Satisfactory ) Unsatisfactory Evaluation: Evaluator Name: Signature Typed or Printed Comments: Form NTP-QA-31.8-1, Rev. 0
REQUIRED TASK INFORMATION ) JOB PERFORMANCE MEASURE SIRO 55.0N.2000.152 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. ON-155-001, CONTROL ROD PROBLEMS (Rev. 34) III. OPERATIONAL ACTIVITIES This JPM satisfies the requirements of Operational Activity(s): None IV. TASK CONDITIONS A. Unit 1 is at 90% power. B. A rod pattern adjustment is scheduled. V. 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. VI. TASK STANDARD Rods 22-39 withdrawn to notch 12; Rod 3S-39 withdrawn to notch OS. VII. TASK SAFETY SIGNIFICANCE Ability to safely add positive Reactivity with control rod motion .
. Form NTP-QA-31.S-1, Rev. 0
PERFORMAN~CHECKlIST ~ ( Page 3 of 11 Appl. To/JPM No.: S/RO SS.ON.2000.1S2 Student Name: _ _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments Setup was snapped to IC-Simulator Setup 391 for LOC-23 NRC
- Load MODE 1 IC-20. Exam.
- Place Simulator in RUN, lower power to -90%
with rods and RRPs.
- Insert the following malfunction:
IMF mfRD1550063839 f:Asls
- 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 performances of this JPM. The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. When student is ready to begin JPM, place the simulator in RUN . ... Critical Step # Critical Sequence Form NTP-QA-31.8-2, Rev. 0
t L PERFORMAN~CHECKLIST Page 4 of 11 Appl. To/JPM No.: SIRO 55.0N.2000.152 Student Name:_ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
*1.
Selects Rod 22~39 for withdraw. Depresses 22 - 39 Verifies 22 and 39: White lights - LIT Four rod display reads notch 06.
*2. Withdraws Rod 22-39 to notch 12. Depresses WID RAW ROD pushbutton.
Verifies: Four rod display changes to notch 08. Depresses WID RAW ROD pushbutton. Verifies: Four rod display changes to notch 10. Depresses W/DRAW ROD pushbutton. Verifies: Four rod display changes to notch 12.
*3.
Selects Rod 38-39 for withdraw. Depresses 38-39 Verifies 38 and 39: White lights - LIT Four rod display reads notch 06.
- Critical Step # Critical Sequence Form NTP-QA-31.8-2, Rev. 0
f PERFORMAN~ CHECKLIST L Page 5 of 11 Appl. To/JPM No.: S/RO 55.0N.2000.152 Student Name: _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments FAULT STATEMENT ROD 38-39 WILL NOT MOVE IN THE NEXT STEP.
- 4. I Withdraws Rod 38-39 to notch 12. Depresses WID RAW ROD pushbutton.
Verifies: Four rod display DID NOT CHANGE to notch 08. EVALUATOR CUE Student may request permission to attempt to move rod ONE MORE time before proceeding to the Off Normal procedure. IF necessary, Role-play Unit Supervisor and grant permission to attempt ONE MORE withdrawal sequence. If necessary, Role Play unit supervisor and direct entry into ON-155 001.
- 5. Proceed to applicable section of OFF-Normal Determines step 4.3 is applicable based on procedure ON-155-001, Control Rod Problems as initial conditions.
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
- Critical Step # Critical Sequence Form NTP-QA-31.8-2, Rev. 0
PERFORMANCE'"6HECKLIST V Page 6 of 11 Appl. To/JPM No.: S/RO 55.0N.2000.152 Student Name: _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments 6. IF rod position indication does not change when Uses any 3 of the following to confirm valid withdraw OR insert signal applied, Perform Rod 38-39 is STILL AT NOTCH 06. the following:
- CRT and SIP 4 ROD DISPLAY.
Confirm control rod position using any 3 of the available rod position indication as follows:
- FULL INIFULL OUT DISPLAY push button.
- CRT and SIP 4 ROD DISPLAY.
- 007
- FULL IN/FULL OUT DISPLAY push button.
- Alarm logging printer, System Event
.007 Display Message
- Alarm logging printer, System Event Display
- RWM Main Display when below Message Low Power Alarm Point.
- 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 rod, Records the following on Attachment A as follows: Date Complete rod data on Attachment A. Time Rod 38-39 Reactor Pressure "S" for Stuck Position 06 -_ __ _ - - - - - -_ _-
...... .... ....... _.- ....... -.~ ....... -.~ ....... - . -...... -.~ ....... - . -......- . - ....- .
.,. Critical Step # Critical Sequence Form NTP-QA*31.8*2, Rev. 0
~
PERFORMAN~CHECKLIST Page 7 of 11 Appl. To/JPM No.: SIRO 55.0N.2000.152 Student Name:,_ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
*8. Places DRIVE WTR PRESS THLTG PV-In - 50 psid increments, Increase drive water pressure 146F003 to CLOSE AND UNTIL Perform following at each increment until ~ 350 psid DRIVE WATER DIFF PRESSURE PDI-C12 reached: 1R602 INCREASES FROM -250 TO -300 PSID.
CAUTION Elevated drive pressure increases the risk of multiple notch movement.
- 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 drive water flows (4 gpm insertl2.5 gpm withdraw). Full core display FOR ROD 38-39 DID NOT CHANGE to notch 08 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
PERFORMAN~ CHECKLIST L Page 8 of 11 Appl. To/JPM No.: SIRO 55.0N.2000.152 Student Name: _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments f--~
- 10. If rod position does not change on 4-rod display, Uses any other available rod position confirm control rod position using available rod indication to confirm rod 38-39 is STILL AT position indications. NOTCH 06.
*11. Places DRIVE WTR PRESS THlTG PV In - 50 psid increments, Increase drive water pressure 146F003 to CLOSE AND UNTil Perform following at each increment until $ 350 psid DRIVE WATER DIFF PRESSURE PDI-C12 reached: 1R602 INCREASES FROM -300 TO ~ 350 PSID.
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. I
- Critical Step # Critical Sequence Form NTP-QA-31.8-2, Rev. 0
( ( PERFORMANCE CHECKLIST L Page 9 of 11 Appl. To/JPM No.: SIRO 55.0N.2000.152 Student Name:._ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
*12. Depresses WIDRAW ROD pushbutton Attempt to operate drive one notch in intended direction, authorized by procedure governing Verifies:
original Control Rod motion, while observing drive water flows (4 gpm insert/2.5 gpm withdraw). Full core display FOR ROD 3S-39 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, Go to step 4.3.1.1.
- Critical Step # Critical Sequence Form NTP-QA-31.S-2, Rev. 0
( L PERFORMANCE CHECKLIST Page 10 of 11 Appl. To/JPM No.: SIRO 55.0N.2000.152 Student Name:._ _ _ _ _ _ _ _ __ Step Action Standard EvaI Comments
- 14. Records the following on Attachment A:
Record drive water pressure required to move control rod on Attachment A. 350 psid drive water pressure required to move control rod. 15. Record drive water flow that is indicated while Records the following on Attachment A: attempting to move stuck control rod on 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
PERFORMAN~ CHECKLIST L Page 11 of 11 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 PDI-C12 1R602 DECREASES TO -250 PSID AND Records the following on Attachment A:
250 psid J EVALUATOR CUE I This completes the JPM. JI 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 ) 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, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET 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 Writer 11/22110 Date Instr~5 Dat:~0() 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 INFORMATION JOB PERFORMANCE MEASURE SIRO 78.0P.3680.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES OP-178-002, PRNMS (Rev. 2) III. OPERATIONAL ACTIVITIES This JPM satisfies the requirements of Operational Activity(s): NONE IV. TASK CONDITIONS A. Unit 1 has entered Single Loop Operation (SLO) 1 hour ago. B. Condition C of TS LCO 3.4.1 is to be performed. V. INITIATING CUE Insert APRM Rod block and Scram Setpoints for Single Loop Operation for APRM 3 in accordance with OP-178-002. 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
' "'p } .,J!I PERFORMANCE CHECKLIST Page 3 of 8 Appl. To/JPM No.: S/RO 78.0P.3680.101 Student Name: _ _ _ _ _ _ _ _ _ __
Step Action Standard Eval Comments EVALUATOR NOTE: Setup was snapped to IC-393 for LOC-23 NRC Exam.
- This JPM must be performed on the simulator.
- Reset to Single Loop IC with SLO setpoints NOT inserted yet.
- Due to Simulator modeling, APRM 3 is the only Module that is modeled.
- Place the simulator in Freeze.
- When student is ready to begin JPM, place the simulator in RUN.
- 1. Obtain a controlled copy of OP-178-002, PRNMS. Student obtains Controlled copy.
- 2. Review Pre-reqs, Precautions, Notes. Student reviews Pre-reqs, Precautions, Notes.
- Pre-reqs, Precautions, Notes reviewed
- 3. Selects the correct section to perform. Student selects section 2.5.3.
- Goes to Section 2.5.3 NOTE This section revises APRM trip and alarm setpoints as required by Tech. Spec. for single loop operation in accordance with LCO 4.3.1.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
/", }
PERFORMANCE CHECKLIST Page 4 of 8 Appl. To/JPM No.: S/RO 78.0P.3680.101 Student Name: _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
- 4. Insert APRM setpoints for SLO: Student establishes coms with pca.
(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. Student bypasses APRM.
- APRM Bypass Joystick to 3 position EV ALUATOR CUE Inform Student that for this JPM, he/she is responsible for bypassing the APRM.
- 6. (c) Confirm at All four 214 Voters, Bypassed LEOs for Student acknowledges cue.
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
.~i:;'
J PERFORMANCE CHECKLIST Page 5 of 8 Appl. To/JPM No.: S/RO 78.0P.3680.101 Student Name: _ _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
*7. (d) Press ETC soft key as required until Enter Set Student presses ETC soft key as Mode is shown above soft key pushbutton across required until Enter Set Mode is bottom of display. displayed.
- 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 key. Student presses Enter Set Mode soft I key.
- Enter Set Mode soft key pressed
- Password entry display screen appears
*9. (f) Enter Password "1234" and Press Ent. Student enters Password "1234" and Press Ent.
- 1 2 3 4 depressed
- Ent depressed
- 10. (g) Confirm Oper-Set mode indicated at APRM or Student confirms Oper-Set mode ODA. indicated at APRM or ODA.
- Oper-Set confirmed at either APRM or ODA
- - - ----~ ~ ------
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
f {.\'1i;fl "11" ) ..,j PERFORMANCE CHECKLIST Page 6 of 8 Appl. To/JPM No.: SIRO 78.0P.3680.101 Student Name: _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
*11. (h) Select Single Loop Operation using (i U Cursor Student selects Single Loop Operation keys to scroll. using (i .1.) Cursor keys.
- Single Loop Operation selected.
*12. (i) Press Set Parameters soft key. Student presses Set Parameters soft key.
- Set Parameter pressed
- 13. mEnsure APRM indicates Set Parameters: Single Student ensures APRM indicates Set Loop Operation. Parameters: Single Loop Operation.
- Set Parameters: Single Loop Operation displayed
*14. (k) Change the Desired: Enabled field to YES using Student changes the Desired: Enabled the (i L) Cursor keys. field to YES using the (i L) Cursor keys.
- YES displayed
*15. (I) Press Accept soft key. Student presses Accept soft key.
- Accept soft key pressed
- 16. (m) Confirm PresentEnabled field changed to YES. Student confirms Present Enabled field I changed to YES.
- Yes displayed
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
K<i:' ) wi PERFORMANCE CHECKLIST Page 7 of 8 Appl. To/JPM No.: S/RO 78.0P.3680.101 Student Name: _ _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
- 17. (n) Press Exit soft key. Student presses Exit soft key.
- Exit depressed
- 18. (0) Press Exit Set Mode soft key. Student presses Exit Set Mode soft key.
- Exit Set Mode depressed
- 19. (p) Press Yes soft key. Student presses Yes soft key.
- Yes soft key depressed
- 20. (q) Confirm the APRM display header indicated Student confirms the APRM display Operate. header indicates Operate.
- Operate displayed I
I
- 21. (r) Confirm the APRM display header indicates SLO. Student confirms the APRM display header indicates SLO.
- SLO displayed EVALUATOR CUE Steps (s), (t) and (u) have been performed satisfactorily by another Operator.
*22. (v) Remove applicable APRM from Bypass. Student unbypasses APRM.
- APRM 3 Bypass Joystick taken out of Bypass
- Critical Step #Critical Sequence Form NTP-QA-31.8-2. Rev. 0
[;) PERFORMANC~HECKUST 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 hour 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, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRAnVE DATA SHEET 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 Path) Completed By: Validated: Bob Pudish Writer 11/22110 Date Inst~' Date' 7 Approval: ~£,,,,])./~ 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 INFORMATION JOB PERFORMANCE MEASURE SIRO 59.0N.2084.151 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, OPERATIONS STANDARDS FOR SHIFT OPERATIONS. B. 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.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator, any safety issue occurs during JPM performance, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. ON-159-002 Containment Isolation (Rev. 29) ~ III. OPERATIONAL ACTIVITIES This JPM satisfies the requirements of Operational Activity(s): NONE IV. 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. V. 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 f~""" Incomplete Containment Isolation could lead to a loss of the ability to maintain secondary containment. ~~ Form NTP-QA-31.8-1, Rev. 0
1
~
l J PERFORMANCE CHECKLIST Page 3 of 13 Appl. Tol S/RO JPM No 59.0N.2084.151 Student Name Step 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 malfunctions:
IMF cmfAV03_HD17657A Auto Logic Fails for HD17657A. IMF cmfAV03_HD17602A Auto Logic Fails for HD17602A. IMF cmfAV03_HD17601A Auto Logic Fails for HD17601A. IMF cmfAV03_HD07543A Auto Logic Fails for HD07543A. IMF cmfPM04_0V109A Auto Logic Fails for OV109A.
- This JPM uses the following 3 Event Triggers:
aet 590N2084151_1(2)(3) Which consists of conditions: diHS17657(02)(01 )A.CurrValue =# OR.diHS17657(02)(01 )A.OPEN And linked commands: DMF cmfAV03_HD17657(02)(01)A
- Place MIS to SID, perform immediate operator actions, stabilize plant, snap IC.
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.
- 1. Obtains ON-159-002. Student executes ON-159-002.
- Reviews Symptoms, Observations, Alarms, Automatic Actions, Notes sections.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
, .J V PERFORMANCE CHECKLIST Page 4 of 13 Appl. Tol SIRO JPM No 59.0N.2084.151 Student Name Step Action Standard Eva I Comments
- 2. As time permits, record date and time of Student records Name, date, time.
event.
- Enters Shift Supervision name, date, time EVALUATOR CUE If Student requests name, date, time: provide "John Doe, current date, current time" 3.
J Immediately evaluate status of Containment Student recalls SPDS unavailable. Isolation using SPDS.
- Student recalls SPDS is unavailable from Task Conditions 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.
- 4. If -38" RPV level &!!Q 1.72# isolation signals Student recognizes *38" ~ 1.72#
are received, Perform ... signals not received.
- NIA (both signals not received)
- 5. Notify SM to refer to EP-PS-100 to determine Student informs SM to refer to E-Plan.
if any E-Plan entry is required.
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
J PERFORMANCE CHECKLIST
'wi Page 5 of 13 Appl. Tol S/RO JPM No 59.0N.2084.151 Student Name Step Action Standard Eval Comments EVALUATOR CUE E-Plan will be referred to by the SM. *6. Perform one of the following Attachments for Student selects Attachment B.
lowest level isolation signal received: If -38" RPV water level isolation signal received, perform Attachment B.
- Student performs Attachment B EVALUATOR CUE ONCE THE STUDENT HAS SELECTED ATTACHMENT B, HAND THE STUDENT THE MARKED-UP COPY OF ATTACHMENT B IN THIS PACKAGE.
- 7. Ensure component in required isolation Student ensures component positions position per the following: per Attachment B.
- Student ensures component position per Attachment B EVALUATOR CUE INFORM THE STUDENT THAT ATTACHMENT B STEPS 1.1 THROUGH 1.48 HAVE BEEN COMPLETED, ALL COMPONENTS WERE IN THE PROPER POSITION.
- 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 Action Standard Eval Comments
- 8. Att B 1.49 TIP System Ball Valves are Student observes TI P System Ball closed. Valves position.
- 4 Green lights LIT FAULT STATEMENT NEXT STEP, STUDENT RECOGNIZES HD17657A FAILED TO AUTO OPEN AND MANUALLY OPENS HD17657A. 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 Student recognizes HD17657A failed to Dmp HD17657A is open. auto open, places switch to OPEN I position. Student observes HD17657A
- Red light NOT LIT OPENS.
- Amber light LIT 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
~,
J ~ PERFORMANCE CHECKLIST Page 7 of 13 Appl. Tol SIRO JPM No 59.0N.20B4.151 Student Name Step Action Standard Eva I Comments EVALUATOR CUE 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 to Dmp HD17602A is open. auto open, places switch to OPEN position. Student observes HD17602A
- Red light NOT LIT OPENS.
- Amber light LIT FAULT STATEMENT NEXT STEP, STUDENT RECOGNIZES HD17601 A FAILED TO AUTO OPEN AND MANUALLY OPENS HD17601 A. STUDENT MAY INFORM SRO ANDIOR ASK FOR DIRECTION.
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 to HD17601A is open. auto open, places switch to OPEN position. Student observes HD17601A
- Red light NOT LIT OPENS.
- Amber light LIT
---- .. -.-~
- Critical Step #Critical Sequence Form NTP-QA~31.8-2, Rev. 0
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PERFORMANCE CHECKLIST Page 8 of 13 Appl. Tol SIRO JPM No 59.0N.2084.151 Student Name Step Action Standard Eval Comments
- 12. Att B 1.53 SGTS Unit 1 Contn Burp & Purge Student observes HD17508A position.
Iso Dmp HD17508A is closed.
- Red light NOT LIT
- Amber light LIT
- 13. Att B 1.54 RRP A Clg Wtr OB Iso Vlvs HV- Student observes HV-18791A1 & HV 18791A1 & HV-18791A2 are closed. 18791A2 position.
- Red light NOT LIT
- Amber light LIT
- 14. Att B 1.55 Zone 1 Exh Sys Isolation Dmp Student observes HD17576A position.
HD17576A is closed.
- Red light NOT LIT
- Amber light LIT
- 15. Att B 1.56 Zone 1 Equip Compt Exh Sys Student observes HD17524A position.
Dmp HD17524A is closed.
- Red light NOT LIT
- Amber light LIT
- 16. Att B 1.57 Zone 1 Sup Sys Isolation Dmp Student observes HD17586A position.
HD17586A is closed.
- Red light NOT LIT
- Amber light LIT
- 17. Att A 1.58 Zone 3 Exh Sys Isolation Dmp Student observes HD17502A position.
HD17502A is closed.
- Red light NOT LIT
- Amber light LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
~, ~
PERFORMANCE CHECKLIST Page 9 of 13 Appl. To/ SIRO JPM No 59.0N.2084.151 Student Name Step Action Standard Eval Comments
- 18. Att B 1.59 Zone 3 Filt Exh Sys Dmp Student observes HD17514A position.
HD17514A is closed.
- Red light NOT LIT
- Amber light LIT
- 19. Att B 1.60 Zone 3 Sup Sys Isolation Dmp Student observes HD17564A position.
HD17564A is closed.
- Red light NOT LIT
- Amber light LIT
- 20. Att B 1.61 RRP B Clg Wtr IB Iso Vlvs HV~ Student observes HV~18792A1 & HV~
18792A1 & HV-18792A2 are closed. 18792A2 position.
- Red light NOT LIT
- Amber light LIT
- 21. Att B 1.62 Recirc Sys to Zone 1 Sup Sys Student observes HD17657B position.
Dmp HD17657B is open.
- Red light LIT
- Amber light NOT LIT
- 22. Att B 1.63 Zone 1 Exh Sys to Recirc Sys Student observes HD17602B position.
Dmp HD17602B is open.
- Red light LIT
- Amber light NOT LIT
- 23. Att B 1.64 Zone 1 Filt Exh to Recirc Sys Student observes HD17601B position.
Dmp HD17601B is open.
- Red light LIT
- Amber light NOT LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
~,
PERFORMANCE CHECKLIST
\..f Page 10 of 13 Appl. Tol SIRO JPM No 59.0N.20B4.151 Student Name Step Action Standard Eval Comments
- 24. Att 8 1.65 RRP 8 Clg Wtr 08 Iso Vlvs HV- Student observes HV-1879181 & HV 1879181 & HV-18791B2 are closed. 1879182 position.
- Red light NOT LIT
- Amber light LIT
- 25. Att B 1.66 SGTS Unit 1 Contn Burp & Purge Student observes HD17508B position.
Iso Dmp HD17508B is closed.
- Red light NOT LIT
- Amber light LIT
- 26. Att B 1.67 Zone 1 Exh Sys Isolation Dmp Student observes HD17576B position.
HD175768 is closed.
- Red light NOT LIT
- Amber light LIT
- 27. Att B 1.68 Zone 1 Equip Compt Exh Sys Student observes HD17524B position.
Dmp HD17524B is closed.
- Red light NOT LIT
- Amber light LIT
- 28. Att B 1.69 Zone 1 Sup Sys Isolation Dmp Student observes HD17586B position.
HD17586B is closed.
- Red light NOT LIT
- Amber light LIT
- 29. Att B 1.70 Zone 3 Exh Sys Isolation Dmp Student observes HD17502B position.
HD17502B is closed.
- Red light NOT LIT
- Amber light LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2. Rev. 0
J PERFORMANCE CHECKLIST
\""I Page 11 of 13 Appl. Tol SIRO JPM No 59.0N.2084.151 Student Name I
Step Action Standard Eval Comments
- 30. Att B 1.71 Zone 3 Filt Exh Sys Dmp Student observes HD17514B position.
HD17514B is closed.
- Red light NOT LIT
- Amber light LIT
- 31. Att B 1.72 Zone 3 Sup Sys Isolation Dmp Student observes HD17564B position.
HD17564B is closed.
- Red light NOT LIT
- Amber light LIT
- 32. Att B 1.73 RRP A Gig Wtr IB Iso Vlvs HV- Student observes HV-18792B1 & HV 18792B1 & HV-18792B2 are closed. 18792B2 position.
- 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 RECOGNIZES HD07543A FAILED TO AUTO OPEN AND MANUALLY OPENS HD07543A. STUDENT MAY INFORM SRO ANDIOR ASK FOR DIRECTION.
- Gritical Step #Gritical Sequence Form NTP-QA-31.8-2, Rev. 0
.~
.J PERFORMANCE CHECKLIST Page 12 of 13 Appl. Tol SIRO JPM No 59.0N.2084.151 Student Name Step Action 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 to HD07543A is open. auto open, places switch to OPEN position. Student observes HD07543A
- 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 to proceed using any/all station policies for observed condition.
*33. Att B 1.83 SGTS Fan OV109A is RUNNING. Student determines OV109A status is incorrect and STARTS the OV109A fan.
- Red light NOT LIT
- Amber light LIT
- Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0
~
\wi PERFORMANciCHECKLIST Page 13 of 13 Appl. Tol SIRO JPM No 59.0N.2084.151 Student Name Step Action Standard Eval Comments EVALUATOR 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
- )
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 .
\
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 Path) Completed By: Validated: Bob Pudish Writer 11/24/10 Date Ins~ Approval:
~. <~.f;, /VI ,0./'5 (I /3 () I( i) -NU@;TlfIg,sUpv.-D-a.;....:t-'e'-""=----
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 ( ) Unsatisfactory Evaluator Name: Signature Typed or Printed Comments: Form NTP-QA-31.8-1. Rev. 0
REQUIRED TASK INFORMATION
) JOB PERFORMANCE MEASURE SIRO 24.0P.1443.051 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP*AD-002, OPERATIONS STANDARDS FOR SHIFT OPERATIONS.
B. 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.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If, in the judgment of the Evaluator, any safety issue occurs during JPM performance, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. OP-024-001 Diesel Generators (Rev. 56) III. OPERATIONAL ACTIVITIES N\A IV* 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'. V. INITIATING CUE Perform Manual Emergency Shutdown of Diesel Generator 'A' in accordance with OP-024-001. VI. 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 Comments NOTE All steps of this JPM are to be simulated.
No component manipulations are to be made.
- 1. Obtains OP-024-001. Student executes OP-024-001, Section 2.7.
- Reviews Notes, Prerequisites, Precautions, Caution sections.
CAUTION LOCA auto start signal is bypassed in local mode.
- 2. If diesel generator running in Emergency Student simulates pOSitioning 43CM Mode, place DG 'A' 43CM Control Mode switch clockwise to Local.
Select Switch in Local.
- 43CM simulated in Local position EVALUATOR CUE 43CM switch "clicks" and is simulated in the Local position.
- 3. At Diesel engine Control Panel OC521 A 5ES, Student simulates depressing the Depress Emergency Stop pushbutton. Emergency Stop pushbutton.
- Emergency Stop pushbutton simulated depressed
- =Critical Step
~--
# =Critical Sequence Form NTP-QA-31.8-2, Rev. 0
"~~}
J PERFORMANCE CHECKLIST
\wi Page 4 of 9 Appl. Tol SIRO JPM No 24.0P.1443.051 Student Name Step Action 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 following: Student determines, from Evaluator
- a. Master Trip Circuit Tripped Green light Cue, that EDG is still running and Illuminates continues in procedure.
- b. Running Idle light Extinguishes
- c. At 280 rpm, DG 'A' Pre-Lube Pump OP532A Starts
- = 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 Step Action Standard Eval Comments EVALUATOR CUE
- 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 before proceeding with this step. Do not perform if area is not safe.
EVALUATOR CUE Inform student that Maintenance is present to assist in the following step.
*5. If the diesel engine fails to stop as expected, Student simulates pulling SX-03483A.
Obtain maintenance assistance and Perform the following:
- a. Pull the black knob labeled SX-03483A, Overspeed Fuel shutdown Vlv Reset.
This knob is located on top of engine on the right side by the overspeed governor.
- 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 Action Standard Eval Comments EVALUATOR CUE SX-03483A is simulated pulled to end of travel. 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 holding hold until the engine comes to a Fuel quadrant lever.
complete stop. The fuel quadrant lever is located on the engine left side above the turning gear motor.
- Fuel quadrant lever simulated pulled down and held EVALUATOR CUE Fuel quadrant lever is simulated pulled down to end of travel and is being held in that position.
--- ---- ---- --- _L.- --~I..-
- =Critical Step # =Critical Sequence Form NTP-QA-31.8-2, Rev. 0
'~
-)
PERFORMANCE CHECKLIST V Page 7 of 9 Appl. Tol SIRO JPM No 24.0P.1443.051 Student Name Step Action Standard Eval Comments
- 7. When diesel generator comes to stop, Student simulates depressing Depress Emergency Stop Reset pushbutton 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.
- 8. Depress Reset pushbutton for Annunciator Student simulates depressing Reset and System Reset to reset emergency trip. pushbutton.
- Reset pushbutton simulated depressed EVALUATOR CUE Spring resistance felt while depressing Reset pushbutton. Pushbutton "bottomed out" and returned to normal when released.
- 9. Observe DG A Master Trip Circuit Reset Student simulates observing DG A Amber light Illuminates. Master Trip Circuit Reset Amber light Illuminated.
- Amber light simulated LIT
- =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 Step Action Standard Eval Comments EVALUATOR CUE Amber light is lit.
- 10. Observe OG A Master Trip Circuit Tripped Student simulates observing OG A Green light extinguishes. Master Trip Circuit Tripped Green light extinguished.
- Green light simulated NOT LIT I
EVALUATOR CUE I 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 pressure. I EVALUATOR CUE High OW pressure condition still present.
No further EOG manipulations required.
- = Critical Step # =Critical Sequence Form NTP-QA-31.8-2, Rev. 0
--.J V PERFORMANCE CHECKLIST Page 9 of 9 Appl. Tol S/RO JPM No 24.0P.1443.051 Student Name Step Action Standard Eval Comments EVALUATOR 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 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, llC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET ) 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 Rods Completed By: Validated: Bob Pudish Writer 11/24/10 Date Inst~ Date ' Approval:
~P1.1l.1h Nu e r ng. SUpv. Date 20 ) 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 INFORMATION JOB PERFORMANCE MEASURE S/RO 55.EO.1995.1 01 ) I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety poliCies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required andlor posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required. II. REFERENCES A. ES-155-001 Venting CRD to Insert Control Rods (Rev. 13) B. EO-000-113-1, Sheet 2 (Rev. 10) III. OPERATIONAL ACTIVITIES NONE. IV. T ASK CONDITIONS A. Unit 1 was at 100 percent power when a transient occurred. B. A hydraulic ATWS 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. V. INITIATING CUE Insert Control Rods in accordance with ES-155-001. VI. TASK STANDARD Control rods correctly grouped on Attachment A of ES-155-001, one control rod fully inserted lAW ES-155-001. VII. 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 Action Standard Eval Comments EVALUATOR NOTE 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 ES~ 155-001. Controlled copy obtained
- 2. 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 limitations. 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
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J PERFORMANCE CHECKLIST V Page 4 of 12 Appl. To/JPM No.: S/RO 55.EO.1995.101 Student Name:._ _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
- 4. Check Off on Attachment A, HCU's to be vented.
I Student fills out Attachment A of ES-155-001.
- Marks Attachment A to reflect the 7 HCU's to be vented:
- 1C2227 - Group A
- 1C2231 - Group B
- 1C2631 - Group C
- 1C2635 - Group 0
- 1C2643 - Group B
- 1C3031 - Group A
- 1C3035 - Group B
- 5. Confirmed By ... Contacts a second operator to confirm the correct HCU's have been identified on Attachment A.
EVALUATOR CUE Role-play the second operator, and inform the student that you confirm the HCU's to be vented. Do not agree or disagree with Student marks.
- 6. Notify HP that CROs will be vented. Uses plant page or telephone to contact HP and report that CROs will be vented.
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): Removes floor drain cover.
- Locate Floor Drain
- Remove floor drain cover Removes drain plug and obstructions, if any.
- Remove drain plug and obstructions, if any Installs threaded floor drain plug with quick
- Install threaded floor drain plug with quick disconnect fitting into floor drain.
disconnect fitting into floor drain.
- Connect Stainless Steel hose to floor drain Connects Stainless Steel hose to floor drain quick quick disconnect 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
~ V PERFORMANCE CHECKLIST Page 6 of 12 Appl. To/JPM No.: SIRO 55.EO.1995.101 Student Name: _ _ _ _ _ _ _ _ __
Step Action Standard Eval Comments EVALUATOR NOTE 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 Physically locates in the plant first HCUin group to Reactor Building elevation 719'. be inserted.
- Select the correct HCU for rod to be inserted.
EVALUATOR 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 1F102, 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 CHECKLIST Page 8 of 12 Appl. To/JPM No.: SIRO 55.EO.1995.101 Student Name: _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments EV ALUATOR CUE High Point Vent Operator fully clockwise and hard resistance is now felt. 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.
- 14. 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 1F1 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
'-..I L, PERFORMANCE CHECKLIST Page 9 of 12 Appl. To/JPM No.: SIRO 55.EO.1995.101 Student Name:_ _ _ _ _ _ _ _ __
Step Action Standard Eval Comments
- 15. If any leakage is present, Perform following: NlA. Determines venting may proceed.
- Immediately Retighten threaded vent plug to stop leak.
- On Attachment A, Record location of HCU with leaking 1F102 valve.
- Notify following of a leak location:
- 1. Health Physics.
- 2. Mechanical Maintenance.
- IF required, Replace threaded vent plug (A) in top of HCU Withdraw Line High Point Vent Valve 1F102.
- 16. Install quick disconnect fitting to Vent Plug (8) at Attaches quick disconnect fitting to Vent Plug (8) at Withdraw Line High Point Vent Valve 1F1 02 Withdraw Line High Point Vent Valve 1F1 02.
(Attachment D). I EVALUATOR CUE Quick disconnect fitting AITACHED to Vent Plug (8) at Withdraw Line High Point Vent Valve 1F1 02. I
- 17. Connect Stainless Steel Hose to quick disconnect Attaches stainless Steel Hose to quick disconnect at Withdraw Line High Point Vent Valve 1F1 02. at Withdraw Line High POint Vent Valve 1F1 02.
EVALUATOR CUE Stainless Steel Hose AITACHED to quick disconnect at Withdraw Line High Point Vent Valve 1F102.
- = Critical Step # =Critical Sequence Form NTP-QA-31.8-1, Rev. 0
,,-. L, PERFORMANCE CHECKLIST Page 10 of 12 Appl. To/JPM No.: SIRO 55.EO.1995.101 Student Name:_ _ _ _ _ _ _ _ __
Step Action Standard Eval Comments CAUnON Student reviews CAUTION. Fully Opening Withdraw Une High Point Vent Valve 1F1 02 With Locking Ring Not Installed May Result In Following:
- Primary System Unisolable Leak
- Valve Damage
- Eject Needle Valve Operator
- 18. Using High Point Vent Lock Ring Operator, Ensure High Point Vent Lock Ring Operator is used to Withdraw Une High Paint Vent Valve 1F102 ensure Withdraw Une High Point Vent Valve locking ring installed and remains stationary. 1F1 02 locking ring installed and remains stationary.
EVALUATOR CUE Withdraw Une High Point Vent Valve 1F102 locking ring is installed and did not move.
- 19. Notify Control Room Operator to observe rod Contacts control room, using plant radio, and motion and reactor power response, THEN requests PCO to observe rod 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
~<.
PERFORMANCE CHECKLIST L Page 11 of 12 Appl. To/JPM No.: SIRO 55.EO.1995.101 Student Name:_ _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
- 20. Using High Point Vent Operator, Crack Open Installs High Point Vent Operator onto Needle Withdraw Line High Point Vent Valve 1F1 02. valve AND SLOWLY turns High Point Vent Operator in the Counter Clockwise (CCW) direction.
EVALUATOR CUE 1F1 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.
- 21. 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 1F102 with High Point Operator in the Clockwise (CW) direction.
Vent Operator. EVALUATOR CUE High Point Vent Operator fully clockwise.
- 22. Confirm HCU vented by recording initials in Initials venting completed column on Attachment A applicable space on Attachment A. for the vented HCU.
- Initials Att A
- = Critical Step # = Critical Sequence Form NTP-QA-31.8-1, Rev. 0
~,
PERFORMANCE CHECKLIST Page 12 of 12 L Appl. To/JPM No.: S/RO 55.EO.1995.101 Student Name:,_ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
- 23. Remove Stainless Steel Hose from quick Removes Stainless Steel Hose from quick disconnect at Withdraw Line High Point Vent Valve disconnect at Withdraw Line High Point Vent Valve 1F102. 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? Task Cue Sheets? Procedures?
- =Critical Step # =Critical Sequence Form NTP-QA-31.8-1, Rev. 0
TASK CONDITIONS A. Unit 1 was at 100 percent power when a transient occurred. B. A hydraulic ATWS 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. V INITIATING CUE Insert Control Rods in accordance with ES-155-001. Page 1 of 2
PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIRO 73.0P.2289.103 o 11/24/10 223001 A2.01 4.3/4.4 Appl. JPM Number Rev. Date NUREG 1123 KIA No. KIA Imp. To No. Sys. No. Task
Title:
Start a Containment H2 Recombiner in Manual lAW OP-173-001 Completed By: Validated: Bob Pudish Writer 11/24/10 Date In¥~ Date' Approval: .~
~ '1Yni'i:? PI .'lUt!,
N cl ar rng. Supv. Date 20 Date of Performance: Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name:
~---------------------------------=-------~~
Last First M.1. Employee # 1 S.S. # Performance Satisfactory ) Unsatisfactory Evaluation: Evaluator Name:
-=-----------------------------.
Signature Typed or Printed Comments: Form NTP-QA-31.8-1, Rev. 0
REQUIRED TASK INFORMATION ) JOB PERFORMANCE MEASURE SIRO 73.0P.2289.103 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required andlor posted as being necessary.
C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check wi" be provided and Self-Checking is required. II. REFERENCES A. OP-173-001, CONTAINMENT ATMOSPHERE CONTROL SYSTEM (Rev. 38) III. OPERATIONAL ACTIVrnES None IV. TASK CONDITIONS A. The plant is in a post-LOCA condition 24 hours after an event. B. Containment pressure is 7.0 psig, steady. C. Containment temperature was 135°F before the LOCA. D. Hi02 concentrations are below combustible limits. V. INITIATING CUE Start Containment Hydrogen Recombiner 1E440A in Manual. VI. TASK STANDARD Selected Recombiner operating manually lAW OP-173-001. VII. 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
)
PERFORMANCeiHECKLIST Page 30t 10 V Appl. To/JPM No.: SIRO 73.0P.2289.103 Student Name:,_ _ _ _ _ _ _ _ __ Step Action 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-173-001. Controlled copy obtained.
- 2. Select the correct procedure section to perform. Selects Section 2.10.
- 3. Review the prerequisites I precautions. Ensures all prerequisites have been met.
Reviews precautions. I EVALUATOR CUE Inform student that all prerequisites have been met.
- 4. Ensure H2 Recombiner aligned as follows prior to Student turning H2 Rcb A Heater Power Adj startup: Control HC-15796A in counter clockwise direction until potentiometer STOPS.
- Turn H2 Rcb A Heater Power Adj Control HC-15796A in counter clockwise direction until potentiometer STOPS
.,. = Critical Step # = Critical Sequence Form NTP-QA-31.8-2, Rev. 0
PERFORMAN"ce"CHECKLIST Page 4 of 10 L, Appl. To/JPM No.: SIRO 73.0P.2289.103 Student Name:_ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments EVALUATOR CUE Control turned counter clockwise until potentiometer STOPS.
- 5.
- Set H2 Rcb A Heater Power Adj Control Student sets H2 Rcb A Heater Power Adj Control HC-15796A to ZERO (000) HC-15796A to ZERO (000).
EVALUATOR CUE Control set to ZERO (000).
- 6.
- Observe H2 RCB A Power In Available Student observes H2 RCB A Power In Available White light illuminated indicating MCC White light illuminated indicating MCC feeder feeder closed closed.
EVALUATOR CUE White light illuminated indicating MCC feeder is closed.
*7. To start H2 Recombiner in Manual: Student simulates placing H2 Rcb A Temp Ctl Select HSS-15796A to Man.
a) Place H2 Rcb A Temp Ctl Select HSS-15796A to Man.
- H2 Rcb A Temp Ctl Select HSS-15796A placed to Man
- = 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.
*8. b) Place H2 Rcb A Power Out Switch HS-15796A Student simulates placing H2 Rcb A Power Out to ON. Switch HS-15796A placed to ON.
- H2 Reb A Power Out Switch HS-15796A placed to ON EVALUATOR CUE Switch clicks and is in ON position. Red light is ON.
- 9. Determine required power setting from Student determines required power setting from Attachment A. ATT A to be 56KW based on Initial Conditions.
- 56KW is determined to be power setting
--~-
- = Critical Step # =Critical Sequence Form NTP-QA-31.8-2, Rev. 0
--) Page60f 10 V PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 73.0P.2289.103 Student Name:,_ _ _ _ _ _ _ _ __
Step Action Standard Eval Comments NOTE 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. CAUTION 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 follows: 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 KW.
HC-15796A until H2 Rcb A Power Out to Heater XI-15796A indicates 5 KW.
- H2 RCB A Heater Power Adj Control HC 15796A slowly adjusted in the CW direction until H2 Rcb A Power Out to Heater XI 15796A indicates 5 KW
-- -- - - - - - - L-.
- =Critical Step # =Critical Sequence Form NTP-QA-31.8-2, Rev. 0
)
PERFORMANCt CHECKLIST Page 7 of 10 \...t Appl. To/JPM No.: SIRO 73.0P.2289.103 Student Name:,_ _ _ _ _ _ _ _ __ I Step Action Standard Eval Comments 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 KW. Evaluator Cue then simulates slowly adjusting H2 RCB A Heater Power Adj Control HC-15796A until H2 Rcb A Power Out to Heater XI-15796A indicates 10 KW.
EVALUATOR CUE 10 minutes has elapsed. After Evaluator Cue, HC 15796A is slowly adjusted CW until XI-15796A indicates 10 KW. EVALUATOR CUE Inform Student HC-15796A is slowly turning in the CW direction. KW indication is riSing. KW indication reads 10KW.
*12. 3) After 10 minutes, Adjust HC-15796A until Student simulates waiting 10 min based on XI-15796A indicates 20 KW. Evaluator Cue then simulates slowly adjusting H2 RCB A Heater Power Adj Control HC-15796A until H2 Rcb A Power Out to Heater XI-15796A indicates 20 KW.
- =Critical Step # = Critical Sequence Form NTP-QA-31.8-2, Rev. 0
~~".
PERFORMAN~' 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, HC 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, HC 15796A is slowly adjusted CW until XI-15796A indicates 56 KW.
- = Critical Step # = Critical Sequence Form NTP-QA-31.8-2, Rev. 0
PERFORMAN~CHECKLIST Page 90f 10 L 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, #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
PERFORMAN~'CHECKLIST Page 10 of 10 l.,... Appl. To/JPM No.: SIRO 73.0P.2289.103 Student Name: _ _ _ _ _ _ _ _ _ __ Step Action Standard Eval Comments
- 15. Adjust HC-15796A between 0 KW and calculated Student verifies TIC-15796A temperature is rising required power setting to maintain following: towards 1250°F not to exceed 1400°F.
a) H2 Recombiner temp - 1250°F not to exceed 1400°F b) Required power setting on H2 Rcb A Power Out to Heater XI-15796A not to exceed 75KW. EVALUATOR CUE Temperature is 1250°F steady. Inform the Student that they are relieved by another Operator to monitor Rcb operation. EVALUATOR 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 )
- The plant is in a post-LOCA condition 24 hours after an event.
- Containment pressure is 7.0 psig, steady.
- Containment temperature was 135°F before the LOCA.
- H2/0 2 concentrations are below combustible limits.
INlrIA-nNG CUE Start Containment Hydrogen Recombiner 1E440A in Manual.
)
Page 1 of 2
TASK CONDITIONS )
- The plant is in a post*LOCA condition 24 hours after an event.
- Containment pressure is 7.0 psig, steady.
- Containment temperature was 135°F before the LOCA.
- H2/0 2 concentrations are below combustible limits.
INITIATING CUE Start Containment Hydrogen Recombiner 1E440A in Manual. Page 2 of 2
NRC Scenario #~ummary 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. EO 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): 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) Malf> EOP (1-2): 2 (SRV tailpipe break, ESS bus Lockout) ABN Events (2-4): 4 (ERC Malf, Loss RBCCW, HPCI start, Main Cond Vac) MAJ Events (1-2): 1 (SRV Tailpipe rupture-PC pressure) EOPs entered (1-2): 2 (RPV Control, PC Control) EOP Contingencies (0-2): o (None) Critical Tasks (2-3): 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 SRO, BOP R 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: 0 NOR: I lie: 2 MAl: I TS: 2 SRO (I) needs minimum total for all Scenarios of: RX: NOR: lie: 4 MAl: 2 TS: 2 RO needs minimum total for all Scenarios of: RX: I NOR: I lie: 4 MAl: 2 TS: 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: ,t----"<~'......
'-'--"', ", "-{-""",~.Y""",,..,......:,:
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. *. ,::_:,\_,'........... ..............."""'}"""'.......
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- '-"""'/_'_ _11 I Prepared By: D. KellY 1 M. Jacopetti Instructor 11/19/10 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 I Form NTP-QA-31.7-1, Rev. 0, Page 2 of 15
Page 3 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 SCENARIO
SUMMARY
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 BLANK 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 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.
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 BLANK 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.
- 7. STANDARDS FOR FAILURES OF PROTECTIVE FEA TURES 7.4 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.
7.4.2 Should a situation occur that an equipment protective feature is found disabled, then the operator shall take prompt action to either:
- a. Restore the protective feature OR
- b. Remove the equipment from service.
- 8. 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 methods: Maximize CRD to drift control rods. Drive control rods after bypassing RWM. Reset and Scram again by performing ES-158-002 Bypass RPS logic trips. De-energizing RPS solenoids by performing ES-158-001. Local venting of Scram Air Header. 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: PC/P-5 WHEN SUPP CHMBR PRESS> 13 PSIG CONTINUE [Directions to initiate drywell sprays] 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 loop Perform a valve alignment to provide a flowpath for spray. 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, A drywell spray initiation limit has been II 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: PC/P-7 SHUT DOWN OW COOLERS SHUT DOWN RECIRC PUMPS INITIATE OW SPRAYS UNLESS PUMPS CONTINUOUSLY NEEDED FOR ADEQUATE CORE COOLING LIMITING FLOW TO BETWEEN 1000 AND 2800 GPM FOR FIRST 30 SEC 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 1C601, 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
Page 15 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 SCENARIO REFERENCES
- 1. OP-149-00S RHR Suppression Pool Cooling
- 2. GO-100-012 Power Maneuvers
- 3. ON-193-001 Turbine EHC System Malfunction
- 4. ON-114-001 Loss of RBCCW
- 5. AR107-001 (003) SBLC Injection HV-148-F006 not fully open
- 6. TS 3.1.7 Standby Liquid Control System
- 7. ON-156-001 Unanticipated Reactivity Change
- 8. OP-152-001 HPCI System
- 9. TS 3.S.1 ECCS Operating
- 10. AR-121-001 (F02) SJAE Condenser Discharge Hi Press
- 11. ON-143-001 Main Condenser Vacuum and Offgas Sys Off-Normal Operation
- 12. ON-156-001 Unanticipated Reactivity Change
- 13. EO-100-102 RPVControl
- 14. EO-100-103 Primary Containment Control 1S.0P-149-004 RHR Containment Cooling
- 16. ON-183-001 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 BLAN~
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
- 1. Initialize the simulator to IC-376: Unit 1 at 75 percent power EOl, Unit 2 in Startup.
- 2. load SCN file LOC23 NRC Scenario Spare
- 3. Place simulator in RUN and verify the following pre-inserts and Key assignments MF RF OR SCN ET 2:2 2:2 4:4 o 0:0 IMF mfRP158003 RPS Fails To Auto Actuate lOR diHSC72A1S03AA f:NORM RPS Manual Scram Fails lOR diHSC72A1S03BB f:DISARM " "
lOR diHSC72A1S03CB f:DISARM " " lOR diHSC72A1S03DA f:NORM " " IMF cmfPM04_1 P21 OB RBCCW Pump 'B' Auto logic Fails Key[1]} IMF cmfMV08_HV151 F028A f:.0001 leak by to simulate loop venting Key[1]} IMF cmfMV08_HV151 F024A r:60 f:.00000001 leak by to simulate loop venting Key[2]} MMF cmfMV08_HV151 F028A f:O Remove leak by Key[2]} IMMF cmfMV08_HV151 F024A f:O Remove leak by Key[3]} MMF cmfMV08_HV151 F028A Delete leak by Key[3]} IMMF cmfMV08_HV151 F024A Delete leak by {Key[4]} IMF mfTC193026 f:10.0 EHC Steam Flow Gain Unit {Key[5]} IMF mfRW114003A RBCCW Pump 'A' Trip {Key[6]} IMF cmfMV07_HV148F006 f:10 SBel Inj Vlv Off Open Seat {Key[7]} IMF mfHP152004 HPCI Inadvertent Start {Key[8]} IMF mfMC143001 f:0.2 Main Condenser Air In leakage {Key[9]} MMF mfMC143001 1:10 f:50 Increase Main Cond Air In leakage {Key[10]} IMF mfMS183010A f:100 SRV 'A' Stuck Open {Key[10]} IMF mfMS183013A f:25 SRV 'A' Tail Pipe Rupture {Key[11]} IMF mfHP152015 HPCI Turbine trip {Key[12]} IMF cmfRV06_PSV141F13A Pull "A" SRV fuses F019 & F020 {Key[13]} IMF cmfEB01_1A201 'A' Bus lockout {Key[14]} IMF cmfEB01_1A202 'B' Bus lockout {Key[15]} IMF cmfEB01_1A203 'C' Bus lockout {Key[16]} IMF cmfEB01_1A204 '0' Bus Lockout
- 4. ENSURE Eccentricity recorder, XR-10116, on 1C652 is displaying BPV POS and CV POS trends.
- 5. 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, BOP) 2 10 min IRaise Rx power (Normal, SRO, ATC) 3 20 min kc II (Component, SRO, BOP) (Reactivity, ATC) 4 35 min RBCCW pump trip (Component, SRO, BOP) 5 40 min SBlC inj valve (Component, SRO) 6 50 min HPCI inadvertent start (Component, SRO, BOP) 7 60 min loss of Main Cond Vac (Reactivity, SRO, ATC) 8 70 min Failure to Scram (Instrument, ATC) 9 75 min SRV tailpipe rupture \ stuck open (Major, All) 10 85 min ESS bus lockout (Component, BOP) 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: _1~ __~____~~~~~________________________________________ Brief
Description:
Secure Suppression Pool cooling POSITION TIME STUDENT ACTIVITIES SRO Direct Suppression Pool cooling secured per OP-149-00S Section 2.1. Direct not to secure RHRSW and ESW after RHR pump shutdown due to subsequent support of scheduled RHR Surveillance Test Steps up to Step 2.1.20 are complete. Enters TRO 3.8.2.1 for Motor Overload Bypass BOP 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 1P202A
- 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: _1~ __~____~~~__~____________________________________ 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 complete Key 2 MMF cmfMV08_HV151 F024A f:O Simulate venting complete Key 3 DMF cmfMV08_HV151 F028A Simulate venting complete Key 3 DMF cmfMV08.:...HV151 F024A Simulate venting complete 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, 3 Brief
Description:
-'-"Ra;; ; I;.; ;.S8.; . .; . ;R""x..; .P. .; o-'-'w. .; e.; .zr,. .; E; .; .H.;. .;C'-o-'-'s; ;. ;c. .;.;I ""la:.:;ti;.; ;.o.:. ;.n_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
POSITION TIME_ STUDENT ACTIVITIES SRO 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 ATC 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.
BOP 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 Task NOTES:
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 PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No: ~2~,~3__~~__-=~__~~________________________________________ 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: _3~ ____________________________________________________________ Brief
Description:
_E=H:.,:.C=...=o.=.sc=-:i:.:.;.lIa::.;t;;,.;io;.,;:.n=---__________________________________________ POSITION TIME STUDENT ACTIVITIES ATC Reports oscillating reactor power, level, and pressure. Reports oscillating generator output. Reports oscillating Turbine Control Valve positions Ceases raising Rx power Depresses TRA Init Button on PCO desk to initiate TRA. SRO 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 ATC Implements ON-193-001 Section 3.4 Reduces Reactor Power with Recirc flow by 5% with RRP "A" and "B" (Double Chevron) DEC buttons BOP 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)
SRO 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 to stop the control valve oscillations. #2: Crew may contact I & C to have the backup pressure regulator placed in service due to control room indications showing pressure regulator oscillations. This is caused by the scenario's EHC malfunction. #3: The SRO may refer to TS 3.7.8, Main Turbine Pressure Regulation System, if the crew believes the
- 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 PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No: _3~ _________________________________________________________ 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) SRO 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. BOP 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 PLAY, AND INSTRUCTOR'S PERSONAL NOTES 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 1C239 PNOV and:
- Depress 1PBCMPA\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 1A RBCCW pump, wait three minutes and report "The Unit 1 A RBCCW Pump outboard pump bearing is extremely hot and discolored." If directed to check 18216-103, wait two minutes and report "1 B216-1 03 is tripped." If directed to check status of RWCU panel, wait two minutes and report "Both RWCU Filters are in Hold." At CIG Panel on 1C239, report that the "Low cooling water pressure alarms are in for both compressors" (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 hours.) 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 PLAY, AND INS"rRUCTOR'S PERSONAL NOTES 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 control room via radio and state "HV-148-F006 appears to be about 10% open." If directed to manually open it, report "I can not engage the clutch." 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 TIME STUDENT ACTIVITIES BOP 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 SRO Verifies no valid initiation signal exists Direct HPCI overridden per OP-152-001
- Directs BOP to enter ON-156-001.
Declares HPCllnoperable 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. BOP Executes OP-152-001 Section 2.16 or Hard Card Overrides HPCI and prevents uncontrolled injection
*
- 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 SRO Directs BOP to enter ON-156-001.
Declares HPCI Inoperable
- 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.
ATC 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 PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No: 6
~~---------------------------------------------------------
Brief
Description:
HPCllnadvertent start INSTRUCTOR ACTIVITY: When SBLC issue is complete, on Lead Instructors cue, insert HPCI inadvertent start by activating Key #7: {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, 8 Brief
Description:
_L::;o::.;ss=-.;M;;.;;.;8::.;I;;.;;.;n.. ;;C;.;::o.::..;n,;:;,de;;;;.;;n.:;.;;s;..=e..:. .r..;;.V.;;;;.8c::.;u;;.:u~m~,...:..F...:::8;;.;;.;lIu::.;r-=e....:.to.:::....;;;S..:;.cr:....;;:a::.;m~_ _ _ _ _ _ _ _ _ _ _ _ __ POSITION TIME STUDENT ACTIVITIES ATC/BOP Responds to page and informs crew. Dispatch NPO / FUS to investigate noise. SRO Contacts Work Week Manager to have FIN investigate. All Recognize MWe lowering, elevated Offgas Flow, and lowering Main Condenser vacuum. (Note 1) SRO 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 ATC Reduces Rx Power by depressing RRP /1:' and "B" DEC buttons on Recirc HMI in attempt to maintain Turbine Exhaust Pressure limits. SRO 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. ATC 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 PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No: 7,8 Brief
Description:
_L=.;o:;.;;ss~M:.:.:a:;;;ln;.;;...;;;.C.;:.;on:..:.;d=.;e:..:.;n;.;;.se.::;,;r;.....V:...:a:.:;;c.;;;;u;;;;.;um;.;..;.z...;!F:....:a:;;;iI;.;;;;u:...:re:...:t;.;;.o....::S;.;:;c.;.;;ra;;.;.;m~_ _ _ _ _ _ _ _ _ _ _ __ 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: ~8~,9~ __ ~ ______________________ ~ _____________________________ Brief
Description:
Failure to Scram, SRV Tailpipe rupture-Stuck Open
".......,111""... TIME STUDENT ACTIVITIES ATC Reports all Rods In Executes ON-1 00-1 01 SRO Enters EO-1 00-1 02 Directs ATC 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 BOP 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 SRO ers ON-183-oo1, Stuck Open SRV, and directs BOP to perform the ON. BOP 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 ATC Align FW for SULC per OP-145-001 Att A, as follows:
- Stop two Condensate Pumps by depressing 1P1 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 ATWS 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 PLAY. AND INSTRUCTOR'S PERSONAL NOTES Event No: ~9~~~~ ____~~~~______________________________________ Brief
Description:
SRV Tailpipe rupture-Stuck Open INSTRUCTOR ACTIVITY: When SRV 'A' is opened, fail the tailpipe and stick it open by activating Key #10: {Key[10]} IMF mfMS183010A f:100 SRV 'A' Stuck Open {Key[10]} IMF mfMS183013A f:25 SRV 'A' Tail Pipe Rupture 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 pull {Key[12]} SRV fuse F020 pull 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: _9~!~10~ ________~__________~~~______________________________ Brief
Description:
SRV Tailpipe rupture \ stuck open - ESS Bus Lockout POSITION TIME STUDENT ACTIVITIES SRO Enters EO-1 00-1 03 (Primary Containment Control) Directs BOP to initiate Suppression Chamber Sprays Directs BOP to monitor for 13 psig Supp Chamber pressure. Monitors PSL Curve BOP Sprays Suppression Chamber iaw OP-149-OO4 Att. A, as follows:
- Places HS-El1-1S17A(B) to Override
- Opens HV-151-F028A(B)
- Closes HV-15l-F017A(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.
*SRO 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.
ATC Shutdown Recirc Pumps by depressing HSOl4001 A and B. Places all Drywell Cooler I Fan handswitches on 1C68l to Stop BOP
- Spray the OW:
Using OP149-004, Att A:
- 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.
Crew Recognize loss of ESS Bus
- Denotes Critical Task NOTES: I STA SPDS is lost if 1BESS is de-energized. PICSY is lost if 1CESS 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 PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No: _1~O~ ________________________________________________________ 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]} IMF 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: _9~,~1~O=_~---__~--~---~~--~~----~--~--------------- Brief
Description:
SRV Tailpipe rupture \ stuck open - ESS bus Lockout continued POSITION TIME STUDENT ACTIVITIES BOP / ATC Assesses electrical plant:
- Reports 1A(l B)(l C)(l D) ESS Bus is de-energized due to a bus lockout.
- References AR-015-oo1 (008 if "A"), (011 if "B"), (014 if "C"), or AR-Ol6 001 (001 if "0")
- Dispatches NPO to check ESS Bus.
*SRO 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 follows:
- Place HS-E11-1S17B(A) to Override
- 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 OW:
- Opens HV-151-F021B(A)
- 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 HV 151 F016B(A). SRO Directs RPV level restored and maintained +13 inches to +54 inches with Condensate. ATC 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. #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>..
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Page 39 Scenario LOC23-NRC-Spare Rev. 0,11/19/2010 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No: 9, 10 Brief
Description:
_S::;..:Rc..:..V.:....;;..Ta=i~lp;.;;.aipe:..::.....;;r..;.;u.r:...pt:..;;;u;;;.;re"-\.:....;s;.;.tu=c;;.;..k;..;;o;.&:p....;;.e;;.;..n_-....;;.E:.::;S..::;;S...;;;b;..;;;;u..;.;s...:;;L..;.;oc.;..;k.:...:;o...;;;u.;..;tc.;..;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::
- 1. If 1BESS was de-energized, once the simulator is reset and placed in Run, restore the two non selected SPOS screens.
- 2. If 1CESS 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 (ATWS). The Crew will enter EO 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 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-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 IAW 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 isolate) ABN Events (2-4): 2 (Loss FW Heating, Control Rod Problems) MAl Events (1-2): (ATWS) EOPs entered (1-2): (Primary Containment Control) EOP Contingencies (0-2): (Level Power Control)
- "\ .
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 IAW EO-100-113 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: 0 NOR: I lie: 2 MAl: I TS: 2 SRO (I) needs minimum total for all Scenarios of: RX: I NOR: I lie: 4 MAl: 2 TS: 2 RO needs minimum total for all Scenarios of: RX: I NOR: I lie: 4 MAl: 2 TS: 0
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SIMULATOR SCENARIO Scenario
Title:
LOC23 NRC SCENARIO 2 Scenario Duration: 90 Minutes Scenario Number: LOC23 NRC-2 Revision/Date: Rev. 0,11/1812010 Course: Fc "
.i .'
;7~:";'if . :,,:>. : .' ...*.... J .*....,. .', *... : ..
Prepared By: Don Kelly 1 Mike Jacopetti 11/18/2010 Instructor Date Reviewed By: rA ~ ..... .oL~
, -C- fl'l. '"U. U-~ "/'hr:Jh 0
( Operations Training Supervisor Date Approved By: '7.f"JUJk
! Sup#rvising Manager/Shift Manager II/'fa/IO Date Form NTP-QA-31.7-1, Rev. 0, Page 1 of 15
Page 2 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 THIS PAGE IS INTENTIONALLY LEfT BLANK Form NTP-QA-31.7-1, Rev. 0, Page 2 of 15
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 (ATWS). 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 EO 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 4 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 THIS PAGE IS INTENTIONALLY LEFT BLANK Form NTP-QA-31.7-1, Rev. 0, Page 4 of 15
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 6 Scenario LOC23 NRC-2 Rev. 0,11/18/2010 THIS PAGE IS INTENTIONALLY lEFT BLANK , .", 'j Form NTP-QA-31.7-1, Rev. 0, Page 6 of 15
Page? Scenario LOC23 NRC-2 Rev. 0, 11/18/2010
- Inlect SLC CRITICAL TASKS I
- Inhibits ADS Safety Significance Early boron injection has the following benefits:
Stop or prevent large magnitude Limit Cycle Oscillations which can lead to core damage. Limit fuel damage from uneven flux patterns that could result from partial rod inserts. Inhibiting ADS prevents uncontrolled injection of large amounts of relatively cold, unborated low pressure ECCS water when the reactor is not shutdown with control rods. Conseguences for Failure to Perform Task Failure to inject Boron can result in Cycle Oscillations which can lead to core damage. Fuel damage from uneven flux patterns that could result from partial rod inserts. Failure to inhibit ADS can result in large amounts of positive reactivity addition due to boron dilution and cold water injection. SSES EOP Basis for: LQ/Q-3 IF INITIAL ATWS PWR > 5% OR CANNOT BE DETERMINED INJECT SLC AND INHIBIT ADS 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 Squib valves and close the Reactor Water Cleanup isolation valve. Alternate SLC injection using RCIC (ES-150-002) Inhibit ADS by placing 1C601 keylock switches to INHIBIT Performance Feedback Successful SLC injection would be indicated by a lowering SLC tank level and a corresponding power level decrease. Successful ADS inhibiting is indicated by Green Indicating Light at switch illuminating. 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: LQlL-13 MAINTAIN LVL BETWEEN -60" AND *161" USING TABLE 15 SYSTEMS BYPASSING INTERLOCKS AS NECESSARY lAW ANY: 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:
- 1. Provides a margin for core coverage.
- 2. Avoids operation near TAF where core power is more responsive to RPV pressure fluctuations.
- 3. 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
- 4. 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.
- 5. Water level can be determined from wide range level instrumentation.
- 6. 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 methods: Maximize CRD to drift control rods. Drive control rods after bypassing RWM. Reset and Scram again by performing ES-158-002 Bypass RPS logic trips. De-energizing RPS solenoids by performing ES-158-001. Local venting of Scram Air Header. 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. OP-115-001 TBCCW
- 2. AR-128-001 (001) DRWL FAN 1V414B FAILED
- 3. TS 3.6.3.2 CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM
- 4. OI-AD-029 EMERGENCY LOAD CONTROL
- 5. GO-100-012 POWER MANEUVERS
- 6. AR-029-001 A01 CS EMER OA SUP FAN FAILED
- 7. TS 3.7.3 PLANT SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY SYSTEM (CREOASS)
- 8. AR-102-001 (C03) 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. ON-155-001 CONTROL ROD PROBLEMS
- 12. EO-1 00-1 02 RPV CONTROL
- 13. EO-100-113 LEVEUPOWER CONTROL
- 14. OP-149-004 RHR CONTAINMENT COOLING
- 15. OP-145-001 RFP AND RFP LUBE OIL SYSTEM
- 16. OP-183-001 AUTOMATIC DEPRESSURIZATION SYSTEM AND SAFETY RELIEF VALVES
- 17. OP-184-001, ATT A EO HARD CARD-BYPASS MSIV AND CIG INTERLOCKS
- 18. OP-150-001, ATT A EO HARD CARD-OVERRIDING RCIC INJECTION
- 19. OP-152-001, ATT C EO HARD CARD-OVERRIDING HPCIINJECTION
- 20. OP-145-001, ATT C EO HARD CARD-ATWS POWER\LEVEL REDUCTION STRATEGY
- 21. OP-149-004, ATT A EO HARD CARD-INITIATE CONTAINMENT COOLING Form NTP-QA-31.7-1, Rev. 0, Page 9 of 15
Page 12 Scenario LOC23 NRC-2 Rev. 0,11/18/2010 THIS PAGE IS INTENTIONALLY LEFT BLANK" Form NTP-QA-31.7-1, Rev. 0, Page 10 of 15
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 1S03AA f:NORM RPS MANUAL SCRAM FAilS II lOR diHSC72A 1S03BB f:DISARM " lOR diHSC72A 1S03CB f:DISARM u " II lOR diHSC72A 1S03DA f:NORM " 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 14 Scenario LOC23 NRC-2 Rev. 0,11/18/2010 THIS PAGElS INTENTIONALLY LEFT BLANK Form NTP-QA-31.7-1, Rev. 0, Page 12 of 15
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 DESCRIPTION 1 2 min SwapTBCCW (Normal: SRO, BOP) 2 10min DW Cool Fan trip (Component: SRO) 3 20 min Min Gen Emerg (Normal: SRO, ATC) 4 30 min CREOASS inop (Component: SRO, BOP) 5 40 min RRP MG hi temp (Component: SRO, BOP) 6 45 min loss FW Heating (Reactivity: SRO, ATC) 7 60 min 3 Rods Drift (Component: ATC) 8 60 min ATWS (Major: All) 9 65 min EHC malfunction (Component) 10 65 min SBlC pump trip (Component: BOP) 11 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: 1 Brief
Description:
_S.;:;.w.;:.:.;;:;a,J;;.p....::T-=B:..;C:..;C;..;W~_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 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 1P1 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 1P1 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
I NOTES: Form NTP-QA-31.7-1, Rev. 0, Page 14 of 15
Page 17 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INS'rRUCTOR'S PERSONAL NOTES Event No: _1~ _________________________________________________________ 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:
- 1. As NPO at TBCCW, when requested, report 1 B TBCCW Pump is ready for a start."
- 2. When directed to close, then open 114011, report dOing so after taking actions as directed above.
- 3. 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
- ~~.-.-------.-----
Page 18 Scenario LOC23 NRC-2 Rev. 0, 11/18/2010 SCENARIO EVENT FORM Event No: ~2~~~~~~ _______________________________________________ Brief
Description:
DW cooling Fan trip POSITION TIME STUDENT ACTIVITIES ATC Report 1C681 Panel Trouble alarm and refer to AR-1 06-001 (B16) BOP Report DW Cooling Fan 1V414B tripped Refer to AR-128-001 (001) Verifies lV414A is running Dispatch NPO to check 1B246061 (Note 1) Monitor D!ywell Temperature SRO 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. I
- Denotes Critical Task NOTES: I
#1: Crew may place 1V414B 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 PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No: ~2~ _________________________________________________________ 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:
- 1. As RB1 NPO: three minutes after being directed to check 1B246061, 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."
- 2. When contacted as the Work Week Manager concerning 1V414B, 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: _3~,4~~ ______________~__~~~~~__~~__~__________________ Brief
Description:
Min Generation Emergency, Loss of CREOASS Fan 'A' Control Power POSITION TIME STUDENT ACTIVITIES ATC Report Min Gen Emergency request from GCC to lower output by 50 MWe. SRO 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. ATC 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.
BOP 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. BOP 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.
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 PLAY, AND INSTRUCTOR'S PERSONAL NOTES 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:
- 1. As Operator dispatched to investigate CREOASS Fan, wait three minutes and report: "Breaker OB136-063 is closed and still/ooks good."
- 2. As Work Week Manager-when contacted concerning CREOASS state, "I will contact FIN to investigate,"
- 3. 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: ~5~ __ ~ ______________________________________________________ Brief
Description:
~R:..;.;R:..;.;P~M;..::G;;..;H...;.;I......:;T..;;;e.;.;.m:.J:p_ _______________________________________
POSITION TIME STUDENT ACTIVITIES ATC 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 BOP 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. SRO Direct BOP to take manual control of "A" RR MG Set Hydraulic Oil temperature controller. Inform Work Week Manager of the controller malfunction ATC Monitor "A" Recirc Pump operation using Recirc HMI screen / PICSY display. BOP 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 PLAY. AND INSTRUCTOR'S PERSONAL NOTES Event No: 5 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: _6~ ___________________________________________________________ Brief
Description:
_L=O::.;:S8~F...;;W..:.....;.;H:..;:;e.:;;;at;;.:;.;;ln.:;,;;gL- ____________________________________ POSITION TIME STUDENT ACTIVITIES BOP 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. ATC Reports RPV power, pressure, and level. SRO 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)
ATC 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:
- 1. 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
- 2. 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.
BOP 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) ATC Maintain Rx power s 71 % by inserting Control Rods iaw the CRC Book. SRO 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 PLAY, AND INSTRUCTOR'S PERSONAL NOTES 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:
- 1. When contacted as the TB NPO to investigate 1C1 02 panel alarm, wait three minutes, then select the 1C1 02 PNOV display. Report alarms currently in. Do not report the closed indication for HV 10241 B unless the crew has already identified it has closed.
- 2. When contacted as the WWM concerning isolation of U1 4B Extraction Steam, reply "I will contact FIN to investigate.
- 3. 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: 7,8 Brief
Description:
-:...:.Ro~d::.:s;;...;D::.:r:..:.;lft~!.-.:..A.:..:.T.-.:..W:..:S=---._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
POSITION TIME STUDENT ACTIVITIES 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 Pushbuttons
- Report failure to Scram
- Inserts SRMs and IRMs by selecting each detector, depressing Power On and the Drive In pushbuttons.
BOP 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 SRO 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 B)
BOP
- Recognize the first SBlC pump started tripped BOP
- Start the other SBlC pump
- 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 Ll/FI 14806.
- Recognizes RWCU HV*144-FOO4 failed to close and closes it, or has ATC close it.
- Denotes Critical Task I
NOTES: Form NTP-QA-31.7-1, Rev. 0, Page 15 of 15
Page 27 Scenario LOC23 NRC-2 Rev. 0,11/18/2010 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No: ~7~,8~~~~~ _______________.______________________________________ 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 PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No: ~8~,9~1~103,~11~~~__~~~~____~~~~~____~~____~__~______ Brief
Description:
ATWS, EHC Malfunction, SBlC pump trip, RWCU fails to auto isolate continued INSTRUCTOR ACTIVITY: When both ARPs are tripped, insert Turbine Trip and TSVs to fail closed by activating Key 8: {Key[8]} IMF mfTC193001 Turbine Trip {Key[8]} IMF mfTC193025 TSVs Fail Closed 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: _8~,9~,~10~,~11~~~ ____~~~______~-=____________________________ Brief
Description:
ATWS, EHC Malfunction, SBlC pump trip. RWCU falls to auto isolate continued POSITION TIME 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 SIC-C32 1R601 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.
BOP Bypass MSIV and CIG interlocks iaw OP-184-001 Att A Hard Card, as follows:
- At 1C645 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. SRO Enters EO-1 00-1 03 when Suppression Pool temperature is > 90F Directs ATC to maximize Suppression Pool Cooli~g.
- Denotes Critical Task NOTES: I
#1 Due to the effectiveness of SBlC the time to reach -60 inches even with feedwater flow terminated may be extended. #2: If, due to reduce power level, ICS initiates alignment to SUlC and "8" and "C" RFPTs are in Idle Mode when ATC reaches applicable step, then ATC will need to verify the~ are in Idle.
Form NTP-QA-31.7-1, Rev. 0, Page 140f 15
Page 31 Scenario LOC23 NRC*2 Rev. 0, 11/18/2010 Event No: ~8~,9~.~10~.~11~________~=-~ ______-=~~~____~~____~__________ Brief
Description:
ATWS, EHC Malfunction, SBlC pump trip, RWCU fails to auto Isolate continued POSITION TIME STUDENT ACTIVITIES BOP 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.
SRO* Direct Control Rod insertion per Sh 2:
- Directs ATC 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 BOP Reports NPO venting Scram Air Header Monitors for Low Scram Air Pressure Alarm Monitors for drifting Rods ATC Reports all control rods full in.
SRO Directs BOP to have Scram Air Header restored and to stop SLC Pump. Contacts the FUS to stop performance of ES-158-oo1 Exits EO-1oo-113 Enters EO-100-102 Directs ATC to slowly restore RPV level to 13" to 54" using Feedwater. ATC Restores RPV level +13" to +54" by depressing INC button on SIC-C32 1R601 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 PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No: 8,9,10.11 Brief
Description:
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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 Header {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 PLAY: See above for specific communications. As necessary 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}}