ML042990551

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RB-09-2004 - Final - Operating Exam
ML042990551
Person / Time
Site: River Bend Entergy icon.png
Issue date: 09/23/2004
From: Gody A
Operations Branch IV
To: Hinnenkamp P
Entergy Operations
References
50-458/04-301, ES-301-1, NUREG-1021, Rev 9, RB-09-2004 50-458/04-301
Download: ML042990551 (305)
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Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: _____RO______ Operating Test Number: __1___

Admin Topic Description of activity to be performed (Type Code*) KA IR Notes Exam JPM No. K/A Statement(s)

Conduct of Complete the Daily Logs verification of power Operations distribution limits during Single Loop Operation (M) (A) Use plant computer to obtain and evaluate 2.1.19 3.0 ADM-R01 parametric information on system or component status.

Conduct of Determine Primary Containment water level and Operations correlated RPV water level per EOP Enclosure 23 (M) Ability to perform specific system and 2.1.23 3.9 ADM-R02 integrated plant procedures during different modes of plant operation.

Equipment Identify required tags and hanging sequence for Control SLC Pump Relief Valve removal and replacement.

(N) Knowledge of tagging and clearance 2.2.13 3.6 ADM-R03 procedures.

Radiation Enter and exit a High Radiation Area for a valve Control lineup.

(N) (A) Ability to perform procedures to reduce 2.3.10 2.9 ADM-RS04 excessive levels of radiation and guard against personnel exposure.

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path Page 1 of 2 NUREG-1021, Draft Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: _____SRO_____ Operating Test Number: __1___

Admin Topic Description of activity to be performed (Type Code*) KA IR Notes Exam JPM No. K/A Statement(s)

Conduct of Determine Alternate Decay Heat Removal Method Operations Ability to obtain and interpret station reference (N) (A) materials such as graphs / monographs / and 2.1.25 3.1 ADM-S01 tables which contain performance data.

Conduct of Complete LCO Status Sheet for inoperable Control Operations Room Fresh Air initiation instrumentation. 2.1.12 4.0 (N) Ability to apply technical specifications for a ADM-S02 system.

Equipment Review completed Quarterly SLC Pump and Valve Control Operability surveillance procedure for approval.

(N) (A) Knowledge of surveillance procedures. 2.2.12 3.4 ADM-S03 Radiation Enter and exit a High Radiation Area for a valve Control lineup.

(N) (A) Ability to perform procedures to reduce 2.3.10 3.3 ADM-RS04 excessive levels of radiation and guard against personnel exposure.

Emergency Classify an Emergency Event Plan 2.4.41 4.1 Knowledge of emergency action level (M) thresholds and classifications.

ADM-S05

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path Page 2 of 2 NUREG-1021, Draft Revision 9

Number: *RJPM-OPS-ADM-R01 RIVER Revision: 1 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • COMPLETE DAILY LOGS VERIFICATION OF POWER DISTRIBUTION LIMITS DURING SINGLE LOOP OPERATIONS REASON FOR REVISION:

NRC Exam JPM RO ADMIN - 1 PREPARE / REVIEW:

Erich Weinfurter 1497 7/7/2004 Preparer KCN Date Roger Persons 0862 7/8/2004 Technical Review (SME) KCN Date Frank McLean 0803 7/9/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-ADM-R01 TASK DESCRIPTION: Complete Daily Log Verification of Power Distribution Limits during Single Loop Operation.

TASK

REFERENCE:

302001002001 K/A REFERENCE & RATING: 2.1.19 (3.0/3.0)

TESTING METHOD: Simulate Actual Performance Performance X Control Simulator Classroom X Room COMPLETION TIME: 6 min.

MAX TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH Yes (FAULTED):

RJPM-OPS-ADM-R01 Page 2 of 10

RJPM-OPS-ADM-R01 SIMULATOR SETUP SHEET Task

Description:

Complete Daily Log Verification of Power Distribution Limits during Single Loop Operation Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-OPS-ADM-R01 Page 3 of 10

RJPM-OPS-ADM-R01 DATA SHEET References for Development: STP-000-0001, Daily Operations Logs GOP-0004, Single Loop Operation Required Materials: STP-000-0001, Daily Operations Logs GOP-0004, Single Loop Operation Attached POWERPLEX Core Performance Log Required Plant Condition: N/A Applicable Objectives: STM-514, Obj. H5 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-ADM-R01 Page 4 of 10

RJPM-OPS-ADM-R01 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The A Reactor Recirc Pump tripped from full power and GOP-0004, Single Loop Operation has been entered. Reactor Engineering has NOT implemented a new core monitoring system thermal limit deck for Single Loop Operation.

Initiating Cue:

The CRS has directed you to complete Step 113 of STP-000-0001, Data Sheet, with the attached Core Performance Log data.

RJPM-OPS-ADM-R01

  • Denotes Critical Step Page 5 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-R01 PERFORMANCE STEP STANDARD S/U COMMENTS STEP 113 NOTES Refer to administrative limits in GOP-0004 Step CUE: Reactor Engineering has 3.4. not implemented the appropriate Power Distribution Limits shall be core monitoring system thermal verified to be within the limits stated limit deck.

in Technical Specifications within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after Thermal Power is 23.8%

1. NOTE: Do NOT provide of rated thermal power and once per GOP-0004, Attachment 1 until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter.

requested by candidate.

During Single Loop Operation, refer to GOP-0004 to determine if administrative limits are applicable.

GOP-0004 Step 3.4 CUE: If asked as CRS, Reactor Engineering has not implemented During Single Loop Operation, an Uses 0.980 Admin limit for MFLCPR and 0.79 the appropriate core monitoring administrative limit of 0.980 shall be for MAPRAT. system thermal limit deck.

applied to MFLCPR and an administrative limit of 0.79 shall be

2. applied to MAPRAT while core flow is greater than 50% rated. The administrative limits may be removed once Reactor Engineering implements the appropriate core monitoring system thermal limit deck.

RJPM-OPS-ADM-R01

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-R01 PERFORMANCE STEP STANDARD S/U COMMENTS Reviews Core Performance Log to Fills in Step 113 identifying MFLCPR at 0.988 as CUE: As CRS, acknowledge obtain values for MFLPD, MAPRAT, exceeding SLO administrative limit. MFLCPR exceeding limit.

___*__3. and MFLCPR for operating log Step 113. Notifies CRS of MFLCPR exceeding limit. NOTE: Reading being circled is NOT critical.

Terminating Cue: Step 113 of STP-000-0001, Data Sheet 1 completed and MFLCPR identified as exceeding limit.

RJPM-OPS-ADM-R01

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-R01 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-ADM-R01 Page 8 of 10

RJPM-OPS-ADM-R01 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The A Reactor Recirc Pump tripped from full power and GOP-0004 Single Loop Operation has been entered.

Reactor Engineering has NOT implemented a new core monitoring system thermal limit deck for Single Loop Operation.

Initiating Cues: The CRS has directed you to complete Step 113 of STP-000-0001, Data Sheet 1, with the attached Core Performance Log data.

RJPM-OPS-ADM-R01 Page 9 of 10

RJPM-OPS-ADM-R01 POWERPLEX - III CORE PERFORMANCE LOG - OPS - 03FEB10 - 164555 B1-01-04 (02.11.03 @ 2100) GEOM=FULL PREDICT CALCULATION - UPD TDXEC PREV PCS Y RESTART 03FEB10 - 161100 POWER 2036.0 MWTH CYCLE EXP 10133.4 MWD/MT CMFLCPR .988 23-22 (67.0%) CORE EXP 23317.4 MWD/MT CMAPRAT .781 21-32-17 FLOW 45.4 MLB/HR PRESS 1015.0 PSIA CMFLPD .824 21-32-17 (53.7%) DHS 30.40 BTU/LB CMTPF 2.558 19-32-15 ELEC 719.6 MWE WFW 7.473 MLB/HR FCBB 1.879 2.46 FT ROD-LN 106.9  % TFW-A 383.7 DEG F P-PCS .000 17-34-18 K-EFF 1.0054 NON-EQ XE .00 P-PCFC -.252 35-10-10 CONTROL RODS SYMMETRIC, C.R. SEQUENCE: B-1, C.R. DENSITY: .070 04 08 12 16 20 24 28 32 36 40 44 48 52 53 -- -- -- -- -- -- -- 53 49 -- -- -- -- -- -- -- -- -- 49 45 -- -- -- -- -- - -- -- -- -- -- 45 KEY 41 -- -- -- -- 06 -- 12 -- 06 -- -- -- -- 41 R-MFLCPR 37 -- -- -- -- -- -- -- -- -- -- -- -- -- 37 M-MAPRAT 33 -- -- 10 P 24* -- -- -- 24 -- 10 -- -- 33 X-FDLRX 29 -- -- -- -- -- -- -- -- -- -- -- -- -- 29 P-PRECOND 25 -- -- 10 -- 24 -- -- -- 24 -- 10 -- -- 25 *-MULT 21 -- -- -- -- -- R- - 12 -- -- -- -- -- -- 21 17 -- -- -- -- 06 -- -- -- 17 -- -- -- -- 17 SUBST RODS 13 -- -- -- -- -- -- -- -- -- -- -- 13 09 -- -- -- -- -- -- -- -- -- 09 05 -- -- -- -- -- -- -- 05 04 08 12 16 20 24 28 32 36 40 44 48 52 THERMAL LIMIT DETAIL (TOP 5) AXIAL REL POWER MFLCPR LOC MAPRAT LOC MFLPD LOC TPF LOC LOC NOTCH RPOW

.988 23-22 .781 21-32-17 .824 21-32-17 2.558 19-32-15 25 .098

.961 27-22 .773 19-24-17 .763 19-32-17 2.461 21-34-15 24 00 .315

.938 21-28 .760 19-32-17 .751 19-24-17 2.438 23-48-04 23 02 .801

.925 15-22 .739 15-20-09 .746 29-48-04 2.376 35-12-04 22 04 1.007

.920 13-20 .737 13-26-21 .746 29-48-04 2.376 35-12-04 21 06 1.100 20 08 1.147 19 10 1.154 18 12 1.150 FUEL TYPE DETAIL AXIAL DISTRIBUTION DETAIL 17 14 1.146 MAX LHGR BATCH 16 16 1.189 TYPE LHGR LOC AVG EXP CORE -AVERAGE 15 18 1.189

----- ------- ------ POWER (PINER) -3.458 14 20 1.193 14 7.427 15-20-20 32.972 13 22 1.199 15 6.380 05-20-20 27.034 CORE-AVERAGE 12 24 1.184 16 5.005 05-30-20 27.375 EXPOSURE (INER) -10.915 11 26 1.179 17 7.140 19-22-17 20.836 10 28 1.180 18 8.616 19-28-17 26.561 09 30 1.178 19 9.622 21-32-15 28.341 08 32 1.166 20 9.045 21-28-17 12.792 07 34 1.149 21 10.185 19-32-17 12.224 06 36 1.124 05 38 1.100 04 40 1.071 03 42 .996 RADIAL RING 1 2 3 4 5 6 7 02 44 .780 RING REL POWER 1.07 1.26 1.29 1.20 1.21 1.13 .59 01 46 .204 RJPM-OPS-ADM-R01 Page 10 of 10

Number: *RJPM-OPS-ADM-R02 RIVER Revision: 4 BEND STATION Page 1 of 8 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • DETERMINE CONTAINMENT WATER LEVEL DURING CONTAINMENT FLOODING REASON FOR REVISION:

NRC Exam JPM RO ADMIN - 2 PREPARE / REVIEW:

Erich Weinfurter 1497 7/7/2004 Preparer KCN Date Roger Persons 0862 7/8/2004 Technical Review (SME) KCN Date Frank McLean 0803 7/9/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-ADM-R02 TASK DESCRIPTION: Determine Containment Water Level During Containment Flooding.

TASK

REFERENCE:

200063005001 K/A REFERENCE & RATING: 2.1.23, 3.9/4.0 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 8 min.

MAX TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-OPS-ADM-R02 Page 2 of 8

RJPM-OPS-ADM-R02 SIMULATOR SETUP SHEET Task

Description:

Determine Containment Water Level During Containment Flooding.

Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-OPS-ADM-R02 Page 3 of 8

RJPM-OPS-ADM-R02 DATA SHEET References for Development: EOP-0005, Enclosure 23, Containment Water Level Determination.

Required Materials: EOP-0005, Enclosure 23, Containment Water Level Determination.

Required Plant Condition: None Applicable Objectives: HLO-516 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-ADM-R02 Page 4 of 8

RJPM-OPS-ADM-R02 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

Containment Flooding is in progress in accordance with SAP-1. Suppression Pool level indication on panel H13-P808 is pegged upscale.

The CRS has directed you to determine Containment water level AND a correlated RPV water level using EOP-0005 Enclosure 23, Containment Water Level Determination. The following plant data has been obtained by completing Sections 3.1 and 3.2 of Enclosure 23:

Div II CMS-PI17B indicates 7.5 psig E51-R604 RCIC PUMP SUCTION PRESSURE indicates 30 psig Initiating Cue:

Complete EOP-0005, Enclosure 23, given the plant data from Division II CMS and E51-R604 for RCIC suction pressure to provide the CRS a Primary Containment water level AND a correlated RPV water level.

Report Containment water level from Enclosure 23 Figure 8 to the CRS as soon as it is obtained.

RJPM-OPS-ADM-R02

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-R02 PERFORMANCE STEP STANDARD S/U COMMENTS EOP Enclosure 23, Figure 8, Primary Uses Figure 8 to determine containment water CUE: When candidate reports Containment Water Level level at ~56 ft (+/-1 foot). level from Figure 8, request

1. Determination, to determine calculated value to confirm Figure Containment Water Level. Reports Primary Containment water level to CRS. 8 value and use calculated value to determine RPV water level.

Confirms Primary Containment Uses PCWL = [(ECCS Suction Press - CTMT NOTE: [30-7.5)2.3]+4 = Level in Water Level from Figure 8 with Press) 2.3] + 4 to determine containment water ft

  • 2. calculation per Step 3.3. level to be 55.75 ft.

[(22.5)2.3]+4 = Level in ft

[51.75]+4 = 55.75 ft Uses Table 1 and calculated value of Uses interpolation of Table 1 with the calculated containment water level to determine containment level (55.75 ft) to determine RPV

  • 3. RPV water level. water level at -237 inches.

Terminating Cue: Primary Containment water level AND correlated RPV water level are provide to the CRS using EOP-0005, Enclosure 23.

RJPM-OPS-ADM-R02

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-R02 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-ADM-R02 Page 7 of 8

RJPM-OPS-ADM-R02 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: Containment Flooding is in progress in accordance with SAP-1.

Suppression Pool level indication on panel H13-P808 is pegged upscale.

The CRS has directed you to determine Containment water level AND a correlated RPV water level using EOP-0005 Enclosure 23, Containment Water Level Determination.

The following plant data has been obtained by completing Sections 3.1 and 3.2 of Enclosure 23:

  • Div II CMS-PI17B indicates 7.5 psig
  • E51-R604 RCIC PUMP SUCTION PRESSURE indicates 30 psig Initiating Cues: Complete EOP-0005, Enclosure 23, given the plant data from Division II CMS and E51-R604 for RCIC suction pressure to provide the CRS a Primary Containment water level AND a correlated RPV water level.

Report a value for Containment water level from Enclosure 23 Figure 8 to CRS as soon as it is obtained.

CONTAINMENT WATER LEVEL from FIG 8 ______________________

CONTAINMENT WATER LEVEL CALCULATED __________________

RPV WATER LEVEL (Based on calculated Containment water level) _________________

RJPM-OPS-ADM-R02 Page 8 of 8

Number: *RJPM-OPS-ADM-R03 RIVER Revision: 0 BEND STATION Page 1 of 12 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • IDENTIFY REQUIRED TAGS AND HANGING SEQUENCE FOR SLC PUMP RELIEF VALVE REMOVAL AND REPLACEMENT REASON FOR REVISION:

NRC Exam JPM RO ADMIN - 3 PREPARE / REVIEW:

Erich Weinfurter 1497 7/17/2004 Preparer KCN Date Roger Persons 0862 7/17/2004 Technical Review (SME) KCN Date Tim Manry 0757 7/19/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-ADM-R03 TASK DESCRIPTION: Identify Required Tags and Hanging Sequence For SLC Pump Relief Valve Removal and Replacement TASK

REFERENCE:

K/A REFERENCE & RATING: 2.2.13, 3.6/3.8 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 17 min.

MAX TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-OPS-ADM-R03 Page 2 of 12

RJPM-OPS-ADM-R03 SIMULATOR SETUP SHEET Task

Description:

Identify Required Tags and Hanging Sequence For SLC Pump Relief Valve Removal and Replacement Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-OPS-ADM-R03 Page 3 of 12

RJPM-OPS-ADM-R03 DATA SHEET References for Development: PID 27-16A, System P&ID SOP-0028, Standby Liquid Control OSP-0038 Protective Tagging Guidelines Tech Spec. 3.2.1, SLC LCO Required Materials: PID 27-16A, System P&ID SOP-0028, Standby Liquid Control OSP-0038 Required Plant Condition: Mode 1, During the last performance of STP-0201-6310, SLC Quarterly Pump and Valve Operability Test, the SLC Pump Relief Valve C41-RVF0029A lifted and would not reseat.

Applicable Objectives: ELP-OPS-CLR Obj. C Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-ADM-R03 Page 4 of 12

RJPM-OPS-ADM-R03 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is operating in Mode 1. Maintenance has requested a tagout to replace the Pump Relief Valve C41-RVF029A Standby Liquid Control Pump 1A Header Press Relief Valve per WO579067, which is expected to take 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to complete. The eSOMs Tagging Computer is down so the tagout is to be manual, and the tags will be entered into the system after it is back in service.

Initiating Cue:

The CRS has directed you to assist in preparing a tagout to replace the valve. Because of the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> LCO for both SLC Pumps out of service, the tagout must not INOP the B SLC pump. A tagging Official will complete the remaining parts of the Tagout Cover Sheet you have been given by the CRS.

RJPM-OPS-ADM-R03

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-R03 PERFORMANCE STEP STANDARD S/U COMMENTS Reviews OSP-0038 Attachment 7 Obtains PID for SLC and SOP-0028 CUE: Provide PID and SOP Tagout Cover Sheet and obtains when requested. Provide OP-102 documents to develop tagging. for manual tagout, if requested.

1.

NOTE: Including the component location on the tagging sheet is NOT critical.

Complete Tagout Tag Hung List C41-S1A in Main Control Room JPM Steps 2 thru 5 may be written down in any order on tagout sheet,

  • 2. Control Switchs NEUTRAL with Key Removed provided that the final Hang List matches the critical steps when completed Complete Tagout Tag Hung List C41-PC001A H22-PNLP011 Control Optional Tag (not required with breaker tagged)
3. Control Switch DISABLE with Key Removed Complete Tagout Tag Hung List EHS-MCC2A BKR 2C
  • 4. Electrical Breaker OFF Complete Tagout Tag Hung List C41-VF003A and C41-VF002A
  • 5. Isolation Valves Both CLOSED RJPM-OPS-ADM-R03
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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-R03 PERFORMANCE STEP STANDARD S/U COMMENTS Complete Tagout Tag Hung List Sequence for Critical Tags Steps 2,4,5 in accordance with attached completed sample.

  • 6. Sequence for Tag installation Control, Breaker, Valves Terminating Cue: Manual Tagout Form completed.

RJPM-OPS-ADM-R03

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-R03 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-ADM-R03 Page 8 of 12

RJPM-OPS-ADM-R03 Clearance # (U-YY-Man-##) 1-04-MAN-01 Tagout: 201-C41-RVF029A -001 Date 9/20/04 st nd Tag Tag Equipment Seq Placement Configuration Placement 1 Placement 2 Seq Restoration Configuration As left Rest Rest No. Type Equipment Desc Verif Verif Config 1st 2nd Equip Location Verif Verif Notes Notes Danger C41-S1A NEUTRAL NEUTRAL 1 SLC Pump A 1 5 136 CB Key Removed Key Removed H13-P601 Danger C41-PC001A DISABLE DISABLE 2 H22-PNLP011 2 4 Control Key Removed Key Removed SLSPNL120 Danger EHS-MCC2A BKR OFF ON 3 2C 3 3 Standby Liquid Control Pump A

141 AB West Danger C41-VF003A CLOSED LOCKED OPEN 4 SLC Pump A 4 2 Manual Discharge Vlv 141 RB Az 80 Danger C41-VF002A CLOSED LOCKED OPEN 5 SLC Pump A 5 1 Suction Valve 141 RB Az 80 RJPM-OPS-ADM-R03 Page 9 of 12

RJPM-OPS-ADM-R03 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is operating in Mode 1.

Maintenance has requested a tagout to replace the Pump Relief Valve C41-RVF029A Standby Liquid Control Pump 1A Header Press Relief Valve per WO579067, which is expected to take 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to complete.

The eSOMs Tagging Computer is down so the tagout is to be manual, and the tags will be entered into the system after it is back in service.

Initiating Cues: The CRS has directed you to assist in preparing the tagout to remove and replace the relief valve.

Because of the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> LCO for both SLC Pumps out of service, it has been determined that the clearance must not INOP the B SLC pump.

A tagging Official will complete the remaining parts of the Tagout Cover Sheet you have been given by the CRS.

RJPM-OPS-ADM-R03 Page 10 of 12

RJPM-OPS-ADM-R03 Clearance No. (U-YY-MAN-##) 1-04-MAN-01 Tagout: (SSS-FFFFFFFFFFFFFF-QQQ) 201-C41-RVF029A-001 Date: 9/20/04 Component To Be Worked: C41-RVF029A, Standby Liq Cntrl Pmp 1A Header Press Relief Vlv

==

Description:==

Clearance for the purpose of replacing the relief valve Placement Inst.

Hazards: Double valve isolation is NOT required and a vent and drain path are NOT required Restoration Inst. None for this JPM Tagout Attributes:

Attribute description Attribute value Tech Spec Impact? Yes\No (circle one)

Compensatory Actions Required? Yes\No (circle one)

Locked Components? Yes\No (circle one)

Fire Protection Impairment? Yes\No (circle one)

Equip Drain/Vent Required? Yes\No (circle one)

Work Order Task List Work Order Description Task #

WO579067 Replace C41-RVF029A, Standby Liq Cntrl Pmp 1A Header Press Relief Vlv Tagout Verification:

Status Description User Verification Date Prepared Ops Prepared By Reviewed Ops reviewed By Approved Approved By Verified Tags Verified By Hung Removal Removal Approved Approved Verified Tags Verified Removed Removed By RJPM-OPS-ADM-R03 Page 11 of 12

RJPM-OPS-ADM-R03 Clearance # (U-YY-Man-##) 1-04-MAN-01 Tagout: 201-C41-RVF029A -001 Date 9/20/04 Tag Tag Equipment Seq Placement Configuration Placement 1st Placement 2nd Seq Restoration Configuration As left Rest Rest No. Type Equipment Desc Verif Verif Config 1st 2nd Equip Location Verif Verif Notes Notes RJPM-OPS-ADM-R03 Page 12 of 12

Number: *RJPM-OPS-ADM-RS04 RIVER Revision: 1 BEND STATION Page 1 of 8 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

NRC Exam JPM RO/SRO ADMIN - 4 PREPARE / REVIEW:

Roger Persons 0862 7/19/2004 Preparer KCN Date Erich Weinfurter 1497 7/19/2004 Technical Review (SME) KCN Date Tim Manry 0757 7/21/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-ADM-RS04 TASK DESCRIPTION: Perform task requiring entry into a High Radiation Area TASK

REFERENCE:

301001005003 301011005003 K/A REFERENCE & RATING: 2.3.10, 2.9/3.3 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Mockup X COMPLETION TIME: 14 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH Yes (FAULTED):

RJPM-OPS- ADM-RS04 Page 2 of 8

RJPM-OPS-ADM-RS04 SIMULATOR SETUP SHEET Task

Description:

Enter and exit a High Radiation Area for a valve lineup Required Power: N/A IC No.: N/A Notes: This will be performed using the Mockup area for Radiation Worker Training in the Main Admin 3 Building.

RJPM-OPS- ADM-RS04 Page 3 of 8

RJPM-OPS-ADM-RS04 DATA SHEET References for Development: EOI Rad Worker Training Required Materials: Mockup area for Radiation Worker Training in the Main Admin 3 Building Required Plant Condition: N/A Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS- ADM-RS04 Page 4 of 8

RJPM-OPS-ADM-RS04 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is operating at 100% power when it becomes necessary to close manually operated Reactor Water Cleanup Drain Valve, G33-V4.

Initiating Cue:

The CRS has directed you to enter the High Radiation in Mockup Area South and close RWCU Drain Valve, G33-V4.

RJPM-OPS-ADM-RS04

  • Denotes Critical Step Page 5 of 8

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-RS04 PERFORMANCE STEP STANDARD S/U COMMENTS Reviews appropriate RWP and Task Selects RWP 2004-2097, Task 1 as the correct Provide the three different RWPs Description for entry requirements. RWP for the task assigned and reviews entry for the area.

  • 1.

requirements and survey map.

Obtains Electronic Alarming Dosimeter Insert EAD into the activation slot SCAN the bar CUE: Inform the candidate that (EAD) from rack and activates at the code on his TLD and follow instructions on the you will play the role of the terminal using appropriate Radiation screen. Entering 2004-2097, Task 1 and answers independent verifier.

  • 2.

Work Permit (RWP) number, and the questions on the computer fields of the access enters CAA entrance through the terminal outside the mockup.

turnstile.

Enters mockup High Radiation area. Before entering mockup High Radiation area and CUE: RP will send a tech out to identifies the RP sign is facing the wrong the area to correct posting as 3.

direction and informs RP of the improper posting required and write a CR.

condition.

Close RWCU Drain Valve, G33-V4. Attempts to close RWCU Drain Valve, G33-V4 CUE: Examiner initiates EAD in mockup High Radiation area. alarm as candidate begins to

  • 4.

approach valve and informs candidate his EAD is alarming.

Exits High Radiation area. Immediately exits area with Independent Verifier CUE: JPM is terminated.

  • 5.

and reports to RP.

Terminating Cue: Entry and exit of the High Radiation area completed.

RJPM-OPS-ADM-RS04

  • Denotes Critical Step Page 6 of 8

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-RS04 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-ADM-RS04 Page 7 of 8

RJPM-OPS-ADM-RS04 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is operating at 100% power when it becomes necessary to close manually operated Reactor Water Cleanup Drain Valve, G33-V4.

Initiating Cues: The CRS has directed you to enter the High Radiation in Mockup Area South and close RWCU Drain Valve, G33-V4.

RJPM-OPS-ADM-RS04 Page 8 of 8

Number: *RJPM-OPS-ADM-S01 RIVER Revision: 0 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

NRC Exam JPM SRO ADMIN - 1 PREPARE / REVIEW:

Roger Persons 0862 7/17/2004 Preparer KCN Date Erich Weinfurter 1497 7/18/2004 Technical Review (SME) KCN Date Tiffany Aley 1338 7/20/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-ADM-S01 TASK DESCRIPTION: Determine Alternate Decay Heat Removal Method per OSP-0041 TASK

REFERENCE:

301001005003 301011005003 K/A REFERENCE & RATING: 2.1.25, 3.1 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 25 min.

MAX TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-OPS-ADM-S01 Page 2 of 9

RJPM-OPS-ADM-S01 SIMULATOR SETUP SHEET Task

Description:

Determine Alternate Decay Heat Removal Method per OSP-0041 Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-OPS-ADM-S01 Page 3 of 9

RJPM-OPS-ADM-S01 DATA SHEET References for Development: OSP-0041, Alternate Decay Heat Removal Required Materials: OSP-0041, Alternate Decay Heat Removal Required Plant Condition: N/A Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-ADM-S01 Page 4 of 9

RJPM-OPS-ADM-S01 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

After operating 200 days at 100% power, the plant was shut down for a refueling outage. The reactor was scrammed to complete the shutdown at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on September 19, 2004. It is now 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on September 20, 2004. RHR A is operating in SDC and the following conditions exist:

  • RPCCW Temperature is 91ºF RHR Loop B has just been declared inoperable for Shutdown Cooling Mode because SWP-MOVF068B, RHR HX B SVCE WTR RTN valve is closed and cannot be opened with its actuator or locally.

Initiating Cue:

The OSM has directed you to determine an Alternate Decay Heat Removal Method for RHR Loop B by completing OSP-0041, Alternate Decay Heat Removal through Step 6.2.4.

RJPM-OPS-ADM-S01

  • Denotes Critical Step Page 5 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-S01 PERFORMANCE STEP STANDARD S/U COMMENTS Determine time since reactor Using information provided, determines time

  • 1. shutdown and record on Attachment 1, after shutdown to be 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and records on Mode Selection. Attachment 1.

Determine core decay heat after Using time after shutdown at 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> determines CUE: Decay Heat information shutdown, per Attachment 6, Decay Decay Heat to be 63 MBtu/hr (+/-2 MBtu/hr) and from Incore Fuels Group is NOT Heat After Shutdown From Full records on Attachment 1. available at this time.

Power or from the Incore Fuels Group

  • 2. if extremely accurate Decay Heat Data is needed. Record Value on Attachment 1.

Determine method of Alternate Decay Records 1 as number of RHR-SDC Loops Heat Removal desired based on the INOP.

capacity of the systems available. IF RHR-SDC is not being used as an Using 63 MBtu/hr (+/-2 MBtu/hr) as a value for alternate for itself, THEN select an Decay Heat, and referring to Step 3 of alternate method from Attachment 1, Attachment 1, determines and records in Substep

  • 3. Mode Selection. 2 of 6.2.3
1. Record number of inoperable SPC/ADHR as Alternate Method RHR-SDC Loops.
2. List alternate method for each inoperable RHR-SDC Loops.

RJPM-OPS-ADM-S01

  • Denotes Critical Step Page 6 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-S01 PERFORMANCE STEP STANDARD S/U COMMENTS Use the appropriate sections of this Reviews procedure Section 6.4 and verifies CUE: If candidate requests procedure, listed below, to verify SPC/ADHR availability. information on availability of availability and/or operate the system various plant components tell 4.

indicated in Step 6.2.3.2. All other him/her that, except for RHR Loop sections of the procedure may be B, all other plant equipment is omitted. operable.

Terminating Cue: OSP-0041, Alternate Decay Heat Removal, Determination of Alternate Decay Heat Removal Method completed.

RJPM-OPS-ADM-S01

  • Denotes Critical Step Page 7 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-S01 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-ADM-S01 Page 8 of 9

RJPM-OPS-ADM-S01 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: After operating 200 days at 100% power, the plant was shut down for a refueling outage.

The reactor was scrammed to complete the shutdown at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on September 19, 2004.

It is now 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on September 20, 2004. RHR A is operating in SDC and the following conditions exist:

  • RPCCW Temperature is 91ºF RHR Loop B has just been declared inoperable for Shutdown Cooling Mode because SWP-MOVF068B, RHR HX B SVCE WTR RTN valve is closed and cannot be opened with its actuator or locally.

Initiating Cues: The OSM has directed you to determine an Alternate Decay Heat Removal Method for RHR Loop B by completing OSP-0041, Alternate Decay Heat Removal through Step 6.2.4.

RJPM-OPS-ADM-S01 Page 9 of 9

CONTINUOUS USE

  • G12.1.28 RIVER BEND STATION STATION OPERATING MANUAL
  • OPERATION SECTION PROCEDURE
  • ALTERNATE DECAY HEAT REMOVAL PROCEDURE NUMBER: *OSP-0041 REVISION NUMBER: *8 Effective Date:
  • NOTE : SIGNATURES ARE ON FILE.

TemRev 2 AddCounter 87 Att Enc DS MSet REGULAR KWN OFF

  • INDEXING INFORMATION

CONTINUOUS USE TABLE OF CHANGES LETTER DESIGNATION DETAILED DESCRIPTION OF CHANGES TRACKING NUMBER OSP-0041 REV - 8 PAGE 1 OF 72

CONTINUOUS USE TABLE OF CONTENTS SECTION PAGE NO.

1 PURPOSE.................................................................................................................................4 2 REFERENCES .........................................................................................................................4 3 DEFINITIONS .........................................................................................................................5 4 ORGANIZATION AND RESPONSIBILITIES ......................................................................5 5 GENERAL REQUIREMENTS................................................................................................6 6 INSTRUCTIONS ...................................................................................................................12 6.1 Prerequisites ..................................................................................................................12 6.2 Determination of Alternate Decay Heat Removal Method...........................................13 6.3 RHR - SDC ...................................................................................................................15 6.4 SPC/ADHR ...................................................................................................................18 6.5 FPC - Assist ..................................................................................................................22 6.6 RHR - LPCI...................................................................................................................24 6.7 CRD...............................................................................................................................30 6.8 RWCU, RWCU/SFC.....................................................................................................32 6.9 Condensate System .......................................................................................................35 6.10 MSL Flooding ...............................................................................................................39 ATTACHMENT 1 - MODE SELECTION ...................................................................................55 ATTACHMENT 2 - FPC ASSIST TEMPERATURE DEPENDENT HEAT REMOVAL CAPACITY TABLE.....................................................................................................57 ATTACHMENT 3 - RWCU TEMPERATURE DEPENDENT HEAT REMOVAL CAPACITY TABLES...................................................................................................58 ATTACHMENT 4 - SFC TEMPERATURE DEPENDENT HEAT REMOVAL CAPACITY TABLES...................................................................................................59 ATTACHMENT 5 - COMBINED RWCU AND SFC TEMPERATURE DEPENDENT HEAT REMOVAL CAPACITY TABLES ..................................................................60 ATTACHMENT 6 - DECAY HEAT AFTER SHUTDOWN FROM FULL POWER.................61 ATTACHMENT 7 - LPCI MODE DATA SHEET.......................................................................62 ATTACHMENT 8 - MSL ALTERNATE DECAY HEAT REMOVAL BOUNDARY CLEARANCE...............................................................................................................64 ATTACHMENT 9 - MSL ALTERNATE DECAY HEAT REMOVAL VALVE LINEUP ........66 OSP-0041 REV - 8 PAGE 2 OF 72

CONTINUOUS USE ATTACHMENT 10 - MSL ALTERNATE DECAY HEAT REMOVAL CONTROL BOARD LINEUP..........................................................................................................68 ATTACHMENT 11 - MSL ALTERNATE DECAY HEAT REMOVAL EQUIPMENT FAILURES....................................................................................................................70 OSP-0041 REV - 8 PAGE 3 OF 72

CONTINUOUS USE 1 PURPOSE 1.1 To demonstrate the operability of at least one alternate method of decay heat removal for each inoperable required RHR Shutdown Cooling Mode Loop within one hour of inoperability, and to establish alternate cooling, if necessary.

2 REFERENCES 2.1 G13.18.14.0*194-1 Rated Power vs Time Curve 2.2 G13.18.14.0*162-1, RWCU and SFC Heat Removal Capability 2.3 G13.18.2.6*176-0, RHR Hx Performance for FPC Assist Mode 2.4 Memorandum, NUPE-86-1180 Alternate Method of Decay Heat Removal 2.5 Memorandum, GE-CEM-8615, Alternate Shutdown Cooling Configuration 2.6 ER 98-0310, Verification of the Decay Heat Removal Capabilities of the Systems in OSP-0041 2.7 EEAR-89-E0218, Condensate/Main Steam Evaluation 2.8 Memorandum, GES-13,127/86, Alternate Shutdown Cooling Configuration 2.9 SER 7-87 2.10 S-CRB-18831 OSP-0041 REV - 8 PAGE 4 OF 72

CONTINUOUS USE 3 DEFINITIONS 3.1 Cycle - the initiation and actual use of RHR-LPCI mode as an Alternate Shutdown Cooling method.

3.2 Demonstrate - to verify at least once through test and/or operations data the capability of the required components to remove the necessary decay heat loads. This one time initial verification may have occurred at any time prior to placing the Alternate Method of Decay Heat Removal in service including, but not limited to, during previous outages or during pre-operational testing. Subsequent demonstrations would then consist of verifying the documentation of the one time actual heat removal capability and then also verifying the system configuration/line-up.

4 ORGANIZATION AND RESPONSIBILITIES 4.1 The Operations Shift Superintendent (OSS) is responsible for the administration of this procedure.

4.2 The Operations Shift Superintendent/Control Room Supervisor (OSS/CRS) shall be responsible for the following:

4.2.1. Identifying the need for Alternate Decay Heat Removal capability, verifying availability, and implementation of this method, if required.

4.2.2. Determining the applicability of alternate decay heat removal:

1. Mode 3 when RPV pressure is below the RHR cut-in permissive of 135 psig, and one or both Shutdown Cooling Loops are inoperable. (LCO 3.4.9)
2. Mode 4 when one or both Shutdown Cooling Loops are inoperable (LCO 3.4.10).
3. Mode 5 when any Shutdown Cooling Loops are inoperable (LCO 3.9.8, LCO 3.9.9).

OSP-0041 REV - 8 PAGE 5 OF 72

CONTINUOUS USE 5 GENERAL REQUIREMENTS 5.1 The OSS/CRS should be immediately informed if any acceptance criteria cannot be met.

5.2 Use of LPCI Mode for Alternate Shutdown Cooling is not a desirable mode due to the thermal stresses on the LPCI Nozzles, LPCI Coupling, and Reactor Shroud. Use of LPCI is limited to 3 cycles per nozzle.

5.3 When changing or establishing the various modes of Decay Heat Removal, changes should be made at a slow enough rate to avoid excessive thermal stresses on system components.

5.4 Pay close attention to RPV metal temperatures. Do not allow RPV metal temperatures to decrease below 70°F.

5.5 Operating Limits during use of RHR-LPCI as Alternate Decay Heat Removal Method:

5.5.1. Core circulation is established. Refer to Step 5.13.

5.5.2. Reactor coolant temperature must be less than or equal to 140°F.

5.5.3. Drywell temperature must be greater than or equal to 65°F prior to startup.

5.5.4. Maintain RHR Hx differential temperature at less than or equal to 40°F.

5.5.5. IF CRD system is operating, THEN maintain at maximum flow.

5.6 IF RHR-LPCI is used for Alternate Decay Heat Removal, THEN initiate a Condition Report and include the following for trending and analysis:

  • Drywell Temperature
  • RHR Hx Differential Temperature
  • Copy of Attachment 7, LPCI Mode Data Sheet used during operation OSP-0041 REV - 8 PAGE 6 OF 72

CONTINUOUS USE 5.7 IF both Feedwater Lines are to be taken out of service, THEN operate RWCU F/Ds at maximum flow for several hours after initiating the LPCI Mode, but before isolating the Feedwater Lines.

5.8 IF E12-F003A(B), RHR HX OUTLET VALVE(s) is closed, THEN use ERIS/Recorder E12-R601 points 5 or 6 for Reactor Coolant Temperature. Do not use the ERIS/Recorders RHR Inlet Temperature Indications.

C 5.9 IF the RPV Flange/Shell metal temperatures are used as an alternate method of determining Reactor Coolant Temperature, THEN a lag is introduced because of the slow transport time across the metal thickness.

To minimize the lag time, consider raising Reactor Water Level, if possible, to be within a close proximity of the thermocouples.

5.10 Reactor Water should be cooled to less than 120°F prior to removing the normal mode of Shutdown Cooling.

C 5.11 During shutdown operations with time to boil less than two hours on the decay heat curves in OSP-0037, SHUTDOWN OPERATIONS PROTECTION PLAN, or any updated curves if provided by Safety and Engineering Analysis, one or more of the following methods of core circulation is REQUIRED:

  • one operating reactor recirc pump,
  • the SPC system operating in the ADHR mode.

C 5.12 STP-050-0700, RCS PRESSURE/TEMPERATURE LIMITS VERIFICATION, is required to be performed when changing decay heat removal modes or systems, and when there is an inadvertent or intentional loss of decay heat removal.

5.13 It may be necessary to operate the Reactor Recirculation Pumps (RRPs) to reduce the effects of Reactor Coolant Temperature stratification (i.e.,

maximum RWCU bottom head drain flow and minimum CRD flow is ineffective). RRPs should be operated periodically, as opposed to continuously, if the pump seal cavities were completely vented following RPV depressurization below 300 psig, and seal purge flow has not been interrupted. (SIL 203)

OSP-0041 REV - 8 PAGE 7 OF 72

CONTINUOUS USE 5.14 IF RHR is inoperable under any of the following conditions, THEN it is considered Administratively Inoperable, and may be used as an Alternate Decay Heat Removal System:

5.14.1. Associated Diesel Generator inoperable.

5.14.2. Associated Standby Service Water inoperable, but cooling water is available.

5.14.3. Associated support systems inoperable (i.e., pump seal cooling, isolation instrumentation, MOV power, unit cooler).

5.14.4. Normal Shutdown Cooling flow paths as defined by SOP-0031, RESIDUAL HEAT REMOVAL.

5.15 Flooding of the Main Steam Lines for Alternate Shutdown Cooling should be minimized due to the increased radiation levels, possible airborne contamination, and reduced fatigue margin for the Steam Line Piping.

5.16 The following administrative requirements apply when using RWCU for Decay Heat Removal in Mode 5:

5.16.1. Maximum reactor coolant temperature should be limited to less than or equal to 125°F.

5.16.2. CCP inlet temperature should be less than or equal to 95°F.

5.16.3. RWCU flow should be greater than or equal to 275 gpm.

C 5.17 During cold shutdown conditions with the RPV head in place, the following conditions will be met to minimize temperature stratification which may cause coolant temperatures to exceed 212°F and inadvertent RPV pressurization.

5.17.1. At least one shutdown cooling loop should be in operation.

5.17.2. RPV water level shall be maintained greater than 75 inches using shutdown level instrumentation when Reactor Recirculation Pumps are secured. This level is the minimum natural circulation level.

5.17.3. In the event forced circulation is unavailable (Reactor Recirculation Pump off) and Reactor Water Level at or below the minimum natural circulation level for any reason, then periodic monitoring of vessel metal temperatures above and below the intended water level should be initiated.

OSP-0041 REV - 8 PAGE 8 OF 72

CONTINUOUS USE 5.18 Precautions Particular to MSL Flooding 5.18.1. To preclude brittle fracture concerns, maintain reactor temperature greater than 120°F and reactor pressure less than 700 psig. Temperature can be monitored at the following locations:

1. Bottom head drain when RWCU is in service
2. RHR Pump discharges when RHR A(B) is in service
3. Reactor Recirc Loops when Recirc Pumps are operating 5.18.2. During MSL flooding operations, the reactor shall remain depressurized. Refer to Attachment 11, MSL Alternate Decay Heat Removal Equipment Failures for guidance on RPV pressure increases.

5.18.3. Radiation levels in the Turbine Building increase during the implementation of this procedure. Appropriate precautions and posting of areas should be performed.

5.18.4. The elevation of the Main Steam Lines is approximately 105".

IF RPV level is allowed to decrease below this level, THEN RPV Cooling via this method is lost.

OSP-0041 REV - 8 PAGE 9 OF 72

CONTINUOUS USE 5.18.5. The Condenser Hotwell is kept at an elevated level. The following cautions apply:

1. Tube immersion has a major influence on Decay Heat Removal. Maintain Hotwell Level less than or equal to 83' (Vacuum Pump Suction Line) and above the bottom of the tube bundle, 73'6".
2. IF the dose rates are high, THEN a tygon tube and a level transmitter is connected to the Hotwell for level indication. It should be monitored frequently when changing level or during activities with a potential for affecting Hotwell Level.
3. The Condensate System should remain on short or long cycle operation through the Demins to prevent water stagnation in the Hotwell.
4. Leakage detection is via Turbine Building Sump Level Alarms and periodic monitoring of Radwaste Influent Flow by the Aux Control Room.
5. WHEN the Hotwell Level is above the bottom of the Tube Bundle, 73'6", THEN the Circulating Water System must be in operation with pressure maintained in all four waterboxes. This prevents any leakage from the Hotwell to the Circulating Water System.
6. Opening of SRVs (i.e., ADS initiation, etc.) causes the Condenser Hotwell Level to decrease. Uncovering Condenser Tubes has a major influence on decay heat removal.
7. The SJAE and Mechanical Vacuum Pump Suction Lines must be isolated prior to increasing Hotwell Level to greater than 83.

5.18.6. Loss of the operating Condensate Pump with FWS-FV104, START UP RECIRC FCV open can result in a RPV Level decrease of approximately 1 inch/min if the RWCU System is in service.

5.18.7. The Turbine Bypass Valves are not to be used for decay heat removal while in MSL Flooding.

OSP-0041 REV - 8 PAGE 10 OF 72

CONTINUOUS USE 5.18.8. RPV Level should be maintained at 108" to 196"

1. The 108" limit is to indicate loss of feed to the Vessel.
2. The 196" limit provides adequate head for drain line flow and allow time for operator response on a MSIV closure.

This level corresponds to approximately 6.5" below the RPV Flange.

5.18.9. IF work is being performed on the Main Turbine, THEN new or ultrasonically clean Condensate Demin Beds should be used when in long cycle cleanup to prevent airborne contamination.

5.18.10. As a result of engineering review of pipe stress calculations, use of the Main Steam Piping for Alternate Shutdown Cooling is acceptable without pinning the spring hangers.

5.18.11. Maintain Condensate Water Temperature greater than 70°F, due to RPV Temperature concerns, and less than 140°F due to Condensate Demin concerns. Temperature can be monitored on CNM-TI-107, OFF GAS COND INLET TEMP at H13-P680 or by use of contact pyrometers on the Condensate Pump Discharge Piping.

OSP-0041 REV - 8 PAGE 11 OF 72

CONTINUOUS USE 6 INSTRUCTIONS 6.1 Prerequisites 6.1.1. Personnel performing this test procedure must be qualified per ADM-0007, SELECTION, TRAINING, QUALIFICATION AND EVALUATION OF PLANT STAFF PERSONNEL.

(Initials) 6.1.2. Personnel performing this test verify this procedure and any associated CN(s) are the most current.

(Initials) 6.1.3. Each performer indicates he has read and understands this procedure by completing the following:

(Signature) (Print Name) (Initials)

(Signature) (Print Name) (Initials)

(Signature) (Print Name) (Initials)

(Signature) (Print Name) (Initials) 6.1.4. Obtain OSM/CRS permission to begin this test.

(Initials) 6.1.5. Inform the NCO of the performance of this procedure.

(NCO)

OSP-0041 REV - 8 PAGE 12 OF 72

CONTINUOUS USE 6.2 Determination of Alternate Decay Heat Removal Method 6.2.1. Determine time since reactor shutdown and record on Attachment 1, Mode Selection.

(Initials)

NOTE The values of decay heat given in Attachment 6 are very conservative, especially if the reactor has not been operating continuously at high power for several weeks.

C 6.2.2. Determine core decay heat after shutdown, per Attachment 6, Decay Heat After Shutdown From Full Power or from the Incore Fuels Group if extremely accurate Decay Heat Data is needed. Record value on Attachment 1.

(Initials)

NOTE RHR SDC loops may be considered as alternates for themselves if Administratively Inoperable per Step 5.14.

6.2.3. Determine method of Alternate Decay Heat Removal desired based on the capacity of the systems available. IF RHR-SDC is not being used as an alternate for itself, THEN select an alternate method from Attachment 1, Mode Selection.

(Initials)

1. Record number of inoperable RHR-SDC Loops.

(Initials)

  1. of SDC Loops INOP
2. List alternate method used for each inoperable RHR-SDC Loops.

(Initials) 1st Alternate Method 2nd Alternate Method OSP-0041 REV - 8 PAGE 13 OF 72

CONTINUOUS USE 6.2.4. Use the appropriate sections of this procedure, listed below, to verify availability and/or operate the systems indicated in Step 6.2.3.2. All other sections of the procedure may be omitted.

(Initials)

Alternate Decay Heat Removal Procedure Mode RHR-SDC 6.3 SPC/ADHR 6.4 FPC Assist 6.5 RHR-LPCI 6.6 CRD 6.7 RWCU, RWCU/SFC 6.8 Condensate System 6.9 MSL Flooding 6.10 6.2.5. Notify Radiation Protection of Alternate Systems used, as local radiological conditions may change.

(Initials)

OSP-0041 REV - 8 PAGE 14 OF 72

CONTINUOUS USE 6.3 RHR - SDC NOTE IF both normal SDC modes are inoperable, THEN only the Alternate Method of Decay Heat Removal not in service need be demonstrated.

It is not required to actually place the RHR-SDC Alternate Decay Heat Removal Mode in operation if the following administrative conditions are met and the normal mode of shutdown cooling has previously demonstrated the ability to remove the Reactor Core Decay Heat.

Section 6.3.1 is used to verify availability of RHR-SDC when any of the following conditions prevent normal SDC operability.

  • Associated support systems inoperable such as pump seal cooling, isolation instrumentation, MOV power, unit cooler.

6.3.1. Administrative Conditions NOTE For the purpose of this section, "available" means the referenced items shall be ready for immediate use, and not impeded by system clearances or in progress maintenance activities.

1. E12-C002A(B), RHR A(B) Pump operable.

(Initials)

OSP-0041 REV - 8 PAGE 15 OF 72

CONTINUOUS USE

2. Operable suction flow path is available:

AND

NOTE E12-F037A(B), RHR A(B) TO UPPER POOL FPC ASSIST is only a valid discharge path when the Reactor Head is removed and Reactor Cavity is flooded.

3. Operable discharge flowpath is available:
  • E12-F053A(B), RHR A(B) SDC INJECTION VALVES (Initials)

OR

  • E12-F037A(B), RHR A(B) TO UPPER POOL FPC ASSIST (Initials)
4. RHR Heat Exchangers are operable with capability to establish flow through Heat Exchanger E12-F003A(B),

RHR A(B) HX OUTLET VLV(s) and E12-F047A(B),

HX INLET VLV(s).

(Initials)

5. RHR Heat Exchanger Cooling Valve E12-F068A(B),

RHR HX A(B) SVCE WTR RTN is operable, and cooling water is available.

(Initials)

OSP-0041 REV - 8 PAGE 16 OF 72

CONTINUOUS USE 6.3.2. Operation

1. Operate RHR in the Shutdown Cooling Mode in accordance with SOP-0031, RESIDUAL HEAT REMOVAL.

(Initials)

2. Use STP-050-0700, RCS PRESSURE/TEMPERATURE LIMITS VERIFICATION to obtain Reactor Coolant Temperatures per Step 5.12.

(Initials)

OSP-0041 REV - 8 PAGE 17 OF 72

CONTINUOUS USE 6.4 SPC/ADHR NOTE IF both normal SDC modes are inoperable, THEN only the alternate method of Decay Heat Removal not in service need be demonstrated.

It is not required to actually place SPC/ADHR in operation, If the following administrative conditions are met and the normal mode of Shutdown Cooling has previously demonstrated the ability to remove the Reactor Core Decay Heat.

6.4.1. Administrative Conditions NOTE For the purpose of this section, available means the referenced items shall be ready for immediate use and not impeded by system clearances or in-progress maintenance activities.

1. Reactor coolant temperature is less than 200°F.

(Initials)

2. SPC-P1A(B), SPC PUMP A(B) operable.

(Initials)

3. SPC-E1, SPC HEAT EXCHANGER, is operable.

(Initials)

4. SPC-AOV16, SPC HX SERVICE WATER OUTLET THROTTLE VALVE, is operable with cooling water available.

(Initials)

5. IF ADHR Configuration 1, SDC suction and LPCI C discharge, is the desired method of Alternate Decay Heat Removal, THEN the following conditions apply:
1. Operable suction flow path available:

OSP-0041 REV - 8 PAGE 18 OF 72

CONTINUOUS USE

  • RHS-AOV62, SPC SUCTION VALVE (Initials)
  • RHS-AOV63, SPC SUCTION VALVE (Initials)
2. Operable discharge flow path available:
  • SPC-AOV20, SPC FILTER-DEMIN SKID BYPASS VALVE (Initials)
  • RHS-AOV64, SPC DISCHARGE VALVE (Initials)
  • E12-F042C, RHR PUMP C LPCI INJECT ISOL VALVE (Initials)

NOTE ADHR Configuration 2 can only be used if the Reactor Head is removed and the Reactor Cavity is flooded.

6. IF ADHR Configuration 2, SDC suction and Upper Pool discharge, is the desired method of Alternate Decay Heat Removal, THEN the following conditions apply:
1. Operable suction flow path available:
  • RHS-AOV62, SPC SUCTION VALVE (Initials)

OSP-0041 REV - 8 PAGE 19 OF 72

CONTINUOUS USE

  • RHS-AOV63, SPC SUCTION VALVE (Initials)
2. Operable discharge flow path available:
  • SPC-AOV20, SPC FILTER-DEMIN SKID BYPASS VALVE (Initials)
  • SFC-MOV121, PRFCN RTN OUTBD ISOL (Initials)
  • SFC-MOV139, RETURN TO PRFCN CONTMT INBD ISOLATION (Initials)

NOTE ADHR Configuration 3 can only be used if the Reactor Head is removed and the Reactor Cavity is flooded.

7. IF ADHR Configuration 3, Upper Pool suction and LPCI C discharge, is the desired method of Alternate Decay Heat Removal, THEN the following conditions apply:
1. Operable suction flow path:
  • SFC-MOV121, PRFCN RTN OUTBD ISOL (Initials)
  • SFC-MOV139, RETURN TO PRFCN CONTMT INBD ISOLATION (Initials)
  • SPC-AOV14, SPC UPPER POOL SUCTION VALVE (Initials)
2. Operable discharge flow path:
  • SPC-AOV20, SPC FILTER-DEMIN SKID BYPASS VALVE (Initials)
  • RHS-AOV64, SPC DISCHARGE VALVE (Initials)

OSP-0041 REV - 8 PAGE 20 OF 72

CONTINUOUS USE

  • E12-F042C, RHR PUMP C LPCI INJECT ISOL VALVE (Initials) 6.4.2. Operation
1. Operate SPC/ADHR per SOP-0140, SUPRESSION POOL CLEANUP AND ALTERNATE DECAY HEAT REMOVAL.

(Initials)

2. Use STP-050-0700, RCS PRESSURE/TEMPERATURE LIMITS VERIFICATION to obtain Reactor Coolant Temperatures per Step 5.12.

(Initials)

OSP-0041 REV - 8 PAGE 21 OF 72

CONTINUOUS USE 6.5 FPC - Assist NOTES IF both normal SDC modes are inoperable, THEN only the alternate method of Decay Heat Removal not in service need be demonstrated.

It is not required to actually place the FPC-Assist Alternate Decay Heat Removal Mode in operation if the following administrative conditions are met and the normal mode of Shutdown Cooling has previously demonstrated the ability to remove the Reactor Core Decay Heat.

6.5.1. Administrative Conditions NOTE For the purpose of this section, "available" means the referenced items shall be ready for immediate use, and not impeded by system clearances or in progress maintenance activities.

1. The Reactor Head is removed with the Reactor Cavity

>23 above RPV flange and gate open.

(Initials)

2. E12-C002A(B), RHR A(B) Pump operable.

(Initials)

3. Operable suction flowpath is available.
  • SFC-V106, FUEL POOL COOLING TO RHR Manual Isolation (Initials)

AND

  • E12-F066A(B) RHR A(B), FUEL POOL COOLING SUCTION (Initials)

OSP-0041 REV - 8 PAGE 22 OF 72

CONTINUOUS USE

4. Operable discharge flowpath is available:
  • E12-F037A(B), RHR A(B) TO UPPER POOL FPC ASSIST (Initials)

AND

  • SFC-V107, RHR RETURN TO FUEL POOL COOLING Manual Isolation (Initials)
5. RHR Heat Exchangers are operable with capability to establish flow through Heat Exchanger E12-F003A(B),

RHR A(B) HX OUTLET VLV(s) and E12-F047A(B),

HX INLET VLV(s).

(Initials)

6. RHR Heat Exchanger Cooling Valve E12-F068A(B),

RHR HX A(B) SVCE WTR RTN is operable, with cooling water available.

(Initials) 6.5.2. Operation NOTES This Mode can only be used if the Reactor Head is removed and >23 above RPV flange and gate open.

Natural circulation must be established if a Reactor Recirculation Pump is not running. It is preferred to have a reactor recirculation pump running for temperature monitoring.

1. IF it is desired, THEN verify at least one Reactor Recirculation Pump operating per SOP-0003, REACTOR RECIRCULATION SYSTEM.

(Initials)

2. Use STP-050-0700, RCS PRESSURE/TEMPERATURE LIMITS VERIFICATION to obtain Reactor Coolant Temperatures per Step 5.12.

(Initials)

3. Operate the FPC-Assist Mode of RHR per SOP-0031, RESIDUAL HEAT REMOVAL.

(Initials)

OSP-0041 REV - 8 PAGE 23 OF 72

CONTINUOUS USE 6.6 RHR - LPCI CAUTION Use of LPCI mode for Alternate Shutdown Cooling is not a desirable mode due to the thermal stresses on the LPCI Nozzles, LPCI Coupling, and Reactor Shroud. Do not use LPCI if other adequate cooling means are available unless plant conditions require its use.

NOTES IF both normal SDC modes are inoperable, THEN only the alternate method of Decay Heat Removal not in service need be demonstrated.

It is not required to actually place the RHR-LPCI Alternate Decay Heat Removal Mode in operation if the following administrative conditions are met and the normal mode of Shutdown Cooling has previously demonstrated the ability to remove the Reactor Core Decay Heat.

Engineering tracks use of RHR-LPCI using EDP-MP-05, Fatigue Management.

6.6.1. Administrative Conditions NOTE For the purpose of this section, "available" means the referenced items shall be ready for immediate use, and not impeded by system clearances or in progress maintenance activities.

1. Reactor Coolant Temperature must be less than or equal to 140°F.

(Initials)

2. Drywell Temperature must be greater than or equal to 65°F.

(Initials)

3. E12-C002A(B), RHR A(B) Pump operable.

(Initials)

OSP-0041 REV - 8 PAGE 24 OF 72

CONTINUOUS USE

4. Operable suction flowpath is available.

AND

5. Operable discharge flowpath through E12-F042A(B),

RHR PUMP A(B) LPCI INJECT ISOL VALVE(S) is available (Initials)

6. RHR Heat Exchangers are operable with capability to establish flow through Heat Exchanger E12-F003A(B),

RHR A(B) HX OUTLET VLV(s) and E12-F047A(B),

RHR A(B) HX INLET VLV(s).

(Initials)

7. RHR Heat Exchanger Cooling Valve E12F068A(B), RHR HX A(B) SVCE WTR RTN is operable, and cooling water is available.

(Initials)

8. Core circulation in accordance with Step 5.13 is or may be readily established.

(Initials) 6.6.2. Operation

1. Check reactor coolant temperature is less than or equal to 140°F.

(Initials)

2. IF CRD is operating, THEN raise CRD cooling water flow to maximum.

(Initials)

3. Flush and preheat the selected RHR Loop for Alternate Shutdown Cooling Mode per SOP-0031, RESIDUAL HEAT REMOVAL.

(Initials)

OSP-0041 REV - 8 PAGE 25 OF 72

CONTINUOUS USE

4. Verify closed the following:
  • E12-F004A(B), RHR PUMP A(B) SUP PL SUCTION VALVE(S).

(Initials)

  • E12-F064A(B), RHR PUMP A(B) MIN FLOW TO SUP PL.

(Initials)

  • E12-F024A(B), RHR PUMP A(B) TEST RTN TO SUP PL (Initials)
  • E12-F037A(B), RHR A(B) TO UPPER POOL FPC ASSIST (Initials)
  • E12-F048A(B), RHR A(B) HX BYPASS VALVE(S).

(Initials)

5. On H13-P870, throttle open E12-F068A(B), HT EXCH A(B) SVCE WTR DISCH to obtain less than or equal to 5800 gpm as indicated at H13-P601, on E12-R602A(B),

RHR HX A(B) SERVICE WATER FLOW.

(Initials)

6. IF a Group 5 Containment Isolation Signal is present, THEN reset isolation by depressing the following:
  • B21H-S33, INBD ISOLATION SEAL IN RESET Pushbutton (Initials)

(Initials)

OSP-0041 REV - 8 PAGE 26 OF 72

CONTINUOUS USE CAUTION IF the Shutdown Cooling Isolation Valves are opened with portions of the RHR Piping empty, THEN a significant drop in Reactor Level can occur. Do not open Shutdown Cooling Isolation Valves unless the RHR piping is filled.

7. Verify the RHR Piping, including Suction Lines, is completely filled.

(Initials)

8. Verify open the following:
1. E12-F010, RHR SDC MAN ISOL VLV (Initials)
2. E12-F009, RHR SHUTDOWN COOLING INBD ISOL VALVE (Initials)

NOTE It may be necessary to place the RHR SHUTDOWN COOLING OUTBD ISOL VALVE ENABLE/DISABLE Switch to ENABLE on Div 1 RSS Panel C61-PNLP001 in order to operate E12-F008, RHR SHUTDOWN COOLING OUTBD ISOL VALVE from the Main Control Room.

3. E12-F008, RHR SHUTDOWN COOLING OUTBD ISOL VALVE (Initials)
4. E12-F006A(B), RHR PUMP A(B) SDC SUCTION VALVE (Initials)
5. E12-F047A(B), RHR A(B) HX INLET VALVE (Initials)
6. E12-F042A(B), RHR PUMP A(B) LPCI INJECT ISOL VALVE(S)

(Initials)

7. E12-F027A(B), RHR PUMP A(B) OUTBD ISOLATION VALVE(S)

(Initials)

OSP-0041 REV - 8 PAGE 27 OF 72

CONTINUOUS USE

9. Close E12-F003A(B), RHR A(B) HX OUTLET VALVES.

(Initials)

10. Record data on Attachment 7, LPCI Mode Data Sheet beginning 5 minutes prior to start of RHR Pump.

(Initials)

NOTE Initial flow to the Reactor Vessel from LPCI should bypass the RHR Heat Exchanger. The flow through the LPCI Lines should be raised quickly to minimize thermal stresses.

11. Verify Average Drywell Temperature is greater than or equal to 65°F prior to RHR Pump start.

(Initials)

CAUTION Failure to establish greater than 1100 gpm within 8 seconds of pump start causes E12-F064A(B), RHR PUMP A(B) MIN FLOW TO SUP PL to open, dumping Reactor Water to the Suppression Pool. Do not start pump unless minimum flow back to the vessel can be established.

12. Start RHR PUMP A(B) and immediately throttle open E12-F048A, RHR A HX BYPASS VALVE to obtain 2000-3000 gpm.

(Initials)

NOTE Attachment 7, LPCI Mode Data Sheet, data is to be recorded every minute for the first five minutes, and hourly thereafter.

13. Establish a stable flow of approximately 5000 gpm by throttling E12-F048A, RHR A HX BYPASS VALVE.

(Initials)

OSP-0041 REV - 8 PAGE 28 OF 72

CONTINUOUS USE

14. Monitor RHR Hx Differential Temperature on the RHR TEMPERATURES Recorder. Maintain Reactor Coolant Temperature drop less than or equal to 40°F T.

(Initials)

15. Establish a cooldown rate of less than 100°F/hr as follows:
1. Slowly jog open E12-F003A(B), RHR A(B) HX OUTLET VLV(S) and monitor the cooldown rate.

(Initials)

2. Throttle E12-F003A(B), RHR A(B) HX OUTLET VLV and E12-F048A(B), RHR A(B) HX BYPASS VALVE(S) to obtain the desired cooldown rate while maintaining a constant RHR loop flow.

(Initials)

16. Continue to record data on Attachment 7, LPCI Mode Data Sheet.

(Initials)

1. Maintain RHR Hx Differential Temperature at less than or equal to 40°F.

(Initials)

2. Maintain Rx Coolant Temperature less than or equal to 140°F.

(Initials)

17. Use STP-050-0700, RCS PRESSURE/TEMPERATURE LIMITS VERIFICATION to obtain Reactor Coolant Temperatures per Step 5.12.

(Initials)

18. Initiate a Condition Report per Step 5.6.

(Initials)

OSP-0041 REV - 8 PAGE 29 OF 72

CONTINUOUS USE 6.7 CRD NOTES IF both normal SDC modes are inoperable, THEN only the Alternate Method of Decay Heat Removal not in service need be demonstrated.

Verification of Alternate Decay Heat Removal by the CRD System may be performed by either the Previous Performance Method, Step 6.7.1, Calculation Method, Step 6.7.2, or Demonstration Method, Step 6.7.3.

6.7.1. Verify that the CRD System Alternate Decay Heat Removal capability has been demonstrated via a previous performance.

(Initials) 6.7.2. Verify that the CRD System Alternate Decay Heat Removal capability is satisfactory by obtaining Engineering Acceptance.

(Initials)

Engineering Calculation Reference Number 6.7.3. Verification by demonstration

1. Reduce Reactor Coolant Temperature to approximately 120°F with the in service Shutdown Cooling Loop or Alternate Method.

(Initials)

OSP-0041 REV - 8 PAGE 30 OF 72

CONTINUOUS USE

2. Verify one of the following:

(Initials)

OR NOTE Natural circulation must be established if a Reactor Recirculation Pump is not running. It is preferred to have a reactor recirculation pump running for temperature monitoring.

  • IF no forced circulation is in service, THEN establish Natural Core Circulation by increasing Reactor Water Level greater than 75 inches as indicated at H13-P601, on B21-R605, RX WTR LEVEL SHUTDOWN RANGE.

(Initials)

3. Operate the CRD system per SOP-0002, CONTROL ROD DRIVE HYDRAULICS to remove Reactor Decay Heat.

(Initials)

4. Remove all Decay Heat Removal Systems in service with exception of the Alternate Decay Heat Removal Method being demonstrated.

(Initials)

5. Use STP-050-0700, RCS PRESSURE/TEMPERATURE LIMITS VERIFICATION to obtain Reactor Coolant Temperatures for Alternate Decay Heat Removal Method verification per Step 5.12.

(Initials)

6. Restore the CRD System to previous configuration.

(Initials)

(IND VERIF)

OSP-0041 REV - 8 PAGE 31 OF 72

CONTINUOUS USE 6.7.4. Operation

1. Operate the CRD System per SOP-0002, CONTROL ROD DRIVE HYDRAULICS to remove Reactor Decay Heat.

(Initials)

2. Use STP-050-0700, RCS PRESSURE/TEMPERATURE LIMITS VERIFICATION to obtain Reactor Coolant Temperatures, per Step 5.12.

(Initials) 6.8 RWCU, RWCU/SFC NOTES IF both normal SDC modes are inoperable, THEN only the Alternate Method of Decay Heat Removal not in service need be demonstrated.

Verification of Alternate Decay Heat removal by the RWCU System may be performed by either the previous Performance Method, Step 6.8.1, Calculation Method, Step 6.8.2, or Demonstration Method, Step 6.8.3.

6.8.1. Verify that the RWCU System Alternate Decay Heat Removal capability has been demonstrated via a previous performance.

(Initials) 6.8.2. Verify that the RWCU System Alternate Decay Heat Removal capability is satisfactory by obtaining Engineering Acceptance.

(Initials)

Engineering Calculation Reference Number OSP-0041 REV - 8 PAGE 32 OF 72

CONTINUOUS USE 6.8.3. Verification by demonstration

1. Reduce reactor coolant temperature to approximately 120°F with the in-service Shutdown Cooling Loop or Alternate Method.

(Initials)

2. Verify one of the following:

(Initials)

OR NOTE Natural circulation must be established if a Reactor Recirculation Pump is not running. It is preferred to have a reactor recirculation pump running for temperature monitoring.

  • IF no forced circulation is in service, THEN establish Natural Core Circulation by increasing Reactor Water Level greater than 75 inches as indicated at H13-P601, on B21-R605, RX WTR LEVEL SHUTDOWN RANGE.

(Initials)

3. Operate the RWCU System per Step 6.8.4.1 to remove Reactor Decay Heat.

(Initials)

4. Remove all Decay Heat Removal Systems in service with exception of the Alternate Decay Heat Removal Method being demonstrated.

(Initials)

5. Use STP-050-0700, RCS PRESSURE/TEMPERATURE LIMITS VERIFICATION to obtain Reactor Coolant Temperatures for Alternate Decay Heat Removal Method verification.

(Initials)

OSP-0041 REV - 8 PAGE 33 OF 72

CONTINUOUS USE

6. Restore the RWCU System to previous configuration.

(Initials)

(IND VERIF)

7. Restore the SFC System to previous configuration.

(Initials)

(IND VERIF) 6.8.4. Operation

1. Operate the RWCU System per SOP-0090, REACTOR WATER CLEANUP SYSTEM.
1. IF in Mode 5, THEN additional administrative requirements for operation of RWCU are as follows:

(Initials)

  • CCP Inlet Temperature should be less than or equal to 95°F.

(Initials)

  • RWCU flow should be greater than 275 gpm.

(Initials)

2. IF possible, THEN bypass the Regenerative Heat Exchanger Return Flow to maximize heat transfer, as follows:

a Throttle open G33-F107 RWCU REGEN HX BYPASS (Initials) b Throttle closed G33-F042 RWCU REGEN HX OUTLET (Initials)

OSP-0041 REV - 8 PAGE 34 OF 72

CONTINUOUS USE NOTE Reactor Head must be removed and vessel flooded >23 above flange to use the SFC System for Alternate Decay Heat Removal.

3. IF the Main Condenser is available, THEN use maximum blowdown as necessary.

(Initials)

4. IF using SFC System in conjunction with the RWCU System, THEN operate SFC with suction on the Upper Pool per SOP-0091, FUEL POOL COOLING AND CLEANUP SYS.

(Initials)

2. Use STP-050-0700, RCS PRESSURE/TEMPERATURE LIMITS VERIFICATION to obtain Reactor Coolant Temperatures, per Step 5.12.

(Initials) 6.9 Condensate System NOTES IF both Normal SDC Modes are inoperable, THEN only the Alternate Method of Decay Heat Removal not in service need be demonstrated.

Verification of Alternate Decay Heat Removal by the Condensate System may be performed by either the Previous Performance Method, Step 6.9.1, Calculation Method, Step 6.9.2, or Demonstration Method, Step 6.9.3.

6.9.1. Verify that the Condensate System Alternate Decay Heat Removal capability has been demonstrated via a previous performance.

(Initials) 6.9.2. Verify that the Condensate System Alternate Decay Heat Removal capability is satisfactory by obtaining Engineering Acceptance.

(Initials)

Engineering Calculation Reference Number OSP-0041 REV - 8 PAGE 35 OF 72

CONTINUOUS USE 6.9.3. Verification by demonstration

1. Reduce Reactor Coolant Temperature to less than 120°F with the In Service Shutdown Cooling Loop or Alternate Method.

(Initials)

2. Verify one of the following:

(Initials)

OR NOTE Natural circulation must be established if a Reactor Recirculation Pump is not running. It is preferred to have a reactor recirculation pump running for temperature monitoring.

  • IF no forced circulation is in service, THEN establish Natural Core Circulation by increasing Reactor Water Level greater than 75 inches as indicated at H13-P601, on B21-R605, RX WTR LEVEL SHUTDOWN RANGE.

(Initials)

3. Operate the Condensate System per SOP-0007, CONDENSATE SYSTEM.

(Initials)

NOTE Either or both of the following flow paths may be utilized in conjunction with the Condensate System.

  • IF RWCU is available, THEN use maximum blowdown.

(Initials)

(Initials)

OSP-0041 REV - 8 PAGE 36 OF 72

CONTINUOUS USE

4. Remove all Decay Heat Removal Systems in service with exception of the Alternate Decay Heat Removal Methods being demonstrated.

(Initials)

5. Use STP-050-0700, RCS PRESSURE/TEMPERATURE LIMITS VERIFICATION to obtain Reactor Coolant Temperatures for Alternate Decay Heat Removal Method verification, per Step 5.12.

(Initials)

6. Restore the Condensate System to previous configuration.

(Initials)

(IND VERIF)

OSP-0041 REV - 8 PAGE 37 OF 72

CONTINUOUS USE 6.9.4. Operation

1. Operate the Condensate System per SOP-0007, CONDENSATE SYSTEM.

(Initials)

CAUTION IF the reactor head is installed and tensioned, THEN do not exceed 115 inches as indicated at H13-P601, on B21-R605, RX WTR LEVEL SHUTDOWN RANGE.

Pay close attention to RPV metal temperatures and maintain Tech Spec minimum temperature.

NOTE Either or both of the following flow paths may be utilized in conjunction with the Condensate System.

  • IF RWCU is available, THEN use maximum blowdown.

(Initials)

(Initials)

2. Use STP-050-0700, RCS PRESSURE/TEMPERATURE LIMITS VERIFICATION to obtain Reactor Coolant Temperatures, per Step 5.12.

(Initials)

OSP-0041 REV - 8 PAGE 38 OF 72

CONTINUOUS USE 6.10 MSL Flooding 6.10.1. Verification of Availability NOTE For the purpose of this section, "available" means the referenced items shall be ready for immediate use, and not impeded by system clearances or in progress maintenance activities.

1. A physical demonstration of Main Steam Line Flooding's ability to adequately remove decay heat has been previously performed. Reference last performance package dated 3-26-90 per GSU file #04302.

(Initials)

2. The Circulating Water System is available with three Circulating Water Pumps, four Cooling Towers, and four Waterboxes.

(Initials)

3. One Condensate Pump is operating on Long Cycle Cleanup through the Demineralizers per SOP-0007, CONDENSATE SYSTEM.

(Initials)

4. Attachment 8, MSL Alternate Decay Heat Removal Boundary Clearance is complete.

(Initials)

Clearance Number

5. Establish Hotwell Level at approximately 74'6",

approximately one foot above the bottom of the Tube Bundles.

(Initials)

6. WHEN hotwell level is established, THEN isolate makeup and reject using administrative controls to preclude inadvertent changes.

(Initials)

7. Verify reactor coolant temperature is greater than or equal to 120°F and less than or equal to 170°F.

(Initials)

OSP-0041 REV - 8 PAGE 39 OF 72

CONTINUOUS USE

8. Verify MSIV Isolation Logic is reset.

(Initials)

NOTE Only one (1) MSL is required for this method of Decay Heat Removal. Other MSL MSIVs may be closed.

1. Identify the MSL available.

MSL _______

(Initials)

2. H13-P622 (for selected MSIVs and drains).
  • Drain Valve Isolation Status Lights are on.

(Initials)

  • MSIV Pilot Solenoid Status Lights are on.

(Initials)

  • MSIV Pilot Solenoid Amps indicate positive amps.

(Initials)

3. H13-P623 (for selected MSIVs and drains)
  • Drain Valve Isolation Status Lights are on.

(Initials)

  • MSIV Pilot Solenoid Status Lights are on.

(Initials)

  • MSIV Pilot Solenoid Amps indicate positive amps.

(Initials)

OSP-0041 REV - 8 PAGE 40 OF 72

CONTINUOUS USE

9. Verify the available Main Steam Line in Step 6.10.1.8.1 is aligned per the following:
1. MSL A

(Initials)

(Initials)

  • B21-MOVF098A, MSL A SHUTOFF VLV open.

(Initials)

  • B21-MOVF067A, MSL A DRAIN VALVE open.

(Initials)

2. MSL B

(Initials)

(Initials)

  • B21-MOVF098B, MSL B SHUTOFF VLV open.

(Initials)

  • B21-MOVF067B, MSL B DRAIN VALVE open.

(Initials)

3. MSL C

(Initials)

(Initials)

  • B21-MOVF098C, MSL C SHUTOFF VLV open.

(Initials)

  • B21-MOVF067C, MSL C DRAIN VALVE open.

(Initials)

OSP-0041 REV - 8 PAGE 41 OF 72

CONTINUOUS USE

4. MSL D

(Initials)

(Initials)

  • B21-MOVF098D, MSL D SHUTOFF VLV open.

(Initials)

  • B21-MOVF067D, MSL D DRAIN VALVE open.

(Initials)

10. Verify all of the following drain paths to the Main Condenser available:
1. INBD MSIV DRAINS
  • B21-F085, MSL WARMUP HDR SHUTOFF VLV (Initials)
  • B21-F021, MSL WARMUP HDR COND DR BYPASS (Initials)
  • B21-F033, MSL WARMUP HDR COND DRAIN (Initials)

(Initials)

(Initials)

OSP-0041 REV - 8 PAGE 42 OF 72

CONTINUOUS USE

2. OUTBD MSIV DRAIN
  • B21-F086, MSL DRAIN HDR SHUTOFF VALVE (Initials)
  • B21-F068, MSL DRAIN HDR COND DRAIN BYPASS (Initials)
  • B21-F069, MSL DRAIN HDR COND DRAIN (Initials)

(Initials)

3. Main Steam Equalizing Header Drains
  • DTM-AOV12A, MSL EQUALIZING HDR DRAIN BYPASS (Initials)
  • DTM-AOV12B, MSL EQUALIZING HDR DRAIN BYPASS (Initials)

(Initials)

(Initials)

OSP-0041 REV - 8 PAGE 43 OF 72

CONTINUOUS USE

4. Turbine Bypass Line Drains
  • DTM-AOV5A, BYP VLV BEFORE SEAT DRAIN (Initials)
  • DTM-AOV5B, BYP VLV BEFORE SEAT DRAIN (Initials)
  • DTM-V27, B/P STM CHEST DR LINE ISOL (TB 95')

(Initials)

5. MSR #1 Drains
  • DTM-MOV51A, MSL TO MSR1 COND DR (Initials)

(Initials)

  • DTM-V172, MN STM SUPPLY TO MSR1 DRN LINE ISOL (TB 95')

(Initials)

6. MSR #2 Drains
  • DTM-MOV51B, MSL TO MSR2 COND DR (Initials)
  • DTM-V174, MN STM SUPPLY TO MSR2 DR LINE ISOL (TB 95)

(Initials)

11. Verify all 16 SRVs are installed and closed.

(Initials)

12. Verify the Main Turbine is tripped.

(Initials)

OSP-0041 REV - 8 PAGE 44 OF 72

CONTINUOUS USE

13. Verify one of the following injection flow paths is available:
1. A FW Injection Line
  • B21-MOVF065A, A FW INBD ISOL (Initials)
  • FWS-MOV7A, A FW OUTBD ISOL (Initials)
  • B21-AOVF032A, A FW TESTABLE CHECK (Initials)
  • B21-VF011A, A FW HDR INBD MANUAL ISOL (Initials)
2. B FW Injection Line
  • B21-MOVF065B, B FW INBD ISOL (Initials)
  • FWS-MOV7B, B FW OUTBD ISOL (Initials)
  • B21-AOVF032B, B FW TESTABLE CHECK (Initials)
  • B21-VF011B, B FW HDR INBD MANUAL ISOL (Initials) 6.10.2. Operation
1. Complete Attachment 9, MSL Alternate Decay Heat Removal Valve Lineup.

(Initials)

2. Complete Attachment 10, MSL Alternate Decay Heat Removal Control Board Lineup.

(Initials)

3. Verify a Mechanical Vacuum Pump is operating with CNM-AOVVB, CNDS VAC BRKR open.

(Initials)

OSP-0041 REV - 8 PAGE 45 OF 72

CONTINUOUS USE

4. Begin using STP-050-0700, RCS PRESSURE/TEMPERATURE LIMITS VERIFICATION to obtain Reactor Coolant Temperatures.

(Initials)

5. Install a tygon tube or appropriate level transmitter at the Condenser Hotwell for level indication.

(Initials)

6. Verify the Shutdown Range Level Alarm on panel H13-P601 is enabled and the alarms set to the following:

High Alarm: 196" Low Alarm: 180" (Initials)

7. Verify the Reactor Vessel is depressurized.

(Initials)

8. Verify the Turbine Building Ventilation System is in operation per SOP-0064, TURBINE BUILDING HVAC SYSTEM.

(Initials)

9. Notify Radiation Protection to take necessary precautions for increased radiation levels due to implementation of this procedure.

(Initials)

10. Notify Chemistry this procedure is being implemented and periodic sampling, as determined by Chemistry Supervision, of Circulating Water and Service Water for isotopic analysis is required.

(Initials)

11. Prior to injecting Condensate Water into the Reactor Vessel, verify water quality requirements of TRM TR 3.4.13 are met.

(Initials)

OSP-0041 REV - 8 PAGE 46 OF 72

CONTINUOUS USE NOTE Circulating Water configuration may be changed per SOP-0006, CIRCULATING WATER, COOLING TOWER, AND VACUUM PRIMING to establish the initial cooldown rate.

Circulating Water pressure should be kept on any out of Service Waterboxes to prevent Hotwell to Circulating Water leakage.

12. Ensure Attachment 11, MSL Alternate Decay Heat Removal Equipment Failures has been reviewed by the Operations Shift.

(Initials)

13. Closely monitor the following parameters while establishing and maintaining Decay Heat Removal:

(Initials)

1. Condensate Temperature greater than 70°F and less than 140°F.

(Initials)

2. Reactor Coolant Temperatures (Initials)

NOTE A decrease in RPV temperature is to be expected when raising water level to fill the Main Steam Lines.

14. Using the Condensate and Feedwater system with the Startup Level Control Valve in manual per SOP-0009, REACTOR FEEDWATER SYSTEM, raise RPV level to greater than 110" but less than 180" as indicated at H13-P601, on B21-R605, RX WTR LEVEL SHUTDOWN RANGE.

(Initials)

OSP-0041 REV - 8 PAGE 47 OF 72

CONTINUOUS USE

15. IF desired, THEN bypass Feedwater Heaters to minimize areas affected by flow of Reactor Coolant Water as follows:
1. Open CNM-MOV136, LP HTRS BYP (Initials)
2. Close CNM-MOV33A, LP HTR STG A INL (Initials)
3. Close CNM-MOV33B, LP HTR STG B INL (Initials)
4. Close CNM-MOV32A, LP HTR STG A OUTL (Initials)
5. Close CNM-MOV32B, LP HTR STG B OUTL (Initials)
16. Maintain Hotwell Level at approximately 74'6" using the Condensate Transfer System.

(Initials)

17. Commence monitoring Hotwell Level at least once per shift and record in the Control Room Log.

(Initials)

18. WHEN flow through the Main Steam Lines has been initiated at greater than 105", THEN initiate a Condition Report for Engineering Analysis to include the following information:

(Initials)

  • DW Average Air Temperature

CONTINUOUS USE CAUTION Flooding and damage to the SJAE and Mechanical Vacuum Pump if hotwell level is increased above 83'. Do not exceed 83 hotwell level without first isolating the SJAE and Mechanical Vacuum Pump Suction Lines.

19. Adjust RPV level and Condenser Hotwell level or Circulating Water Temperature to obtain the desired cooldown rate.

(Initials)

20. Decrease the cooling of the operating SDC Loop as necessary to control RPV temperature.

(Initials)

NOTE Closing of the RPV head vents provides a cushion to lessen any water hammer effects should the MSIVs close and the RPV start to pressurize.

The Head Vents may be opened at any time to relieve pressure or to adjust RPV Water Level.

Maintaining Reactor Coolant Temperature less than or equal to 170°F should preclude flashing the Shutdown Level Instrument Reference Leg if a vacuum is drawn on the Vessel.

21. WHEN the desired RPV level is reached AND stabilized, THEN close the following:
1. B21-F001, RX DN STREAM HEAD VENT TO DW EQUP DR SUMP (Initials)
2. B21-F002, RX UP STREAM HEAD VENT TO DW EQUP DR SUMP (Initials)

OSP-0041 REV - 8 PAGE 49 OF 72

CONTINUOUS USE NOTE Whenever E12-F003A(B), RHR HX OUTLET VALVE(s) is closed, ERIS/E12-R601 recorder RHR inlet temperature indication for Reactor Coolant Temperature is not accurate. During this time, ERIS/E12-R601 recorder points 5 or 6, is more accurate and should be used for Reactor Coolant Temperature Indication.

22. WHEN RPV level is stabilized, THEN slowly bypass the operating SDC Loop Heat Exchanger by performing the following:
1. Close E12-F003A(B), RHR A(B) HX OUTLET VALVE (Initials)
2. Open E12-F048A(B), RHR A(B) HX BYPASS VLV to maintain a constant RHR Loop Flow.

(Initials)

NOTE A reactor coolant temperature decrease, which may take up to four hours, constitutes a successful demonstration of the adequacy of this method. A constant reactor coolant temperature over a period of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> also contitutes a successful demonstration.

23. Verify adequate decay heat removal as indicated by temperatures decreasing or constant using STP-050-0700, RCS PRESSURE/TEMPERATURE LIMITS VERIFICATION, per Step 5.12.

(Initials)

OSP-0041 REV - 8 PAGE 50 OF 72

CONTINUOUS USE

24. Record the following data:

(Initials)

  • RPV Water Level ____________
  • RPV Temperature ____________
  • Hotwell Level ____________
  • SW Temperature ____________
  • FW Temperature ____________
  • CW Pumps In Operation ____________
  • Waterboxes Valved In ____________
  • CWS Inlet Temperature ____________
  • CWS Outlet Temperature ____________
25. Based upon the amount of Decay Heat, the following Drain Valves may be operated in conjunction with RPV Level and Hotwell Level to control temperature.
1. INBOARD MSIV DRAINS (120 gpm)
  • B21-F021 (Initials)
  • B21-F033 (Initials)
2. OUTBOARD MSIV DRAIN (48 gpm)
  • B21-F068 (Initials)
  • B21-F069 (Initials)
3. MS EQUALIZE HEADER DRAIN A (150 gpm)
  • DTM-AOV12A (Initials)

OSP-0041 REV - 8 PAGE 51 OF 72

CONTINUOUS USE

4. MS EQUALIZE HEADER DRAIN B (150 gpm)
  • DTM-AOV12B (Initials)
5. TURB BYPASS DRAIN LINE A (50 gpm)
  • DTM-AOV5A (Initials)
6. TURB BYPASS DRAIN LINE B (50 gpm)
  • DTM-AOV5B (Initials)
7. MSR #1 UPSTREAM DRAIN (365 gpm)
  • DTM-MOV51A (Initials)
8. MSR #2 UPSTREAM DRAIN (365 gpm)
  • DTM-MOV51B (Initials) 6.10.3. WHEN Decay Heat Removal is no longer required via this method, THEN perform the following:
1. Open RPV Head Vents:
  • B21-F001, RX DN STREAM HEAD VENT TO DW EQPT DR SUMP (Initials)
  • B21-F002, RX UP STREAM HEAD VENT TO DW EQPT DR SUMP (Initials)
2. Establish a normal shutdown cooling method.

(Initials)

3. Transfer decay heat removal method by lowering RPV Level below the Main Steam Lines, 104, while controlling temperature with the operating Shutdown Cooling Loop.

(Initials)

OSP-0041 REV - 8 PAGE 52 OF 72

CONTINUOUS USE

4. Notify Radiation Protection that RPV Level is being lowered below the Main Steam Lines.

(Initials)

5. Notify Chemistry that Decay Heat Removal via the Main Condenser is not in effect.

(Initials)

6. IF this mode of cooling is to be left in standby and/or is required, THEN Alternate Decay Heat Removal Verification must be completed at its specified frequency.

(Initials)

7. To restart decay heat removal per this means, perform the applicable portions of Section 6.10.1 and 6.10.2.

(Initials) 6.10.4. Shutdown of MSL Alternate Decay Heat Removal

1. Verify Main Steam Line Decay Heat Removal is no longer required.

(Initials)

2. Restore RPV Water Level as necessary for plant conditions.

(Initials)

3. Request I&C to perform recalibration of RPV Level Instrumentation per TSP-0054, Shutdown Range Reactor Water Level indication B21-LTN027 and C33-LTN017.

(Initials)

4. Request I&C to reset the Shutdown Level Alarms to the desired band.

(Initials)

5. Restore the Condenser Hotwell Level per SOP-0008, CONDENSATE STORAGE, MAKEUP AND TRANSFER.

(Initials)

6. Remove the Condenser level tygon tube and Level Transmitter, if installed.

(Initials)

OSP-0041 REV - 8 PAGE 53 OF 72

CONTINUOUS USE

7. Restore Valves per SOP-0007, CONDENSATE SYSTEM.

(Initials)

8. Remove the clearance installed in Step 6.10.1.4 clearance and restore per the applicable SOPs.

(Initials)

OSP-0041 REV - 8 PAGE 54 OF 72

CONTINUOUS USE ATTACHMENT 1 PAGE 1 OF 2 MODE SELECTION 1 Time Since Reactor Shutdown Record current date and time /

Record date and time of Reactor shutdown Determine length of time since Reactor shutdown Hours 2 Reactor Core Decay Heat from Attachment 6 or Incore Fuels Group

____________________106 BTU/HR Attachment 6 / Incore Fuels Group (Circle one)

OSP-0041 REV - 8 PAGE 55 OF 72

CONTINUOUS USE ATTACHMENT 1 PAGE 2 OF 2 MODE SELECTION NOTE An Alternate Method is required for each inoperable RHR-SDC mode.

More than one system may be needed to meet Reactor Core Decay Heat requirements, however, credit for each system may be used only once.

3 Compare Reactor Core Decay Heat value from Step 2 of this attachment to the systems heat removal capacities below and determine the Alternate Shutdown Cooling Methods. Record Alternate Shutdown Cooling Methods in Step 6.2.3.2.

HEAT REMOVAL SYSTEM CAPACITY (BTU/HR) CONDITIONS/ ASSUMPTIONS SPC/ADHR 2500 gpm, 83°F Service Water &

37.67 x 106 2250 gpm, 120°F Rx Coolant 40.12 x 106 2250 gpm, 140°F Rx Coolant 70.86 x 106 2250 gpm, 200°F Rx Coolant FPC Assist See Attachment 2 2000 gpm, 95°F Service Water CRD 2.5 x 106 50 gpm, 100°F CRD & 200°F Rx Coolant Condensate 7.5 x 106 200 gpm, 124°F Condensate &

200°F Rx Coolant RWCU See Attachment 3 471 gpm RPCCW** & 248 gpm Rx Coolant RHR-LPCI 126 x 106 5800 gpm, 95°F Service Water &

5050 gpm, 185°F Rx Coolant SFC See Attachment 4 2000 gpm Service Water & 2500 gpm Rx Coolant MSL Flooding 60 x 106 1758 gpm/20 hrs after shutdown &,

120°F to 170°F Rx Coolant &,

65°F to 100°F Circulating Water

    • This pertains to the non-regenerative heat exchanger only.

OSP-0041 REV - 8 PAGE 56 OF 72

CONTINUOUS USE ATTACHMENT 2 PAGE 1 OF 1 FPC ASSIST TEMPERATURE DEPENDENT HEAT REMOVAL CAPACITY TABLE FPC Assist of RHR, Service Water Flow @ 2000GPM SW Heat Removal Capacity (MBtu/hr)

Tci (°F) Pool = Pool = Pool = Pool = Pool = Pool = Pool =

95°F 100°F 105°F 110°F 120°F 130°F 140°F 75 11.5 19.17 23.00 26.84 34.50 42.17 49.84 77 9.97 17.64 21.47 25.30 32.97 40.64 48.31 79 8.43 16.10 19.94 23.77 31.44 39.11 46.77 81 6.90 14.57 18.40 22.24 29.90 37.57 45.24 83 5.37 13.04 16.87 20.70 28.37 36.04 43.71 85 3.83 11.50 15.34 19.17 26.84 34.50 42.17 87 2.30 9.97 13.80 17.64 25.30 32.97 40.64 89 .77 8.43 12.27 16.10 23.77 31.44 39.11 91 6.90 10.73 14.57 22.24 29.90 37.57 93 5.37 9.20 13.04 20.70 28.37 36.04 95 3.83 7.67 11.50 19.17 26.84 34.50 97 2.30 6.13 9.97 17.64 25.30 32.97 99 .77 4.60 8.43 16.10 23.77 31.44 101 3.07 6.90 14.57 22.24 29.90 103 1.53 5.37 13.04 20.70 28.37 105 3.83 11.5 19.17 26.84 FPC ASSIST OF RHR, SERVICE WATER FLOW @ 2000GPM SW Heat Removal Capacity (MBtu/hr)

Tci (°F) Pool = 150°F Pool = 160°F Pool = 170°F Pool = 180°F Pool = 190°F Pool = 200°F 75 57.51 65.18 72.84 80.51 88.18 95.85 77 55.97 63.64 71.31 78.98 86.65 94.31 79 54.44 62.11 69.78 77.44 85.11 92.78 81 52.91 60.57 68.24 75.91 83.58 91.25 83 51.37 59.04 66.71 74.38 82.04 89.71 85 49.84 57.51 65.18 72.84 80.51 88.18 87 48.31 55.97 63.64 71.31 78.98 86.65 89 46.77 54.44 62.11 69.78 77.44 85.11 91 45.24 52.91 60.57 68.24 75.91 83.58 93 43.71 51.37 59.04 66.71 74.38 82.04 95 42.17 49.84 57.51 65.18 72.84 80.51 97 40.64 48.31 55.97 63.64 71.31 78.98 99 39.11 46.77 54.44 62.11 69.78 77.44 101 37.57 45.24 52.91 60.57 68.24 75.91 103 36.04 43.71 51.37 59.04 66.71 74.38 105 34.50 42.17 49.84 57.51 65.18 72.84 OSP-0041 REV - 8 PAGE 57 OF 72

CONTINUOUS USE ATTACHMENT 3 PAGE 1 OF 1 RWCU TEMPERATURE DEPENDENT HEAT REMOVAL CAPACITY TABLES RWCU RPCCW Heat Removal Capacity (MBtu/hr)

Tci (°F) Rx = 90°F Rx = 100°F Rx = 110°F Rx = 120°F Rx = 130°F Rx = 140°F 75 1.48 2.47 3.46 4.44 5.43 6.42 77 1.28 2.27 3.26 4.25 5.23 6.22 79 1.09 2.07 3.06 4.05 5.04 6.03 81 0.89 1.88 2.86 3.85 4.84 5.83 83 0.69 1.68 2.67 3.65 4.64 5.63 85 0.49 1.48 2.47 3.46 4.44 5.43 87 0.30 1.28 2.27 3.26 4.25 5.23 89 0.10 1.09 2.07 3.06 4.05 5.04 91 0.89 1.88 2.86 3.85 4.84 93 0.69 1.68 2.67 3.65 4.64 95 0.49 1.48 2.47 3.46 4.44 97 0.30 1.28 2.27 3.26 4.25 99 0.10 1.09 2.07 3.06 4.05 101 0.89 1.88 2.86 3.85 103 0.69 1.68 2.67 3.65 105 0.49 1.48 2.47 3.46 RWCU RPCCW Heat Removal Capacity (MBtu/hr)

Tci (°F) Rx = 150°F Rx = 160°F Rx = 170°F Rx = 180°F Rx = 190°F Rx = 200°F 75 7.41 8.40 9.38 10.37 11.36 12.35 77 7.21 8.20 9.19 10.17 11.16 12.15 79 7.01 8.00 8.99 9.98 10.96 11.95 81 6.82 7.80 8.79 9.78 10.77 11.75 83 6.62 7.61 8.59 9.58 10.57 11.56 85 6.42 7.41 8.40 9.38 10.37 11.36 87 6.22 7.21 8.20 9.19 10.17 11.16 89 6.03 7.01 8.00 8.99 9.98 10.96 91 5.83 6.82 7.80 8.79 9.78 10.77 93 5.63 6.62 7.61 8.59 9.58 10.57 95 5.43 6.42 7.41 8.40 9.38 10.37 97 5.23 6.22 7.21 8.20 9.19 10.17 99 5.04 6.03 7.01 8.00 8.99 9.98 101 4.84 5.83 6.82 7.80 8.79 9.78 103 4.64 5.63 6.62 7.61 8.59 9.58 105 4.44 5.43 6.42 7.41 8.40 9.38 OSP-0041 REV - 8 PAGE 58 OF 72

CONTINUOUS USE ATTACHMENT 4 PAGE 1 OF 1 SFC TEMPERATURE DEPENDENT HEAT REMOVAL CAPACITY TABLES SSW or SFC RPCCW Heat Removal Capacity (MBtu/hr)

Tci (°F) Rx = 90°F Rx = 100°F Rx = 110°F Rx = 120°F Rx = 130°F Rx = 140°F 75 6.96 11.61 16.25 20.89 25.54 30.18 77 6.04 10.68 15.32 19.97 24.61 29.25 79 5.11 9.75 14.39 19.04 23.68 28.32 81 4.18 8.82 13.47 18.11 22.75 27.39 83 3.25 7.89 12.54 17.18 21.82 26.47 85 2.32 6.96 11.61 16.25 20.89 25.54 87 1.39 6.04 10.68 15.32 19.97 24.61 89 0.46 5.11 9.75 14.39 19.04 23.68 91 4.18 8.82 13.47 18.11 22.75 93 3.25 7.89 12.54 17.18 21.82 95 2.32 6.96 11.61 16.25 20.89 97 1.39 6.04 10.68 15.32 19.97 99 0.46 5.11 9.75 14.39 19.04 101 4.18 8.82 13.47 18.11 103 3.25 7.89 12.54 17.18 105 2.32 6.96 11.61 16.25 SSW or SFC RPCCW Heat Removal Capacity (MBtu/hr)

Tci (°F) Rx = 150°F Rx = 160°F Rx = 170°F Rx = 180°F Rx = 190°F Rx = 200°F 75 34.82 39.47 44.11 48.75 53.40 58.04 77 33.90 38.54 43.18 47.82 52.47 57.11 79 32.97 37.61 42.25 46.90 51.54 56.18 81 32.04 36.68 41.32 45.97 50.61 55.25 83 31.11 35.75 40.40 45.04 49.68 54.33 85 30.18 34.82 39.47 44.11 48.75 53.40 87 29.25 33.90 38.54 43.18 47.82 52.47 89 28.32 32.97 37.61 42.25 46.90 51.54 91 27.39 32.04 36.68 41.32 45.97 50.61 93 26.47 31.11 35.75 40.40 45.04 49.68 95 25.54 30.18 34.82 39.47 44.11 48.75 97 24.61 29.25 33.90 38.54 43.18 47.82 99 23.68 28.32 32.97 37.61 42.25 46.90 101 22.75 27.39 32.04 36.68 41.32 45.97 103 21.82 26.47 31.11 35.75 40.40 45.04 105 20.89 25.54 30.18 34.82 39.47 44.11 OSP-0041 REV - 8 PAGE 59 OF 72

CONTINUOUS USE ATTACHMENT 5 PAGE 1 OF 1 COMBINED RWCU AND SFC TEMPERATURE DEPENDENT HEAT REMOVAL CAPACITY TABLES RWCU and SFC RPCCW Heat Removal Capacity (MBtu/hr)

Tci (°F) Rx = 90°F Rx = 100°F Rx = 110°F Rx = 120°F Rx = 130°F Rx = 140°F 75 8.45 14.08 19.71 25.34 30.97 36.60 77 7.32 12.95 18.58 24.21 29.84 35.47 79 6.19 11.82 17.46 23.09 28.72 34.35 81 5.07 10.70 16.33 21.96 27.59 33.22 83 3.94 9.57 15.20 20.83 26.47 32.10 85 2.82 8.45 14.08 19.71 25.34 30.97 87 1.69 7.32 12.95 18.58 24.21 29.84 89 0.56 6.19 11.82 17.46 23.09 28.72 91 5.07 10.70 16.33 21.96 27.59 93 3.94 9.57 15.20 20.83 26.47 95 2.82 8.45 14.08 19.71 25.34 97 1.69 7.32 12.95 18.58 24.21 99 0.56 6.19 11.82 17.46 23.09 101 5.07 10.70 16.33 21.96 103 3.94 9.57 15.20 20.83 105 2.82 8.45 14.08 19.71 RWCU and SFC RPCCW Heat Removal Capacity (MBtu/hr)

Tci (°F) Rx = 150°F Rx = 160°F Rx = 170°F Rx = 180°F Rx = 190°F Rx = 200°F 75 42.23 47.86 53.49 59.12 64.76 70.39 77 41.11 46.74 52.37 58.00 63.63 69.26 79 39.98 45.61 51.24 56.87 62.50 68.13 81 38.85 44.48 50.12 55.75 61.38 67.01 83 37.73 43.36 48.99 54.62 60.25 65.88 85 36.60 42.23 47.86 53.49 59.12 64.76 87 35.47 41.11 46.74 52.37 58.00 63.63 89 34.35 39.98 45.61 51.24 56.87 62.50 91 33.22 38.85 44.48 50.12 55.75 61.38 93 32.10 37.73 43.36 48.99 54.62 60.25 95 30.97 36.60 42.23 47.86 53.49 59.12 97 29.84 35.47 41.11 46.74 52.37 58.00 99 28.72 34.35 39.98 45.61 51.24 56.87 101 27.59 33.22 38.85 44.48 50.12 55.75 103 26.47 32.10 37.73 43.36 48.99 54.62 105 25.34 30.97 36.60 42.23 47.86 53.49 OSP-0041 REV - 8 PAGE 60 OF 72

CONTINUOUS USE ATTACHMENT 6 PAGE 1 OF 1 DECAY HEAT AFTER SHUTDOWN FROM FULL POWER RBS Decay Heat after Shutdown from Full Power 180 160 140 120 Decay Heat (MBtu/hr) 100 80 60 40 20 0

1 10 100 1000 Time after Shutdown (hours)

OSP-0041 REV - 8 PAGE 61 OF 72

CONTINUOUS USE ATTACHMENT 7 PAGE 1 OF 2 LPCI MODE DATA SHEET SYSTEM START TIME RHR LOOP USED (A, B)

RHR Rx Rx Hx T Recirc DW Aux Press Temp Out Rx-Hx LPCI A/B Temp Cont Bldg

<135 <140 Temp Out Flow RWCU Flow >65 Temp Temp (psig) (°F) (°F) (°F) (gpm) Flow (gpm) (°F) (°F) (°F) 5 Min Prior to Start 1 Min Prior to Start 1 Min After Start 2 Min After Start 3 Min After Start 4 Min After Start 5 Min After Start Time Initials (hr) 01 02 03 04 05 06 07 08 09 10 11 12 OSP-0041 REV - 8 PAGE 62 OF 72

CONTINUOUS USE ATTACHMENT 7 PAGE 2 OF 2 LPCI MODE DATA SHEET RHR Rx Rx Hx T Recirc DW Aux Press Temp Out Rx-Hx LPCI A/B Temp Cont Bldg Time <135 <140 Temp Out Flow RWCU Flow >65 Temp Temp (hr) Initials (psig) (°F) (°F) (°F) (gpm) Flow (gpm) (°F) (°F) (°F) 13 14 15 16 17 18 19 20 21 22 23 24 OSP-0041 REV - 8 PAGE 63 OF 72

CONTINUOUS USE ATTACHMENT 8 PAGE 1 OF 2 MSL ALTERNATE DECAY HEAT REMOVAL BOUNDARY CLEARANCE The following equipment shall be placed in the indicated position and danger tagged to the OSS. Tagging shall be done in accordance with ADM-0027, Protective Tagging.

  • FWS-P1A, RFP A MOTOR: Breaker Racked Open
  • FWS-P1B, RFP B MOTOR: Breaker Racked Open
  • FWS-P1C, RFP C MOTOR: Breaker Racked Open
  • One Condensate Pump, CNM-P1A, P1B, OR P1C Breaker Racked Open
  • C85-D002A, BYPASS HPU PUMP A: Breaker Off
  • C85-D002B, BYPASS HPU PUMP B: Breaker Off
  • FWS-MOV27A, FWREG VLV 1A INLT A: Closed
  • FWS-MOV27B, FWREG VLV 1B INLT B: Closed
  • FWS-MOV27C, FWREG VLV 1C INLT C: Closed
  • TMB-HFPM A, EHC FLUID PUMP A: Breaker Racked Out
  • TMB-HFPM B, EHC FLUID PUMP B: Breaker Racked Out
  • MSS-MOV164, SJAE PCV SPLY ISOL VLV: Closed
  • MSS-MOV106, SJAE PCV BYPASS VLV: Closed
  • MSS-MOV153, OFG PRE-HEATER SHUTOFF: Closed
  • MSS-MOV155, MN STM SPLY TO SSE ISOL: Closed
  • MSS-MOV154, RW RBLR PCV SPLY ISOL: Closed
  • MSS-MOV112, MSR2 STM SPLY SHUTOFF: Closed
  • DTM-MOVRSDV1, MSS-PVRSHLV1 BODY DR: Closed
  • DTM-MOV54B, MSL TO MSR2 COND DR: Closed
  • DTM-V176, MSS-MOV155 DOWN STREAM DRAIN LINE ISOL: Closed
  • E51-F076, RCIC WARMUP LINE SHUT OFF VALVE: Closed OSP-0041 REV - 8 PAGE 64 OF 72

CONTINUOUS USE ATTACHMENT 8 PAGE 2 OF 2 MSL ALTERNATE DECAY HEAT REMOVAL BOUNDARY CLEARANCE

  • E51-FO63, RCIC STEAM SUPPLY INBD ISOL VALVE: Closed
  • MSS-V31, MSL SAMPLE LINE ROOT VALVE: Closed
  • B21-F005, RX HEAD VENT TO MSL A: Closed
  • E33-MOVF028, MS ISOL VALVE LK CONT SYS: Closed
  • E33-MOVF008, MN STM POS LEAK CONT INBD ISOL: Closed
  • MSS-MOV111, MSR1 STM SPLY SHUTOFF: Closed
  • DTM-MOV54A, MSL TO MSR1 COND DR: Closed OSP-0041 REV - 8 PAGE 65 OF 72

CONTINUOUS USE ATTACHMENT 9 PAGE 1 OF 2 MSL ALTERNATE DECAY HEAT REMOVAL VALVE LINEUP VALVE VALVE NAME REQD INITIALS VALVE NUMBER (OR DESCRIPTION) POSITION LABELED LOCATION: AUX BLDG. 114 EL.

DTM-V60 INBD MSIV BODY DRN LINE ISOL OPEN LOCATION: RADWASTE 65 EL.

DTM-V44 MSIV DRN LINE TO COND ISOL OPEN LOCATION: TURBINE BLDG. 95 EL.

DTM-V1 MN STM EQUAL HDR DRN LINE OPEN ISOL VLV DTM-V2 MN STM EQUAL HDR DRN LINE OPEN ISOL VLV DTM-V27 B/P STM CHEST DRN LINE ISOL OPEN VLV DTM-V28 B/P STM CHEST DRN LIEN ISOL OPEN VLV DTM-V173 1MSS-MOV111 DN STM DRAIN LINE OPEN ISOL VLV DTM-V172 MN STM SUPPLY TO MSR1 DRN OPEN LINE ISOL VLV DTM-V174 MN STM SUPPLY TO MSR2 DRN OPEN LINE ISOL VLV OSP-0041 REV - 8 PAGE 66 OF 72

CONTINUOUS USE ATTACHMENT 9 PAGE 2 OF 2 MSL ALTERNATE DECAY HEAT REMOVAL VALVE LINEUP Remarks:

Performed By:

Signature KCN Initials Date/Time Signature KCN Initials Date/Time Signature KCN Initials Date/Time Reviewed By:

OSS/CRS KCN Date/Time OSP-0041 REV - 8 PAGE 67 OF 72

CONTINUOUS USE ATTACHMENT 10 PAGE 1 OF 2 MSL ALTERNATE DECAY HEAT REMOVAL CONTROL BOARD LINEUP PANEL ITEM PANEL ITEM POSITION INDICATION INITIALS THE FOLLOWING ITEMS ARE LOCATED ON PANEL H13-P601 B21-F016, MSL WARMUP HDR AUTO AFTER OPEN RED INBD CONTMT ISOL VLV B21-F019, MSL WARMUP HDR AUTO AFTER OPEN RED OUTBD CONTMT ISOL VLV B21-F021, MSL WARMUP HDR NEUTRAL AFTER OPEN RED COND DRAIN VALVE B21-F033, MSL WARMUP HDR OPEN RED COND DRAIN VALVE B21-F086, MSL DRAIN HDR OPEN RED SHUTOFF VALVE B21-F068, MSL DRAIN HDR NEUTRAL AFTER OPEN RED COND DRAIN BYP VALVE B21-F069, MSL DRAIN HDR OPEN RED COND DRAIN VALVE B21-F020, MSL WARMUP HDR NEUTRAL AFTER OPEN GREEN SUPPLY VALVE THE FOLLOWING ITEMS ARE LOCATED ON PANEL H13-P870 DTM-AOV12A, MSL OPEN RED EQUALIZING HDR DRAIN BYPASS VALVE DTM-AOV12B, MSL OPEN RED EQUALIZING HDR DRAIN BYPASS VALVE DTM-AOV5A, BYP VLV OPEN RED BEFORE SEAT DR DTM-AOV5B, BYP VLV OPEN RED BEFORE SEAT DR DTM-MOV51A, MSL TO MSR1 NEUTRAL AFTER OPEN RED COND DR DTM-MOV51B, MSL TO MSR2 NEUTRAL AFTER OPEN RED COND DR OSP-0041 REV - 8 PAGE 68 OF 72

CONTINUOUS USE ATTACHMENT 10 PAGE 2 OF 2 MSL ALTERNATE DECAY HEAT REMOVAL CONTROL BOARD LINEUP Remarks:

Performed By:

Signature KCN Initials Date/Time Signature KCN Initials Date/Time Signature KCN Initials Date/Time Reviewed By:

OSS/CRS KCN Date/Time OSP-0041 REV - 8 PAGE 69 OF 72

CONTINUOUS USE ATTACHMENT 11 PAGE 1 OF 3 MSL ALTERNATE DECAY HEAT REMOVAL EQUIPMENT FAILURES During the use of this procedure, equipment failures could result in an increase of Reactor Pressure, a decrease in Reactor Level, or a loss of Decay Heat Removal capability. Prompt operator action is required to mitigate the transient and restore a method of Decay Heat Removal.

1 MSIV Isolation NOTES An isolation causes a significant increase in reactor pressure in approximately 5 minutes assuming a RPV Feed Rate of 2000 gpm.

Only one (1) Main Steam Line open to the Turbine Stop Valves is required for this procedure.

1.1 Close C33LVF002, START UP FWREG VALVE.

NOTE A decrease in RPV Level of approximately 1 inch/min can occur if FWS-FV104, STARTUP RECIRC FCV is open and RWCU is in service.

1.2 Adjust FWS-FV104, STARTUP RECIRC FCV as necessary to control RPV Water Level.

1.3 Restore the operating loop of RHR in Shutdown Cooling as the means of Decay Heat Removal.

OSP-0041 REV - 8 PAGE 70 OF 72

CONTINUOUS USE ATTACHMENT 11 PAGE 2 OF 3 MSL ALTERNATE DECAY HEAT REMOVAL EQUIPMENT FAILURES 2 Increase in Condensate Flow to the RPV 2.1 Inadvertent ECCS Initiation NOTE Two (2) Low Pressure ECCS Pumps injecting into the RPV can result in a significant pressure increase in approximately one to two minutes.

2.1.1. Verify ECCS Injection Systems are not required for RPV Level Control.

2.1.2. Stop ECCS injection by securing pumps or closing injection valves.

2.1.3. Restore Reactor Pressure to zero and RPV Water Level as directed by the OSS/CRS.

2.1.4. Restore the operating loop RHR in Shutdown Cooling as the means of Decay Heat Removal.

2.2 C33-LVF002, START UP FWREG VALVE fails open.

2.2.1. Adjust FWS-FV104, STARTUP RECIRC FCV to control RPV Water Level.

2.2.2. IF Condensate flow to the vessel is still excessive, THEN isolate the Feedwater Injection Lines by closing:

OSP-0041 REV - 8 PAGE 71 OF 72

CONTINUOUS USE ATTACHMENT 11 PAGE 3 OF 3 MSL ALTERNATE DECAY HEAT REMOVAL EQUIPMENT FAILURES 2.3 FWS-FV104, STARTUP RECIRC FCV fails closed.

2.3.1. Adjust the Startup Level Control Valve to maintain RPV Water Level.

2.3.2. Restore the operating loop of RHR in Shutdown Cooling as the means of Decay Heat Removal.

3 Decrease in Condensate Flow to the RPV 3.1 Condensate Pump trip or C33-LVF002, STARTUP FWREG VALVE fails closed.

3.1.1. Close C33-LVF002, STARTUP FWREG VALVE.

3.1.2. Close FWS-FV104, STARTUP RECIRC FCV.

3.1.3. Restore the operating loop of RHR in Shutdown Cooling as the means of Decay Heat Removal.

3.2 Inadvertent SRV opening NOTE An open SRV results in a decrease in Hotwell Level and an increase in Suppression Pool Level. As Condenser Tubes are uncovered, Decay Heat Removal via this method is lost.

3.2.1. Close the open SRV.

3.2.2. IF the SRV cannot be closed, THEN restore the operating loop of RHR in Shutdown Cooling as the means of Decay Heat Removal.

3.3 FWS-FV104, STARTUP RECIRC FCV fails open NOTE This condition results in reduced or zero condensate flow to the RPV.

3.3.1. Secure this method of Alternate Decay Heat Removal and restore the operating loop of RHR in Shutdown Cooling as the means of Decay Heat Removal.

OSP-0041 REV - 8 PAGE 72 OF 72

Number: *RJPM-OPS-ADM-S02 RIVER Revision: 1 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • COMPLETE LCO STATUS SHEET FOR INOPERATIVE CONTROL ROOM FRESH AIR INITIATION INSTRUMENTATION REASON FOR REVISION:

NRC Exam JPM SRO ADMIN - 2 PREPARE / REVIEW:

Erich Weinfurter 1497 7/16/2004 Preparer KCN Date Roger Persons 0862 7/18/2004 Technical Review (SME) KCN Date Tiffany Aley 1338 7/20/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-ADM-S02 TASK DESCRIPTION: Complete LCO Status Sheet for Inoperative Control Room Fresh Air System TASK

REFERENCE:

301001005003 K/A REFERENCE & RATING: 2.1.12, 2.9/4.0 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 15 min.

MAX TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-OPS-ADM-S02 Page 2 of 10

RJPM-OPS-ADM-S02 SIMULATOR SETUP SHEET Task

Description:

Complete LCO Status Sheet for Inoperative Control Room Fresh Air System Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-OPS-ADM-S02 Page 3 of 10

RJPM-OPS-ADM-S02 DATA SHEET References for Development: OSP-0040, LCO Tracking and Safety Function Determination Program Technical Specification 3.3.7.1 Required Materials: OSP-0040, LCO Tracking and Safety Function Determination Program Technical Specification 3.3.7.1 Required Plant Condition: N/A Applicable Objectives: HLO-408 Obj. 2 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-ADM-S02 Page 4 of 10

RJPM-OPS-ADM-S02 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is operating at 100% power on 9/20/2004. Control Room Local Intake Radiation Monitor RMS-RE13B failed high at 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br />.

The eSOMs Computer system is Out of Service for critical system upgrade to correct a known problem, and will not be available for the remainder of this shift.

Initiating Cue:

Complete attached LCO Status Sheet LCO 1-TS-04-016 RJPM-OPS-ADM-S02

  • Denotes Critical Step Page 5 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-S02 PERFORMANCE STEP STANDARD S/U COMMENTS Complete LCO Status Sheet Blocks 5, Completes LCO Status Sheet Blocks 5, 6, and 8 NOTE: LCO Status Sheet KEY

  • 1. 6, and 8. per attached LCO Status Sheet. provided showing correct entries.

Provide a brief description of the Completes LCO Status Sheet Block 10 per Condition(s) entered. All conditions attached LCO Status Sheet.

  • 2. that must be entered due to the inoperability should be documented.

Provide the Required Actions if the Completes LCO Status Sheet Block 11 per

  • 3. TS LCO is not met. attached LCO Status Sheet.

Record the Completion Time Completes LCO Status Sheet Block 12 per

  • 4. associated with each Required Action. attached LCO Status Sheet.

When an LCO is entered for a system Completes LCO Status Sheet Blocks 13 and 15 designated as a support system in per attached LCO Status Sheet.

Attachment 1, Support - Supported LCO Matrix of this procedure, evaluate the operability of the

5. supported system. If T.S. 3.0.6 is to be used to prevent entering Conditions and Required Actions for supported systems, perform an evaluation per T.S. 5.5.10 to ensure that no loss of safety function exists.

Terminating Cue: Status Sheet LCO 1-TS-04-016 completed.

RJPM-OPS-ADM-S02

  • Denotes Critical Step Page 6 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-S02 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-ADM-S02 Page 7 of 10

RJPM-OPS-ADM-S02 ATTACHMENT 1 - LCO STATUS SHEET (TYPICAL)

LCO No.: 1-TS 016 1 Date: 2 Time: 1005 3 % PWR 100 4 Mode: 1 Page 1 of 1 9/20/04 5 TS/TRM No.: 3.3.7.1 6 Mode Change Allowed:_ X _Yes _ _No 7 Mark No. RMS-RE13B Sys. No.: 511 8 Applicable Modes:_X_1 _X_2 _X_3 ___4 ___5 Description Control Room Local Intake Ventilation Other OPDRVs and Movement of recently irradiated Radiation Monitor fuel assemblies in Containment or Fuel Building 9 CONDITION INITIATING LCO: Scheduled Outage______ Equipment Failure__XX___

Control Room Local Intake Radiation Monitor RMS-RE13B failed high 10 Condition 11 Required Action 12 Completion Time A. One or more required A.1 Enter the condition Required by: Completed:

channels inoperable referenced in Table 3.3.7.1-1 Date: 09/20/2004 Date:___/___/___

__________________________ for the channel Time:__________

_________________ ________________ Time: 1005 Initials:_________

D. As required by Required D.1 Declare associated CRFA Required by: Completed:

Action A.1 and referenced in subsystem inoperable Date:___/___/___ Date:___/___/___

Table 3.3.7.1-1 __________________________ Time:__________

_________________ _________________ Time:__________ Initials:_________

__________________________ D.2 Place channel in Trip Required by: Completed:

__________________________ __________________________ Date: 09/20/2004 Date:___/___/___

__________________________ __________________________ Time:__________

__________________ _______________ Time: 1605 Initials:_________

__________________________ __________________________ Required by: Completed:

__________________________ __________________________ Date: :___/___/___ Date:___/___/___

__________________ ____________ Time:__________

Time: __________ Initials:_________

13 LCO 3.0.6 ENTERED N/A 14 LOSS OF SAFETY FUNCTION EVALUATION COMPLETED Initials/KCN:____/____

15 PREPARED BY: Candidates Name 16 REVIEWED BY:

LCO CLOSEOUT 17 COMMENTS/CORRECTIVE ACTIONS 18 LCO RESTORED DATE/TIME 19 RESTORED BY: 20 REVIEWED BY:

RJPM-OPS-ADM-S02 Page 8 of 10

RJPM-OPS-ADM-S02 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is operating at 100% power on 9/20/2004. Control Room Local Intake Radiation Monitor RMS-RE13B failed high at 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br />.

The eSOMs Computer system is Out of Service for critical system upgrade to correct a known problem, and will not be available for the remainder of this shift.

Initiating Cues: Complete attached LCO Status Sheet LCO 1-TS-04-016 RJPM-OPS-ADM-S02 Page 9 of 10

RJPM-OPS-ADM-S02 ATTACHMENT 2 - LCO STATUS SHEET (TYPICAL)

LCO No.: 1-TS 016 1 Date: 2 Time: 1005 3 % PWR 100 4 Mode: 1 Page 1 of 1 9/20/04 5 TS/TRM No.: 6 Mode Change Allowed: ____Yes ____No 7 Mark No. ______________ Sys. No.: ____ 8 Applicable Modes:___1 ___ 2 ___3 ___4 ___5 Description _________________________________ Other _______________________________________

9 CONDITION INITIATING LCO: Scheduled Outage______ Equipment Failure_______

10 Condition 11 Required Action 12 Completion Time

__________________________ __________________________ Required by: Completed:

__________________________ __________________________ Date:___/___/___ Date:___/___/___

__________________________ __________________________ Time:__________

Time:__________ Initials:_________

__________________________ __________________________ Required by: Completed:

__________________________ __________________________ Date:___/___/___ Date:___/___/___

__________________________ __________________________ Time:__________

Time:__________ Initials:_________

__________________________ __________________________ Required by: Completed:

__________________________ __________________________ Date:___/___/___ Date:___/___/___

__________________________ __________________________ Time:__________

Time:__________ Initials:_________

__________________________ __________________________ Required by: Completed:

__________________________ __________________________ Date: :___/___/___ Date:___/___/___

__________________________ __________________________ Time:__________

Time: __________ Initials:_________

13 LCO 3.0.6 ENTERED 14 LOSS OF SAFETY FUNCTION EVALUATION COMPLETED Initials/KCN:____/____

15 PREPARED BY: 16 REVIEWED BY:

LCO CLOSEOUT 17 COMMENTS/CORRECTIVE ACTIONS 18 LCO RESTORED DATE/TIME 19 RESTORED BY: 20 REVIEWED BY:

RJPM-OPS-ADM-S02 Page 10 of 10

Number: *RJPM-OPS-ADM-S03 RIVER Revision: 0 BEND STATION Page 1 of 8 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • REVIEW COMPLETED IST SURVEILLANCE PROCEDURE FOR APPROVAL REASON FOR REVISION:

NRC Exam JPM SRO ADMIN - 3 PREPARE / REVIEW:

Roger Persons 0862 7/19/2004 Preparer KCN Date Erich Weinfurter 1497 7/19/2004 Technical Review (SME) KCN Date Tiffany Aley 1338 7/20/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-ADM-S03 TASK DESCRIPTION: Review completed IST Surveillance Procedure for approval.

TASK

REFERENCE:

K/A REFERENCE & RATING: 2.2.12, 3.4 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 11 min.

MAX TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH Yes (FAULTED):

RJPM-OPS-ADM-S03 Page 2 of 8

RJPM-OPS-ADM-S03 SIMULATOR SETUP SHEET Task

Description:

Review and approve completed IST Surveillance Procedure.

Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-OPS-ADM-S03 Page 3 of 8

RJPM-OPS-ADM-S03 DATA SHEET References for Development: ADM-0015, Station Surveillance Test Program Required Materials: ADM-0015, Station Surveillance Test Program Completed STP-201-6310 Required Plant Condition: N/A Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-ADM-S03 Page 4 of 8

RJPM-OPS-ADM-S03 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is operating at 100% power. STP-201-6310, SLC Quarterly Pump and Valve Operability Test has been completed and submitted for Section Superintendent approval.

Initiating Cue:

As CRS, perform the Section Superintendent review and approval of STP-201-6310, SLC Quarterly Pump and Valve Operability Test.

RJPM-OPS-ADM-S03

  • Denotes Critical Step Page 5 of 8

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-S03 PERFORMANCE STEP STANDARD S/U COMMENTS Reviews ADM-0015 for Provide copy of ADM-0015, responsibilities of Section Station Surveillance Test Program,

1. Superintendent or Designee. if requested.

Reviews steps of STP for Identifies Step 7.2.3 requiring independent

2. completeness. verification that was signed by the performer instead of the verifier who signed Step 7.2.4.

Reviews pump and valve data sheets Identifies MEASURED VALUE recorded for NOTE: The flow value of 40.4 for meeting TS acceptance criteria. Step 7.3.7 is in the Required Action Range and gpm recorded on Pump Data Sheet

  • 3.

does NOT meet Technical Specifications. for C41-PC001B, Step 7.3.7, STP Page 21 and 22 is unacceptable.

Rejects STP based on results. Does NOT sign approval of STP and states a CR CUE: CR and TS entry will be

  • 4. must be written and TS LCO for INOP SLC Loop done by another CRS. JPM is B must be entered. completed.

Terminating Cue: Review of STP completed and NOT approved based on unacceptable value for SLC Pump B flowrate.

RJPM-OPS-ADM-S03

  • Denotes Critical Step Page 6 of 8

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-S03 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-ADM-S03 Page 7 of 8

RJPM-OPS-ADM-S03 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is operating at 100% power.

STP-201-6310, SLC Quarterly Pump and Valve Operability Test has been completed and submitted for Section Superintendent approval.

Initiating Cues: As CRS, perform the Section Superintendent review and approval of STP-201-6310, SLC Quarterly Pump and Valve Operability Test.

RJPM-OPS-ADM-S03 Page 8 of 8

Number: *RJPM-OPS-ADM-S05 RIVER Revision: 1 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • CLASSIFY AN EMERENCY EVENT REASON FOR REVISION:

NRC Exam JPM SRO ADMIN - 5 PREPARE / REVIEW:

Erich Weinfurter 1497 7/16/2004 Preparer KCN Date Roger Persons 0862 7/17/2004 Technical Review (SME) KCN Date Tiffany Aley 1338 7/20/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-ADM-S05 TASK DESCRIPTION: Classify an Emergency Event TASK

REFERENCE:

K/A REFERENCE & RATING: 2.4.41, 4.1 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 10 min.

MAX TIME: 15 min.

JOB LEVEL: SRO TIME CRITICAL: Yes (Max Time is limit)

EIP CLASSIFICATION Yes REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-OPS-ADM-S05 Page 2 of 10

RJPM-OPS-ADM-S05 SIMULATOR SETUP SHEET Task

Description:

Classify an Emergency Event Required Power: N/A IC No.: N/A Notes: The performer has 15 minutes, from the time the information is given to classification of the event and complete the short notification form for the communicator to transmit.

RJPM-OPS-ADM-S05 Page 3 of 10

RJPM-OPS-ADM-S05 DATA SHEET References for Development: EIP-2-001 Required Materials: EIP-2-001 Notification Message Short Forms for all 4 classifications Required Plant Condition: N/A Applicable Objectives: ETT-032 Obj. 4 ETT-032R Obj. 4 ETT-023 Obj. 8 ETT-023R Obj. 8 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-ADM-S05 Page 4 of 10

RJPM-OPS-ADM-S05 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

A portion of this JPM is time critical. You may take time to review and familiarize yourself with the JPM Task Conditions/Cues.

Let me know when you have completed familiarizing yourself with the JPM Task Conditions/Cues. You will then begin the time critical portion of the JPM.

Then let me know when you have classified the event.

RJPM-OPS-ADM-S05

  • Denotes Critical Step Page 5 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-S05 Initial Conditions:

The plant was operating at 100% power when an electrical fault in the EHC Control panel started a small fire which quickly filled the Main Control Room with smoke. The Fire Brigade started suppression efforts to prevent the fire from spreading to the Safety Related RMS panels.

Smoke reduced the visibility in the Main Control Room to the point that the Operations Shift Manager (OSM) ordered the evacuation of the Main Control Room (MCR). The following is a time line of the events:

1034 hrs Electrical Fault in EHC Panel results in fire with heavy smoke.

1036 hrs MCR personal in SCBA 1038 hrs ATC Operator overcome by smoke due to a faulty Air Pack and is removed from MCR to the Services Building for treatment 1039 hrs Evacuation of MCR ordered by OSM due to heavy smoke.

1040 hrs Fire Brigade attempts to extinguish fire with CO2 1045 hrs Fire continues to burn, Div 1 Safety Related RMS panels threatened, but not involved.

1046 hrs Off-Site Fire Departments assistance requested by Fire Brigade.

1052 hrs Unit Operator completes AOP-0031 immediate operator actions, and begins working Attachment 12 actions for ATC.

1057 hrs CRS reports that RHR and RCIC Systems have just been placed in operation from Div.1 Remote Shutdown Panels and that reactor pressure is being controlled by manual operation of one SRV.

1059 hrs Fire Brigade Leader reports the fire under control.

Current Met Tower data is as follows:

  • Wind direction is 202 degrees
  • Wind speed is 5 miles per hour
  • No precipitation.

Initiating Cue:

As OSM and Emergency Director, classify the event and complete the notification short form.

RJPM-OPS-ADM-S05

  • Denotes Critical Step Page 6 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-S05 PERFORMANCE STEP STANDARD S/U COMMENTS Review Emergency Action Levels for EIP-2-001 reviewed NOTE: JPM Step 2 is TIME event classification. CRITICAL and is to be completed 15 minutes from the time the candidate states he/she

1. understands plant conditions and is ready to begin the classification task.

CUE: Provide EIP-0-001, when requested.

Classify event. Event classified in 15 minutes as SAE (per EAL

15) as an SAE due to failure to establish RSP with in 15 min of evacuation of the Main Control START Time________________
  • 2. Room STOP Time__________________

RJPM-OPS-ADM-S05

  • Denotes Critical Step Page 7 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-S05 PERFORMANCE STEP STANDARD S/U COMMENTS Complete short form for notification Short form notification completed as follows: CUE: Use current clock time for of SAE. Form GSUN0952.1-99-99(Sept) filled out the time that the emergency was correctly for communicator. declared.

Declared : Time of Performance Step 2 On: Current Date For: Evacuation of the Main Control Room

  • 3. and Control of Shutdown Systems not established at Remote Shutdown Panels in 15 Min.

Wind from: 202 deg.

At: 5 miles Release: No Authorized by: Signature

Title:

Emergency Director or ED/RM Terminating Cue: Classification determined and the short form notification completed.

RJPM-OPS-ADM-S05

  • Denotes Critical Step Page 8 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-ADM-S05 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-ADM-S05 Page 9 of 10

RJPM-OPS-ADM-S05 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant was operating at 100% power when an electrical fault in the EHC Control panel started a small fire which quickly filled the Main Control Room with smoke. The Fire Brigade started suppression efforts to prevent the fire from spreading to the Safety Related RMS panels.

Smoke reduced the visibility in the Main Control Room to the point that the Operations Shift Manager (OSM) ordered the evacuation of the Main Control Room (MCR). The following is a time line of the events:

1034 hrs Electrical Fault in EHC Panel results in fire with heavy smoke.

1036 hrs MCR personal in SCBA 1038 hrs ATC Operator overcome by smoke due to a faulty Air Pack and is removed from MCR to the Services Building for treatment.

1039 hrs Evacuation of MCR ordered by OSM due to heavy smoke.

1040 hrs Fire Brigade attempts to extinguish fire with CO2 1045 hrs Fire continues to burn, Div 1 Safety Related RMS panels threatened, but not involved.

1046 hrs Off-Site Fire Departments assistance requested by Fire Brigade 1052 hrs Unit Operator completes AOP-0031 immediate operator actions, and begins working Attachment 12 actions for ATC.

1057 hrs CRS reports that RHR and RCIC Systems have just been placed in operation from Div.1 Remote Shutdown Panels and that reactor pressure is being controlled by manual operation of one SRV.

1059 hrs Fire Brigade Leader reports the fire under control.

Current Met Tower data is as follows:

  • Wind direction is 202 degrees
  • Wind speed is 5 miles per hour
  • No precipitation.

Initiating Cues: As OSM and Emergency Director, classify the event and complete the notification short form.

RJPM-OPS-ADM-S05 Page 10 of 10

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: RO Operating Test Number: 1 CONTROL ROOM SYSTEMS (8 for RO)

System / JPM Title and No. / (Type Codes*) SF KA IR Notes

1. 201005 Rod Control and Information System 7 K1.02 3.3 295037 SCRAM and Reactor Power Above K5.02 2.8 APRM Downscale or Unknown A1.01 3.2 Defeat RCIS Interlocks Per EOP Enclosure EK2.12 3.6 14 EA1.08 3.6 Exam JPM No. CRS-01 (D) (C)
2. 400000 Component Cooling Water System 8 K1.01 3.2 Loss of Normal Service Water creates Alternate CCP Valve Quarterly Stroke Test A4.01 3.1 Path requiring action to Surveillance AK3.07 3.1 allow initiation of Exam JPM No. CRS-02 (N) (A) (S) AA1.01 3.3 Standby Service Water.
3. 223001 Primary Containment and Auxiliaries 5 K1.13 3.4 Failure of RHS-AOV63 creates Alternate Path Makeup to Suppression Pool Using A2.11 3.6 requiring use of HPCS SPC/ADHR for SP makeup.

Exam JPM No. CRS-03 (M) (A) (S)

4. 259002 Reactor Water Level Control System 2 K5.01 3.1 Failure of FWRC C to open creates Alternate Place FWRV C in service on Master A1.05 2.9 Path requiring selection FWLC with Startup FWRV A4.03 3.8 of alternate FWRV Exam JPM No. CRS-04 (M) (A) (S) (L)
5. 239001 Main and Reheat Steam System 3 K1.01 3.4 Bypass MSR Steam Supply Valves Interlock K1.05 2.8 per EOP Enclosure 5 Exam JPM No. CRS-05 (D) (C)
6. 288000 Plant Ventilation System 9 K4.03 2.8 Restore Fuel Building Ventilation to A2.01 3.3 Standby Following Auto Initiation. A4.01 3.1 Exam JPM No. CRS-06 (D) (S)
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA entry Page 1 of 6 NUREG-1021, Draft Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: RO Operating Test Number: 1 CONTROL ROOM SYSTEMS, continued (8 for RO)

System / JPM Title and No. / (Type Codes*) SF KA IR Notes

7. 262001 AC Electrical Distribution 6 A2.01 3.5 Generator Ground condition creates 295003 Partial/Complete Loss of AC Power A2.05 3.6 Alternate Path requiring Parallel Offsite Power to ENS-SWG1B A4.02 3.4 manual trip of O/P Supplied by Div II EDG AA1.02 4.2 breaker and Diesel Exam JPM No. CRS-07 (M) (A) (S) (L) shutdown.
8. 201003 Control Rod and Drive Mechanism 1 K4.02 3.8 Control Rod Overtravel alarm indicating Perform Control Rod Operability Check A2.02 3.7 uncoupled rod, creates Exam JPM No. CRS-08 (D) (A) (S) A4.02 3.5 the Alternate Path.

IN-PLANT SYSTEMS (3 for RO)

1. 201001 Control Rod Drive Hydraulic System 1 K1.09 3.1 Requires CAA and Primary Containment 295037 SCRAM and Reactor Power Above EK3.07 4.2 entry.

APRM Downscale or Unknown Vent Scram Air Header per EOP Enclosure 11 Exam JPM No. IPS-01 (D) (R)

2. 264000 Emergency Diesel Generators 6 K6.07 3.8 Trip of SWP-P2A creates Alternate Path 295016 Control Room Abandonment AK2.01 4.4 requiring start of SWP-Place Standby Service Water in service for AK2.02 4.0 P2C from different panel Div I EDG from Remote Shutdown Panel (EGS-PNL4C)

Exam JPM No. IPS-02 (D) (A) (L)

3. 212000 Reactor Protection System 7 K1.04 3.4 Restore RPS B Normal power supply. K2.01 3.2 Exam JPM No. IPS-03 (D) A1.01 2.8 A2.01 3.7
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA entry Page 2 of 6 NUREG-1021, Draft Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: SRO-Instant Operating Test Number: 1 CONTROL ROOM SYSTEMS (7 for SRO-I)

System / JPM Title and No. / (Type Codes*) SF KA IR Notes

1. 201005 Rod Control and Information System 7 K1.02 3.5 295037 SCRAM and Reactor Power Above K5.02 3.3 APRM Downscale or Unknown A1.01 3.3 Defeat RCIS Interlocks Per EOP Enclosure EK2.12 3.8 14 EA1.08 3.6 Exam JPM No. CRS-01 (D) (C)
2. 400000 Component Cooling Water System 8 K1.01 3.3 Loss of Normal Service Water creates Alternate CCP Valve Quarterly Stroke Test A4.01 3.0 Path requiring action to Surveillance AK3.07 3.2 allow initiation of Exam JPM No. CRS-02 (N) (A) (S) AA1.01 3.4 Standby Service Water.
3. 223001 Primary Containment and Auxiliaries 5 K1.13 3.5 Failure of RHS-AOV63 creates Alternate Path Makeup to Suppression Pool Using A2.11 3.8 requiring use of HPCS SPC/ADHR for SP makeup.

Exam JPM No. CRS-03 (M) (A) (S)

4. 259002 Reactor Water Level Control System 2 K5.01 3.1 Failure of FWRC C to open creates Alternate Place FWRV C in service on Master A1.05 2.9 Path requiring selection FWLC with Startup FWRV A4.03 3.6 of alternate FWRV Exam JPM No. CRS-04 (M) (A) (S) (L)
5. 239001 Main and Reheat Steam System 3 K2.01 3.2 Bypass MSR Steam Supply Valves Interlock K4.05 3.7 per EOP Enclosure 5 K6.04 3.2 Exam JPM No. CRS-05 (D) (C) A2.03 4.2
6. 288000 Plant Ventilation System 9 K4.03 2.9 Restore Fuel Building Ventilation to A2.01 3.4 Standby Following Auto Initiation. A4.01 2.9 Exam JPM No. CRS-06 (D) (S)
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA entry Page 3 of 6 NUREG-1021, Draft Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: SRO-Instant Operating Test Number: 1 CONTROL ROOM SYSTEMS, continued (7 for SRO-I)

System / JPM Title and No. / (Type Codes*) SF KA IR Notes

7. 262001 AC Electrical Distribution 6 A2.01 3.6 Generator Ground condition creates 295003 Partial/Complete Loss of AC Power A2.05 3.6 Alternate Path requiring Parallel Offsite Power to ENS-SWG1B A4.02 3.4 manual trip of O/P Supplied by Div II EDG AA1.02 4.3 breaker and Diesel Exam JPM No. CRS-07 (M) (A) (S) (L) shutdown.

IN-PLANT SYSTEMS (3 for SRO-I)

1. 201001 Control Rod Drive Hydraulic System 1 K1.09 3.2 Requires CAA and Primary Containment 295037 SCRAM and Reactor Power Above EK3.07 4.3 entry.

APRM Downscale or Unknown Vent Scram Air Header per EOP Enclosure 11 Exam JPM No. IPS-01 (D) (R)

2. 264000 Emergency Diesel Generators 6 K6.07 3.9 Trip of SWP-P2A creates Alternate Path 295016 Control Room Abandonment AK2.01 4.5 requiring start of SWP-Place Standby Service Water in service for AK2.02 4.1 P2C from different panel Div I EDG from Remote Shutdown Panel (EGS-PNL4C)

Exam JPM No. IPS-02 (D) (A) (L)

3. 212000 Reactor Protection System 7 K1.04 3.6 Restore RPS B Normal power supply. K2.01 3.3 Exam JPM No. IPS-03 (D) A1.01 2.9 A2.01 3.9
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA entry Page 4 of 6 NUREG-1021, Draft Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: SRO-Upgrade Operating Test Number: 1 CONTROL ROOM SYSTEMS (2 or 3 for SRO-U)

System / JPM Title and No. / (Type Codes*) SF KA IR Notes

1. 201005 Rod Control and Information System 7 K1.02 3.5 295037 SCRAM and Reactor Power Above K5.02 3.3 APRM Downscale or Unknown A1.01 3.3 Defeat RCIS Interlocks Per EOP Enclosure EK2.12 3.8 14 EA1.08 3.6 Exam JPM No. CRS-01 (D) (C)
2. 400000 Component Cooling Water System 8 K1.01 3.3 Loss of Normal Service Water creates Alternate CCP Valve Quarterly Stroke Test A4.01 3.0 Path requiring action to Surveillance AK3.07 3.2 allow initiation of Exam JPM No. CRS-02 (N) (A) (S) AA1.01 3.4 Standby Service Water.
3. 223001 Primary Containment and Auxiliaries 5 K1.13 3.5 Failure of RHS-AOV63 creates Alternate Path Makeup to Suppression Pool Using A2.11 3.8 requiring use of HPCS SPC/ADHR for SP makeup.

Exam JPM No. CRS-03 (M) (A) (S)

IN-PLANT SYSTEMS (3 or 2 for SRO-U)

1. 201001 Control Rod Drive Hydraulic System 1 K1.09 3.2 Requires CAA and Primary Containment 295037 SCRAM and Reactor Power Above EK3.07 4.3 entry.

APRM Downscale or Unknown Vent Scram Air Header per EOP Enclosure 11 Exam JPM No. IPS-01 (D) (R)

2. 264000 Emergency Diesel Generators 6 K6.07 3.9 Trip of SWP-P2A creates Alternate Path 295016 Control Room Abandonment AK2.01 4.5 requiring start of SWP-Place Standby Service Water in service for AK2.02 4.1 P2C from different panel Div I EDG from Remote Shutdown Panel (EGS-PNL4C)

Exam JPM No. IPS-02 (D) (A) (L)

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA entry Page 5 of 6 NUREG-1021, Draft Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: ALL (Backup JPM) Operating Test Number: 1 CONTROL ROOM SYSTEMS IN-PLANT SYSTEMS System / JPM Title and No. / (Type Codes*) SF KA IR Notes RO/SRO

1. 223002 Containment Isolation System 5 K1.10 3.1/3.2 500000 High Containment Hydrogen Conc. K4.08 3.3/3.7 Perform emergency containment venting for EK1.01 3.3/3.9 high H2 concentration per EOP Enclosure 21 Exam JPM No. BU-02 (D) (R) (L)
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA entry Page 6 of 6 NUREG-1021, Draft Revision 9

Number: *RJPM-OPS-CRS-01 RIVER Revision: 0 BEND STATION Page 1 of 11 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • DEFEAT RC&IS INTERLOCKS PER EOP ENCLOSURE 14 REASON FOR REVISION:

NRC Exam JPM CR SYSTEMS - 1 PREPARE / REVIEW:

Roger L. Persons 0862 6/10/2004 Preparer KCN Date Erich Weinfurter 1496 6/30/2004 Technical Review (SME) KCN Date Frank McLean 0803 7/13/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-CRS-01 TASK DESCRIPTION: Defeat RC&IS Interlocks per EOP Enclosure 14 TASK

REFERENCE:

200049005001 K/A REFERENCE & RATING: 201005 K1.02, 3.3/3.5 201005 K5.02, 2.8/3.3 201005 A1.01, 3.2/3.3 295037 EK2.12, 3.6/3.8 295037 EA1.08, 3.6/3.6 TESTING METHOD: Simulate Actual Performance X Performance Control Room X Simulator In-Plant COMPLETION TIME: 12 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

SAFETY FUNCTION: 7 RJPM-OPS-CRS-01 Page 2 of 11

RJPM-OPS-CRS-01 SIMULATOR SETUP SHEET Task

Description:

Defeat RC&IS Interlocks per EOP Enclosure 14.

Required Power: N/A IC No.: N/A Notes: This JPM is to be performed in the Control Room.

RJPM-OPS-CRS-01 Page 3 of 11

RJPM-OPS-CRS-01 DATA SHEET References for Development: EOP-0005, Enclosure 14 Required Materials: EOP-0005, Enclosure 14 Required Plant Condition: N/A Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-CRS-01 Page 4 of 11

RJPM-OPS-CRS-01 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

A Reactor SCRAM has occurred and 17 rods have failed to insert, Control Rod Withdraw Blocks and Control Rod Insert Blocks exists.

Initiating Cue:

The CRS directs you to defeat the RC&IS Control Rod Insert Blocks using EOP-0005, Enclosure 14. He informs you that EOP-0005, Enclosure 16, Defeating Containment Instrument Air Isolation Interlocks has already been installed.

RJPM-OPS-CRS-01

  • Denotes Critical Step Page 5 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-01 PERFORMANCE STEP [ENCL Step] STANDARD S/U COMMENTS OBTAIN EOP-0005 ENCL 14 key, ENCL Key obtained. CUE: Key obtained. Once

  • 1.

one (1). [ENCL Step 3.2] Emergency Key Locker has been opened and key identified.

NOTE: Either trip unit, C11-N654A or C11-N654B can be done first.

Location: 1H13-P618 Locking bar is removed. CUE: Locking Bar removed.

  • 2. Affected Trip Unit: C11-N654B, FIRST STAGE TURBINE Note: See Encl 14 Page 4 of 4 for PRESSURE (left column, 2nd row MCR backpanel P618 location.

from top, 1st Unit)

UNLOCK and REMOVE bar.

[ENCL Step 3.2.1.1]

VERIFY center knob is full out. Center knob on CAL Switch is full out. CUE: Center knob is full out.

3.

[ENCL Step 3.2.1.2]

Note: Center knob is located on the CAL Unit CAL Select Switch.

VERIFY TRANSIENT CURRENT TRANSIENT CURRENT Knob is full out. CUE: TRANSIENT CURRENT 4.

Knob is full out. [ENCL Step 3.2.1.3] Knob is full out.

Note: TRANSIENT CURRENT Knob is located on the CAL Unit.

RJPM-OPS-CRS-01

  • Denotes Critical Step Page 6 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-01 PERFORMANCE STEP [ENCL Step] STANDARD S/U COMMENTS VERIFY center knob is rotated fully Center knob is rotated fully counter-clockwise. CUE: Center knob is rotated 5.

counter clockwise. [ENCL Step fully counter-clockwise.

3.2.1.4]

ROTATE center knob 1 click Center knob is in Position 1. CUE: Center knob is in

  • 6.

clockwise to position 1. [ENCL Step Position 1.

3.2.1.5]

TURN power switch to ON. [ENCL Power switch is in the ON position. CUE: Power switch is on.

  • 7.

Step 3.2.1.6]

NOTE: Power switch is located on the CAL Unit.

DEPRESS center knob. [ENCL Step Center knob depressed. CUE: Center knob is depressed.

  • 8.

3.2.1.7]

ROTATE STABLE CURRENT knob STABLE CURRENT Knob fully clockwise and CUE: Stable Current Knob is

  • 9. fully clockwise UNTIL meter on trip trip reset. fully clockwise, trip unit C11-unit is full scale and TRIP is reset. N654B is full scale and red trip

[ENCL Step 3.2.1.8] Red trip light on C11-N654B - OFF light on C11-N654B is OFF.

NOTE: Stable Current Knob is located on CAL Unit.

RJPM-OPS-CRS-01

  • Denotes Critical Step Page 7 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-01 PERFORMANCE STEP [ENCL Step] STANDARD S/U COMMENTS Location: 1H13-P629 Locking bar is removed. CUE: Locking Bar removed.

  • 10. Affected Trip Unit: C11-N654A, FIRST STAGE TURBINE Note: See Encl 14 Page 4 of 4 for PRESSURE (right column, bottom MCR backpanel P629 location.

row, 8th unit)

UNLOCK and REMOVE bar.

[ENCL Step 3.2.1.1]

VERIFY center knob is full out. Center knob on CAL Switch is full out. CUE: Center knob is full out.

11.

[ENCL Step 3.2.1.2]

Note: Center knob is located on the CAL Unit CAL Select Switch.

VERIFY TRANSIENT CURRENT TRANSIENT CURRENT Knob is full out. CUE: TRANSIENT CURRENT 12.

Knob is full out. [ENCL Step 3.2.1.3] Knob is full out.

Note: TRANSIENT CURRENT Knob is located on the CAL Unit.

VERIFY center knob is rotated fully Center knob is rotated fully counter-clockwise. CUE: Center knob is rotated 13.

counter clockwise. [ENCL Step fully counter-clockwise.

3.2.1.4]

ROTATE center knob 8 clicks Center knob is in Position 8. CUE: Center knob is in

  • 14.

clockwise to position 8. [ENCL Step Position 8.

3.2.1.5]

RJPM-OPS-CRS-01

  • Denotes Critical Step Page 8 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-01 PERFORMANCE STEP [ENCL Step] STANDARD S/U COMMENTS TURN power switch to ON. [ENCL Power switch is in the ON position. CUE: Power switch is on.

  • 15.

Step 3.2.1.6]

NOTE: Power switch is located on the CAL Unit.

DEPRESS center knob. [ENCL Step Center knob depressed. CUE: Center knob is depressed.

  • 16.

3.2.1.7]

ROTATE STABLE CURRENT knob STABLE CURRENT Knob fully clockwise and CUE: Stable Current Knob is

  • 17. fully clockwise UNTIL meter on trip trip reset. fully clockwise, trip unit C11-unit is full scale and TRIP is reset. N654A is full scale and red trip

[ENCL Step 3.2.1.8] Red trip light on C11-N654A - OFF light on C11-N654A is OFF.

NOTE: Stable Current Knob is located on CAL Unit.

NOTE: If candidate does not reinstall locking bars, as may be the case if this was being done in an actual emergency, have him/her replace the locking bars at the conclusion of the JPM.

Terminating Cue: RC&IS Control Rod Insert Blocks defeated using EOP-0005, Enclosure 14.

RJPM-OPS-CRS-01

  • Denotes Critical Step Page 9 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-01 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-CRS-01 Page 10of 11

RJPM-OPS-CRS-01 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A Reactor SCRAM has occurred and 17 rods have failed to insert, Control Rod Withdraw Blocks and Control Rod Insert Blocks exists.

Initiating Cues: The CRS directs you to defeat the RC&IS Control Rod Insert Blocks using EOP-0005, Enclosure 14. He informs you that EOP-0005, Enclosure 16, Defeating Containment Instrument Air Isolation Interlocks has already been installed.

RJPM-OPS-CRS-01 Page 11of 11

Number: *RJPM-OPS-CRS-02 RIVER Revision: 0 BEND STATION Page 1 of 12 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • CCP VALVE QUARTERLY STROKE TEST REASON FOR REVISION:

NRC Exam JPM CR SYSTEMS - 2 PREPARE / REVIEW:

Roger L. Persons 0862 6/11/2004 Preparer KCN Date Erich Weinfurter 1497 7/7/2004 Technical Review (SME) KCN Date Frank McLean 0803 7/9/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-CRS-02 TASK DESCRIPTION: CCP Valve Quarterly Stroke Test Surveillance TASK

REFERENCE:

208007001001 277007001001 K/A REFERENCE & RATING: 400000 K1.01, 3.2/3.3 400000 A4.01, 3.1/3.2 295018 AK3.07, 3.1/3.2 295018 AA1.01, 3.3/3.4 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 15 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH Yes (FAULTED):

SAFETY FUNCTION: 8 RJPM-OPS-CRS-02 Page 2 of 12

RJPM-OPS-CRS-02 SIMULATOR SETUP SHEET Task

Description:

CCP Valve Quarterly Stroke Test Surveillance (STP-115-6301).

Required Power: Any IC No.: 168 Notes: Malfunctions to trip of both operating Normal Service Water Pumps are setup to be inserted by Trigger 1. Initiate Trigger 1 when stroke test time has been recorded for CCP-MOV16A, JPM Step 11.

RJPM-OPS-CRS-02 Page 3 of 12

RJPM-OPS-CRS-02 DATA SHEET References for Development: STP-115-6301, Div 1 Reactor Plant Component Cooling Water Quarterly Valve Operability Test Required Materials: STP-115-6301, Div 1 Reactor Plant Component Cooling Water Quarterly Valve Operability Test Stopwatch Required Plant Condition: N/A Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-CRS-02 Page 4 of 12

RJPM-OPS-CRS-02 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The Plant is operating at 12% power with no equipment out of service.

Initiating Cue:

The CRS directs you to complete STP-115-6301, Div 1 Reactor Plant Component Cooling Water Quarterly Valve Operability Test, starting at Step 7.4. Steps 7.1 through 7.3 have been completed by the Reactor Building Operator. The CRS has designated you as the dedicated operator to maintain Div I Standby Service Water System availability during the surveillance testing, per Step 7.4.1.

RJPM-OPS-CRS-02

  • Denotes Critical Step Page 5 of 12

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-02 PERFORMANCE STEP [STP Step] STANDARD S/U COMMENTS Establish a dedicated operator(s) per

1. ADM-0096 in order to maintain Div I Standby Service Water System availability during testing throughout this section. The dedicated operator(s) will establish communications with the Main Control Room to perform the following functions: [STP Step 7.4.1]

In the Main Control Room:

Reviews step and initials step completion Place the SWP-P2A, STBY SVCE WTR PUMP 2A (LOCKOUT)

Switch in RESET upon the Loss of Normal Service Water, Loss of CCP and/or directed by the OSM/CRS.

[STP Step 7.4.1.a]

Place the SWP-P2C, STBY SVCE WTR (LOCKOUT) Switch in RESET upon the Loss of Normal Service Water, Loss of CCP and/or directed by the OSM/CRS [STP Step 7.4.1.b]

RJPM-OPS-CRS-02

  • Denotes Critical Step Page 6 of 12

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-02 PERFORMANCE STEP [STP Step] STANDARD S/U COMMENTS Place the STBY SVCE WTR TEST

1. (DIV 1) to OFF upon the Loss of (contd) Normal Service Water, Loss of CCP and/or directed by the OSM/CRS.

[STP Step 7.4.1.c] Reviews step and initials step completion.

Place the RPCCW DIV 1 TEST to OFF upon the Loss of Normal Service Water, Loss of CCP and/or directed by the OSM/CRS. [STP Step 7.4.1.d]

Prohibit the initiation of Standby RPCCW DIV 1 TEST Switch in TEST position NOTE: Will receive alarm P870-

2. Service Water, isolation of RPCCW, 55A-G04, DIVISION 1 RPCCW and trip of the CRD Pumps, by SYSTEM INOPERATIVE performing the following:

Place RPCCW DIV 1 TEST Switch in TEST. [STP Step 7.4.2]

Place the STBY SVCE WTR TEST STBY SVCE WTR TEST (Div 1) Switch in NOTE: Will receive alarm P870-3.

(Div 1) Switch in TEST. [STP Step TEST position. 55A-H07, DIVISION 1 STBY 7.4.2] SERVICE WTR INOPERATIVE Place SWP-P2A, STBY SVCE WTR SWP-P2A, STBY SVCE WTR PUMP 2A

4. LOCKOUT pushbutton depressed. (P870)

PUMP 2A in LOCKOUT. [STP Step 7.4.2]

RJPM-OPS-CRS-02

  • Denotes Critical Step Page 7 of 12

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-02 PERFORMANCE STEP [STP Step] STANDARD S/U COMMENTS Place SWP-P2C, STBY SVCE WTR SWP-P2C, STBY SVCE WTR PUMP 2C NOTE: Will receive alarm P601-5.

in LOCKOUT [STP Step 7.4.2] LOCKOUT pushbutton depressed. (P601) 18A-B01, DIV 3 STBY SVCE WATER SYSTEM INOPERATIVE Close and time CCP-MOV130, Starts stop watch when control switch moved to

  • 6. LOOP A DN STREAM RETURN close and stops when CCP-MOV130 Closed.

[STP Step 7.4.3]

Green light ON Red light OFF Record closing stroke time, full Closing time for CCP-MOV130 recorded at 28.9

  • 7. stroke exercise result, and valve seconds (+/- 4.3 seconds) acceptance determination for CCP-MOV130 on Data Sheet 1. [STP Step 7.4.4]

Close and time CCP-MOV335, Starts stop watch when control switch moved to

  • 8. LOOP A UP STREAM RETURN. close and stops when CCP-MOV335 Closed.

[STP Step 7.4.5]

Green light ON Red light OFF Record closing stroke time, full Closing time for CCP-MOV335 recorded at 29.6

  • 9. stroke exercise result, and valve seconds (+/- 4.4 seconds) acceptance determination for CCP-MOV335 on Data Sheet 1. [STP Step 7.4.6]

RJPM-OPS-CRS-02

  • Denotes Critical Step Page 8 of 12

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-02 PERFORMANCE STEP [STP Step] STANDARD S/U COMMENTS Close and time CCP-MOV16A, Starts stop watch when control switch moved to

  • 10.

RPCCW LOOP A SUPPLY. [STP close and stops when CCP-MOV16A Closed.

Step 7.4.7]

Green light ON Red light OFF Record closing stroke time, full Closing time for CCP-MOV16A recorded at 29.2 NOTE: ALTERNATE PATH

11. stroke exercise result, and valve seconds (+/- 4.3 seconds) acceptance determination for CCP- NOTE: The following will alarm MOV16A on Data Sheet 1. [STP ~15 seconds apart:

Step 7.4.8]

P870-55A-H04, RPCCW TO DIV 1 EXTREME LOW PRESSURE P870-55A-G07, DIVISION 1 STBY SERVICE WATER LOW PRESSURE P870-55A-D07, DIV 1 STBY SERVICE WTR VALVE MISALIGNMENT Place the SWP-P2A, STBY SVCE SWP-P2A Starts (P870) CUE: As CRS, if candidate

  • 12. WTR PUMP 2A (LOCKOUT) reports loss of NSW, direct Switch in RESET upon the Loss of Green light OFF Red light ON taking action per STP.

Normal Service Water, Loss of CCP and/or directed by the OSM/CRS.

[STP Step 7.4.1.a]

RJPM-OPS-CRS-02

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-02 PERFORMANCE STEP [STP Step] STANDARD S/U COMMENTS Place the SWP-P2C, STBY SVCE SWP-P2C Starts (P601)

  • 13. WTR (LOCKOUT) Switch in RESET upon the Loss of Normal Green light OFF Red light ON Service Water, Loss of CCP and/or directed by the OSM/CRS. [STP Step 7.4.1.b]

Place the STBY SVCE WTR TEST Normal Service Water Isolation Valves SWP-

  • 14. (DIV 1) to OFF upon the Loss of MOV57A and SWP-MOV96A Close (P870)

Normal Service Water, Loss of CCP and/or directed by the OSM/CRS. Green light ON Red light OFF

[STP Step 7.4.1.c]

Standby Cooling Tower Inlet SWP-MOV55A opens Green light OFF Red light ON Place the RPCCW DIV 1 TEST to NOTE: No valves should

15. OFF upon the Loss of Normal reposition when this switch is Service Water, Loss of CCP and/or removed from TEST because the directed by the OSM/CRS. [STP Step vital loop isolation valves were 7.4.1.d] closed as part of the STP.

Terminating Cue: Div I Standby Service Pumps SWP-P2A and SWP-P2C operating with NSW supply and return valves closed.

RJPM-OPS-CRS-02

  • Denotes Critical Step Page 10 of 12

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-02 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-CRS-02 Page 11of 12

RJPM-OPS-CRS-02 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The Plant is operating at rated conditions with no equipment out of service.

Initiating Cues: The CRS directs you to complete STP-115-6301, Div 1 Reactor Plant Component Cooling Water Quarterly Valve Operability Test, starting at Step 7.4.

Steps 7.1 through 7.3 have been completed by the Reactor Building Operator.

The CRS has designated you as the dedicated operator to maintain Div I Standby Service Water System availability during the surveillance testing, per Step 7.4.1 RJPM-OPS-CRS-02 Page 12of 12

Number: *RJPM-OPS-CRS-03 RIVER Revision: 1 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • SUPPRESSION POOL MAKEUP, EOP ENLCOSURE 30 USING SPC/ADHR REASON FOR REVISION:

NRC Exam JPM CR SYSTEMS - 3 PREPARE / REVIEW:

Roger L. Persons 0862 7/9/2004 Preparer KCN Date Erich Weinfurter 1497 7/9/2004 Technical Review (SME) KCN Date Frank McLean 0803 7/9/2004 Training Supervisor KCN Date

  • Indexing Information

RJPM-OPS-CRS-03 TASK DESCRIPTION: Suppression Pool Makeup per EOP-0005, Enclosure 30 TASK

REFERENCE:

200017005002 K/A REFERENCE & RATING: 223001 K1.13, 3.4/3.5 223001 A2.11, 3.6/3.8 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 15 min.

MAX TIME: N/A JOB LEVEL: All TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH Yes (FAULTED):

SAFETY FUNCTION: 8 RJPM-OPS-CRS-03 Page 2 of 9

RJPM-OPS-CRS-03 SIMULATOR SETUP SHEET Task

Description:

Suppression Pool Makeup per EOP-0005, Enclosure 30.

Required Power: Any IC No.: 162 Notes: Insert Override to close RHS-AOV63 to occur when valve reaches OPEN position.

RJPM-OPS-CRS-03 Page 3 of 9

RJPM-OPS-CRS-03 DATA SHEET References for Development: EOP-0005, Enclosure 30, Suppression Pool Makeup Required Materials: EOP-0005, Enclosure 30, Suppression Pool Makeup Required Plant Condition: N/A Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-CRS-03 Page 4 of 9

RJPM-OPS-CRS-03 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The Plant is operating at rated conditions with RCIC out of service. Suppression Pool level has lowered to 18 feet.

Initiating Cue:

The CRS directs you to raise Suppression Pool water level using SPC/ADHR per EOP-0005, Enclosure 30.

RJPM-OPS-CRS-03

  • Denotes Critical Step Page 5 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-03 PERFORMANCE STEP [Encl Step] STANDARD S/U COMMENTS Obtain copy of EOP-0005, Enclosure Enclosures are located in drawer

1. 30. to the left of the DRMS Monitor.

VERIFY E12-F105, RHR PUMP C Verifies E12-F105, RHR PUMP C SUP PL 2.

SUP PL SUCTION VALVE is open SUCTION VALVE is open.

(1H13-P601) [SPC/ADHR Step 1]

Green light OFF Red light ON VERIFY open RHS-AOV62, SPC Places RHS-AOV62, SPC SUCTION VALVE

  • 3. SUCTION VALVE (1H13-P601) control switch to OPEN.

[SPC/ADHR Step 2]

Green light OFF Red light ON VERIFY open RHS-AOV63, SPC Places RHS-AOV63, SPC SUCTION VALVE NOTE: ALTERNATE PATH

  • 4. SUCTION VALVE (1H13-P601) control switch to OPEN.

[SPC/ADHR Step 3] RHS-AOV63 recloses when it Green light OFF Red light ON reaches full open and cannot be reopened.

Reports failure of RHS-AOV63 to CUE: As CRS, acknowledge

5. remain open and informs CRS. failure of AOV63 and direct using HPCS.

RJPM-OPS-CRS-03

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-03 PERFORMANCE STEP [Encl Step] STANDARD S/U COMMENTS VERIFY HPCS pump suction is Verifies E22-MOVF001, HPCS CST SUCTION 4.

aligned to the CST. [HPCS Step1] VALVE is open.

Green light OFF Red light ON Verifies E22-MOVF015, HPCS SP SUCTION VALVE is closed.

Green light ON Red light OFF START the HPCS pump. (1H13- Places HPCS control switch to START

  • 5. P601)

Green light OFF Red light ON VERIFY HPCS pump motor current is less than or equal to 350 amps Pump current verified <350 amps

[HPCS Step2.a]

VERIFY OPEN E22-F012 HPCS Verifies E22-F012 open. CUE: As CRS, additional

6. MIN FLOW VALVE TO makeup is NOT reqired.

SUPPRESSION POOL. (1H13-P601) Green light OFF Red light ON

[HPCS Step2.b]

Terminating Cue: HPCS operating with minimum flow open transferring water to the Suppression Pool from the CST.

RJPM-OPS-CRS-03

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-03 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-CRS-03 Page 8of 9

RJPM-OPS-CRS-03 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The Plant is operating at rated conditions with RCIC out of service.

Suppression Pool level has lowered to 18 feet.

Initiating Cues: The CRS directs you to raise Suppression Pool water level using SPC/ADHR per EOP-0005, Enclosure 30.

RJPM-OPS-CRS-03 Page 9of 9

Number: *RJPM-OPS-CRS-04 RIVER Revision: 1 BEND STATION Page 1 of 11 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • PLACE FWREG VALVE C IN MANUAL WITH STARTUP LEVEL CONTROL VALVE IN AUTO REASON FOR REVISION:

NRC Exam JPM CR SYSTEMS - 4 PREPARE / REVIEW:

Erich Weinfurter 1497 6/29/2004 Preparer KCN Date Roger Persons 0862 7/7/2004 Technical Review (SME) KCN Date Frank McLean 0803 7/9/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-CRS-04 TASK DESCRIPTION: Place FWREG Valve C In Manual With Startup Level Control Valve In Auto TASK

REFERENCE:

259013001001 K/A REFERENCE & RATING: 259002 K5.01, 3.1/3.1 259002 A1.05, 2.9/2.9 259002 A4.03, 3.8/3.6 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 15 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH Yes (FAULTED):

RJPM-OPS-CRS-04 Page 2 of 11

RJPM-OPS-CRS-04 SIMULATOR SETUP SHEET Task

Description:

Place FWREG Valve C In Manual With Startup Level Control Valve In Auto.

Required Power: 12%

IC No.: IC-168 Notes: Malfunction on FWREG Valve is initiated in IC-168.

RJPM-OPS-CRS-04 Page 3 of 11

RJPM-OPS-CRS-04 DATA SHEET References for Development: SOP-0009, Reactor Feedwater System Required Materials: SOP-0009, Reactor Feedwater System Required Plant Condition: Plant at approximately 10% power with Startup Feedwater Level Controller in Automatic Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: 007, Manual Control of Feedwater Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-CRS-04 Page 4 of 11

RJPM-OPS-CRS-04 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is operating at approximately 12% power with Startup Feedwater Level Controller in Automatic.

Initiating Cue:

The CRS has directed you to place FWREG Valve C in manual with the Startup Level Control Valve in Auto in accordance with SOP-0009, Section 4.8, Reactor Feedwater System. An SNEO is stationed at the valve.

RJPM-OPS-CRS-04

  • Denotes Critical Step Page 5 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-04 PERFORMANCE STEP [SOP Step] STANDARD S/U COMMENTS Verify C33-R602A, FWREG VALVE Controller verified to be in MANUAL and set at C FLOW CONTROLLER in 0%.

1.

MANUAL and set at 0%. [SOP Step 4.8.1]

Verify the bias thumbwheel on Bias thumbwheels set at 50.

C33-R601A, FWREG VALVE A FLOW CONTROLLER and 2.

C33-R602A, FWREG VALVE C FLOW CONTROLLER set at 50.

[SOP Step 4.8.2]

Verify C33-R600, FWREG VALVES Master FRV controller verified in manual at 0%.

MASTER FLOW CONTROLLER in 3.

MANUAL set at 0%. [SOP Step 4.8.3]

Place C33-R602A, FWREG VALVE Controller is placed in AUTO.

  • 4. FLOW CONTROLLER C in AUTO.

[SOP Step 4.8.4] Green light ON Amber light OFF Verify FWS-MOV27C, FW REG FWS-MOV27C closed.

5. VLV C INLET is closed. [SOP Step 4.8.5] Green light ON Red light OFF RJPM-OPS-CRS-04
  • Denotes Critical Step Page 6 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-04 PERFORMANCE STEP [SOP Step] STANDARD S/U COMMENTS Test stroke C33-LVF001C, FWREG Operator is stationed locally for observation of CUE: If contacted by Gaitronics VAVLE C as follows: the valve during stroking. respond as Turbine Building Operater stationed locally to

6. Station an operator locally at the valve observe valve movement and to verify proper valve movement and position during stroking.

position. [SOP Step 4.8.6.1]

Use the OPEN and CLOSE Recognizes and reports to the CRS that C33- NOTE: ALTERNATE PATH Pushbuttons on C33-R600, FW REG LVF001C could not be stroked.

VALVES MASTER FLOW CUE: As Turbine Building CONTROLLER to stroke open and Amber light ON above C33-LVF001C position Operator, inform the candidate closed C33-LVF001C [SOP Step indication that the valve did not move.

4.8.6.2] Valve appears to be bound or stuck.

Check proper valve movement and

  • 7. smooth operations. [SOP Step 4.8.6.3] CUE: As CRS direct placing the A FWREG valve in service. You Check C33-LVF001A full closed. will notify I&C to investigate the

[SOP Step 4.8.6.4] failure of the C FRV.

NOTE: May Place C33-R601C, FWREG VALVE FLOW CONTROLLER C back in MANUAL.

Verify C33-R601A, FWREG VALVE Controller verified to be in MANUAL and set at A FLOW CONTROLLER in 0%.

8.

MANUAL and set at 0%. [SOP Step 4.8.1]

RJPM-OPS-CRS-04

  • Denotes Critical Step Page 7 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-04 PERFORMANCE STEP [SOP Step] STANDARD S/U COMMENTS Verify the bias thumbwheel on Bias thumbwheels set at 50.

C33-R601A, FWREG VALVE A FLOW CONTROLLER and 9.

C33-R602A, FWREG VALVE C FLOW CONTROLLER set at 50.

[SOP Step 4.8.2]

Verify C33-R600, FWREG VALVES Master FRV controller verified in manual at 0%.

MASTER FLOW CONTROLLER in 10 MANUAL set at 0%. [SOP Step 4.8.3]

Place C33-R601A, FWREG VALVE Controller is placed in AUTO.

  • 11. FLOW CONTROLLER A in AUTO.

[SOP Step 4.8.4] Green light ON Amber light OFF Verify FWS-MOV27A, FW REG FWS-MOV27A closed.

12. VLV A INLET is closed. [SOP Step 4.8.5] Green light ON Red light OFF Test stroke C33-LVF001A, FWREG Operator is stationed locally for observation of CUE: If contacted by Gaitronics VAVLE A as follows: the valve during stroking. respond as Turbine Building Operater stationed locally at
13. Station an operator locally at the valve C33-LVF001A to observe valve to verify proper valve movement and movement and position during position. [SOP Step 4.8.6.1] stroking.

RJPM-OPS-CRS-04

  • Denotes Critical Step Page 8 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-04 PERFORMANCE STEP [SOP Step] STANDARD S/U COMMENTS Use the OPEN and CLOSE Uses OPEN and CLOSE Pushbuttons on C33- CUE: As Turbine Building Pushbuttons on C33-R600, FW REG R600 to fully open and reclose C33-LVF001A Operator, inform the candidate VALVES MASTER FLOW per valve position meter above control for FWS- that the valve moved from full CONTROLLER to stroke open and MOV27A. closed to full open and back to closed C33-LVF001A [SOP Step full closed. Valve operation was Verifies Building Operator observation of proper

14. 4.8.6.2] smooth.

valve movement locally.

Check proper valve movement and smooth operations. [SOP Step 4.8.6.3]

Check C33-LVF001A full closed.

[SOP Step 4.8.6.4]

Open FWS-MOV27A, FW REG VLV FWS-MOV27A open.

  • 15. A INLET is closed. [SOP Step 4.8.6.5] Green light OFF Red light ON Use the manual pushbuttons on C33- C33-LVF001C, FWREG VALVE C open and R600, FW REG VALVES MASTER START UP FWREG VALVE position greater CONTROLLER to open than 20 and less than 50% open.

C33-LVF001A, FWREG VALVE A

  • 16 and then maintain C33-LVF002, START UP FWREG VALVE position greater than 20 and less than 50%

open. [SOP Step 4.8.7]

Terminating Cue: RPV level is being maintained automatically by the Startup Level Controller with the A FWREG valve in AUTO and the Master Level Controller is in MANUAL.

RJPM-OPS-CRS-04

  • Denotes Critical Step Page 9 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-04 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-CRS-04 Page 10 of 11

RJPM-OPS-CRS-04 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is operating at approximately 12% power with Startup Feedwater Level Controller in Automatic.

Initiating Cues: The CRS has directed you to place FWREG Valve C in manual with the Startup Level Control Valve in Auto in accordance with SOP-0009, Section 4.8, Reactor Feedwater System.

An SNEO is stationed at the valve.

RJPM-OPS-CRS-04 Page 11 of 11

Number: *RJPM-OPS-CRS-05 RIVER Revision: 3 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • BYPASS MSR STEAM SUPPLY VALVES INTERLOCK PER EOP ENCLOSURE 5 REASON FOR REVISION:

NRC Exam JPM CR SYSTEMS - 5 PREPARE / REVIEW:

Roger Persons 0862 7/13/2004 Preparer KCN Date Erich Weinfurter 1497 7/13/2004 Technical Review (SME) KCN Date Frank McLean 0803 7/13/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-CRS-05 TASK DESCRIPTION: Bypass MSR Steam Supply Valves Interlock Per EOP Enclosure 5 TASK

REFERENCE:

200005005004 K/A REFERENCE & RATING: 239001 K1.01, 3.4/3.4 239001 K1.01, 2.8/2.8 TESTING METHOD: Simulate Actual Performance X Performance Control Room X Simulator In-Plant COMPLETION TIME: 11 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-OPS-CRS-05 Page 2 of 9

RJPM-OPS-CRS-05 SIMULATOR SETUP SHEET Task

Description:

Bypass MSR Steam Supply Valves Interlock Per EOP Enclosure 5 Required Power: N/A IC No.: N/A Notes: This JPM will be simulated in the Main Control Room.

RJPM-OPS-CRS-05 Page 3 of 9

RJPM-OPS-CRS-05 DATA SHEET References for Development: EOP-0005, Enclosure 5 Required Materials: EOP-0005, Enclosure 5 Required Plant Condition: A scram has occurred following extended high power operations. EOP-0001 and EOP-0002 are being executed. A malfunction in the turbine bypass valves and high suppression pool temperature require use of alternate pressure control methods.

Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: None Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-CRS-05 Page 4 of 9

RJPM-OPS-CRS-05 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

A scram has occurred following extended high power operations. EOP-0001 and EOP-0002 are being executed. A malfunction in the turbine bypass valves and high suppression pool temperature require use of alternate pressure control methods.

Initiating Cue:

The CRS has directed you to install EOP-0005, Enclosure 5 Defeating MSR Steam Supply Valves Interlock.

RJPM-OPS-CRS-05 Page 5 of 9

RJPM-OPS-CRS-05 PERFORMANCE STEP [ENCL Step] STANDARD S/U COMMENTS OBTAIN EOP-0005 ENCL 5 jumper EOP-0005 ENCL 5 jumper Kit No. 5 obtained NOTE: Have candidate return

1. kit from the Control Room Emergency from Control Room Emergency Locker jumper kit to Emergency Locker Locker. [ENCL Step 3.1] once identified and inventoried.

Inspect kit for 2 jumpers. [ENCL Step Two jumpers located in Jumper Kit No 5. NOTE: Controls and indications

2. 3.1.1] for MSRs are located on H13-P870, Insert 52 Verify MSS-MOV111, MSR 1 STM MSS-MOV111 in CLOSE Position CUE: MSS-MOV111 Green SPLY SHUTOFF AND, MSS- light is on and red light is off MOV112, MSR 2 STM SPLY Green light ON Red light OFF SHUTOFF Control Switches are in NOTE: With the plant at power
3. MSS-MOV112 in CLOSE Position CLOSE. [ENCL Step 3.2] these valves should indicate open.

Green light ON Red light OFF CUE: MSS-MOV112 Green light is on and red light is off Location: 1H13-P869 Bay D Locates H13-P869 Bay D and identifies relay NOTE: Relay is labeled 63B-63B-1MSSN17 and describes squeezing upper 1MSSN17 and is in left row of Affected relay: 63B-1MSSN17 and lower cover latches to remove relay. agastat relays, 8th relay from top (Left row of agastat relays, 8th relay

  • 4.

from top) CUE: Relay 63B-1MSSN17 removed REMOVE relay 63B-1MSSN17

[ENCL Step 3.3.1]

Jumper No. 1 [ENCL Step 3.1.2] Identifies terminals to install Jumper No. 1 CUE: Jumper No. 1 installed

  • 5. JUMPER Terminal M3 on Relay NOTE: Enclosure 5 contains Block 63B-1MSSN17 to Terminal R3 sketch of relay terminals for on Relay Block 63B-1MSSN17 reference.

RJPM-OPS-CRS-05 Page 6 of 9

RJPM-OPS-CRS-05 PERFORMANCE STEP [ENCL Step] STANDARD S/U COMMENTS Jumper No. 2 [ENCL Step 3.1.3] Identifies terminals to install Jumper No. 2 CUE: Jumper No. 2 installed

  • 6. JUMPER Terminal M4 on Relay Block 63B-1MSSN17 to Terminal R4 on Relay Block 63B-1MSSN17 OPEN MSS-MOV111, MSR 1 STM Places MSS-MOV111 control switch to OPEN CUE: As CRS, direct opening SPLY SHUTOFF AND, MSS- Position both MSS-MOV111 and 112.

MOV112, MSR 2 STM SPLY SHUTOFF as directed by the CRS. Green light OFF Red light ON

  • 7. [ENCL Step 3.4]

Places MSS-MOV112 control switch to OPEN Position Green light OFF Red light ON Terminating Cue: EOP-0005, Enclosure 5 installed and both MSR Steam Supply Shutoff Valves open.

RJPM-OPS-CRS-05 Page 7 of 9

RJPM-OPS-CRS-05 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-CRS-05 Page 8 of 9

RJPM-OPS-CRS-05 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A scram has occurred following extended high power operations.

EOP-0001 and EOP-0002 are being executed.

A malfunction in the turbine bypass valves and high suppression pool temperature require use of alternate pressure control methods.

Initiating Cues: The CRS has directed you to install EOP-0005, Enclosure 5 Defeating MSR Steam Supply Valves Interlock.

RJPM-OPS-CRS-05 Page 9 of 9

Number: *RJPM-OPS-CRS-06 RIVER Revision: 0 BEND STATION Page 1 of 13 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • RESTORE FUEL BUILDING FILTRATION SYSTEM TO STANDBY FOLLOWING AN AUTOMATIC INITIATION REASON FOR REVISION:

NRC Exam JPM CR SYSTEMS - 6 PREPARE / REVIEW:

Erich Weinfurter 1497 7/1/2004 Preparer KCN Date Roger Persons 0988 7/7/2004 Technical Review (SME) KCN Date Frank McLean 0803 7/9/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-CRS-06 TASK DESCRIPTION: Restore Fuel Building Filtration System to Standby following an Automatic Initiation TASK

REFERENCE:

289008001001 K/A REFERENCE & RATING: 288000 K4.03, 2.8/2.9 288000 A2.01, 3.3/2.4 288000 A4.01, 3.1/2.9 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 12 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-OPS-CRS-06 Page 2 of 13

RJPM-OPS-CRS-06 SIMULATOR SETUP SHEET Task

Description:

Restore Fuel Building Filtration System to Standby following an Automatic Initiation Required Power: NA IC No.: IC-162 Notes:

RJPM-OPS-CRS-06 Page 3 of 13

RJPM-OPS-CRS-06 DATA SHEET References for Development: SOP-0062, Fuel Building Ventilation Required Materials: SOP-0062, Fuel Building Ventilation Required Plant Condition: N/A Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-CRS-06 Page 4 of 13

RJPM-OPS-CRS-06 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The Division I Fuel Building Ventilation Filter Train received an automatic initiation signal from an I&C Surveillance. All conditions are normal and I&C has corrected the problem.

Initiating Cue:

The Control Room Supervisor has directed you to restore the Fuel Building Ventilation System to standby, per SOP-0062. The prerequisites have been verified complete.

RJPM-OPS-CRS-06

  • Denotes Critical Step Page 5 of 13

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-06 PERFORMANCE STEP [SOP Step] STANDARD S/U COMMENTS Verify all initiation and isolation Observes that No LOCA or Fuel Building NOTE: Candidate should use signals have been reset [SOP Step Ventilation Exhaust radiation high-high signals SOP-0062, Section 5.7.

5.7.1] present.

1.

CUE: If candidate asks, NO fuel movement is in progress in the Fuel Building (P&L 2.2)

Verify only one HVF-FN3A or B, Observes that only Division 1 Fuel Building

2. EXH FLTR TRAIN is running [SOP Exhaust Filter Train is operating.

Step 5.7.3]

IF DIVISION 1 and 2 RADIATION Neither switch in OVERRIDE. NOTE: Override Switches were OVERRIDE Switches were utilized to not used.

override a High-High Radiation signal for Refuel Mode Operation, THEN place the following in NORM: [SOP

3. Step 5.7.3]

DIVISION 1 RADIATION OVERRIDE DIVISION 2 RADIATION OVERRIDE RJPM-OPS-CRS-06

  • Denotes Critical Step Page 6 of 13

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-06 PERFORMANCE STEP [SOP Step] STANDARD S/U COMMENTS Opens HVF-AOD102 and HVF-AOD104 NOTE: Only HVFAOD102 and Verify open the following dampers:

[SOP Step 5.7.4] HVF-AOD104 are critical actions Green light OFF Red light ON for this step, the remaining

  • HVF-AOD102, FUEL BLDG dampers listed in this step are EXH FAN INLT already open.

Verifies that all other listed dampers are open

  • HVF-AOD112, FUEL BLDG EXH FAN INLT Green light OFF Red light ON
  • HVF-AOD104, FUEL BLDG
  • HVF-AOD137, FUEL BLDG EXH ISOL
  • HVF-AOD101, FUEL BLDG AIR SPLY ISOL
  • HVF-AOD122, FUEL BLDG AIR SPLY ISOL RJPM-OPS-CRS-06
  • Denotes Critical Step Page 7 of 13

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-06 PERFORMANCE STEP [SOP Step] STANDARD S/U COMMENTS Verifies one fan operating.

IF no Fuel Building Supply Fan is running, THEN start one of the Green light OFF Red light ON following fans: [SOP Step 5.7.5]

5.
  • HVF-ACU1 FN1A, FUEL BLDG SPLY FAN A
  • HVF-ACU1 FN1B, FUEL BLDG SPLY FAN B Check associated HVF-AOD13A(B), HVF-AOD13A(B) damper open for fan operating
5. FUEL BLDG SPLY FAN A(B)

DISCH opens [SOP Step 5.7.6] Green light OFF Red light ON Stop the running HVF-FN3A(B), Places HVF-FN3A fan control switch to STOP.

  • 6. EXH FLTR TRAIN. [SOP Step 5.7.7]

Green light ON Red light OFF RJPM-OPS-CRS-06

  • Denotes Critical Step Page 8 of 13

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-06 PERFORMANCE STEP [SOP Step] STANDARD S/U COMMENTS Verify the following: [SOP Step 5.7.8] All listed dampers are open

  • Associated HVF-AOD20A(B), Green light OFF Red light ON FILTER 2A(B) INLET is closed.
  • Associated HVF-AOD31A(B),

FAN 3A(B) DISCH is closed. HVF-FN7A is running

  • Associated HVF-FN7A(B), FLT Green light OFF Red light ON 2A(B) DECAY HEAT
7. REMOVAL is running.
  • Associated HVF-AOD3A(B),

DECAY HEAT REMOVAL INLET is open.

  • Associated HVF-AOD33A(B),

DECAY HEAT REMOVAL DISCH is open.

Start one HVF-FN8A(B), FUEL Places HVF-FN8A(B) fan control switch to BLDG EXH FAN A(B) [SOP Step START and verifies fan started

  • 8.

5.7.9]

Green light OFF Red light ON Check associated HVF-AOD6A(B), HVF-AOD6A(B) damper open FUEL BLDG EXH FAN A(B) DISCH

9. opens. [SOP Step 5.7.10] Green light OFF Red light ON RJPM-OPS-CRS-06
  • Denotes Critical Step Page 9 of 13

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-06 PERFORMANCE STEP [SOP Step] STANDARD S/U COMMENTS Place the non-running HVF-FN8B(A), Places HVF-FN8A(B) fan control switch to FUEL BLDG EXH FAN B(A) in AUTO 10 AUTO. [SOP Step 5.7.11]

WHEN system flow has stabilized, Places HVF-FN3A(B) fan control switch to THEN place the stopped HVF- AUTO FN3A(B) EXH FLTR TRAIN in

  • 11 AUTO. [SOP Step 5.7.12]

Verify closed HVF-AOD37A, FUEL Closes HVF-AOD37A and B BLDG ALT AIR SUPPLY and Green light ON Red light OFF

  • 12 HVF-AOD37B, FUEL BLDG ALT AIR SUPPLY. [SOP Step 5.7.13]

RJPM-OPS-CRS-06

  • Denotes Critical Step Page 10 of 13

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-06 PERFORMANCE STEP [SOP Step] STANDARD S/U COMMENTS Places HVF-FN7A(B) fan control switch to CUE: CRS directs securing the WHEN 30 minutes has elapsed, OR at decay heat removal fan now.

STOP, verifies that the fan stops.

the discretion of the OSM/CRS, THEN perform the following: [SOP Green light ON Red light OFF Step 5.7.143]

  • Stop the running HVF-FN7A(B),

FLT 2A(B) DECAY HEAT Listed dampers are closed REMOVAL fan.

Green light ON Red light OFF

  • 13
  • Check associated HVF-AOD3A(B),

DECAY HEAT REMOVAL INLET closes.

Places HVF-FN7A(B) fan control switch to AUTO

  • Return the stopped HVF-FN7A(B),

FLT 2A(B) DECAY HEAT REMOVAL fan to AUTO.

Operator Contacts Reactor Building operator for CUE: Reactor Building At FB 148 el., check Fuel Building Differential pressure reading. Operator reports that Fuel pressure is greater than or equal to Building pressure on HVF-0.104 Water Gauge (WG) on HVF- PDI103 is 0.125 water gauge 14 PDI103, FUEL BLDG PRESSURE MONITOR DIFFERENTIAL PRESSURE INDICATOR. [SOP Step 5.7.15]

Terminating Cue: The Fuel Building Ventilation System has been restored to Standby.

RJPM-OPS-CRS-06

  • Denotes Critical Step Page 11 of 13

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-06 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-CRS-06 Page 12 of 13

RJPM-OPS-CRS-06 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The Division I Fuel Building Ventilation Filter Train received an automatic initiation signal from an I&C Surveillance. All conditions are normal and I&C has corrected the problem.

Initiating Cues: The Control Room Supervisor has directed you to restore the Fuel Building Ventilation System to standby, per SOP-0062. The prerequisites have been verified complete.

RJPM-OPS-CRS-06 Page 13 of 13

Number: *RJPM-OPS-CRS-07 RIVER Revision: 1 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • PARALLEL OFFSITE POWER WITH DIVISION II EDG SUPPLYING ENS-SWG1B REASON FOR REVISION:

NRC Exam JPM CR SYSTEMS - 7 PREPARE / REVIEW:

Erich Weinfurter 1497 6/29/2004 Preparer KCN Date Roger Persons 0862 7/6/2004 Technical Review (SME) KCN Date Frank McLean 0803 7/9/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-CRS-07 TASK DESCRIPTION: Parallel Offsite Power With Div 2 EDG Supplying ENS-SWG1B.

TASK

REFERENCE:

264009001001 K/A REFERENCE & RATING: 264000 A2.01, 3.5/3.6 264000 A2.05, 3.6/3.6 264000 A4.02, 3.4/3.4 295003 AA1.02, 4.2/4.3 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 10 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: Yes ALTERNATE PATH Yes (FAULTED):

RJPM-OPS-CRS-07 Page 2 of 10

RJPM-OPS-CRS-07 SIMULATOR SETUP SHEET Task

Description:

Parallel Offsite Power With Div 2 EDG Supplying ENS-SWG1B Required Power: Cold Shutdown following a Loss of Offsite Power IC No.: 162 Notes:

The simulator will be setup with the plant shutdown. The P877 panel configuration is consistent with expected conditions for performance of this JPM as the final step in recovering Offsite Power. ENS-SWG1A has been returned to normal lineup and Div I EDG has been shutdown.

RJPM-OPS-CRS-07 Page 3 of 10

RJPM-OPS-CRS-07 DATA SHEET References for Development: AOP-0004, Loss of Offsite Power SOP-0053, Standby Diesel Generator and Auxiliaries Required Materials: SOP-0053, Standby Diesel Generator and Auxiliaries Required Plant Condition: Following LOP Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-CRS-07 Page 4 of 10

RJPM-OPS-CRS-07 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

A Loss of Offsite Power has occurred with the plant in cold shutdown. AOP-0004, Loss of Offsite Power was entered and all required actions taken. Plant conditions are stable and Offsite power is being restored to the plant per AOP-0004, Section 5.16. AOP-0004 has been completed through Step 5.16.11.

Initiating Cue:

The CRS has directed you to parallel Offsite Power to the ENS-SWG1B per SOP-0053 using the normal supply breaker ACB26.

RJPM-OPS-CRS-07

  • Denotes Critical Step Page 5 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-07 PERFORMANCE STEP [SOP/ARP Step] STANDARD S/U COMMENTS IF ENS-ACB06(26), NORMAL REMOTE SYNC SW to NORM. SOP-0053, Section 5.1 SUPPLY BRKR is to be closed,

  • 1. THEN place the REMOTE SYNC SW to NORM. [SOP Step 5.1.1]

Adjust diesel voltage, as observed on RUNNING VOLTAGE to approximately 1- 2 V-1RUN-1SYDA(B)01, RUNNING volts above V-1IN-1SYDA(B)01, INCOMING VOLTAGE to approximately 1- 2 VOLTAGE.

volts above V-1IN-1SYDA(B)01,

2. INCOMING VOLTAGE using the STBY DIESEL GENERATOR A(B)

VOLTAGE REGULATOR CONT.

[SOP Step 5.1.3]

Adjust diesel speed, using the STBY SYNCHROSCOPE indicator is rotating slowly in DIESEL GENERATOR A(B) the SLOW direction.

GOVERNOR CONTROL, to bring the frequency within the range of grid frequency. Adjust speed so the SY SYDA(B)01, STBY BUS A(B)

  • 3. SYNCHROSCOPE indicator is rotating slowly in the SLOW direction (counterclockwise)at a rate of one revolution in greater than or equal to 4 seconds and less than or equal to 6 seconds. [SOP Step 5.1.4]

RJPM-OPS-CRS-07

  • Denotes Critical Step Page 6 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-07 PERFORMANCE STEP [SOP/ARP Step] STANDARD S/U COMMENTS WHEN the synchroscope indicator is NORMAL SUPPLY BRKR closed. NOTE: ALTERNATE PATH moving slowly in the SLOW direction RED light ON AND the synchroscope indicator is 5 NOTE: Annunciator for minutes to 2 minutes before the 12 GREEN light OFF STANDBY DIESEL GEN B o'clock position, THEN close the BACKUP PROT ACTIVATED desired feeder breaker, ENS- will alarm at this time.

  • 4. ACB06(26), NORMAL SUPPLY BRKR or ENS-ACB04(24),

ALTERNATE SUPPLY BRKR.

Verify the red breaker closed light comes ON. If not, return the breaker handswitch to TRIP. [SOP Step 5.1.5]

Acknowledges alarm, informs CRS, Alarm acknowledged and CRS informed. CUE: Direct Candidate to

5. and refers to ARP-P877-32A-H02. complete ARP Operator Actions Section.

Trips ENS-ACB31, STBY D/G B Opens ENS-ACB31, STBY D/G B NEUTRAL NOTE: Candidate must NEUTRAL BRKR. [ARP Step 2.b.1] BRKR determine from initial conditions that EDG is operating in

6. Emergency Mode and Neutral RED light OFF Breaker should have tripped per GREEN light ON ARP.

RJPM-OPS-CRS-07

  • Denotes Critical Step Page 7 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-07 PERFORMANCE STEP [SOP/ARP Step] STANDARD S/U COMMENTS Reduce load with the STBY DIESEL Reduces load to ~175 Kw CUE: As CRS, the Div 2 EDG is GENERATOR A(B) GOVERNOR no longer required. Rapidly CONTROL to approximately 175 Kw, unload and shutdown the EDG per and reactive load to no less than 0 SOP-0053.

  • 7. KVAR using the STBY DIESEL GENERATOR A(B) VOLTAGE REGULATOR CONT. Allow diesel cylinder temperatures to stabilize.

[SOP Step 6.1.1]

Trip ENS-ACB27, STBY D/G B Trips ENS-ACB27, STBY D/G B OUTPUT CUE: As CRS, if requested, Step OUTPUT BRKR. [SOP Step 6.1.2] BRKR 6.1.3 to adjust EDG frequency to 60 Hz may be NAd.

  • 8.

RED light OFF GREEN light ON Depress the STBY DIESEL ENGINE Depresses STBY DIESEL ENGINE B CUE: After candidate depresses A(B) EMERGENCY START RESET EMERGENCY START RESET pushbutton EMERGENCY START RESET

  • 9. pushbutton on H13-P877. Div 2 EDG pushbutton, state that the Div 2

[SOP Step 6.1.4] EDG has now run unloaded for 2 minutes.

Allow the diesel to run unloaded for Depresses both STBY DIESEL ENGINE B CUE: JPM is terminated, another approximately 2 minutes, then depress STOP pushbuttons simultaneously. operator will complete the EDG

  • 10. both STBY DIESEL ENGINE A(B) shutdown.

STOP pushbuttons simultaneously

[SOP Step 6.1.5]

Terminating Cue: Offsite Power supplying ENS-SWG1B and the Div II Emergency Diesel shutdown.

RJPM-OPS-CRS-07

  • Denotes Critical Step Page 8 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-07 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-CRS-07 Page 9 of 10

RJPM-OPS-CRS-07 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A Loss of Offsite Power has occurred with the plant in cold shutdown.

AOP-0004, Loss of Offsite Power was entered and all required actions taken. Plant conditions are stable and Offsite power is being restored to the plant per AOP-0004, Section 5.16. AOP-0004 has been completed through Step 5.16.11.

Initiating Cues: The CRS has directed you to parallel Offsite Power to the ENS-SWG1B per SOP-0053 using the normal supply breaker ACB26.

RJPM-OPS-CRS-07 Page 10 of 10

Number: *RJPM-OPS-CRS-08 RIVER Revision: 2 BEND STATION Page 1 of 11 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

NRC Exam JPM CR SYSTEMS - 8 PREPARE / REVIEW:

Erich Weinfurter 1497 6/29/2004 Preparer KCN Date Roger Persons 0862 7/9/2004 Technical Review (SME) KCN Date Tom Naylor 0803 9/7/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-CRS-08 TASK DESCRIPTION: Perform Control Rod Operability Check With Rod Over-Travel TASK

REFERENCE:

201024001001 201001002001 K/A REFERENCE & RATING: 201003 K4.02, 3.8/3.9 201003 A2.02, 3.7/3.8 201003 A$.02, 3.5/3.5 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 12 min.

MAX TIME: N/A JOB LEVEL: All TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH Yes (FAULTED):

RJPM-OPS-CRS-08 Page 2 of 11

RJPM-OPS-CRS-08 SIMULATOR SETUP SHEET Task

Description:

Perform control rod operability check with rod over-travel.

Required Power: >27%

IC No.: 161 Notes: Before start of JPM enter the following at the instructor console:

Malfunction(MFS) 15 Rod 16-29 Failure E (Rod Uncoupled) on Trigger 1 Malfunction to be removed when rod is driven into position 46 the second time at JPM Step 9.

RJPM-OPS-CRS-08 Page 3 of 11

RJPM-OPS-CRS-08 DATA SHEET References for Development: STP-052-0101 REP-0051 Required Materials: STP-052-0101 ARP-P680-Required Plant Condition: Reactor at power, steady state >27%

Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-CRS-08 Page 4 of 11

RJPM-OPS-CRS-08 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

Reactor at power, steady state 100%.

Initiating Cue:

The CRS has directed you to perform control rod operability check on control rod 16-29 ONLY.

RJPM-OPS-CRS-08

  • Denotes Critical Step Page 5 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-08 PERFORMANCE STEP [STP/ARP Step] STANDARD S/U COMMENTS Print out an OD-7 of initial control rod OD-7 printed out. CUE: Provide copy of OD7 positions. [Step 7.1] (JPM Page 11)

NOTE: OD-7 print out not available in simulator. Both 1.

copies of OD-7 to be given to the candidate have identical rod pattern only time and slight variations expected in CTP, WT and LL are different.

If any control rod is not fully Verifies all control rods on Data Sheet 1 are NA NOTE: CRS has already NAd withdrawn to position 48 or is except Control Rod 16-29. all control rods on Data Sheet 1 inoperable, THEN record NA for that except 16-29.

2.

control rod on Data Sheet 1, CONTROL ROD OPERABILITY DATA SHEET. [Step 7.2]

Perform Data Sheet 1, CONTROL Depresses pushbuttons 16 and 29 simultaneously NOTE: Candidates may refer to ROD OPERABILITY DATA SHEET on Operator Control Module Rod Select matrix SOP-0071 RC&IS to confirm

[Step 7.3] control rod manipulation steps per

  • 3 Control rod 16-29 position displayed as 48 on full that procedure are Reference Select control rod 16-29. [Step 7.3.1] core display. only meaning they can perform the steps in this procedure without having to use SOP-0071 also.

Insert control rod to position 46 and Depresses INSERT pushbutton momentarily

  • 4. verify position indication changes. Position reads 46 on full core display.

[Step 7.3.2]

RJPM-OPS-CRS-08

  • Denotes Critical Step Page 6 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-08 PERFORMANCE STEP [STP/ARP Step] STANDARD S/U COMMENTS Withdraw control rod to position 48 Depresses WITHDRAW pushbutton momentarily

  • 5. and verify position indication change. Position reads 48 on full core display.

[Step 7.3.3]

Perform coupling check. [Step 7.3.4] Depresses WITHDRAW pushbutton. NOTE: ALTERNATE PATH

  • 6.

Annunciator P680-7A-C02 CONTROL ROD OVERTRAVEL Acknowledges alarm P680-7A-C02 Alarm acknowledged and CRS notified. CUE: CRS directs the Operator CONTROL ROD OVERTRAVEL to take actions per ARP-P680-7.

and notifies CRS of uncoupled rod 16- 7A-C02.

29.

Determine uncoupled rod. Depress Refers to ARP-P680-7A-C02:

ROD UNCOUPLED pushbutton and Depresses ROD UNCOUPLED pushbutton

8. observe red lights. [ARP OA Step 1]

Red light observed next to control rod 16-29 on full core display.

Attempt to recouple rod by driving in Depresses INSERT pushbutton momentarily NOTE: Simulator operator will to Position 46 and withdrawing to Position reads 46 on full core display. remove malfunction when insert

  • 9. Position 48 [ARP OA Step 2] signal is initiated to recouple.

Depresses WITHDRAW pushbutton momentarily Position reads 48 on full core display.

RJPM-OPS-CRS-08

  • Denotes Critical Step Page 7 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-08 PERFORMANCE STEP [STP/ARP Step] STANDARD S/U COMMENTS Check the success of recoupling by Depresses WITHDRAW pushbutton momentarily CUE: As CRS, acknowledge rod attempting to withdraw beyond Position reading returns to 48 on full core 16-29 recoupling successful and position 48. [ARP LTA Step 1] display. that he will consult with Reactor

  • 10.

Engineering the disposition of Notifies CRS rod 16-29 recoupling successful. the STP. Direct the candidate to complete his/her ARP actions.

IF successfully recoupled, THEN note Notes Control Rod 16-29 successfully recoupled 11.

in Logbook. [ARP LTA Step 1.a] in log.

Terminating Cue: Control rod operability check for 16-29 completed in accordance with STP-052-0101.

RJPM-OPS-CRS-08

  • Denotes Critical Step Page 8 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-CRS-08 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-CRS-08 Page 9 of 11

RJPM-OPS-CRS-08 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: Reactor at power, steady state 100%.

Initiating Cues: The CRS has directed you to perform control rod operability check on control rod 16-29 ONLY.

RJPM-OPS-CRS-08 Page 10 of 11

RJPM-OPS-CRS-08 OD7 Control Rod Positions 09 / 20 / 04 12:10:04 RIVER BEND 53 40 49 45 10 41 37 06 20 06 33 29 40 10 20 20 10 40 25 21 06 20 06 17 13 10 09 05 40 04 08 12 16 20 24 28 32 36 40 44 48 52 Control Rod Sequence : Control Rod Density : 0.0667

% CTP: 99.72  % WT: 92.47  % LL 105.13 RJPM-OPS-CRS-08 Page 11 of 11

Number: *RJPM-OPS-IPS-01 RIVER Revision: 2 BEND STATION Page 1 of 13 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

NRC Exam JPM IN-PLANT - 1 PREPARE / REVIEW:

Erich Weinfurter 1497 6/29/2004 Preparer KCN Date Roger Persons 0862 7/5/2004 Technical Review (SME) KCN Date Frank McLean 0803 7/8/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-IPS-01 TASK DESCRIPTION: Vent the Scram Air Header per EOP-0005, Enclosure 11, Venting Scram Air Header TASK

REFERENCE:

201001005004 K/A REFERENCE & RATING: 201001 K1.09, 3.1/3.2 295037 EK3.07, 4.2/4.3 295037 EA1.05, 3.9/4.0 TESTING METHOD: Simulate Actual Performance X Performance Control Room Simulator In-Plant X COMPLETION TIME: 18 min.

MAX TIME: N/A JOB LEVEL: All TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-OPS-IPS-01 Page 2 of 8

RJPM-OPS-IPS-01 SIMULATOR SETUP SHEET Task

Description:

N/A Required Power: N/A IC No.: N/A Notes: This JPM is to be simulated in the plant. It involves entering the CAA and Primary Containment.

RJPM-OPS-IPS-01 Page 3 of 8

RJPM-OPS-IPS-01 DATA SHEET References for Development: EOP-0005, Enclosure 11, Venting Scram Air Header Required Materials: EOP-0005, Enclosure 11, Venting Scram Air Header Required Plant Condition: A scram condition has occurred but all control rods failed to insert and power is above 6%.

Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-IPS-01 Page 4 of 8

RJPM-OPS-IPS-01 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues, I may provide cues during the performance of this JPM, I may ask follow-up questions as part of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied, you should inform me when you have completed the task.

Initial Conditions:

A scram condition has occurred but all control rods failed to insert and power is above 6%

Initiating Cue:

The CRS has instructed you to implement EOP-0005, Enclosure 11, VENTING SCRAM AIR HEADER, to insert control rods per Emergency Procedure EOP-0001A, RPV CONTROL - ATWS.

RJPM-OPS-IPS-01

  • Denotes Critical Step Page 5 of 8

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-IPS-01 PERFORMANCE STEP [ENCL Step] STANDARD S/U COMMENTS

1. OBTAIN EOP-0005 ENCL 11 tool kit Key to emergency locker obtained and the tool kit NOTE: This JPM begins in the from Control Room Emergency Locker for EOP-0005, Enclosure 11 identified. Control Room but involves

[ENCL Step 3.1] entering the CAA and Primary Containment.

2. INSPECT kit for the following: [ENCL Verifies Flashlight and two cresent wrenches in Step 3.1.1] tool kit.

CUE: Return tool kit to

1. One (1) Flashlight with batteries Emergency Locker
2. Two (2) 10" Cresent wrenches
  • 3. CLOSE C11-VF095 INSTR AIR Identifies C11-VF095 and indicates valve is CUE: Valve is closed SUPPLY TO SCRAM PILOT VALVES closed by turning handwheel in clockwise ISOL (Containment EL 114 ft AZ 195, to direction.

right of backup scram valves) [ENCL Step 3.2]

  • 4. Remove test connection cap downstream Identifies test connection and cap downstream of CUE: Cap is removed of C11-PT-N052-V2 PILOT AIR C11-PT-N052-V2. Describes removal of cap HEADER PRESSURE TRANSMITTER using cresent wrenches in tool kit.

TEST VALVE (above and left of backup scram valve) [ENCL Step 3.3]

  • 5. OPEN C11-PT-N052-V2 PILOT AIR Identifies C11-PT-N052-V2 and indicates valve CUE: Valve is open and the HEADER PRESSURE TRANSMITTER is opened by turning handwheel in counter- sound of air flow is present at test TEST VALVE [ENCL Step 3.4] clockwise direction. connection.

Terminating Cue: Scram air header vented in accordance with EOP-0005, Enclosure 11 VENTING SCRAM AIR HEADER RJPM-OPS-IPS-01

  • Denotes Critical Step Page 6 of 8

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-IPS-01 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-IPS-01 Page 7 of 8

RJPM-OPS-IPS-01 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A scram condition has occurred but all control rods failed to insert and power is above 6%

Initiating Cues: The CRS has instructed you to implement EOP-0005, Enclosure 11, VENTING SCRAM AIR HEADER, to insert control rods per Emergency Procedure EOP-0001A, RPV CONTROL - ATWS RJPM-OPS-IPS-01 Page 8 of 8

Number: *RJPM-OPS-IPS-02 RIVER Revision: 1 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

NRC Exam JPM IN-PLANT - 2 PREPARE / REVIEW:

Erich Weinfurter 1497 6/29/2004 Preparer KCN Date Roger Persons 0862 7/7/2004 Technical Review (SME) KCN Date Frank McLean 0803 7/9/2004 Operations Verification KCN Date

  • Indexing Information

RJPM-OPS-IPS-02 TASK DESCRIPTION: Place Div. 1 Standby Service Water System in service from the Remote Shutdown Panel (with SWP-P2A Pump Trip)

TASK

REFERENCE:

400076004001 K/A REFERENCE & RATING: 264000 K6.07, 3.8/3.9 295016 AK2.01, 4.4/4.5 295016 AK2.02, 4.0/4.1 TESTING METHOD: Simulate Actual Performance X Performance Control Room Simulator In-Plant X COMPLETION TIME: 10 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: Yes ALTERNATE PATH Yes (FAULTED):

RJPM-OPS-IPS-02 Page 2 of 9

RJPM-OPS-IPS-02 SIMULATOR SETUP SHEET Task

Description:

Place Div. 1 Standby Service Water in service from the Remote Shutdown Panel (with SWP-P2A Pump Trip)

Required Power: N/A IC No.: N/A Notes: This JPM is to be simulated in the Control Building.

RJPM-OPS-IPS-02 Page 3 of 9

RJPM-OPS-IPS-02 DATA SHEET References for Development: AOP-0031, Shutdown from Outside the Main Control Room Required Materials: AOP-0031, Shutdown from Outside the Main Control Room, without attachments Required Plant Condition: Any Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-IPS-02 Page 4 of 9

RJPM-OPS-IPS-02 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions: The Control Room has been evacuated. The Reactor is in Hot Shutdown and control has been established at the Remote Shutdown Panel. There has been no fire. Normal Service Water is NOT available.

Initiating Cue: The CRS has directed you to place the Division 1 Standby Service Water System in service by starting SWP-P2A (preferred) or SWP-P2C from the appropriate Remote Shutdown Panel, per AOP-0031, step 5.10.5 RJPM-OPS-IPS-02

  • Denotes Critical Step Page 5 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-IPS-02 PERFORMANCE STEP [AOP Step] STANDARD S/U COMMENTS On C61-P001, verify both LOCAL Verifies both lights on. CUE: If operator requests as CRS SWP EMERGENCY CONTROL direct him to begin with procedure ALIGNED Lights are on. [AOP Step step 5.10.5

1. 5.10.5.1]

CUE: Inform operator that both lights are on.

On RSS-PNL101,start SWP-P2A Places SWP-P2A pump control switch to START NOTE: ALTERNATE PATH

[AOP Step 5.10.5.2.a] and verifies tripped (or started and tripped).

CUE: SWP-P2A Pump Status RED light on, GREEN light off; and immediately, RED light off,

  • 2.

GREEN light on.

CUE: As CRS if P2A is reported as failing to start, direct starting P2C.

On EGS-PNL4C, start SWP-P2C Places SWP-P2C pump control switch to START CUE: SWP-P2C Pump Status

  • 3. (Located in Div 3 Swgr Room) [AOP and verifies pump started. RED light on, GREEN light off Step 5.10.5.2.a]

Verify SWP-MOV40C STBY SVCE SWP-MOV40C STBY SVCE WTR PUMP CUE: SWP-MOV40C STBY WTR PUMP DISCHARGE Valve DISCHARGE Valve open SVCE WTR PUMP DISCHARGE

4. opens. [AOP Step 5.10.5.2.b] Valve status RED light on, GREEN light off RJPM-OPS-IPS-02
  • Denotes Critical Step Page 6 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-IPS-02 PERFORMANCE STEP [AOP Step] STANDARD S/U COMMENTS Open SWP-MOV55A STBY CLG Places SWP-MOV55A STBY CLG TOWER 1 CUE: SWP-MOV55A STBY TOWER 1 INLET [AOP Step INLET valve control switch momentarily to CLG TOWER 1 INLET Valve

  • 5. 5.10.5.2.c] OPEN (then released). Verifies valve has status RED light on, GREEN light opened. off.

Close both of the following valves: Places SWP-MOV96A NORM SVCE WTR CUE: SWP-MOV96A NORM RETURN Valves control switch momentarily to SVCE WTR RETURN Valve

  • 6. On RSS-PNL101, SWP-MOV96A CLOSE (then released). Verifies valve has status RED lights off, GREEN NORM SVC WTR RETURN [AOP closed. lights on.

Step 5.10.5.2.d]

On RSS-PNL102, SWP-MOV96B Places SWP-MOV96B NORM SVCE WTR CUE: SWP-MOV96B NORM NORM SVC WTR RETURN [AOP RETURN Valves control switch momentarily to SVCE WTR RETURN Valve

  • 7. Step 5.10.5.2.d] CLOSE (then released). Verifies valve has status RED lights off, GREEN closed. lights on.

IF check valve leakage is excessive, Reports Div 1 SSW operating with P2C running CUE: As CRS acknowledges THEN locally, close the following and requests CRS have Standby Cooling Tower Dive 1 SSW in service with P2C valves: Basin Level monitored for excessive leakage running and request for Basin

8. from Standby Service Water to Normal Service Level monitoring for leakage from SWP-MOV57A and SWP-Water System. SSW.

MOV57B NORMAL SERVICE WATER SUPPLY VALVES.

[AOP Step 5.10.5.2.e] Terminate JPM.

Terminating Cue: Division 1 Standby Service Water is in service.

RJPM-OPS-IPS-02

  • Denotes Critical Step Page 7 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-IPS-02 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-IPS-02 Page 8 of 9

RJPM-OPS-IPS-02 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The Control Room has been evacuated.

The Reactor is in Hot Shutdown and control has been established at the Remote Shutdown Panel.

There has been no fire.

Normal Service Water is NOT available.

Initiating Cues: The CRS has directed you to place the Division 1 Standby Service Water System in service by starting SWP-P2A (preferred) or SWP-P2C from the appropriate Remote Shutdown Panel, per AOP-0031, Step 5.10.5.

RJPM-OPS-IPS-02 Page 9 of 9

Number: *RJPM-OPS-IPS-03 RIVER Revision: 6 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • RESTORE RPS B NORMAL POWER SUPPLY REASON FOR REVISION:

NRC Exam JPM IN-PLANT - 3 PREPARE / REVIEW:

Erich Weinfurter 1497 6/29/2004 Preparer KCN Date Roger Persons 0862 7/7/2004 Technical Review (SME) KCN Date Frank McLean 0803 7/9/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-IPS-03 TASK DESCRIPTION: Restore RPS B Normal Power Supply TASK

REFERENCE:

212004001004 K/A REFERENCE & RATING: 212000 K1.04, 3.4/3.6 212000 K2.01, 3.2/3.3 212000 A1.01, 2.8/2.9 212000 A2.01, 3.7/3.9 TESTING METHOD: Simulate Actual Performance X Performance Control Simulator In-Plant X Room COMPLETION TIME: 10 min.

MAX TIME: N/A JOB LEVEL: All TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-OPS-IPS-03 Page 2 of 10

RJPM-OPS-IPS-03 SIMULATOR SETUP SHEET Task

Description:

Restore RPS B Normal Power Supply Required Power: N/A IC No.: N/A Notes: This JPM is to be performed at the Plant in the Control Building.

RJPM-OPS-IPS-03 Page 3 of 10

RJPM-OPS-IPS-03 DATA SHEET References for Development: SOP-0079, Reactor Protection System Required Materials: SOP-0079, Reactor Protection System Required Plant Condition: N/A Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-IPS-03 Page 4 of 10

RJPM-OPS-IPS-03 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is at 100% power. Electrical maintenance has completed work on the RPS B MG set generator output breaker. RPS B Bus is being supplied from the Alternate Power Supply.

Initiating Cue:

The CRS has directed you to start the RPS MG set and close the appropriate breakers to make RPS Bus B ready to transfer to the Normal Supply, in accordance with SOP-0079, Reactor Protection System.

RJPM-OPS-IPS-03

  • Denotes Critical Step Page 5 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-IPS-03 PERFORMANCE STEP [SOP Step] STANDARD S/U COMMENTS At NHS-MCC10B, close BKR 1C, Indicates Breaker 1C on NHS-MCC10B closed NOTE: MG Set components are REACTOR PROT SYSTEM MOTOR by moving handle all the way to left. located on 116 EL of the Control

  • ^ 1. GENERATOR SET. [SOP Step 4.1.1] Building.

NOTE: The CAUTION at the beginning of the procedure requires checking the torque seal intact prior to closing the Generator Output Breaker. This is NOT a Critical Step since the torque seal is intact for the JPM.

CUE: If verified, torque seal is intact.

Breaker closed when red end of breaker control level is in the fully left position (red end of handle against the breaker compartment).

CUE: Breaker BKR 1C is closed.

At MG Set Panel C71-S001B, depress MOTOR ON pushbutton depressed as motor CUE: MG status lights above the MOTOR ON pushbutton while generator comes up to proper voltage.. motor control pushbuttons are observing the Motor Generator Set output voltmeter. [SOP Step 4.1.2.1] Green light OFF Red light ON

  • ^ 2. AND Generator Output voltage is rising.

RJPM-OPS-IPS-03

  • Denotes Critical Step Page 6 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-IPS-03 PERFORMANCE STEP [SOP Step] STANDARD S/U COMMENTS Verify Motor Generator Set output Motor Generator Set output voltage verified to be CUE: MG Set output voltmeter voltmeter stabilizes at 123.5 volts. 123.5 volts. indicates 124 volts.

  • 3. [SOP Step 4.1.2.3]

WHEN the MG Set output voltmeter Torque seal verified intact, and indicates the NOTE: The CAUTION at the is 123.5 volts, THEN at C71-S001B, Generator Output Breaker on C71-S001B is beginning of the procedure

  • 4. close the Generator Output Breaker. closed by moving it to the upper position. requires checking the torque seal

[SOP Step 4.1.3] intact prior to closing the Generator Output Breaker. This is NOT a Critical Step since the torque seal is intact for the JPM.

CUE: If verified, torque seal is intact.

CUE: Generator Output Breaker is Closed.

On EPA Breaker C71-S003B:

EPA INPUT - Red light ON POWER SUPPLY OUTPUT -

Red light ON RJPM-OPS-IPS-03

  • Denotes Critical Step Page 7 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-IPS-03 PERFORMANCE STEP [SOP Step] STANDARD S/U COMMENTS Close C71-S003B, MG SET LOAD Indicates how EPA Breaker C71-S003B is closed CUE: EPA Breaker C71-S003B BREAKER [SOP Step 4.1.4] by rotating breaker lever to the ON (fully EPA OUTPUT red light ON and

  • ^ 5. counter-clockwise) position on EPA Breaker C71-S003D:

EPA INPUT - Red light ON POWER SUPPLY OUTPUT -

Red light ON Close C71-S003D, RPS BUS B Indicates how EPA Breaker C71-S003D is closed CUE: EPA Breaker C71-S003D NORMAL SUPPLY Breaker. [SOP by rotating breaker lever to the ON (fully EPA OUTPUT red light ON

  • ^ 6. Step 4.1.5] counter-clockwise) position Verify targets are reset on all EPA Verifies targets on EPA breakers C71-S003B and CUE: All targets on EPA breakers. [SOP Step 4.1.10] D are reset Breakers are reset.

7.

Terminating Cue: RPS MG Set B running with power available to transfer RPS B Bus to the Normal Supply.

RJPM-OPS-IPS-03

  • Denotes Critical Step Page 8 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-IPS-03 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-IPS-03 Page 9of 10

RJPM-OPS-IPS-03 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is at 100% power.

Electrical maintenance has completed work on the RPS B MG set generator output breaker.

RPS B Bus is being supplied from the Alternate Supply.

Initiating Cues: The CRS has directed you to start the RPS MG set and close the appropriate breakers to make RPS bus B ready to transfer to the Normal supply, in accordance with SOP-0079, Reactor Protection System.

RJPM-OPS-IPS-03 Page 10of 10

Number: *RJPM-OPS-BU-02 RIVER Revision: 0 BEND STATION Page 1 of 12 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

  • ESTABLISH EMERGENCY CONTAINMENT VENTING PER EOP ENCLOSURE 21 REASON FOR REVISION:

NRC Exam JPM BACKUP - 2 PREPARE / REVIEW:

Roger L. Persons 0862 6/10/2004 Preparer KCN Date Erich Weinfurter 1496 6/30/2004 Technical Review (SME) KCN Date Frank McLean 0803 7/9/2004 Operations Validation KCN Date

  • Indexing Information

RJPM-OPS-BU-02 TASK DESCRIPTION: Establish Emergency Containment Venting per EOP Enclosure 21 TASK

REFERENCE:

200023005002 K/A REFERENCE & RATING: 223002 K1.10, 3.1/3.2 223002 K4.08, 3.3/3.7 500000 EK1.01, 3.3/3.9 TESTING METHOD: Simulate Actual Performance X Performance Control Room X Simulator In-Plant X COMPLETION TIME: 23 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

SAFETY FUNCTION: 7 RJPM-OPS-BU-02 Page 2 of 12

RJPM-OPS-BU-02 SIMULATOR SETUP SHEET Task

Description:

Establish Emergency Containment Venting per EOP Enclosure 21 Required Power: N/A IC No.: N/A Notes: This JPM is to be performed in the Control Room and requires entering the CAA to perform the final step in the Auxiliary Building.

RJPM-OPS-BU-02 Page 3 of 12

RJPM-OPS-BU-02 DATA SHEET References for Development: EOP-0005, Enclosure 21 Required Materials: EOP-0005, Enclosure 21 Required Plant Condition: N/A Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-OPS-BU-02 Page 4 of 12

RJPM-OPS-BU-02 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

A large break LOCA has occurred in the Drywell. Containment pressure is 12 psig and Containment Hydrogen concentration cannot be maintained in the Safe Zone of the Hydrogen Deflagration Overpressure Limit (HDOL). Normal Containment Vent and Purge, Hydrogen Mixing and the Hydrogen Recombiners have been secured. EOP-0005, Enclosure 16, Defeating Containment Instrument Air Isolation Interlocks has been installed.

Initiating Cue:

The CRS has directed you install EOP-0005, Enclosure 21, Emergency Containment Venting and Defeating Containment Vent Path Isolation Interlocks.

RJPM-OPS-BU-02

  • Denotes Critical Step Page 5 of 12

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-BU-02 PERFORMANCE STEP [ENCL Step] STANDARD S/U COMMENTS OBTAIN EOP-0005 ENCL 21 Obtains jumper kit. NOTE: Simulate obtaining

1. jumper kit from the Control Room jumper kit Emergency Locker. [ENCL Step 3.2]

INSPECT kit for 2 jumpers [ENCL Kit contains two jumpers.

2.

Step 3.2.1]

DEFEAT isolation interlocks as Locates P852 Bay E, opens door and shows CUE: Jumper No.1 installed.

  • 3. how/where Jumper No. 1 is installed.

follows: [ENCL Step 3.3]

1. Location:1H13*P852 Bay E(left side of bay) [ENCL Step 3.3.1]
  • Affected Terminal Boards:

TB0175 (5th row of terminal boards from door, 2nd board from top)

TB0317(2nd row of terminal boards from door, top terminal board)

Jumper No. 1 JUMPER Terminal 12 on TB0175 to Terminal 2 on TB0317 RJPM-OPS-BU-02

  • Denotes Critical Step Page 6 of 12

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-BU-02 PERFORMANCE STEP [ENCL Step] STANDARD S/U COMMENTS

2. Location: 1H13*P952 Bay A Locates P952 Bay A, opens door and shows CUE: Jumper No.2 installed.
  • 4. how/where Jumper No. 2 is installed.

[ENCL Step 3.3.2]

Affected Relay: 45-1HVRB20 (2nd row of relays from top, 4th relay from left)

Jumper No. 2 JUMPER Terminal M1 on Relay Block 45-1HVRB20.

to Terminal R1 on Relay Block 45-1HVRB20.

OPEN 1HVR*AOV128 CONTMT At P863, demonstrates placing HVR-AOV128 CUE: CRS directs you to open

  • 5. RTN INBD ISOL as directed by the control switch to open momentarily and verifies 1HVR*AOV128.

CRS. [ENCL Step 3.5] valve open RED light ON CUE: 1HVR*AOV128 RED light on, GREEN light off GREEN light OFF VENT Primary Containment as Obtains ENCL 21 Key.

  • 6.

follows: [ENCL Step 3.6]

1. OBTAIN EOP-0005 ENCL 21 key, one (1) for CPP-PNL102. [ENCL Step 3.6.1]

RJPM-OPS-BU-02

  • Denotes Critical Step Page 7 of 12

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-BU-02 PERFORMANCE STEP [ENCL Step] STANDARD S/U COMMENTS

2. VERIFY the Annulus Mixing At P863, verifies at least one Annulus Mixing CUE: Annulus Mixing is in
7. System in operation with flow Train in operation aligned to SGTS: operation with flow to SGTS.

to SGTS. [ENCL Step 3.6.2] HVR-FN11A(B) ANNULUS MIXING FAN on RED light ON GREEN light OFF HVR-AOD53A(B) ANNULUS MIX FAN A(B) DISCH open RED light ON GREEN light OFF HVR- AOD22A(B) ANNULUS MIX SPLY TO SGTopen RED light ON GREEN light OFF RJPM-OPS-BU-02

  • Denotes Critical Step Page 8 of 12

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-BU-02 PERFORMANCE STEP [ENCL Step] STANDARD S/U COMMENTS

3. VERIFY the SGTS in At P863, verifies at least one SGTS Train in CUE: SGTS is aligned to Main
8. operation with flow to the operation aligned to main plant exhaust duct: Plant Stack.

main plant exhaust duct. GTS-AOD1A(B) SGT FILTER A(B) SUCT

[ENCL Step 3.6.3] ISOL open RED light ON GREEN light OFF GTS -FN1A(B) SGT EXH FAN A(B) on RED light ON GREEN light OFF GTS -AOD3A(B) SGT EXH FAN A(B)

DISCH open RED light ON GREEN light OFF

4. VERIFY 1IAS*MOV107 At P870, verifies both MOVs are open. CUE: 1IAS*MOV107 and
9. INST AIR SHUTOFF 1IAS*MOV106 both have RED RED light ON VALVE AND light on, GREEN light off 1IAS*MOV106 INST AIR GREEN light OFF OUTBD ISOL are open (1H13*P870) [ENCL Step 3.6.4]

RJPM-OPS-BU-02

  • Denotes Critical Step Page 9 of 12

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-BU-02 PERFORMANCE STEP [ENCL Step] STANDARD S/U COMMENTS

5. VERIFY 1HVR*AOV128 At P863, verifies 1HVR*AOV128 open. CUE: 1HVR*AOV128 RED light
10. CONTMT RTN INBD ISOL on, GREEN light off RED light ON is open (1H13*P863). [ENCL Step 3.6.5] GREEN light OFF
6. OPEN 1HVR-AOD127 At P863, demonstrates placing HVR-AOV127 CUE: 1HVR-AOD127 RED light
  • 11. CONTMT PURGE RTN control switch to open momentarily and verifies on, GREEN light off.

ISOL (1H13*P863). [ENCL valve open Step 3.6.6] RED light ON NOTE: The next step is in the plant (Aux Bldg) requiring CAA GREEN light OFF entry.

7. OPEN 1CPP*MOV105 H2 Locates panel, opens door with key and CUE: CPP*MOV105 RED light
  • 12. PURGE FAN DISCH demonstrates placing CPP*MOV105 control on, GREEN light off..

VALVE TO ANNULUS at switch to open momentarily and verifies valve 1CPP-PNL102 (171 ft Aux open Bldg East Side, Containment RED light ON Purge FLT 6/HVR FAN 14 Room). [ENCL Step 3.6.7] GREEN light OFF Terminating Cue: EOP-0005, Enclosure 21 installation has been completed and the Containment is being vented.

RJPM-OPS-BU-02

  • Denotes Critical Step Page 10 of 12

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-OPS-BU-02 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-OPS-BU-02 Page 11of 12

RJPM-OPS-BU-02 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A large break LOCA has occurred in the Drywell.

Containment pressure is 12 psig and Containment Hydrogen concentration cannot be maintained in the Safe Zone of the Hydrogen Deflagration Overpressure Limit (HDOL).

Normal Containment Vent and Purge, Hydrogen Mixing and the Hydrogen Recombiners have been secured.

EOP-0005, Enclosure 16, Defeating Containment Instrument Air Isolation Interlocks has been installed.

Initiating Cues: The CRS has directed you install EOP-0005, Enclosure 21, Emergency Containment Venting and Defeating Containment Vent Path Isolation Interlocks.

RJPM-OPS-BU-02 Page 12of 12

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 1 (SIS-19.0, IC-163) Op.-Test No.: 1 NEW SCENARIO Examiners: Operators: CRS - Control Room Suprv. (SRO)

ATC - At-the-Controls (RO)

UO - Unit Operator (BOP-RO)

Initial Conditions: Plant startup in progress at 40% power. Reactor Recirc pumps were shifted to fast speed last shift. Reactor Engineering has requested that reactor power be raised with recirc flow to raise core flow to 50%.

Turnover: APRM C INOP and bypassed due to power supply failure. Heater Drain Pumps, HDL-P1A and C tagged out due to excessive leakage. Main Generator voltage regulator in Manual due to erratic operation in Auto. Continue plant startup by raising core flow with Recirc flow control valves per Reactor Engineer request.

Event No. Malf. No. Event Type

  • Event Description 1 N/A R Raise power and core flow with recirc flow control valves T = 0 min. (ATC) 2 CRD001B C CRD Pump B trip.

T = 8 min. (UO/CRS)

CRDM4813(2) I Accumulator instrument failure causes accumulator trouble to (ATC/CRS) not clear when CRD Pump A is started. (Tech Specs for CRS) 3 CRDM2405(1) C Control Rod Drifts out. (Tech Spec for CRS)

T = 20 min. (ATC/CRS) 4 RPS003B C Loss of RPS B T = 30 min. (ALL) 5 FWS007C I FWRV C control signal fails high failing FWRV open.

T = 40 min. (ATC/CRS)

Automatic scram signal will be initiated on (or manual scram signal before reaching) high reactor water level.

6 CRD014 M Hydraulic ATWS T = 40 min (ALL) 7 RCIC003 C RCIC flow controller fails low. (After EOP Entry)

T = 42 min. (UO/CRS)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 1 Page 1 of 7 Event

Description:

The CRS directs the ATC to raise reactor power with recirc flow control valves to raise core flow to 50%. Reactor Engineer stated there are no core related restrictions on the power ramp rate.

Time Position Applicants Actions or Behaviors T=0 CRS Directs ATC to raise core flow (and reactor power) to 50% of rated flow.

ATC Alternately opens both recirc FCVs to raise core flow to 50% (P680).

Monitors reactor power and RPV level during changes in flow (P680)

Monitors loop flows to maintain them within 10% of each other per Tech Spec requirements (P680)

NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 2 Page 2 of 7 Event

Description:

UO responds to CRD Pump B Trip. ATC identifies Control Rod 48-13 with accumulator fault that does not clear when CRDH charging header pressure returns to normal. CRS consults TS LCO for CR Accumulator instrumentation.

Time Position Applicants Actions or Behaviors T=8 CUES:

min Alarm P601-22A-A01, CRD PUMP A OR B AUTO TRIP P601 CRDH flows, pressures and Ps drop to zero.

CRS Directs UO to start standby pump per ARP CUES:

Alarm P680-7A-C03, ACCUMULATOR TROUBLE ATC Referring to ARP-P680-7A-C03, depresses P680 ACC FAULT button to display CR 48-13 with fault and reports to CRS.

NOTE: Other accumulator faults may come in while recovering the CRD pump UO Refers to ARP-P601-22A-A01 for the following:

Starts CRD Pump A oil pump (P601).

Places CRD Flow Controller to MANUAL (P601).

Closes CRD Flow Control Valve (P601).

Starts Standby CRD Pump (P601).

Reopens CRD Flow Control Valve (P601).

Places CRD Flow Controller to AUTO (P601).

ATC Reports to CRS that accumulator fault does not clear on return of CRD Pump.

CRS Directs investigation of Accumulator Trouble on CR 48-13.

Consults Tech Spec 3.1.5, Accumulators Directs RB Operator to blowdown level switch per SOP-0002 Consults TR 3.1.5.1, Accumulator Instrumentation when blowdown fails NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 3 Page 3 of 7 Event

Description:

ATC responds to Control Rod 24-05 drifting out due to the failure of a directional control valve. Control rod HCU must be hydraulically isolated.

Time Position Applicants Actions or Behaviors T = 20 CRS CUES:

min Alarm P680-07A-B02, CONTROL ROD DRIFT When selected, CR 24-05 position indicates rod moving out.

ATC Refers to ARP-P680-07A-B02 Depresses ROD DRIFT pushbutton to find drifting control rod on Full Core display (P680)

Selects drifting control rod 24-05 with RCIS Select Matrix (P680)

Depresses and holds INSERT pushbutton (P680)

Verifies (or requests UO verify) cooling water pressure @ 20 psid (P601)

UO As directed or requested, monitors/verifies normal CRDH parameters (P601)

ATC Releases INSERT pushbutton and reports control rod drifting out (P680)

Depresses and holds INSERT pushbutton (P680)

CRS Directs Reactor Building Operator to Hydraulically Isolate CR 24-05 ATC After HCU is reported hydraulically isolated, releases INSERT pushbutton and reports control rod stays inserted (P680)

CRS Per ARP-P680-07A-B02:

Refers to AOP-0061, Control Rod(s) Mispositioned/Malfuntion Notifies Reactor Engineering of directional control valve failure on control rod 24-05.

Consults TS 3.1.3 for inoperable control rod NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 4 Page 4 of 7 Event

Description:

RPS MG Set B output breaker trips. Crew must transfer RPS bus is re-energized, reset isolation logic and restore isolated systems.

Time Position Applicants Actions or Behaviors T = 30 CRS CUES:

min Alarms P680-DIV 2 RPS LOGIC ACTUATED All trip status lights for all four RPS B APRMs are lit (P680).

B RPS scram solenoid white light above each manual scram pushbutton NOT lit.

ATC Recognizes loss of RPS Bus B and reports to CRS UO When directed, transfers RPS bus B to Alternate power (P610 backpanel switches in simulator)

Reset CRVICS depressing both RESET pushbuttons (P601)

CRS Directs entry and execution of AOP-0010, Loss of One RPS Bus Directs investigation of the loss of RPS Bus B ATC Requests Backpanel Operator to reset NMS power supplies Resets RPS B Trip once all APRM trips are cleared.

UO CRITICAL TASK: Restores RPCCW to Reactor Recirc Pump Seals (P870)

Verifies/restores Drywell cooling (P877, P870, P863)

Verifies/restores remaining isolation valves, as directed by CRS (P870, P808).

Continues AOP-0010 system restoration actions, as directed by CRS NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 5 Page 5 of 7 Event

Description:

FWRV C fails open causing rapid RPV level rise and High RPV Water Level Scram. ATC may initiate manual scram when he determines the automatic scram is imminent.

Time Position Applicants Actions or Behaviors T = 40 CUES:

min Alarm P680-3A REACTOR HIGH/LOW WATER LEVEL FWRV C Position vs Demand 5% Error Amber light lit (P680)

RPV level rising on all P680 level instruments CRS Directs entry into AOP-0001 and AOP-0002 for Level 8 ATC Per AOP-0006, Condensate/Feedwater Failures:

May place flow controller for FWRV C in MAN and attempt to close (P680) or recognize controller is demanding zero and proceed to inform CRS manual scram required (P680)

Per AOP-0001, Reactor Scram:

Arms and Depresses four manual scram pushbuttons (P680)

Places Reactor Mode switch in SHUTDOWN (P680)

Initiates ARI (P680)

Per AOP-0002, Turbine Generator Trip:

Verifies Turbine trip and Generator Output breakers open (P680)

NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 6 Page 6 of 7 Event

Description:

On scram initiation, the RPS functions correctly de-energizing scram solenoids and depressurizing scram air header but a hydraulic lock due to a partially filled SDV prevents most of the control rods from scramming. Use of EOP Encl. 12 will insert all rods after two more scrams.

Time Position Applicants Actions or Behaviors T = 40 ATC CUES:

min P680 Alarms RPS TRIP LOGICS ACTIVATED Alarm P680 SCRAM PILOT VALVE AIR HEADER PRESS LOW Most Control Rods on Full Core Display indicating full out APRMs reactor power at ~15%

CRS Enters EOP-0001 RPV Control and transitions to execute EOP-0001A RPV Control - ATWS.

Enters EOP-0002, Containment Control following High DW Temperature ATC Per AOP-0001, determines numerous Control Rods Failed to insert and that power remaining above 5%. Reports to CRS When directed, trips recirc pumps (P680)

When directed, attempts to insert rods by individual insertion and using Encl 12 to reset and manual scram. (P680)

Isolates FWRV C and opens Inlet Isolation for FWRV A or B and if directed, starts RFP to inject into RPV (P680)

UO When directed, inhibits ADS (P601)

When directed, maximizes CRD flow (P601)

When directed, terminates and prevents ECCS injection to lower RPV water level.

Installs EOP Enclosures Verifies Isolations per AOP-0003 ALL CRITICAL TASK: Lower RPV water level to -56 inches.

NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 7 Page 7 of 7 Event

Description:

RCIC initiates or is manually initiated by UO and fails to inject due to flow controller failed in AUTO. UO must recognize failure of flow controller and take manual control to inject into RPV Time Position Applicants Actions or Behaviors T = 42 CUES:

min Alarm P601-16A-A04, HPCS INITIATION LOW RX WATER LEVEL 2 RCIC steam stop, trip & throttle and injection valves open (P601)

RCIC flow controller output low with 0 injection flow (P601)

UO Recognizes failure of RCIC to inject and reports to CRS (P601)

If directed by CRS to inject with RCIC, transfers RCIC Flow Controller to Manual. (P601)

Raises Manual setting of RCIC Flow Controller to raise turbine speed and inject into RPV to maintain level as directed by CRS (P601)

If directed to secure RCIC (ATC restoring level with Feed System then shuts down RCIC (P601)

UO/ATC CRITICAL TASK: Restore injection into the RPV to maintain RPV level above

-186 inches.

Termination Criteria:

1. RPV Level stabilized above -186 inches
2. RPV pressure stabilized.
3. Containment parameters stabilized CRITICAL TASKS:
1. Restore RPCCW cooling to Reactor Recirculation Pumps
2. Lower RPV water level to -56 inches.
3. Restore injection into the RPV to maintain RPV level above -186 inches.

NUREG-1021, Draft Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 2 (SIS-21.0, IC-165) Op.-Test No.: 1 MODIFIED SCENARIO Examiners: Operators: CRS - Control Room Suprv. (SRO)

ATC - At-the-Controls (RO)

UO - Unit Operator (BOP-RO)

Initial Conditions: Steady state operation at 100% power. RHR B is in suppression pool cooling.

Turnover: APRM C INOP and bypassed due to power supply failure. Heater Drain Pumps, HDL-P1A and C tagged out due to excessive leakage. Main Generator voltage regulator in Manual due to erratic operation in Auto. RCIC slow roll was completed last shift and suppression pool temperatures have been returned to normal. Remove RHR B from suppression pool cooling.

Event No. Malf. No. Event Type

  • Event Description 1 N/A N Remove RHR B from suppression pool cooling.

T = 0 min. (UO/CRS) 2 HPCS004 C Spurious HPCS automatic start and injection. (Tech Specs for T = 10 min. (UO/CRS) CRS) 3 NMS015F I APRM F flow reference signal fails downscale.

T = 17 min. (ALL) (Tech Specs for CRS) 4 MSS010 C Turbine gland seal pressure regulator valve fails closed.

T = 27 min. (UO/CRS) 5 P680_2a:e_8 C Heater Drain Pump HDL-P1D overload.

T = 35 min. (ATC /CRS)

N/A R Lower reactor power with Recirc flow to maintain RPV level (ATC)

Scram will be automatically initiated on high drywell pressure.

6 RCS001 M Rupture of A recirculation loop (Large break LOCA)

T = 45 min (ALL)

Override C Recirc loop A suction isolation valve fails in open position.

(ATC/CRS) (After EOP Entry) 7 LPCS002 C LPCS injection valve fails to open (After EOP Entry).

T = 47 min. (UO/CRS)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 1 Page 1 of 7 Event

Description:

Unit Operator removes RHR B from Suppression Pool cooling and returns it to standby lineup.

Time Position Applicants Actions or Behaviors T=0 CRS Directs UO to remove RHR B from Suppression Pool Cooling UO Using SOP-0031:

Closes RHR Pump B Test Return to Suppression Pool [E12-MOVF024B] (P601).

Stops RHR Pump B (P601).

Verifies minimum flow [E12-MOVF064B] and HX outlet valves

[E12-MOVF003B] are open (P601).

Opens RHR B HX Bypass valve [E12-MOVF048B] (P601).

Closes RHR HX B Service Water Return [SWP-MOVF068B] (P870).

NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 2 Page 2 of 7 Event

Description:

Unit Operator responds to a spurious initiation of HPCS.

Time Position Applicants Actions or Behaviors T = 10 CUES:

min P601 HPCS initiation signal white light lit P601 HPCS pump breaker closed and injection valve open.

Alarm P601-16A-C02, DIV III D/G RUNNING P680 All three FWLC level instruments stable above 35 inches P680 Stable feed flow indication lower than steam flow.

ATC Confirms/reports FWLC controlling at higher stable level and Feed Flow/Steam Flow mismatch exists (P680).

Enters AOP-0006 and verifies proper operation of FWLC system (P680).

CRS Directs UO to verify by two independent means adequate core cooling to confirm HPCS misoperation Directs UO to secure HPCS injection UO Verifies adequate core cooling PAM recorders (P601)

When directed by CRS, overrides HPCS injection valve [E22-MOVF004] closed (P601)

When directed by CRS, stops HPCS pump (P601)

Verifies HPCS minimum flow valve [E22-MOVF012] closes (P601)

Refers to ARP-P601-16A-C02 for HPCS Diesel Start and directs local operator to shutdown HPCS Diesel.

CRS Directs investigation of spurious HPCS initiation Consults TS 3.5.1 for inoperable HPCS and TS 3.3.5.1 HPCS initiation instrumentation.

NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 3 Page 3 of 7 Event

Description:

APRM F flow reference signal fails downscale resulting in a half-scram.

Time Position Applicants Actions or Behaviors T = 17 CUES:

min Alarm P680-06A-A03, APRM B OR F UPSCALE TRIP OR INOP P680 Recorder and PMS indicates APRM F reading ~100%

Alarm P680-6A-B03, APRM UPSCALE OR INOP TRIP ATC Refers to ARPs for P680-06A-A03 and P680-06A-B03 Identifies APRM Channel F causing failed upscale (P680)

Compares APRM F with other APRMs Verifies no control rod scrams (P680)

When directed by CRS, bypasses APRM F (P680).

When directed by CRS, resets half-scram (P680).

CRS Directs ATC to bypass APRM F when determined failed Consults Tech Spec Section 3.3.1.1, RPS Instrumentation UO Investigates APRM F failure at Backpanel Identifies flow unit downscale NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 4 Page 4 of 7 Event

Description:

A failure of the Turbine Gland Seal header pressure control valve causes a loss of gland seal steam.

Time Position Applicants Actions or Behaviors T = 27 CUES:

min Alarm P870-54A-E05, SEAL STEAM EVAP STEAM HEADER LOW PRESSURE Seal Steam Header Pressure indication lowering to or at 0 psig on TME-PIEPR-4 (P870)

UO Refers to ARP-P870-54A-E05:

Diagnoses loss of seal steam condition (P870)

CRITICAL TASK: Opens seal steam PCV bypass [TME-MOVS2] (P870)

Monitors seal steam header pressure TME-PIEPR-4 (P870)

Adjusts MOVS2 to maintain 4-6 psig seal steam header (P870)

CRS Directs entery into AOP-0005 ATC to monitor condenser vacuum Requests TB operator investigate status of seal steam header pressure control valve TME-PCVSSFV ATC Monitors condenser vacuum and (P680)

NOTE: May receive Blown Offgas loop seals alarms on Offgas panel during this event which would be expected due to a rapid rise in condenser air in-leakage upon loss of LP turbine sealing steam.

NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 5 Page 5 of 7 Event

Description:

ATC responds to Heater Drain Pump P1D Overload. ATC must reduce reactor power to prevent a low suction pressure trip of a Reactor Feedwater Pump.

Time Position Applicants Actions or Behaviors T = 35 CUES:

min Alarm P680-02A-F08, HTR DR PUMP 1HDL-P1D OVERLOAD HDL-P1D Current indicates 175 amps (P680)

CRS Directs implementation of AOP-0006 ATC Refers to ARP-P680-02A-F08:

Reduces reactor power (~83%) to prevent RFP low suction trip(P680)

Closes HDL-P1D discharge valve [HDL-MOV55D] (P680)

Stops HDL-P1D (P680)

CRS Directs WMC investigate HDL-P1D overload NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 6 Page 6 of 7 Event

Description:

A large break LOCA occurs on the A Recirculation Loop suction line. ATC attempts to isolate and the recirc loop A suction isolation valve will not close.

Time Position Applicants Actions or Behaviors T = 45 CUES:

min All Division of ECCS initiation signal white lights lit (P601)

Alarm P680-6A-B05,NSSSS INIT DRYWELL HIGH PRESSURE and reactor scram (P680)

Rapidly rising Drywell Pressure and Temperature, Suppression Pool Level and Temperature on ERIS and P808 CRS Enters EOP-0001, RPV Control and EOP-0002, Primary Containment Control and directs actions Implements EOP-0004, Emergency Depressurization for high suppression pool level or because reactor water level cannot be determined.

ATC Completes applicable actions for AOP-0001, Reactor Scram and AOP-0002, Turbine Trip (P680)

Maximizes injection flow from the Condensate and Feedwater Systems to inject contents of condenser hotwell. (P680)

Attempts to close Recirc Loop Suction isolation to isolate leak and reports failure to CRS (P680)

UO Verifies ECCS initiation and injection as applicable (P601)

Maximizes CRD flow Inhibits ADS CRITICAL TASK: Opens seven ADS valves for Emergency Depressurization, when directed.

NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 7 Page 7 of 7 Event

Description:

The LPCS injection valve fails to open when the system automatically initiates.

Time Position Applicants Actions or Behaviors T = 47 CUES:

min DIV 1 ECCS initiation signal white light lit (P601)

Alarm P601-21A-D08, LPCS PUMP E21-C001 AUTO START Alarm P601-21A-E06, LPCS INJ RX PRESS LOW PERMISSIVE LPCS pump running with injection valve closed (P601)

UO Recognizes failure of LPCS injection valve F005 (P601)

Attempts to open injection valve F005 (P601)

Reports failure to CRS When directed by CRS, directs Building Operator to attempt to manually open LPCS injection valve.

Termination Criteria:

1. RPV level restored and maintained above -162 inches.
2. Containment parameters stabilized.

CRITICAL TASKS:

1. Manually bypass the Seal Steam Header pressure control valve to re-establish gland seal steam.
2. Emergency Depressurize RPV due to high Suppression Pool level.

NUREG-1021, Draft Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 3 [BU] (SIS-20.0, IC-164) Op.-Test No.: 1 BANK SCENARIO Examiners: Operators: CRS - Control Room Suprv. (SRO)

ATC - At-the-Controls (RO)

UO - Unit Operator (BOP-RO)

Initial Conditions: Power ascension to rated in progress, holding at 90% power for Reactor Engineer to check core performance and effects of new rod pattern. RHR B in Suppression Pool Cooling Mode for RCIC slow roll to be done this shift.

Turnover: APRM C INOP and bypassed due to power supply failure. Heater Drain Pumps, HDL-P1A and C tagged out due to excessive leakage. Main Generator voltage regulator in Manual due to erratic operation in Auto. Complete preparations and slow roll RCIC following lube oil addition.

Event No. Malf. No. Event Type

  • Event Description 1 N/A N Place Containment HVAC in High Volume Purge.

T = 0 min. (UO/CRS) 2 NMS011D I APRM D fails upscale with single rod scram.

T = 10 min. CRDM4829 (ATC/CRS) (Tech Specs for CRS) 3 RCIC001 C RCIC trip throttle valve fails to open during turbine slow roll.

T = 20 min. (UO/CRS) (Tech Specs for CRS) 4 OR_P680_3a:d-2 C Loss of TPCCW to Reactor Feed Pump FWS-P1A Gear T = 30 min. (Alarm Override) (ATC/CRS) Increaser Lube Oil Cooler (requiring P1A shutdown).

N/A R Lower power with Recirc flow as needed for RFP shutdown.

(ATC/CRS)

Scram should be manually initiated before automatic on high reactor pressure with Turbine CVs shutting.

RPS failure to scram requires ARI initiation to insert control rods.

5 EHC001 M Turbine governor fails low closing Turbine Control Valves T = 40 min (ALL)

ED002B Loss of NPS-SWG1B on transfer from Main Generator to Preferred Transformer.

RPS001A RPS fails to scram automatically and manually.

6 MSS001 A steam leak in Drywell rises to 500 GPM over 3 minutes.

T = 41 min. (After EOP Entry).

7 HPCS003 C HPCS fails to auto initiate. (After EOP Entry).

T = 42 min. (UO/CRS)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 3 [BU] Event No.: 1 Page 1 of 7 Event

Description:

Unit Operator places Containment HVAC in High Volume Purge.

Time Position Applicants Actions or Behaviors T=0 CRS Directs UO to place Containment HVAC in High Volume Purge UO Using SOP-0059, Containment HVAC. Section 5.5 Opens containment purge valves and dampers (P863)

HVR-AOV165, Contmt Sply Outbd Isol HVR-AOV123, Contmt Sply Inbd Isol HVR-AOD124, Contmt Purge Sply Isol HVR-AOD127, Contmt Purge Rtn Isol HVR-AOV128, Contmt Rtn Inbd Isol HVR-AOV166, Contmt Rtn Outbd Isol HVR-AOD245, Contmt Purge to SGT HVR-AOD162, Contmt Purge to SGT Starts either train of SGTS (P863)

Verifies proper start in alignment of SGTS (P863)

Starts HVR-FN8 High Volume Purge supply fan (P863)

Verifies HVR-FN8 Discharge Damper opens (P863)

NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 3 [BU] Event No.: 2 Page 2 of 7 Event

Description:

APRM D Upscale failure. Using ARPs ATC identifies single scrammed control rod.

Time Position Applicants Actions or Behaviors T = 10 CUES:

min Alarm P680-6A-B03, APRM D OR H UPSCALE TRIP OR INOP Alarm P680-7A-B02, CONTROL ROD DRIFT APRM D recorder pen full scale (P680)

Full Core display CR 48-29 full in green light lit (P680)

ATC Refers to ARP-P680-06A-B03 Verifies half scram (P680)

Compares channel with other APRMs (P680)

Verifies core flow unchanged (P680)

CRS Refers to AOP-0061, Mispositioned Control Rod(s)

ATC Bypasses APRM D on CRS direction (P680)

Resets half scram on CRS direction (P680)

Refers to ARP-P680-07A-B02 Identifies scrammed rod [48-29 ] using RCIS (P680)

Reports scrammed rod 48-29 to CRS CRS Consults Tech Spec 3.3.1.1 for APRM Consults Tech Spec 3.1.3 for scrammed Control Rod Notifies RE for predictor case and control rod pattern recovery directions NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 3 [BU] Event No.: 3 Page 3 of 7 Event

Description:

UO attempts to slow roll RCIC and discovers RCIC Trip & Throttle Valve fails to open. Reports condition to CRS and places RCIC in lineup as directed by CRS.

Time Position Applicants Actions or Behaviors T = 20 CRS Directs UO to Slow Roll RCIC per SOP-0035 min UO Refers to SOP-0035, RCIC, Section 4.3:

Starts Gland Seal Compressor (P601)

Closes Trip & Throttle Valve [E51-MOVC002] operator (P601)

Acknowledges RCIC SYSTEM INOPERATIVE alarm (P601)

Opens E51-F045, Steam Supply Turbine Stop Valve (P601)

Verifies closed E51-F025, F026, F004, F005 Supply and Exh Drain Pot isolation valves (P601)

Attempts to reopen Trip & Throttle valve [E51-MOVC002] to raise turbine speed to 3000 RPM (P601)

CUES:

The Trip & Throttle valve indicates full closed - green light on, red light off as Trip & Throttle Valve Operator indication goes to intermediate position green light on and red light on.

RCIC SYSTEM INOPERATIVE alarm does not clear.

UO Reports to CRS that Trip & Throttle Valve failed to open.

CRS Directs local attempt to reset RCIC Trip & Throttle Valve Directs UO to return RCIC to pre-start lineup Determines RCIC remains inoperable and stays in LCO 3.5.3 UO When directed by CRS, returns RCIC to pre-start lineup NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 3 [BU] Event No.: 4 Page 4 of 7 Event

Description:

Loss of TPCCW to Reactor Feed Pump FWS-P1A Gear Increaser Lube Oil Cooler requires lowering reactor power and shutdown of FWS-P1A.

Time Position Applicants Actions or Behaviors T = 30 CRS CUES:

min Alarm P680-3A-B05, REACTOR FEED PUMP COOLING COIL LEAKAGE Alarm P680-3A-D02, RX FWP 1A GEAR INCREASER HIGH TEMP ATC Refers to ARPs P680-3A-B05 and P680-3A-D02 and informs CRS ATC/UO Contacts Turbine Bldg Operator to investigate alarms on feed pumps.

CRS Enters AOP-0006, Condensate/Feedwater Failures Directs ATC to lower reactor power with Recirc flow to within capacity of 2 reactor feed pumps (~75-80%)

ATC When directed by CRS, lowers power with individual RR FCV controllers (P680)

CRS Directs ATC to secure RFP A ATC Refers to SOP-0009, Feedwater System Directs Turbine Building Operator to isolate Hydrogen injection for RFP A Closes FWS-P1A discharge valve [FWS-MOV26A] on (P680).

Verifies min flow valve [FWR-FV2A] for P1A opens (P680).

Monitors SF/FF mismatch and RPV Level to verify capability of remaining RFPs (P680).

Stops Reactor Feed Pump FWS-P1A (P680).

NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 3 [BU] Event No.: 5 Page 5 of 7 Event

Description:

EHC governor fails low closing Turbine Control Valves. An automatic scram will be initiated on High RPV pressure if operators fail to manually scram. RPS will fail to initiate electrically requiring ARI initiation to scram all control rods. NPS-SWG1B is lost on the automatic bus transfer failure following the Generator Output Breaker trip resulting in a loss of normal feed.

Time Position Applicants Actions or Behaviors T = 40 CUES:

min MW Electric lowering on Main Generator Alarm P680-7A-A07, TURBINE BYPASS VALVE OPEN Alarm P680-3A-A09, REACTOR HIGH PRESSURE Alarms P680-5A-A09 & A10 RPS TRIP LOGICS ACTIVATED Control Rods on Full Core Display indicating full out (P680)

APRMs reactor power ~80% (P680)

CRS Directs implementation of AOP-0001, Reactor Scram and AOP-0002, Turbine Trip ATC Executes AOP-0001 and AOP-0002 immediate and applicable subsequent actions Recognizes RPS failure to insert control rods CRITICAL TASK: Initiates ARI (P680)

Reports RPS failed to scram and ARI inserted all rods Reports loss of Feedwater due to loss of power to RFPs CRS Enters and coordinates executing EOP-0001, depending on how quickly loss of feed is diagnosed and HPCS recovered, may enter EOP-0004, Alternate Level Control.

NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 3 [BU] Event No.: 6 Page 6 of 7 Event

Description:

The high RPV pressure caused by the EHC failure causes a steam leak to develop in the Drywell. The leak grows to 500 gpm three minutes after the scram.

Time Position Applicants Actions or Behaviors T = 41 CUES:

min Alarm P680-6A-C05, DRYWELL HIGH/LOW PRESSURE followed shortly by Alarm P680-6A-B05, NSSSS INIT DRYWELL HIGH PRESSURE Alarm P601-19A-B05, DRYWELL AIR COOLER DRAIN HIGH LEAKAGE FLOW DRMS Drywell Rad Monitors trending up ERIS Drywell temperature trending up CRS Enters EOP-0002, Containment Control following High DW Pressure /

Temperature UO/ATC Recognize indications of leak in the Drywell and report to CRS UO Verifies ECCS initiations (P601) and EDG starts (P877).

When directed by CRS, maximizes CRD flow (P601)

When directed by CRS, maximizes Drywell Cooling (P863)

When directed by CRS, verifies auto isolations per AOP-0003 (P601, P870, P808)

Installs EOP Enclosures as directed by CRS NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 3 [BU] Event No.: 7 Page 7 of 7 Event

Description:

Following the High Drywell Pressure condition caused by the steam leak, HPCS will fail to auto initiate.

Time Position Applicants Actions or Behaviors T = 42 CUES:

min Alarm P601-16A-A04, HPCS INITIATION LOW RX WATER LEVEL 2 HPCS Pump not running (P601)

HPCS Injection Valve E22-MOVF004 closed (P601)

UO Recognizes failure of HPCS to initiate and reports to CRS Attempts to auto start with manual initiation pushbutton (P601).

CRITICAL TASK: Starts HPCS pump with pump breaker control switch and opens Injection valve [E22-MOVF004].

Injects into RPV with HPCS as directed by CRS Termination Criteria:

1. RPV level stabilized in control band of 10 - 51 inches
2. Containment parameters stabilized CRITICAL TASKS:
1. Initiate ARI to insert all control rods
2. Establish HPCS injection into the RPV to maintain RPV level above -162 inches.

NUREG-1021, Draft Revision 9

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