ML16280A437: Difference between revisions
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| number = ML16280A437 | | number = ML16280A437 | ||
| issue date = 09/12/2016 | | issue date = 09/12/2016 | ||
| title = | | title = 2016-09 Final Op Test | ||
| author name = Gaddy V | | author name = Gaddy V | ||
| author affiliation = NRC/RGN-IV/DRS/OB | | author affiliation = NRC/RGN-IV/DRS/OB | ||
Revision as of 07:17, 10 April 2019
| ML16280A437 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 09/12/2016 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | |
| References | |
| Download: ML16280A437 (321) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: River Bend Nuclear Station Date of Examination: 9/12/201 6 Examination Level: RO SRO Operating Test Number: LOT-201 6 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R - N CRD pump clearance Conduct of Operations R - N Calculation for leakage Equipment Control R - N Electrical Print Reading (Determine effect of removing fuses in RPS system)
Radiation Control R - N Determine emergency entry requirements for high dose Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from (N)ew or (M)odified from
ES-301 Administrative Topics Outline Form ES-301-1 Facility: River Ben Nuclear Station Date of Examination:
9/12/201 6 Examination Level: RO SRO Operating Test Number: LOT-201 6 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R - N Print Reading (RPS fuse removal)
Conduct of Operations R - N Leakage calculation and TS call associated with leakage.
Equipment Control R - N Evaluate a CRD pump clearance
Radiation Control R - N Emergency entry for high dose and who authorizes the entry.
Emergency Plan R - N Emergency Classification NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from (N)ew or (M)odified from
RJPM-NRC-S 1 6-A 1 Rev 3 River Bend Station Initial License Exam Page 1 of 11 Perform a Manual Tagout for Control Rod Drive Pump B CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA VALIDATION TIME:
Average Time (min):
20 PERFORMANCE TIME:
Time Critical No Alt Path N o License Level RO EVALUATION METHOD
- EVALUATION LOCATION
- X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: June 29, 2016 Reviewed: John Fralick Date: July 8, 2016 (Operations Representative)
Approved: Dan James Date: July 14, 2016
(Operations Management)
RJPM-NRC-S 1 6-A 1 Rev. 3 RJPM-NRC-S 1 6-A 1 Rev 3 Page 2 of 11 EXAMINER INFO SHEET Task Standard
- The applicant identified the Tag Type, Equipment/Equipment Description, and Placement Configuration for a manual tagout on Control Rod Drive Pump B IAW the attached key.
Synopsis: eSOMS Clearance Module is unavailable due to a network failure. This task will have the applicant write a paper tagout using the form found in the attachments of EN
-OP-102-01. Only three columns are required to be filled out in accordance with the initiating cue.
NOTE: This JPM is Administrative and will be performed in a classroom
. 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
"
- 2) Initiating Cues
- The CRS has directed you to perfor m a manual tagout on Control Rod Drive Pump 'B' using Attachment 9.3 of EN
-OP-102-01, Tagout Tags Sheet.
Identify the following on the manual Tagout Tags Sheet:
Tag Type Equipment/Equipment Description, and Placement Configuration
- 3) Initial Conditions
- The plant is Mode 1, 100%.
Maintenance is scheduled to replace pump oil on CRD-PC001B, Control Rod Drive Pump 'B'. The eSOMS Clearance Module is unavailable due to problems with the network.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S 1 6-A 1 Rev. 3 RJPM-NRC-S 1 6-A 1 Rev 3 Page 3 of 11 ANSWER KEY Critical Items are:
- Danger NN S-SWG1B ACB 18 OPEN, RACKED OUT or REM
- Danger SCA-PNL8B1 BKR1 4 O FF
- Danger C11-V F 014B CLOSED
- Danger C11-VF015B CLOSED RJPM-NRC-S 1 6-A 1 Rev. 3 RJPM-NRC-S 1 6-A 1 Rev 3 Page 4 of 11 DATA SHEET TASK Title
- Task Number K&A SYSTEM
- K&A RATING
- Perform Hand Written Tagout for CRD Pump B Oil Replacement 300095003001 G 2.1.29 4.1 Rev 2 included recommendation made by the ops validation team.
Rev 3 clarified the task standard and initiating cue to better direct the applicant.
REFERENCES
- APPLICABLE OBJECTIVES PID-36-01A, Rev 21 RLP-HLO-0201, Obj 4 SOP-00 02, Rev 47 E E-001 G, Rev 11 E SK-05RDS02, Rev 1 8 ESK-07RDS01, Rev 04 EN-OP-0102, Rev 18 EN-OP-0102-01, Rev 10 Archived Tagout 1-C1 5-0 1 052-001-C11-PC001 B REQUIRED MATERIALS
- PID-36-01A, Rev 21 SOP-0002, Rev 47 EE-001G, Rev 11 ESK-05RDS02, Rev 18 ESK-07RDS01, Rev 04 EN-OP-0102, Protective and Caution Tagging, Rev 18 Attachment 9.3 of EN
-OP-0102-1, Rev 10 (attached)
LICENSE LEVEL: RO SIMULATOR CONDITIONS
& SETUP: 1. This is a classroom/Admin JPM
- There is no simulator setup but pictures/diagrams must be developed for the applicants use.
CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: The applicant identified the Tag Type, Equipment/Equipment Description, and Placement Configuration for a manual tagout on Control Rod Drive Pump B IAW the attached key
.
RJPM-NRC-S 1 6-A 1 Rev. 3 RJPM-NRC-S 1 6-A 1 Rev 3 Page 5 of 11 PERFORMANCE
- START TIME:
- 1. Procedure Step:
Applicant uses drawings and EN
-OP102-01 Att 9.3 to complete required tagout list Standard Applicant uses Att 9.3 to complete the task Cue Notes 2. *Procedure Step:
Identify the Tag Type, Equipment/Equipment Description, and Placement Configuration to be tagged for a manual tagout of Control Rod Drive Pump B.
Standard Applicant identified the Tag Type, Equipment/Equipment Description, and Placement Configuration for a manual tagout on Control Rod Drive Pump B IAW the attached key. The critical items are as follows:
Danger NNS-SWG1B ACB18 OPEN, RACKED OUT or REM Danger SCA-PNL8B1 BKR14 OFF Danger C11-VF014B CLOSED Danger C11-VF015B CLOSED Cue Notes Provide applicant with attachments as necessary Results SAT UNSAT Terminating Cue: The applicant identified the Tag Type, Equipment/Equipment Description, and Placement Configuration for a manual tagout on Control Rod Drive Pump B IAW the attached key.
This completes this JPM.
STOP TIME:
RJPM-NRC-S 1 6-A 1 Rev. 3 RJPM-NRC-S 1 6-A 1 Rev 3 Page 6 of 11 CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable
. 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S 1 6-A 1 Rev. 3 RJPM-NRC-S 1 6-A 1 Rev 3 Page 7 of 11 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S 1 6-A 1 Rev. 3 RJPM-NRC-S 1 6-A 1 Rev 3 Page 8 of 11 OPERATOR CUE SHEET Initiating Cues
- The CRS has directed you to perfor m a manual tagout on Control Rod Drive Pump 'B' using Attachment 9.3 of EN
-OP-102-01, Tagout Tags Sheet.
Identify the following on the manual Tagout Tags Sheet:
Tag Type Equipment/Equipment Description, and Placement Configuration Initial Conditions
- The plant is mode 1, 100%.
Maintenance is scheduled to replace pump oil on CRD
-PC001B, Control Rod Drive Pump 'B'. The eSOMS Clearance Module is unavailable due to problems with the network.
RJPM-NRC-S 1 6-A 1 Rev. 3 RJPM-NRC-S 1 6-A 1 Rev 3 Page 9 of 11 RJPM-NRC-S 1 6-A 1 Rev. 3 RJPM-NRC-S 1 6-A 1 Rev 3 Page 10 of 11 RJPM-NRC-S 1 6-A 1 Rev. 3 RJPM-NRC-S 1 6-A 1 Rev 3 Page 11 of 11 RJPM-NRC-S 1 6-A 2 Rev 2 River Bend Station Initial License Exam Page 1 of 10 Determine Unidentified Leakage and Leak Rates Manually CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA PERFORMANCE TIME:
Average Time (min):
8 Actual Time (min):
VALIDATION TIME:
Time Critical No Alt Path N o License Level RO EVALUATION METHOD
- EVALUATION LOCATION
- X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: July 9, 2016 Reviewed: John Fralick Date: July 8, 2016
(Operations Representative)
Approved: Dan James Date: July 14, 2016
(Operations Management)
RJPM-NRC-S16-A 2 Rev. 2 RJPM-NRC-S16-A 2 Rev 2 Page 2 of 10 EXAMINER INFO SHEET Task Standard:
The applicant calculated the identified and unidentified leakage rates IAW the attached key
.
Synopsis: The Drains Process Computer is inoperable due to a component failure. This task will have the applicant perform a manual leakage calculation using SOP-0104, Floor and Equipment Drain System, Section 5.2.3.5. The applicant will use attachment 6 in the procedure to calculate values for leakage using columns D through J; K will not be performed for this JPM.
- 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
" NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.
- 2) Initial Conditions
- The plant is operating at 100% power The Drains Process Computer is inoperable due to a component failure Sumps have been pumped down IAW section 5.2.3 of SOP-0104 , Floor and Equipment Drains System, and the appropriate data entered on Attachment 6
- 3) Initiating Cues
- The CRS has directed you to determine identified and unidentified leakage rates manually. Complete columns D through J of Attachment 6 IAW Section 5.2.3.5.3 of SOP-0104, Floor and Equipment Drains System.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S16-A 2 Rev. 2 RJPM-NRC-S16-A 2 Rev 2 Page 3 of 10 DATA SHEET TASK Title:
Task Number K&A SYSTEM
- K&A RATING
- Determine Unidentified Leakage and Leak Rates Manually 231014001001 G2.1.23 2950 36 EA1.01 4.3 / 4.4 3.2 /
3.3 REFERENCES
- APPLICABLE OBJECTIVES SOP-0104, Floor and Equipment Drain RLP-HLO-405, Obj 1 System, Rev 39 Tech Spec 3.4.5 REQUIRED MATERIALS
- SOP-0104, Floor and Equipment Drain System, with marked up Attachments 5 & 6 LICENSE LEVEL:
R O SIMULATOR CONDITIONS
& SETUP: 1. This is a classroom/Admin JPM
- There is no simulator setup but pictures/diagrams must be developed for the applicants use. CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed.
Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: The applicant calculated the identified and unidentified leakage rates IAW the attached key
.
RJPM-NRC-S16-A 2 Rev. 2 RJPM-NRC-S16-A 2 Rev 2 Page 4 of 10 ANSWER KEY Evaluator Notes:
Column H acceptable range can be calculated between 2.
24 and 2.26 Column J acceptable range can be calculated between 4.40 and 4.43
RJPM-NRC-S16-A 2 Rev. 2 RJPM-NRC-S16-A 2 Rev 2 Page 5 of 10 PERFORMANCE
- START TIME:
SOP-0104 Section 5.2.3.5, Perform the following to calculate Primary Containment Leakage Rates:
- 3) Record the following on Attachment 6, Manual Calculation
- Current Leak Rate History on the hour
- 1. Procedure Step:
a) Present time under PUMP STOP TIME Standard NA Cue Notes The handout of Attachment 6 already has the current sump pumpdown data.
- 2. *Procedure Step:
b) Under column D calculate the Unidentified Leakage (UL) by adding the changes in levels of column A to the changes in levels of column B since the previous hourly calculations Standard Applicant calculated the delta from column A (250
-150) as 100 gallons, then calculated the delta from column B (22 5-190) as 35 gallons; applicant then added 100 plus 3 5 and recorded 13 5 gallons in column D Cue Notes Results SAT UNSAT
RJPM-NRC-S16-A 2 Rev. 2 RJPM-NRC-S16-A 2 Rev 2 Page 6 of 10 5.2.3.5. 3) continued
- 3. *Procedure Step:
c) Under column E calculate the Identified Leakage (IL) by entering the changes in level of column C since the previous hourly calculations Standard Applicant calculated the delta from column C (2 8 0-150) and recorded 130 gallons in column E Cue Notes Results SAT UNSAT 4. Procedure Step:
d) Under column F calculate the Total Leakage by adding the values of UL column D and IL column E
. Standard Applicant calculated the sum of column D and E (13 5+130) and recorded 26 5 gallons in column F Cue Notes Results SAT UNSAT 5. Procedure Step:
e) Record 60 minutes in column G.
Standard Applicant recorded 60 minutes in column G.
Cue Notes Results SAT UNSAT RJPM-NRC-S16-A 2 Rev. 2 RJPM-NRC-S16-A 2 Rev 2 Page 7 of 10 5.2.3.5. 3) continued
- 6. *Procedure Step:
f) Calculate Unidentified Leakage Rate (ULR) in column H by dividing the UL from column D by column G
. Standard Applicant calculated the quotient of column D by column G (13 5 / 60) and recorded a value of between 2.24 and 2.26 gallons per hour in column H.
Cue Notes Results SAT UNSAT 7. Procedure Step: g) Calculate Total Leakage Rate (TLR) in column J by dividing the TL in column F by column G
. Standard Applicant calculated the quotient of column F by column G (26 5 / 60) and recorded a value of between 4.40 and 4.43 gallons per hour in column H.
Cue Notes Results SAT UNSAT Terminating Cue: The applicant calculated the identified and unidentified leakage rates IAW the attached key.
STOP TIME:
This completes this JPM.
RJPM-NRC-S16-A 2 Rev. 2 RJPM-NRC-S16-A 2 Rev 2 Page 8 of 10 CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable.
- 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S16-A 2 Rev. 2 RJPM-NRC-S16-A 2 Rev 2 Page 9 of 10 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S16-A2 Rev. 2 River Bend Station Initial License Exam Page 10 of 10 OPERATOR CUE SHEET Initial Conditions
- The plant is operating at 100% power The Drains Process Computer is inoperable due to a component failure Sumps have been pumped down IAW section 5.2.3 of SOP-0104 , Floor and Equipment Drains System, and the appropriate data entered on Attachment 6
. Initiating Cues
- The CRS has directed you to determine identified and unidentified leakage rates manually. Complete columns D through J of Attachment 6 IAW Section 5.2.3.5.3 of SOP-0104, Floor and Equipment Drains System.
CONTINUOUS USEATTACHMENT 6PAGE 1 OF 1MANUAL CALCULATION - CURRENT LEAK RATE HISTORYSOP-0104 REV - 039 PAGE 105 OF 119DATE:____9/12/2016___PumpStopTime A B C D E F G*H J KDRYWELLFLOOR DRSUMPLEVELDFR-LI105PEDESTALFLOOR DRSUMPLEVELDFR-LI128DRYWELLEQPT DRSUMPLEVELDER-LI118UN-IDENTIFIED LEAKAGE UL (A +B)IDENTIFIED LEAKAGE ILCTOTAL LEAKAGE(D+E)DELTATIME(min)UN-IDENTIFIED LEAKAGERATED / GTOTAL LEAKAGERATEF / GTLR24 AVG I F I F I F0030 160 150 NA 190 270 150 10 120 130 60 0.17 2.17 2.120130 160 150 NA 190 270 150 10 120 130 60 0.17 2.17 2.120230 170 150 195 190 280 150 25 130 155 60 0.42 2.58 2.140330 165 150 195 190 270 150 20 120 140 60 0.33 2.33 2.150430 175 150 195 190 270 150 30 120 150 60 0.50 2.50 2.160530 175 150 195 190 280 150 30 130 160 60 0.50 2.67 2.190630 180 150 195 190 270 150 35 120 155 60 0.58 2.58 2.210730 180 150 195 190 270 150 35 120 155 60 0.58 2.58 2.230830 190 150 195 190 280 150 45 130 175 60 0.75 2.92 2.260930 190 150 200 190 280 150 50 130 180 60 0.83 3.00 2.301030 195 150 200 190 270 150 55 120 175 60 0.92 2.92 2.331130 200 150 200 190 270 150 60 120 180 60 1.00 3.00 2.371230 220 150 200 190 280 150 80 130 210 60 1.33 3.50 2.431330 230 150 210 190 280 150 100 130 230 60 1.67 3.83 2.501430 250 150 225 190 280 150* TECHNICAL SPECIFICATION LIMITING CONDITIONS RJPM-NRC-S 1 6-A 3 Rev 2 River Bend Station Initial License Exam Page 1 of 8 Determine the Effect of Removing a Fuse in RPS System CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA PERFORMANCE TIME:
Average Time (min):
28 Actual Time (min):
VALIDATION TIME:
Time Critical No Alt Path N o License Level RO EVALUATION METHOD
- EVALUATION LOCATION
- X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: June 30, 2016 Reviewed: John Fralick Date: July 8, 2016
(Operations Representative)
Approved: Dan James Date: July 14, 2016
(Operations Management)
RJPM-NRC-S 1 6-A 3 Rev. 2 RJPM-NRC-S 1 6-A 3 Rev 2 Page 2 of 8 EXAMINER INFO SHEET Task Standard
- The applicant determined the effects of removing fuse F50B in Panel P 69 2 in accordance with the attached key.
Synopsis: The applicant will use plant drawings to determine the effects of removing a fuse in the RPS system to support a maintenance activity.
NOTE: This JPM is Administrative and will be performed in a classroom
. 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied. Inform me when you have completed the task.
" 2) Initiating Cues
- Given the appropriate drawings, the CRS has directed you to determine the following upon the removal of the fuse
- 2. Complete the following table:
Component Affected?
Associated Effect (position or condition)
- 1. SDV Vent and Drain Valves (F010, F011, F180, F181)
Y / N 2. 3-way Vent Valves for SDV Vent and Drain Valves (F009 & F182)
Y / N 3. Div 2 solenoid valves for 3-way Vent Valves Y / N 4. White Lights for Backup Scram Valve "B" Y / N 3) Initial Conditions
- A maintenance activity requires the removal of a fuse in the RPS system.
Electricians are ready to remove fuse F 50B in Panel P69 2 for work to begin
. 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S 1 6-A 3 Rev. 2 RJPM-NRC-S 1 6-A 3 Rev 2 Page 3 of 8 ANSWER KEY Critical Steps are marked with an asterisk (*)
Initiating Cues
- Given the appropriate drawings, the CRS has directed you to determine the following upon the removal of the fuse
- 2. Complete the following table:
Component Affected?
Associated Effect (position or condition)
- 1. SDV Vent and Drain Valves (F010, F011, F180, F181)
Y / N None - will not re
-position 2. 3-way Vent Valves for SDV Vent and Drain Valves (F009 & F182)
Y / N None - will not re
-position *3. Div 2 solenoid valves for 3-way Vent Valves Y / N Solenoids will de
-energize 4. White Lights for Backup Scram Valve "B" Y / N One light will extinguish
RJPM-NRC-S 1 6-A 3 Rev. 2 RJPM-NRC-S 1 6-A 3 Rev 2 Page 4 of 8 DATA SHEET TASK Title
- Task Number K&A SYSTEM
- K&A RATING
- Use Plant Drawings to Determine Effect of Fuse Removal 300246003001 299003001001 G 2.2.15
3.9 REFERENCES
- APPLICABLE OBJECTIVES G E-828E531AA RLP-HLO-542-1, Obj 5, 6, 7 REQUIRED MATERIALS
& SETUP: 1. This is a classroom/Admin JPM
- There is no simulator setup but pictures/diagrams must be developed for the applicants use. CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires th e JPM to be evaluated as Unsatisfactory.
TASK STANDARD: The applicant determined the effects of removing fuse F50B in Panel P692 in accordance with the attached key.
RJPM-NRC-S 1 6-A 3 Rev. 2 RJPM-NRC-S 1 6-A 3 Rev 2 Page 5 of 8 PERFORMANCE
- START TIME:
- 1. *Procedure Step:
Determine the scram condition of the RPS system
. Standard Applicant determined that is it not a scram condition (as indicated in the attached key).
Cue Notes Provide applicant with drawings and procedures as necessary Results SAT UNSAT 2. *Procedure Step:
Complete the table affected by removal of fuse F50B. Standard Applicant determined th at: the Vent and Drain valves do not re
-position and the Div 2 solenoids for SDV vent and drain valves de
-energize (as indicated in the attached key). Cue Notes Provide applicant with drawings and procedures as necessary Results SAT UNSAT Terminating Cue:
The applicant determined the effects of removing fuse F50B in Panel P692 in accordance with the attached key
. This completes this JPM.
STOP TIME:
RJPM-NRC-S 1 6-A 3 Rev. 2 RJPM-NRC-S 1 6-A 3 Rev 2 Page 6 of 8 CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable
. 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S 1 6-A 3 Rev. 2 RJPM-NRC-S 1 6-A 3 Rev 2 Page 7 of 8 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S 1 6-A 3 Rev. 2 RJPM-NRC-S 1 6-A 3 Rev 2 Page 8 of 8 OPERATOR CUE SHEET Initial Conditions
- A maintenance activity requires the removal of a fuse in the RPS system.
Electricians are ready to remove fuse F 50B in panel H13
-P69 2 for work to begin
. Initiating Cues
- Given the appropriate drawings, the CRS has directed you to determine the followi ng upon the removal of the fuse
- 2. Complete the following table:
Component Affected?
Associated Effect (position or condition)
- 1. SDV Vent and Drain Valves (F010, F011, F180, F181)
Y / N 2. 3-way Vent Valves for SDV Vent and Drain Valves (F009 & F182)
Y / N 3. Div 2 solenoid valves for 3-way Vent Valves Y / N 4. White Lights for Backup Scram Valve "B" Y / N RJPM-NRC-S 1 6-A 4 Rev 2 River Bend Station Initial License Exam Page 1 of 8 Determine Emergency Entry Requirements for a High Dose Situation CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA PERFORMANCE TIME:
Average Time (min):
1 5 Actual Time (min):
VALIDATION TIME:
Time Critical No Alt Path N o License Level RO EVALUATION METHOD
- EVALUATION LOCATION
- X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: Ju ly 6, 2016 Reviewed: John Fralick Date: July 8, 2016
(Operations Representative)
Approved: Dan James Date: July 14, 2016
(Operations Management)
RJPM-NRC-S 1 6-A 4 Rev. 2 RJPM-NRC-S 1 6-A 4 Rev 2 Page 2 of 8 EXAMINER INFO SHEET Task Standard
- The applicant determined admin dose limits are suspended and that the allowed dose for performing this task in a high rad area during an emergency is 4350 mrem exactly.
Synopsis:
NOTE: This JPM is Administrative and will be performed in a classroom
. 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
" 2) Initial Conditions
- The Emergency Response Organization is operational and the site has declared a Site Area Emergency due to a station blackout.
An entry must be made to the RWCU Pump Room to stop a steam leak.
Dose rates in the vicinity of the steam leak isolation valves are 3 rem per hour.
- 3) Initiating Cues
- The CRS has directed you to determine the following:
- 1. The RBS Routine Administrative Total Effective Dose Equivalent (TEDE) whole body exposure limit is _____ per year; the 10CFR20 TEDE Radiation Exposure limit is _____ per year.
- 2. Based on the initial conditions, the administrative exposure limits for River Bend Station are applicable / suspended. (circle one)
- 3. Determine the dose allowed by an operator whose current yearly dose is 650 mrem to isolate the leak in the RWCU Pump Room without exceeding the correct limit.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S 1 6-A 4 Rev. 2 RJPM-NRC-S 1 6-A 4 Rev 2 Page 3 of 8 ANSWER KEY Complete the following:
- 1. The RBS Routine Administrative Total Effective Dose Equivalent (TEDE) whole body exposure limit is _2 R (2000 mR)_ per year; the 10CFR20 TEDE Radiation Exposure limit is __5R (5000 mR)__ per year.
- 2. Based on the initial conditions, the administrative exposure limits for River Bend Station are applicable / suspended
. (circle one)
- 3. Determine the dose allowed by an operator whose current yearly dose is 650 mrem to isolate the leak in the RWCU Pump Room without exceeding the correct limit
. 5000 mrem (10CFR limit)
- 650 mrem (current dose) 4350 mrem (allowed dose)
RJPM-NRC-S 1 6-A 4 Rev. 2 RJPM-NRC-S 1 6-A 4 Rev 2 Page 4 of 8 DATA SHEET TASK TITLE: Task Number K&A SYSTEM
- K&A RATING
- Determine Emergency Entry Requirements for a High Dose Situation.
300 241 00 4 00 2 301023005003 G 2.3.4 G 2.3.12 3.2 3.2 Rev 2 corrected the initiating cue to better reflect task standard, per the NRC validation.
REFERENCES
- APPLICABLE OBJECTIVES EN-RP-201, Dosimetry Administration, Rev 4 EIP-2-012, Radiation Exposure Controls, Rev 21 10CFR20.1201, Occupational Dose Limits REQUIRED MATERIALS
- EIP-2-012, Radiation Exposure Controls, Rev 21 Calculator LICENSE LEVEL: RO SIMULATOR CONDITIONS
& SETUP: 1. This is a classroom/Admin JPM
- There is no simulator setup but pictures/diagrams may need to be developed for the applicants use. CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: The applicant determined admin dose limits are suspended and that the allowed dose for performing this task in a high rad area during an emergency is 4350 mrem exactly.
RJPM-NRC-S 1 6-A 4 Rev. 2 RJPM-NRC-S 1 6-A 4 Rev 2 Page 5 of 8 PERFORMANCE
- START TIME:
- 1. Procedure Step:
Identify the Administrative and 10CFR dose limits.
Standard Applicant identified the Administrative and 10CFR dose limits are 2000mR and 5000mR (respectively), in accordance with the attached key. Cue Notes 2. *Procedure Step:
Determine Administrative Dose Limits should be suspended
. Standard Applicant determined that Administrative Dose Limits should be suspended in accordance with the attached key.
Cue Notes Results SAT UNSAT 3. *Procedure Step:
Calculate the allowed dose for a task during emergency conditions
. Standard Applicant calculated allowed dose to be 4350 mrem (in accordance with attached key). No error bars allowed.
Cue Notes Results SAT UNSAT Terminating Cue: The applicant determined admin dose limits are suspended and that the allowed dose for performing this task in a high rad area during an emergency is 4350 mrem exactly.
This completes this JPM.
STOP TIME:
RJPM-NRC-S 1 6-A 4 Rev. 2 RJPM-NRC-S 1 6-A 4 Rev 2 Page 6 of 8
CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable
. 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S 1 6-A 4 Rev. 2 RJPM-NRC-S 1 6-A 4 Rev 2 Page 7 of 8 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S 1 6-A 4 Rev. 2 RJPM-NRC-S 1 6-A 4 Rev 2 Page 8 of 8 OPERATOR CUE SHEET Initial Conditions
- The Emergency Response Organization is operational and the site has declared a Site Area Emergency due to a station blackout.
An entry must be made to the RWCU Pump Room to stop a steam leak.
Dose rates in the vicinity of the steam leak isolation valves are 3 rem per hour.
Initiating Cues
- The CRS has directed you to determine the following:
- 1. The RBS Routine Administrative Total Effective Dose Equivalent (TEDE) whole body exposure limit is _____ per year; the 10CFR20 TEDE Radiation Exposure limit is _____ per year.
- 2. Based on the initial conditions, the administrative exposure limits for River Bend Station are applicable / suspended
. (circle one)
- 3. Determine the dose allowed by an operator whose current yearly dose is 650 mrem to isolate the leak in the RWCU Pump Room without exceeding the correct limit
.
RJPM-NRC-S 1 6-A 5 Rev 2 River Bend Station Initial License Exam Page 1 of 10 Evaluate a Manual Tagout for Control Rod Drive Pump B CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA PERFORMANCE TIME:
Average Time (min):
12 Actual Time (min):
VALIDATION TIME:
Time Critical No Alt Path N A License Level SRO EVALUATION METHOD
- EVALUATION LOCATION
- X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: June 29, 2016 Reviewed: John Fralick Date: July 8, 2016
(Operations Representative)
Approved: Dan James Date: July 14, 2016
(Operations Management)
RJPM-NRC-S 1 6-A 5 Rev. 2 RJPM-NRC-S 1 6-A 5 Rev 2 Page 2 of 10 EXAMINER INFO SHEET Task Standard
- Applicant reviewed the prepared tagout and determined that it is (1) not approved (2) due to not including
- Danger C11-VF015B, CRD Pump B Recirc Line Isolation Valve CLOSED Danger CKTBRK-SCA-PNL8B1 BKR 14 OFF Rev 2 incorporated comments from NRC Prep Week to clarify task standards Synopsis: eSOMS Clearance Module is unavailable due to a network failure. This task will have the applicant review a paper tagout using the form found in the attachments of EN
-OP-102-01 and determine if the tagout could be approved.
NOTE: This JPM is Administrative and will be performed in a classroom
. 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
"
- 2) Initiating Cues
- You are the CRS. Review the attached manual tagout (non-shaded areas only) and approve or disapprove as appropriate.
If disapproved, list the reason(s) why.
- 3) Initial Conditions
- The plant is Mode 1, 100%.
Maintenance is scheduled to replace pump oil on CRD-PC001B, Control Rod Drive Pump B. The eSOMS Clearance Module is unavailable due to problems with the network.
A Reactor Operator has prepared a manual tagout using Attachment 9.3 of EN
-OP-102-01, Tagout Tags Sheet.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S 1 6-A 5 Rev. 2 RJPM-NRC-S 1 6-A 5 Rev 2 Page 3 of 10 ANSWER KEY Critical Items are:
- (1) Tagout is approved / not approved. (circle one)
- (2) Applicant adds the following:
Danger C11-VF015B, CRD PUMP B RECIRC LINE ISOL VLV CLOSED Danger SCA-PNL8B1 BKR 18, CRD Aux Oil Pump B OFF RJPM-NRC-S 1 6-A 5 Rev. 2 RJPM-NRC-S 1 6-A 5 Rev 2 Page 4 of 10 DATA SHEET TASK Title
- Task Number K&A SYSTEM
- K&A RATING
- Perform Hand Written Tagout for CRD Pump B Oil Replacement 300095003001 G 2.1.29
4.1 REFERENCES
- APPLICABLE OBJECTIVES PID-36-01A, Rev 21 RLP-HLO-0201, Obj 4 SOP-00 02, Rev 47 E E-001 G, Rev 11 E SK-05RDS02, Rev 1 8 ESK-07RDS01, Rev 04 EN-OP-0102, Rev 18 and EN-OP-0102-01, Forms, Rev 10 Archived Tagout 1-C1 5-0 1 052-001-C11-PC001 B REQUIRED MATERIALS
- PID-36-01A, Rev 21 SOP-0002, Rev 47 EE-001G, Rev 11 ESK-05RDS02, Rev 18 ESK-07RDS01, Rev 04 EN-OP-102, Protective and Caution Tagging, Rev 18 Attachment 9.3 of EN
-OP-0102-1 (attached)
LICENSE LEVEL: SRO SIMULATOR CONDITIONS
& SETUP: 1. This is a classroom/Admin JPM
- There is no simulator setup but pictures/diagrams must be developed for the applicants use. CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: The applicant reviewed the prepared tagout and determined that it is (1) not approved, (2) due to not including
- Danger C11-VF015B, CRD Pump B Recirc Line Isolation Valve CLOSED Danger CKTBRK-SCA-PNL8B1 BKR 14 OFF RJPM-NRC-S 1 6-A 5 Rev. 2 RJPM-NRC-S 1 6-A 5 Rev 2 Page 5 of 10 PERFORMANCE
- START TIME: 1. *Procedure Step:
Determine if Tagout is approved for Control Rod Drive Pump B
. Standard Applicant used data provided to disapprove the tagout
. Cue Notes Provide applicant with attachments as necessary Results SAT UNSAT 2. *Procedure Step:
List the reason(s) why this tagout is not approved.
Standard Applicant used data provided to state that the tagout did not include valve C11-VF015B or Circuit Breaker 14 on SCA Panel 8B1
. Cue Notes Results SAT UNSAT Terminating Cue:
Applicant reviewed the prepared tagout and determined that it is (1) not approved (2) due to not including
- Danger C11-VF015B, CRD Pump B Recirc Line Isolation Valve CLOSED Danger CKTBRK-SCA-PNL8B1 BKR 14 OFF This completes this JPM. STOP TIME:
RJPM-NRC-S 1 6-A 5 Rev. 2 RJPM-NRC-S 1 6-A 5 Rev 2 Page 6 of 10 CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable
. 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S 1 6-A 5 Rev. 2 RJPM-NRC-S 1 6-A 5 Rev 2 Page 7 of 10 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S 1 6-A 5 Rev. 2 RJPM-NRC-S 1 6-A 5 Rev 2 Page 8 of 10 OPERATOR CUE SHEET Initiating Cues: You are the CRS. Review the attached manual tagout (shaded areas only) and approve or disapprove as appropriate.
If disapproved, list the reason(s) why.
Initial Conditions
- The plant is Mode 1, 100%.
Maintenance is scheduled to replace pump oil on CRD-PC001B, Control Rod Drive Pump B. The eSOMS Clearance Module is unavailable due to problems with the network.
A Reactor Operator has prepared a manual tagout using Attachment 9.3 of EN
-OP-102-01, Tagout Tags Sheet.
(1) Tagout is approved
/ not approved. (circle one)
(2) If disapproved, list the reason(s) why:
RJPM-NRC-S 1 6-A 5 Rev. 2 RJPM-NRC-S 1 6-A 5 Rev 2 Page 9 of 10 RJPM-NRC-S 1 6-A 5 Rev. 2 RJPM-NRC-S 1 6-A 5 Rev 2 Page 10 of 10 RJPM-NRC-S 1 6-A 6 Rev 1 River Bend Station Initial License Exam Page 1 of 10 Determine Unidentified Leakage and Leak Rates Manually CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA PERFORMANCE TIME:
Average Time (min):
8 Actual Time (min):
VALIDATION TIME:
Time Critical No Alt Path N o License level SRO EVALUATION METHOD
- EVALUATION LOCATION
- X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: July 9, 2016 Reviewed: John Fralick Date: July 8, 2016
(Operations Representative)
Approved: Dan James Date: July 14, 2016
(Operations Management)
RJPM-NRC-S16-A 6 Rev. 1 RJPM-NRC-S16-A 6 Rev 1 Page 2 of 10 EXAMINER INFO SHEET Task Standard:
The applicant calculated the identified and unidentified leakage rates and tech spec entry IAW the attached key
.
Synopsis: The Drains Process Computer is inoperable due to a component failure. This task will have the applicant perform a manual leakage calculation using SOP-0104, Floor and Equipment Drain System, 5.2.3.5. The applicant will use attachment 6 in the procedure to calculate values for leakage using columns D through J; K will not be performed for this JPM. The SRO applicant will then go on to determine that Tech Specs 3.4.5 Condition B should be entered. 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied. Inform me when you have completed the task.
" NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.
- 2) Initial Conditions
- The plant is operating at 100% power The Drains Process Computer is inoperable due to a component failure Sumps have been pumped down IAW section 5.2.3 of SOP-0104 , Floor and Equipment Drains System, and the appropriate data entered on Attachment 6
- 3) Initiating Cues
- The Shift Manager has directed you to determine identified and unidentified leakage rates manually. Complete columns D through J of Attachment 6 IAW Section 5.2.3.5.3 of SOP-0104, Floor and Equipment Drains System and determine any tech spec entries (if any) that are required
, with a basis for your conclusion.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S16-A 6 Rev. 1 RJPM-NRC-S16-A 6 Rev 1 Page 3 of 10 DATA SHEET TASK Title:
Task Number K&A SYSTEM
- K&A RATING
- Determine Unidentified Leakage and Leak Rates Manually 231014001001 G2.1.23 2950 36 EA1.01 4.3 / 4.4 3.2 /
3.3 REFERENCES
- APPLICABLE OBJECTIVES SOP-0104, Floor and Equipment Drain RLP-HLO-405, Obj 1 System, Rev 39 Tech Spec 3.4.5 REQUIRED MATERIALS
- SOP-0104, Floor and Equipment Drai n System, with marked up Attachments 5 & 6 Copy of Tech Specs LICENSE LEVEL: SRO SIMULATOR CONDITIONS
& SETUP: 1. This is a classroom/Admin JPM
- There is no simulator setup but pictures/diagrams must be developed for the applicants use. CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed.
Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: The applicant calculated the identified and unidentified leakage rates and tech spec entry IAW the attached key
.
RJPM-NRC-S16-A 6 Rev. 1 RJPM-NRC-S16-A 6 Rev 1 Page 4 of 10 ANSWER KEY Evaluator Notes:
Column H acceptable range can be calculated between 2.24 and 2.26 Column J acceptable range can be calculated between 4.40 and 4.43
- Critical Task:
(The reason may be paraphrase d) Enter Tech Spec 3.4.5 Condition B.
Due to RCS Leakage where there must be less than or equal to a 2 gallon per minute increase in unidentified leakage within the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period in mode 1.
According to the 1430 calculations, a 2.08 gpm increase has occurred.
RJPM-NRC-S16-A 6 Rev. 1 RJPM-NRC-S16-A 6 Rev 1 Page 5 of 10 PERFORMANCE
- START TIM E: SOP-0104 Section 5.2.3.5, Perform the following to calculate Primary Containment Leakage Rates:
- 3) Record the following on Attachment 6, Manual Calculation
- Current Leak Rate History on the hour
- 1. Procedure Step:
a) Present time under PUMP STOP TIME Standard NA Cue Notes The handout of Attachment 6 already has the current sump pumpdown data.
- 2. *Procedure Step:
b) Under column D calculate the Unidentified Leakage (UL) by adding the changes in levels of column A to the changes in levels of column B since the previous hourly calculations Standard Applicant calculated the delta from column A (250
-150) as 100 gallons, then calculated the delta from column B (22 5-190) as 35 gallons; applicant then added 100 plus 3 5 and recorded 13 5 gallons in column D Cue Notes Results SAT UNSAT
RJPM-NRC-S16-A 6 Rev. 1 RJPM-NRC-S16-A 6 Rev 1 Page 6 of 10 5.2.3.5. 3) continued
- 3. *Procedure Step:
c) Under column E calculate the Identified Leakage (IL) by entering the changes in level of column C since the previous hourly calculations Standard Applicant calculated the delta from column C (2 8 0-150) and recorded 130 gallons in column E Cue Notes Results SAT UNSAT 4. Procedure Step:
d) Under column F calculate the Total Leakage by adding the values of UL column D and IL column E. Standard Applicant calculated the sum of column D and E (13 5+130) and recorded 26 5 gallons in column F Cue Notes Results SAT UNSAT 5. Procedure Step:
e) Record 60 minutes in column G.
Standard Applicant recorded 60 minutes in column G.
Cue Notes Results SAT UNSAT RJPM-NRC-S16-A 6 Rev. 1 RJPM-NRC-S16-A 6 Rev 1 Page 7 of 10 5.2.3.5. 3) continued
- 6. *Procedure Step:
f) Calculate Unidentified Leakage Rate (ULR) in column H by dividing the UL from column D by column G
. Standard Applicant calculated the quotient of column D by column G (13 5 / 60) and recorded a value of between 2.24 and 2.26 gallons per minute in column H.
Cue Notes Results SAT UNSAT 7. Procedure Step:
g) Calculate Total Leakage Rate (TLR) in column J by dividing the TL in column F by column G
. Standard Applicant calculated the quotient of column F by column G (265 / 60) and recorded a value of between 4.40 and 4.43 gallons per hour in column H.
Cue Notes Results SAT UNSAT RJPM-NRC-S16-A 6 Rev. 1 RJPM-NRC-S16-A 6 Rev 1 Page 8 of 10 8. *Procedure Step:
Determine Tech Spec entry (if any) and reason for entry
. Standard Applicant determined that TS 3.4.5 Condition B should be entered based on greater than 2 gpm increase in unidentified leakage within the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
Cue Notes Results SAT UNSAT Terminating Cue: The applicant calculated the identified and unidentified leakage rates and tech spec entry IAW the attached key.
STOP TIME:
This completes this JPM.
CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable.
- 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S16-A 6 Rev. 1 RJPM-NRC-S16-A 6 Rev 1 Page 9 of 10 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
River Bend Station Initial License Exam Page 10 of 10 OPERATOR CUE SHEET Initial Conditions
- The plant is operating at 100% power The Drains Process Computer is inoperable due to a component failure Sumps have been pumped down IAW section 5.2.3 of SOP-0104 , Floor and Equipment Drains System, and the appropriate data entered on Attachment 6
. Initiating Cues
- The Shift Manager has directed you to determine identified and unidentified leakage rates manually. Complete columns D through J of Attachment 6 IAW Section 5.2.3.5.3 of SOP-0104, Floor and Equipment Drains System and determine any tech spec entries (if any) that are required, with a basis for your conclusion.
RJPM-NRC-S 1 6-A 7 Rev 1 River Bend Station Initial License Exam Page 1 of 7 Determine the Effect of Removing a Fuse in RPS CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA PERFORMANCE TIME:
Average Time (min):
22 Actual Time (min):
VALIDATION TIME:
Time Critical No Alt Path N A License Level S RO EVALUATION METHOD
- EVALUATION LOCATION
- X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: June 30, 2016 Reviewed: John Fralick Date: July 8, 2014
(Operations Representative)
Approved: Dan James Date: July 14, 2016
(Operations Management)
RJPM-NRC-S 1 6-A 7 Rev. 1 RJPM-NRC-S 1 6-A 7 Rev 1 Page 2 of 7 EXAMINER INFO SHEET Task Standard
- The applicant determined the effects of removing fuse F50B in Panel P69 2 in accordance with the attached key.
Synopsis: The applicant will use plant drawings to determine the effects of removing a fuse in the RPS system to support a maintenance activity.
NOTE: This JPM is Administrative and will be performed in a classroom
. 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied. Inform me when you have completed the task.
" 2) Initiating Cues
- Given the appropriate drawings, the CRS has directed you to determine the following upon the removal of the fuse
- 2. Complete the following table:
Component Affected?
Associated Effect (position or condition)
- 1. SDV Vent and Drain Valves (F010, F011, F180, F181)
Y / N 2. 3-way Vent Valves for SDV Vent and Drain Valves (F009 & F182)
Y / N 3. Div 2 solenoid valves for 3-way Vent Valves Y / N 4. White Lights for Backup Scram Valve "B" Y / N 3) Initial Conditions
- A maintenance activity requires the removal of a fuse in the RPS system.
Electricians are ready to remove fuse F 50B in panel H13
-P69 2 for work to begin
. 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S 1 6-A 7 Rev. 1 RJPM-NRC-S 1 6-A 7 Rev 1 Page 3 of 7 ANSWER KEY Critical Steps are marked with an asterisk (*)
Initiating Cues
- Given the appropriate drawings, the CRS has directed you to determine the following upon the removal of the fuse
- 2. Complete the following table:
Component Affected?
Associated Effect (position or condition)
- 1. SDV Vent and Drain Valves (F010, F011, F180, F181)
Y / N None - will not re
-position 2. 3-way Vent Valves for SDV Vent and Drain Valves (F009 & F182)
Y / N None - will not re
-position *3. Div 2 solenoid valves for 3-way Vent Valves Y / N Solenoids will de
-energize 4. White Lights for Backup Scram Valve "B" Y / N One light will extinguish
RJPM-NRC-S 1 6-A 7 Rev. 1 RJPM-NRC-S 1 6-A 7 Rev 1 Page 4 of 7 DATA SHEET TASK Title
- Task Number K&A SYSTEM
- K&A RATING
- Use Plant Drawings to Determine Effect of Fuse Removal 300246003001 299003001001 G 2.2.15
3.9 REFERENCES
- APPLICABLE OBJECTIVES G E-828E531AA RLP-HLO-542-1, Obj 5, 6, 7 REQUIRED MATERIALS
- GE-828E531AA Sheets 1, 2, 6, 9, and 11 SIMULATOR CONDITIONS
& SETUP: 1. This is a classroom/Admin JPM
- There is no simulator setup but pictures/diagrams must be developed for the applicants use. CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: The applicant determined the effects of removing fuse F50B in Panel P692 in accordance with the attached key.
RJPM-NRC-S 1 6-A 7 Rev. 1 RJPM-NRC-S 1 6-A 7 Rev 1 Page 5 of 7 PERFORMANCE
- START TIME:
- 1. *Procedure Step:
Determine the scram condition of the RPS system
. Standard Applicant determined the fail position in accordance with the attached key.
Cue Notes Provide applicant with attachments as necessary Results SAT UNSAT 2. *Procedure Step:
Determine component positions affected by removal of fuse F 50B. Standard Applicant determined the position(s) of other components affected in accordance with the attached key.
Cue Notes Provide applicant with attachments as necessary Results SAT UNSAT Terminating Cue:
The applicant determined the effects of removing fuse F 50B in Panel P 6 5 2 in accordance with the attached key
. This completes this JPM. STOP TIME:
CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable
. 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S 1 6-A 7 Rev. 1 RJPM-NRC-S 1 6-A 7 Rev 1 Page 6 of 7 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S 1 6-A 7 Rev. 1 RJPM-NRC-S 1 6-A 7 Rev 1 Page 7 of 7 OPERATOR CUE SHEET Initial Conditions
- A maintenance activity requires the removal of a fuse in the RPS system.
Electricians are ready to remove fuse F 50B in panel H13
-P69 2 for work to begin
. Initiating Cues
- Given the appropriate drawings, the CRS has directed you to determine the following upon the removal of the fuse
- 2. Complete the following table:
Component Affected?
Associated Effect (position or condition)
- 1. SDV Vent and Drain Valves (F010, F011, F180, F181)
Y / N 2. 3-way Vent Valves for SDV Vent and Drain Valves (F009 & F182)
Y / N 3. Div 2 solenoid valves for 3-way Vent Valves Y / N 4. White Lights for Backup Scram Valve "B" Y / N RJPM-NRC-S 1 6-A 8 Rev 2 River Bend Station Initial License Exam Page 1 of 8 Determine Emergency Entry Requirements for a High Dose Situation and Identify Who Authorizes the Entry CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA PERFORMANCE TIME: Average Time (min):
1 5 Actual Time (min):
VALIDATION TIME:
Time Critical No Alt Path N o License Level SRO EVALUATION METHOD
- EVALUATION LOCATION
- X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: Ju ly 6, 2016 Reviewed: John Fralick Date: July 8, 2016
(Operations Representative)
Approved: Dan James Date: July 14, 2016
(Operations Management)
RJPM-NRC-S 1 6-A 8 Rev. 2 RJPM-NRC-S 1 6-A 8 Rev 2 Page 2 of 8 EXAMINER INFO SHEET Task Standard
- The applicant determined emergency allowed dose of 9350 mrem for performing a task in a high rad area and identified the Emergency Director or the Emergency Plant Manager as authorize d to allow the entry IAW the attached key.
Synopsis: NOTE: This JPM is Administrative and will be performed in a classroom
. 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied. Inform me when you have completed the task.
" 2) Initial Conditions
- The Emergency Response Organization is operational and the site has declared a Site Area Emergency due to a station blackout.
An entry must be made to the RWCU Pump Room to stop a steam leak. Dose rates in the vicinity of the steam leak isolation valves are 13 rem per hour.
- 3) Initiating Cues
- The CRS has directed you to determine the following:
- 1. The RBS Routine Administrative Total Effective Dose Equivalent (TEDE) whole body exposure limit is _______ per year; the 10CFR20 TEDE Radiation Exposure limit is _______ per year; and the Emergency TEDE limit for immediate actions taken to prevent major damage to equipment, prevent the release of radioactive materials, or control fires i s _________.
- 2. Based on the initial conditions, the administrative exposure limits of the RBS Radiation Protection Plan, RBNP
-024 and RBNP
-202 are applicable / suspended. (circle one)
- 3. Determine the dose allowed by an operator whose current yearly dose is 650 mrem to isolate the leak in the RWCU Pump Room without exceeding the correct limit
. 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S 1 6-A 8 Rev. 2 RJPM-NRC-S 1 6-A 8 Rev 2 Page 3 of 8 ANSWER KEY Complete the following:
- 1. The RBS Routine Administrative Total Effective Dose Equivalent (TEDE) whole body exposure limit is _2 R (2000 mR)_ per year; the 10CFR20 TEDE Radiation Exposure limit is __5R (5000 mR)__ per year
- and the Emergency TEDE limit for immediate actions taken to prevent major damage to equipment, prevent the release of radioactive materials, or control fires is
__10R (10,000 mR)
__. *2. Based on the initial conditions, the administrative exposure limits of the RBS Radiation Protection Plan are applicable / suspended
. (circle one)
- 3. Determine the dose allowed by an operator whose current yearly dose is 650 mrem to isolate the leak in the RWCU Pump Room without exceeding the correct limit
. 10000 mrem (10CFR limit)
- 650 mrem (current dose) 9350 mrem (allowed dose)
- 4. Identify who must authorize this entry.
One of the following:
Emergency Director or Emergency Plant Manager
RJPM-NRC-S 1 6-A 8 Rev. 2 RJPM-NRC-S 1 6-A 8 Rev 2 Page 4 of 8 DATA SHEET TASK TITLE: Task Number K&A SYSTEM
- K&A RATING
- Determine Emergency Entry Requirements for a High Dose Situation.
300 241 00 4 00 2 301023005003 G 2.3.4 G 2.3.12 3.7 3.7 Rev 2 corrected the initiating cue to better reflect task standard, per the NRC validation.
REFERENCES
- APPLICABLE OBJECTIVES EN-RP-201, Dosimetry Administration, Rev 4 EIP-2-012, Radiation Exposure Controls, Rev 21 10CFR20.1201, Occupational Dose Limits REQUIRED MATERIALS
- EIP-2-012, Radiation Exposure Controls, Rev 21 Calculator LICENSE LEVEL: SRO SIMULATOR CONDITIONS
& SETUP: 1. This is a classroom/Admin JPM
- There is no simulator setup but pictures/diagrams may need to be developed for the applicants use. CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: The applicant determined emergency allowed dose of 9350 mrem for performing a task in a high rad area and identified the Emergency Director or the Emergency Plant Manager as authorized to allow the entry IAW the attached key.
RJPM-NRC-S 1 6-A 8 Rev. 2 RJPM-NRC-S 1 6-A 8 Rev 2 Page 5 of 8 PERFORMANCE
- START TIME:
- 1. Procedure Step:
Identify the Administrative
, 10CFR, and emergency dose limits.
Standard Applicant identified the Administrative and 10CFR dose limits (2R, 5R, and 10R) in accordance with the attached key.
Cue Notes 2. *Procedure Step:
Determine i f Administrative Dose Limits should be suspended
. Standard Applicant determined that Administrative Dose Limits should be suspended in accordance with the attached key.
Cue Notes 3. *Procedure Step:
Calculate the allowed dose for a task during emergency conditions.
Standard Applicant calculated allowed dose (9350 mrem) in accordance with attached key.
Cue Notes RJPM-NRC-S 1 6-A 8 Rev. 2 RJPM-NRC-S 1 6-A 8 Rev 2 Page 6 of 8 4. *Procedure Step:
Identify who must authorize this entry
. Standard Applicant identified position of person who must authorize dose (the ED or the EPM) in accordance with attached key.
Cue Notes Terminating Cue: The applicant determined emergency allowed dose of 9350 mrem for performing a task in a high rad area and identified the Emergency Director or the Emergency Plant Manager as authorized to allow the entry IAW the attached key.
This completes this JPM.
STOP TIME:
CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable
. 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S 1 6-A 8 Rev. 2 RJPM-NRC-S 1 6-A 8 Rev 2 Page 7 of 8 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S 1 6-A 8 Rev. 2 RJPM-NRC-S 1 6-A 8 Rev 2 Page 8 of 8 OPERATOR CUE SHEET Initial Conditions
- The Emergency Response Organization is operational and the site has declared a Site Area Emergency due to a station blackout.
An entry must be made to the RWCU Pump Room to stop a steam leak.
Dose rates in the vicinity of the steam leak isolation valves are 13 rem per hour.
Initiating Cues
- The CRS has directed you to determine the following:
- 1. The RBS Routine Administrative Total Effective Dose Equivalent (TEDE) whole body exposure limit is _______ per year; the 10CFR20 TEDE Radiation Exposure limit is __
_____ per year
- and the Emergency TEDE limit for immediate actions taken to prevent major damage to equipment, prevent the release of radioactive materials, or control fires is
_________. 2. Based on the initial conditions, the administrative exposure limits of the RBS Radiation Protection Plan are applicable / suspended. (circle one)
- 3. Determine the dose allowed by an operator whose current yearly dose is 650 mrem to isolate the leak in the RWCU Pump Room without exceeding the correct limit
.
- 4. Identify who must authorize this entry: _____________________________________
RJPM-NRC-S 1 6-A 9 Rev 1 River Bend Station Initial License Exam Page 1 of 6 Classify an Emergency CRITICAL TIME FRAME:
Required Time (min):
15 Actual Time (min):
NA PERFORMANCE TIME:
Average Time (min):
Actual Time (min):
VALIDATION TIME:
Time Critical Yes Alt Path N o License Level SRO EVALUATION METHOD
- EVALUATION LOCATION
- X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: June 16, 2016 Reviewed: John Fralick Date: July 8, 2016
(Operations Representative)
Approved: Dan James Date: July 14, 2016
(Operations Management
)
RJPM-NRC-S 16-A9 Rev 1 RJPM-NRC-S 16-A9 Rev 1 Page 2 of 6 EXAMINER INFO SHEET This is a Time Critical JPM Task Standard:
Applicant classifie d the event as an ALERT (FA1, RC3) within fifteen minutes. Synopsis: This JPM is based on simulator scenario
- RSMS-OPS-508. The task will have the applicant determine the classification of an event. This is a TIME CRITICAL JPM.
NOTE: This JPM is Administrative and will be performed in a classroom
. 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
" 2) Initiating Cues
- You are the Emergency Director. Classify the event.
- 3) Initial Conditions
- The plant was operating at 100% power APRM G was in bypass due to its flow biased trip card requiring replacement Standby Gas Treatment B was tagged out for decay heat removal fan replacement APRM C failed downscale; CRD Flow Control Valve B failed closed and FCV A was placed in service; A steam leak occurred in the Drywell which force d the crew to insert a scram
- EOP-1 was entered due to the steam leak; EOP-2 was entered due to High Drywell Temperature A fault developed on EJS
-ACB 066 which caused 3 DW coolers to be unavailable Bypass Leakage was observed EOP-2 was entered for High Containment Pressure The highest unidentified leakage report was 50 gpm Emergency Depressurization was performed due to Pressure Suppression Pressure
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S 16-A9 Rev 1 RJPM-NRC-S 16-A9 Rev 1 Page 3 of 6 DATA SHEET TASK Title
- Task Number K&A SYSTEM
- K&A RATING
- Classify an Emergency 300 00 1 005 00 3 G 2.4.41
4.6 REFERENCES
- APPLICABLE OBJECTIVES EI P-2-001, Rev 2 6 RCBT-EP-SRORMED Obj 16 REQUIRED MATERIALS
- EIP-2-001, Rev 2 6 (Simulator Copy)
LICENSE LEVEL: SRO SIMULATOR CONDITIONS
&/or SETUP: 1. This is a classroom/Admin JPM
- There is no simulator setup
- 2. CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed.
Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD
- Applicant classified the event as an ALERT (FA1, RC3) within fifteen minutes.
RJPM-NRC-S 16-A9 Rev 1 RJPM-NRC-S 16-A9 Rev 1 Page 4 of 6 PERFORMANCE
- START TIME:
- 1. *Procedure Step:
1 Classify the event
. Standard Applicant classified the event as a n ALERT (FA1, RC3) within 15 minutes
. Cue Notes Results SAT UNSAT Terminating Cue: Applicant classified the event as an ALERT (FA1, RC3) within fifteen minutes. This completes this JPM.
STOP TIME:
RJPM-NRC-S 16-A9 Rev 1 RJPM-NRC-S 16-A9 Rev 1 Page 5 of 6 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable
. 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S 16-A9 Rev 1 RJPM-NRC-S 16-A9 Rev 1 Page 6 of 6 OPERATOR CUE SHEET This is a Time Critical JPM Initiating Cues
- You are the Emergency Director. Classify the event.
Initial Conditions
- The plant was operating at 100% power APRM G was in bypass due to its flow biased trip card requiring replacement Standby Gas Treatment B was tagged out for decay heat removal fan replacement APRM C failed downscale; CRD Flow Control Valve B failed closed and FCV A was placed in service; A steam leak occurred in the Drywell which force d the crew to insert a scram
- EOP-1 was entered due to the steam leak; EOP-2 was entered due to High Drywell Temperature A fault developed on EJS
-ACB 066 which caused 3 DW coolers to be unavailable Bypass Leakage was observed EOP-2 was entered for High Containment Pressure The highest unidentified leakage report was 50 gpm Emergency Depressurization was performed due to Pressure Suppression Pressure Answer Below:
The Emergency Action Level (EAL) Classification is:
ES-301 Control Room/In
-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND NUCLEAR STATION Date of Examination:
9/12/201 6 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 201 6 Control Room Systems
-I; 2 or 3 for SRO
-U System / JPM Title Type Code*
Safety Function S1. Perform Rod Withdrawal Limiter Test with a MSIV inadvertent closure. A - N - S 1 S2. Align SU FRV and controller drifts open.
A - N - S - L 2 S3. Open MSIVs per SOP
-011. M - S - L 3 S4. Align Division 3 DG to power ENS
-SWGR1A E - N - S - L 4 ** S5. SBGT fails to start with dampers fail to open.
A - EN - N - S 9 ** S6. Swap electrical bus power supplies N - S 6 S7. Drive In IRM/SRM Detectors Following a SCRAM D - S - L 7 ** S8. Start RHR in Suppression Pool Cooling Mode with high pump amps.
A - D - S - L 5 In-Plant Systems
-I); (3 or 2 for SRO
-U) ** P1. CRD filter swap with new filter clogged (CR-2016-1724) A - N - R 1 ** P2. ATC actions to Man the RSP. AOP 31 Att 12 Section 1.1.4-1.1.6 N - E - L 2 P3. Place Inverter ENB
-IV01B in Service M 6
-I control room (and in
-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in
-plant systems and functions may overlap those tested in the control room.
- and bolded indicates SRO
-U selected JPMs
. Shaded JPM indicates RO only JPM.
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in
-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 /
RJPM-NRC-S 1 6-S 1 Rev 2 River Bend Station Initial License Exam Page 1 of 11 RWL Functional Test CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA VALIDATION TIME: Average Time (min):
15 Actual Time (min):
LICENSE LEVEL: SRO / RO ALTERNATE PATH: YES (MANUAL TRIGGER)
SIMULATOR IC: 68 with S6 EVALUATION METHOD: EVALUATION LOCATION
- X Perform Plant Simulate X Simulator Control Room Prepared: Gabe Kimich Date: 7/8/2016 Reviewed: Danny James Date: 7/21/2016 (Operations Representative)
Approved: John Fralick Date: 8/5/2 016 (Facility Reviewer)
RJPM-NRC-S16-S 1 Rev. 2 RJPM-NRC-S16-S1 Rev 2 Page 2 of 11 EXAMINER INFO SHEET Task Standard:
ROD WITHDRAWAL LIMITER FUNCTIONAL TEST is completed and reactor power is reduced with critical steps completed satisfactory.
Synopsis: Operator performs ROD WITHDRAWAL LIMITER FUNCTIONAL TEST and when the ROD WITHDRAWAL BLOCK clears, a MSIV will close requiring reactor power to be reduced to 75%.
NOTE: This will be a MANUAL trigger
. 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
" NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.
- 2) Initial Conditions
- The reactor is at 87%. 3) Initiating Cues
-500-0704, ROD WITHDRAWAL LIMITER FUNCTIONAL TEST, section 7.1 and restore per 7.3.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S16-S 1 Rev. 2 RJPM-NRC-S16-S1 Rev 2 Page 3 of 11 DATA SHEET TASK Title:
Task Number K&A SYSTEM
- K&A RATING
- Perform Rod Withdrawal Limiter Functional Test 214001002001 201005 A 3.0 3 295020 A K1.0 2 3.4 / 3.3 3.5 /
3.8 REFERENCES
- APPLICABLE OBJECTIVES STP-500-0704, RLP-STM-0500, Obj 7, 9, 13, 22 ROD WITHDRAWAL LIMITER FUNCTIONAL TEST REQUIRED MATERIALS
- SAFETY FUNCTION:
STP-500-0704 __1__ LICENSE LEVEL: SRO / RO ALTERNATE PATH: YES LOCATION: Simulator ORIGIN (Previous 2 exams): NEW EMERGENCY: NO ENGINEERED SAFETY FEATURE: NO LOW POWER: NO SIMULATOR CONDITIONS
& SETUP: 1. IC # 68 Run this with S6
- 2. Rx Power: above the RPCS high power set point (67.9%)
- 3. Insert MSS016 (Closes B21
-F022A) when control rod block alarm clears.
- 4. STP-500-0704: Step 6.4 3087 MWt Step 6.6 28
-13 Start Position 10, Final Position 1 4 N/A section 7.2
- 5. INDIVID DRIVE light on.
- 6. Select rod 28
-13 CRITICAL ELEMENTS: Items marked with an "
- " are Critical Steps and are required to be performed.
Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: ROD WITHDRAWAL LIMITER FUNCTIONAL TEST is completed and reactor power is reduced with critical steps completed satisfactory.
RJPM-NRC-S16-S 1 Rev. 2 RJPM-NRC-S16-S1 Rev 2 Page 4 of 11 PERFORMANCE
- START TIME:
STP-500-0704, ROD WITHDRAWAL LIMITER FUNCTIONAL TEST Section 7.1, Reactor Power Above RPCS High Power Set Point
- 1. Procedure Step:
7.1.1. Verify
the selected rod is in the start position recorded in Step 6.6. Record rod position.
Standard Operator depresse d the two numbers (28-13) corresponding to the rod to be withdrawn. The full core display show ed the rod position for the selected rod (Start Position 10).
Cue N/A Notes Results SAT UNSAT 2. *Procedure Step:
7.1.2. On the ROD SELECT module, perform the following:
- 1. Deselect the rod.
Standard Operator depressed the Rod Select Clear pushbutton
. Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S 1 Rev. 2 RJPM-NRC-S16-S1 Rev 2 Page 5 of 11 3. *Procedure Step:
- 2. Select the rod that corresponds to the rod coordinate position recorded in Step 6.6. Standard Operator depressed the two numbers (28-13) corresponding to the rod to be withdrawn. The full core display showed the rod position for the selected rod. Cue N/A Notes Results SAT UNSAT 4. *Procedure Step:
7.1.3. Withdraw
the rod two notches in the notch withdrawal mode.
Standard Operator depressed the WITHDRAW pushbutton until the IN indicator was on or the start of rod motion was observed.
Released the WITHDRAW pushbutton until SETTLE light extinguished. Operator verified the rod notch position was at the next highest even number. Then depressed the WITHDRAW pushbutton until the IN indicator was on or the start of rod motion was observed to move the rod the second notch.
Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S 1 Rev. 2 RJPM-NRC-S16-S1 Rev 2 Page 6 of 11 5. Procedure Step:
7.1.4. Check
Annunciator P680-07A-C01, CONTROL ROD WITHDRAWAL BLOCK alarms.
Standard Operator verified the Annunciator P680-07A-C01, CONTROL ROD WITHDRAWAL BLOCK is in alarm.
Cue N/A Notes Results SAT UNSAT 6. *Procedure Step:
7.1.5. Check
the rod withdrawal limiter stops rod motion at the second notch by attempting to withdraw the rod a third notch and verifying the rod does not move. Standard Operator depressed the WITHDRAW pushbutton and verified no rod motion.
Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S 1 Rev. 2 RJPM-NRC-S16-S1 Rev 2 Page 7 of 11 7. *Procedure Step:
7.3 Restoration
7.3.1. On the ROD SELECT module, perform the following:
- 1. Deselect the rod.
Standard Operator depressed the Rod Select Clear pushbutton.
Cue N/A Notes Results SAT UNSAT 8. *Procedure Step:
- 2. Select the rod that corresponds to the rod coordinate position recorded in Step 6.6. Standard Operator depressed the two numbers (28-13) corresponding to the rod to be withdrawn. The full core display showed the rod position for the selected rod. Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S 1 Rev. 2 RJPM-NRC-S16-S1 Rev 2 Page 8 of 11 9. Procedure Step:
7.3.2. Check
Annunciator P680
-07A-C01, CONTROL ROD WITHDRAWAL BLOCK is clear.
Standard Operator verified Annunciator P680
-07A-C01, CONTROL ROD WITHDRAWAL BLOCK is clear.
Cue N/A Notes When the alarm is clear, the MSIV will close and H13
-P680/06A/B06 will alarm. (NOTE: This is a manual trigger from the booth. This requires no cueing when the alarm clears the booth will trigger open MSIV.)
Results SAT UNSAT ALTERNATE PATH
- 10. Procedure Step:
Operator verifies Main Steam Isolation Valve Closure on P601.
Per H13-P680/06A/B06, MAIN STEAM ISOLATION VLVS CLOSURE:
-0001, Reactor Scram.
- 2. Determine cause of MSIV closure.
- 3. If operating with a Main Steam Line isolated, THEN reduce power to less than or equal to 75% per SOP
-11, Main Steam System. SOP-11, MAIN STEAM SYSTEM Precautions and Limitations 2.4 Reactor power shall be limited to less than or equal to 75% RTP with one Main Steam Line out of service.
Standard Operator may dispatch SNEO or maintenance to investigate MSIV closure.
Operator should inform CRS to reduce flow to 75%.
Cue If required, concur with recommendation to reduce flow to 75% using Recirc Flow Control Valves.
Notes Results SAT UNSAT RJPM-NRC-S16-S 1 Rev. 2 RJPM-NRC-S16-S1 Rev 2 Page 9 of 11 11. *Procedure Step:
Per the Reactivity Management Plan, Casualty Step Reduce reactor recirculation flowrate to reduce reactor power to 75%.
Standard Operator toggles B33-K603A(B), RECIRC LOOP A(B) FLOW CONTROL down and to the left to reduce flow in slow speed. The operator will alternate between A and B Recirc Loop Flow Control Valves to reduce power.
Cue N/A Notes The first step of the RMP casualty step requires recirc flow to be lowered to 80%. Then rods must be inserted to lower power to 75%.
ONCE THE OPERATOR REDUCES FLOW 1% WITH FIRST FCV END THE JPM.
Results SAT UNSAT Terminating Cue: ROD WITHDRAWAL LIMITER FUNCTIONAL TEST is completed and reactor power is reduced with critical steps completed satisfactory.
STOP TIME:
CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable.
- 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or
otherwise reduced the level of safety of the plant
RJPM-NRC-S16-S 1 Rev. 2 RJPM-NRC-S16-S1 Rev 2 Page 10 of 11 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S 1 6-S 1 Rev 2 OPERATOR CUE SHEET Initial Conditions
- The reactor is at 87%.
Initiating Cues
-500-0704, ROD WITHDRAWAL LIMITER FUNCTIONAL TEST, section 7.1 and restore per 7.3.
RJP M-NRC-S 1 6-S2 Rev 1 River Bend Station Initial License Exam Page 1 of 8 Align SU FRV in Auto CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA VALIDATION TIME: Average Time (min):
7 Actual Time (min):
LICENSE LEVEL: SRO / RO ALTERNATE PATH: YES (MANUAL TRIGGER)
SIMULATOR IC: 67 with S8 EVALUATION METHOD: EVALUATION LOCATION
- X Perform Plant Simulate X Simulator Control Room Prepared: Gabe Kimich Date: 7/8/2016 Reviewed: Danny James Date: 7/21/2016 (Operations Representative)
Approved: John Fralick Date: 8/5/2 016 (Facility Reviewer)
RJPM-NRC-S16-S2 Rev. 1 RJPM-NRC-S16-S2 Rev 1 Page 2 of 8 EXAMINER INFO SHEET Task Standard:
SU FRV placed in manual after control failure, restore reactor water level prior to Narrow Range Level 8 trip (51 inches) with all critical steps completed satisfactory. Synopsis: SU FRV placed in AUTO per SOP
-9, Section 4.7. Once FRV is in AUTO, the FRV will drift open requiring the operator to place the FRV back to MANUAL to restore reactor water level, per AOP
-6. (Note: This will require a manual trigger when the operator begins adjusting controller to raise reactor water level.)
- 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
" NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.
- 2) Initial Conditions
- The reactor is being shut down. Feed system is aligned to the vessel through the startup level control valve The startup level control valve is in manual per SOP-9, section 4.6 and tape is set at 25 inches. 3) Initiating Cues
-9, Section 4.7.
Adjust reactor water level to 36 inches narrow range.
- 4) Solicit and answer any questions the operator may have.
RJPM-NRC-S16-S2 Rev. 1 RJPM-NRC-S16-S2 Rev 1 Page 3 of 8 DATA SHEET TASK Title:
Task Number K&A SYSTEM
- K&A RATING
- SU FRV placed in manual after control failure 259010001001 2 5 90 23 001001 2 5 9001 K6.0 7 2 5 900 1 A 2.0 7 295008 AA1.01 3.8 / 3.8 3.7 / 3.8 3.7 /
3.7 REFERENCES
- APPLICABLE OBJECTIVES SOP-00 09, Rev 73 RLP-STM-010 7, Obj 7, 1 0 AOP-0006, Rev 22 REQUIRED MATERIALS
- SAFETY FUNCTION:
SOP-00 09, Main Steam System (Sim Copy)
__2__ AOP-0006, Condensate/Feedwater Failures (Sim Copy)
LICENSE LEVEL: SRO / RO ALTERNATE PAT H: YES LOCATION: Simulator ORIGIN (Previous 2 exams): NEW EMERGENCY: NO ENGINEERED SAFETY FEATURE: NO LOW POWER: YES SIMULATOR CONDITIONS
& SETUP: 1. IC # 67 Run with S8.
- 2. Reactor is critical.
- 3. Trigger 1 AO_FWVFF002 to 100 ramped over 2 minutes.
- 4. Trigger 2 Delete malfunction.
- 5. Event 1 AUTO Pushbutton for SUFRV zdi6(73)
- 6. Event 2 MANUAL Pushbutton zdi6(74)
- 7. STEAM TO AIR EJECT LOW P870_52A:H_3 to OFF nuisance alarm.
- 8. Thumbwheel 0 to 100% 35" = 58.4% 30"=50.3% (0
-60") 9. AI_C33_R602_CTW to 100 on event 1 ramped 30 seconds 10. Event 1 zdi6(74) SUFRV AUTO pushbutton
- 11. AI_C33_R602_CTW delete in 1 on event 2
- 12. Event 2 zdi6(73) SU FRV Man P/B CRITICAL ELEMENTS:
Items marked with an "
- " and gray box are Critical Steps and are required to be performed.
Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: SU FRV placed in manual after control failure, restore reactor water level prior to Narrow Range Level 8 trip (51 inches) with all critical steps completed satisfactory.
RJPM-NRC-S16-S2 Rev. 1 RJPM-NRC-S16-S2 Rev 1 Page 4 of 8 START TIME:
SOP-9 Section 4.7, Placing Startup Level Control in Automatic
- 1. *Procedure Step:
4.7.1. Return
C33 R602, START UP FWREG VALVE FLOW CONTROLLER to AUTO as follows:
- 1. Adjust tape set 2 inches above actual vessel level and observe the deviation signal is positive.
Standard Uses thumbwheel to adjust tape set to 2 inches above actual vessel level and verify the deviation signal is positive.
Cue N/A Notes Results SAT UNSAT 2. *Procedure Step:
- 2. Lower tape set 2 inches below actual vessel level and observe the deviation signal is negative.
Standard Uses thumbwheel to adjust tape set to 2 inches below actual vessel level and verify the deviation signal is negative.
Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S2 Rev. 1 RJPM-NRC-S16-S2 Rev 1 Page 5 of 8 3. *Procedure Step:
- 3. Match tape set to actual vessel level in order to null the deviation signal.
Standard Uses thumbwheel to adjust tape set to actual vessel level and verify the deviation signal is approximately zero.
Cue N/A Notes Results SAT UNSAT 4. *Procedure Step:
- 4. Depress the AUTO Pushbutton and check green light above the pushbutton is on.
Standard Operator depresses the AUTO pushbutton and verifies the green light is on.
Cue N/A Notes Results SAT UNSA T 5. *Procedure Step:
4.7.2. Adjust
C33 R602, START UP FWREG VALVE FLOW CONTROLLER Tape Set to maintain the level requested by the OSM/CRS.
Standard Adjust C33 R602, START UP FWREG VALVE FLOW CONTROLLER Tape Set to 36 inches.
Cue N/A Notes When the thumbwheel is moved, the booth will manually trigger the controller failure and Reactor Water Level will continue to go up.
Results SAT UNSAT RJPM-NRC-S16-S2 Rev. 1 RJPM-NRC-S16-S2 Rev 1 Page 6 of 8 ALTERNATE PATH
- 6. *Procedure Step:
AOP-6, 5.1, (Immediate Action) Manually control the feedwater level control system and/or reduce reactor power to mitigate any level transient.
AOP-6, 6.2, IF any of the following flow control valves have failed, THEN attempt to take manual control or isolate the flow control valve to control reactor vessel level:
Place C33 R602, START UP FWREG VALVE FLOW CONTROLLER in MANUAL. FWS FV104, START UP RECIRC FCV isolated by closing FWS MOV103, LONG CYCLE CLEANUP ISOL Standard Start Up FWREG Valve Flow Controller MANUAL pushbutton is depressed. Operator is able to manually restore reactor water level by depressing the open / closed pushbuttons on the controller to open / close the valve prior to reaching Narrow Range Level 8 trip (51 inches)
. Cue N/A Notes Narrow Range A/B/C gages are located at P680, Insert 3, Vertical Section, top row, and on the right. They are labeled with large 4A, 4B, and 4C on top.
Results SAT UNSAT Terminating Cue: SU FRV placed in manual after control failure, restore reactor water level prior to Narrow Range Level 8 trip (51 inches) with all critical steps completed satisfactory
.. STOP TIME:
CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable.
- 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S16-S2 Rev. 1 RJPM-NRC-S16-S2 Rev 1 Page 7 of 8 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature: Date:
RJPM-NRC-S16-S2 Rev 1 OPERATOR CUE SHEET Initial Conditions
- The reactor is being shut down. Feed system is aligned to the vessel through the startup level control valve The startup level control valve is in manual per SOP
-9, section 4.6.
Initiating Cue s: The CRS has directed you to place the Startup Level Control in Automatic per SOP
-9, Section 4.7.
Adjust reactor water level to 36 inches narrow range.
RJPM-NRC-S16-S3 Rev 2 River Bend Station Initial License Exam Page 1 of 18 Reopen MSIVs Following Automatic Isolation CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA PERFORMANCE TIME:
Average Time (min):
20 Actual Time (min):
LICENSE LEVEL: SRO / RO ALTERNATE PATH: No IC: 66 EVALUATION METHOD
- EVALUATION LOCATION
- X Perform Plant Simulate X Simulator Control Room
Prepared: Gabe Kimich Date: 7/8/2016 Reviewed: Danny James Date: 7/21/2016 (Operations Representative)
Approved: John Fralick Date: 8/5/2016 (Facility Reviewer)
RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 2 of 18 EXAMINER INFO SHEET Task Standard:
Inboard MSIV's are open with all critical steps completed satisfactory
. Synopsis: The reactor is shutdown, pressurized with the MSIVs closed following an automatic isolation. This task wi ll re-open inboard MSIV's using SOP
-0011, Main Steam System, Section 4.2, Opening MSIVs During Hot Startup/Recovery From Automatic Isolation.
- 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
" NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.
- 2) Initial Conditions
- The reactor is scrammed and pressurized.
All MSIV's are closed (NSSSS isolation is clear).
Main Condenser vacuum is established.
The Circulating Water System is lined up in accordance with SOP
-0006. 3) Initiating Cues
- The CRS has directed you to open the Main Steam Isolation Valves (MSIVs) in accordance with SOP
-0011, Main Steam, Section 4.2.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 3 of 18 DATA SHEET TASK Title:
Task Number K&A SYSTEM
- K&A RATING
- Open MSIVs During Recovery from Automatic Isolation 239007001001 239001 A4.01 295020 AA1.01 4.2 / 4.0 3.6 /
3.6 REFERENCES
- APPLICABLE OBJECTIVES SOP-0011, Rev 2 9 RLP-STM-0109, Obj 7, 12 REQUIRED MATERIALS
- SAFETY FUNCTION:
SOP-0011, Main Steam System (Sim Copy)
__3__ LICENSE LEVEL: SRO / RO ALTERNATE PATH: No LOCATION: Simulator ORIGIN (Previous 2 exams): Modified (Removed alternate path)
EMERGENCY: NO ENGINEERED SAFETY FEATURE: NO LOW POWER: YES SIMULATOR CONDITIONS
& SETUP: 1. IC # 66 2. Rx Power: Shutdown. pressurized
- 3. MSIVs closed on an initiation signal
- (MSS021A&B) signal has been cleared.
- 4. Condenser Vacuum established
, with Condenser Air Removal Pump A
. CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed.
Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: Inboard MSIV's are open with all critical steps completed satisfactory
.
RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 4 of 18 PERFORMANCE
- START TIME:
SOP-0011, Main Steam System Section 4.2 , Opening MSIVs During Hot Startup/Recovery From Automatic Isolation CAUTION Bypassing the Condenser Low Vacuum trip and opening the MSIVs following an Automatic Isolation could result in a Condenser overpressurization condition. The Condenser Low Vacuum Bypass switches should only be used during startup.
- 1. Procedure Step:
4.2.1. IF Main Condenser vacuum is not established, THEN place the following switches in BYPASS:
B21H S24A, DIV 1 CONDENSER LOW VACUUM BYPASS B21H S24B, DIV 2 CONDENSER LOW VACUUM BYPASS B21H S24C, DIV 3 CONDENSER LOW VACUUM BYPASS B21H S24D, DIV 4 CONDENSER LOW VACUUM BYPASS Standard N/A Cue N/A Notes Results SAT UNSAT 2. Procedure Step:
4.2.2. Verify
the current alignment of the Circulating Water Pumps, Cooling Towers and Condenser Waterboxes is in accordance with SOP
-0006, Circulating Water System.
Standard N/A Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 5 of 18 3. Procedure Step:
4.2.3. At H13 P601, place the following control switches in the CLOSE position: B21 AOVF022A, MSL A INBD MSIV B21 AOVF022B, MSL B INBD MSIV B21 AOVF022C, MSL C INBD MSIV B21 AOVF022D, MSL D INBD MSIV B21 AOVF028A, MSL A OUTBD MSIV B21 AOVF028B, MSL B OUTBD MSIV B21 AOVF028C, MSL C OUTBD MSIV B21 AOVF028D, MSL D OUTBD MSIV Standard No switch manipulation required.
Operator verified all four Inboard MSIV control switches to CLOSE.
Operator verified all four Outboard MSIV control switches to CLOSE.
Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 6 of 18 NOTE Step 2.11 contains the MSIV isolation signals.
2.11 The Main Steam System automatically isolates when any of the following conditions exist:
Reactor Low
-Low-Low Water Level, Level 1 (-143 in.) Main Steam Line High Flow MSL A, 185 psid MSL B, 189 psid MSL C, 189 psid MSL D, 189 psid Main Steam Line Low Pressure, 849 psig, bypassed when Reactor Mode Switch not in RUN position. Steam Tunnel High Temperature, 173 o F Low Condenser Vacuum, 8.5 inches Hg, may be bypassed during startup.
Manual Isolation via B21H
-S25(A)(B)(C)(D), MANUAL ISOLATION Pushbuttons.
- 4. Procedure Step:
4.2.4. Check
that an MSIV isolation signal is not present. Standard Applicant verified that all MSIV isolation signals listed in Step 2.11 are clear.
Cue As backpanel operator, report that Main Steam Line Flow is zero psid.
As backpanel operator, report that Steam Tunnel Temperature is 126°F Notes Results SAT UNSAT RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 7 of 18 5. Procedure Step:
4.2.5. At H13 P680, check the Turbine Pressure Regulator setpoint is greater than RPV pressure.
Standard Applicant compared RPV Pressure to the Turbine Pressure Regulator Setpoint. Cue N/A Notes Turbine Pressure Regulator Setpoint is located P680, Insert 7, 3 rd and 4 th squint meter above the red pushbuttons.
Results SAT UNSAT 6. *Procedure Step:
4.2.6. Depress
the following pushbuttons to reset the inboard and outboard MSIV isolation logic:
B21H S33, INBD ISOLATION SEAL IN RESET B21H S32, OUTBD ISOLATION SEAL IN RESET Standard Applicant depressed the B21H
-S33, Inboard Isolation Seal
-In Reset Pushbutton. Applicant depressed the B21H
-S32, Outboard Isolation Seal
-In Reset Pushbutton
. Cu e N/A Notes The pushbuttons S33 and S32 need not be pressed in any particular order, but both must be pushed.
Indications after action
, MSL Drains white light is on Results SAT UNSAT RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 8 of 18 7. *Procedure Step:
4.2.7. Verify
open the following to equalize pressure across the outboard MSIVs: B21 MOVF067A, MSL A DRAIN VALVE B21 MOVF067B, MSL B DRAIN VALVE B21 MOVF067C, MSL C DRAIN VALVE B21 MOVF067D, MSL D DRAIN VALVE B21 MOVF086, MSL DRAIN HDR SHUTOFF VALVE PROCEDURE NOTE When opening B21
-MOVF068, the valve should be cracked open a few percent and then slowly opened over a period of greater than a minute to allow any condensate to clear upstream of the valve. (Ref: EC
-63114) B21-MOVF068, MSL DRAIN HDR COND DRAIN BYP VALVE Standard Applicant verified open the 67A, B, C, and D drain valves. No manipulation was required.
Applicant verified open the keylock B21
-MOVF086 drain valve open, by verifying red light is ON and green light is OFF.
No manipulation was required. Applicant opened B21
-MOVF068 drain valve by turning the switch to open and holding it until the red light is on and the green light is off.
This is a throttle valve so the operator must hold the handswitch in the open position until the valve is open. Valve stroke takes about 65 seconds. Cue N/A Notes The 6 valves in step 4.2.7 may be verified in any order.
Valve is open when red light is ON and green light is OFF.
Results SAT UNSAT RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 9 of 18 8. Procedure Step:
4.2.8. Verify
B21 MOVF020, MSL WARMUP HDR SUPPLY VALVE is close d. Standard Applicant verified the B21 MOVF020 valve was closed as indicated by the green light on and the red light off.
No manipulation required.
Cue N/A Notes Results SAT UNSAT 9. Procedure Step:
4.2.9. IF the differential pressure across the outboard MSIVs is greater than 50 psid as indicated by the difference between MSS PI101, MAIN STEAM HEADER PRESSURE and Main Condenser Vacuum, THEN perform the following to reduce the differential pressure:
Standard Applicant identified that differential pressure is less than 50 psid as seen by comparing Main Steam Header Pressure and Condenser Vacuum.
Cue N/A Notes Main Condenser Vacuum is on the process computer to the left of the full core display in the middle of the screen.
Main steam header pressure is read on MSS PI101 on P870 Insert 52 in the middle of the panel.
Results SAT UNSAT RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 10 of 18 10. *Procedure Step:
4.2.10. Place the following control switches in AUTO:
B21 AOVF028A, MSL A OUTBD MSIV B21 AOVF028B, MSL B OUTBD MSIV B21 AOVF028C, MSL C OUTBD MSIV B21 AOVF028D, MSL D OUTBD MSIV Standard Applicant rotated four Outboard MSIV control switches clockwise to AUTO.
These valves can be placed in AUTO in any order.
Cue N/A Notes Results SAT UNSAT 11. Procedure Step: 4.2.11. Check outboard MSIVs are open.
Standard Applicant checked all four outboard MSIVs indicate open by observing red lights on and green lights off.
Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 11 of 18 12. Procedure Step:
4.2.12. On H13 P623, observe the indicating lights and ammeters to confirm the energization of both solenoids on each outboard MSIV.
Standard N/A Cue Examiner role play as a backpanel operator, report MSIV solenoid lights are energized and ammeters readings are normal.
Notes No actions are taken by the applicant except to simulate going to the backpanel.
This panel is not in the simulator.
Results SAT UNSAT 13. *Procedure Step:
4.2.13. Verify closed the following:
B21 MOVF021, MSL WARMUP HDR COND DRAIN BYP VALVE B21 AOVF033, MSL WARMUP HDR COND DRAIN VALVE B21 MOVF068, MSL DRAIN HDR COND DRAIN BYP VALVE B21 AOVF069, MSL DRAIN HDR COND DRAIN VALVE Standard B21 MOVF021 is verified closed. No manipulation required.
Applicant closed the drain valve by rotating the control switch from AUTO to CLOSE and verified the green light on and the red light off.
Applicant closed the drain bypass valve by rotating and holding the control switch in the close direction until the red light is off and the green light is on.
Applicant closed the drain valve by placing the control switch to CLOSE and verified the green light on and the red light off.
Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 12 of 18 14. Procedure Step:
4.2.14. Verify open the following:
B21 MOVF016, MSL WARMUP HDR INBD CONTMT ISOL VLV B21 MOVF019, MSL WARMUP HDR OUTBD CONTMT ISOL VLV B21 MOVF085, MSL WARMUP HDR SHUTOFF VALVE Standard Applicant verified the two warmup header valves open by checking the red lights on and the green lights off.
Applicant verified th e B21 F085 valve open by checking the red light on and the green light off.
Cue N/A Notes Results SAT UNSAT PROCEDURE NOTE When opening B21
-MOVF020 slowly, the valve should be cracked open a few percent and then slowly opened over a period of greater than a minute to allow any condensate to clear upstream of the valve. (Ref: EC
-63114) 15. *Procedure Step:
4.2.15. Open slowly B21 MOVF020, MSL WARMUP HDR SUPPLY VALVE to equalize pressure across the inboard MSIVs.
Standard Applicant throttled opened the warmup header supply valve.
Cue N/A Notes Applicant will move back and forth between throttling the 20 valve and checking pressures per the next step.
How aggressively the applicant is willing to open the 20 valve will determine the time it takes to equalize pressure; It takes about 7 minutes to equalize pressure Results SAT UNSAT RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 13 of 18 16. Procedure Step:
4.2.16. Monitor differential pressure across the inboard MSIVs using the following:
C33 R605, REACTOR PRESSURE MSS PI101, MAIN STEAM HEADER PRESSURE Standard Applicant monitored differential pressure across the inboard MSIVs using the appropriate meters.
Cue N/A Notes The Reactor Pressure meter is on insert 3 of the 680 panel The Main Steam pressure meter is on insert 52 of the 870 panel.
Results SAT UNSAT RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 14 of 18 NOTES Opening an MSIV can cause a Reactor water level transient. Slowly opening the MSIV using the OPEN/SLOW TEST position and intermittent release of the TEST Pushbutton can mitigate the level transient.
If only one Main Steam Line is to be unisolated, then Main Steam Line A should be unisolated to ensure a vent path for the Reactor Vessel.
- 17. *Procedure Step:
4.2.17. WHEN differential pressure across the inboard MSIVs is less than or equal to 50 psid, THEN place the following switches in AUTO to open the inboard MSIVs:
B21 AOVF022A, MSL A INBD MSIV B21 AOVF022B, MSL B INBD MSIV B21 AOVF022C, MSL C INBD MSIV B21 AOVF022D, MSL D INBD MSIV Standard Applicant placed the A, B, C, and D inboard MSIV switch es to AUTO (AFTER d/p was equal or less than 50 psid).
These may be placed in AUTO in any order.
Cue N/A Notes The applicant may use the test pushbutton in accordance with the note listed above. The test pushbutton is not required to complete the step.
Results SAT UNSAT RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 15 of 18 18. *Procedure Step:
4.2.18. Check inboard MSIVs are open.
Standard Applicant checked all four inboard MSIVs indicate open (Red lights on/Green lights off)
Cue N/A Notes Results SAT UNSAT 19. Procedure Step:
4.2.19. On H13 P622, observe the indicating lights and ammeters to confirm the energization of both solenoids on each inboard MSIV.
Standard N/A Cue If requested, the lights are on and the ammeters are indicating normal.
Notes NOTE: Once the inboard MSIVs are open the JPM is complete. Examiner should end JPM prior to next step.
Results SAT UNSAT Terminating Cue: Inboard MSIV's are open with all critical steps completed satisfactory
. STOP TIME:
CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable.
- 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable.
- RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 16 of 18 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S16-S3 Rev. 2 RJPM-NRC-S16-S3 Rev 2 Page 17 of 18 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM: minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S16-S 3 Rev 2 OPERATOR CUE SHEET Initial Conditions
- The reactor is shutdown and pressuriz ed. All MSIV's are closed.
Main Condenser vacuum is established.
The Circulating Water System is lined up in accordance with SOP
-0006. Initiating Cues
- The CRS has directed you to open the Main Steam Isolation Valves (MSIVs) in accordance with SOP
-0011, Main Steam, Section 4.2.
RJPM-NRC-S16-S 4 Rev 2 River Bend Station Initial License Exam Page 1 of 11 Align Division 3 DG to power ENS
-SWGR1A CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA VALIDATION TIME: Average Time (min):
1 5 Actual Time (min):
LICENSE LEVEL: SRO / RO ALTERNATE PATH: No IC: 69 (Instructor needed on floor to silence alarms.)
EVALUATION METHOD
- EVALUATION LOCATION
- X Perform Plant Simulate X Simulator Control Room Prepared: Gabe Kimich Date: 7/8/2016 Reviewed: Danny James Date: 7/21/2016 (Operations Representative)
Approved: John Fralick Date: 8/5/2016 (Facility Reviewer)
RJPM-NRC-S16-S4 Rev. 2 RJPM-AUD-D14-S4 Rev 2 Page 2 of 11 EXAMINER INFO SHEET Task Standard:
ENS-SWG1 A is aligned to Division 3 Diesel Generator completing all critical steps satisfactory
.
Synopsis: Division 3 Diesel Generator is aligned to ENS-SWG1A. 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.
- 2) Initiating Cues
The CRS has directed you to energize ENS SWGR 1A from Division 3 Diesel Generator per AOP-50, Attachment 9, starting with step 2.5.
- 3) Initial Conditions
- Station Blackout in progress.
RCIC maintaining Reactor Water level. AOP-50, Steps 2.1
-2.4 are complete.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S16-S4 Rev. 2 RJPM-AUD-D14-S4 Rev 2 Page 3 of 11 DATA SHEET TASK Title
- Task Number K&A SYSTEM
- K&A RATING
- Manually tie HPCS Diesel Generator to Dead Bus 1E22*S004 258013001001 23900 3 A A1.0 2 4.2 /
4.3 REFERENCES
- APPLICABLE OBJECTIVES AOP-50, Rev. 55 RLP-STM-0309H, Obj 8 REQUIRED MATERIALS
- SAFETY FUNCTION:
AOP-50, Rev. 55
__3__ LICENSE LEVEL: SRO / RO ALTERNATE PATH: No LOCATION: Simulator ORIGIN (Previous 2 exams)
- New EMERGENCY: Yes ENGINEERED SAFETY FEATURE: NO LOW POWER: YES SIMULATOR CONDITIONS
& SETUP: 1. IC # 69 2. Station instructor at P680 to silence alarms as they come in. Turns horns off after the expected alarm for the fast transfer.
- 3. Rx Power: Shutdown. pressurized
- 4. MSIVs closed on an initiation signal
- (MSS021A&B) signal has been cleared.
- 5. Condenser Vacuum established
, with Condenser Air Removal Pump A
. 6. RHR-A in Suppression Pool Cooling
- 7. Several Alarms are forced on (they continue to come in and out, causing distraction
) P680_4-A5, A11, _5
-C6 P870_52-E4, F1, G3, H1, H3 INSTALL ATTACHMENT FOR AOP ATTACHMENT 9.
CRITICAL ELEMENTS:
Items marked with an "
- " and gray box are Critical Steps and are required to be performed.
Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: ENS-SWG1A is aligned to Division 3 Diesel Generator completing all critical steps satisfactory
.
RJPM-NRC-S16-S4 Rev. 2 RJPM-AUD-D14-S4 Rev 2 Page 4 of 11 START TIME:
A OP-00 50 Attachment 9, Using the Division 3 Diesel Generator to supply power to ENS
-SWG1A. 1. *Procedure Step:
2.5 On H13-P870, depress the STOP and LOCKOUT push buttons for the following pumps:
- SWP-P2A, STBY SVCE WTR PUMP 2A
- CCS-P1A, TPCCW PUMP 1A
- CCS-P1B, TPCCW PUMP 1B
- CCS-P1C, TPCCW PUMP 1C Standard Operator depresses the STOP pushbutton and then the LOCKOUT pushbuttons for the associated pumps.
Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S4 Rev. 2 RJPM-AUD-D14-S4 Rev 2 Page 5 of 11 2. *Procedure Step:
2.6 On H13-P808, verify the following breaker alignment:
- NNS-ACB23, NNS SWGR 1C/1A BRKR is open.
- NNS-ACB25, HPCS BUS S004 BRKR is closed.
- NNS-ACB24, NNS SWGR 1C/1B BRKR is closed.
- NNS-ACB28, NNS SWGR 1B/1C BRKR is closed.
- NNS-ACB20, NNS SWGR 4B/1B BRKR is open.
- NNS-ACB14, NORM SUPPLY BRKR is open.
- NNS-ACB15, 4160V PFD SUPPLY BRKR is open.
Standard NNS-ACB23, 24, 20, and 15 switches must be operated to OPEN/CLOSE the breakers.
NNS-ACB-25, 28, and 14 only require verification. No manipulation required.
Cue N/A Notes Results SAT UNSAT 3. Procedure Step: 2.7 On H13-P877, verify ENS
-ACB04, ALTERNATE SUPPLY BRKR is open. Standard ENS-ACB04 is verified open. No manipulation required.
Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S4 Rev. 2 RJPM-AUD-D14-S4 Rev 2 Page 6 of 11 4. Procedure Step:
2.8 On H13-P808, close NNS
-ACB13, STBY BUS A ALTN SUPPLY. Standard NNS-ACB13 is closed. No manipulation is required.
Cue N/A Notes Results SAT UNSAT 5. *Procedure Step:
2.9 WHEN Steps 2.2 through 2.8 have been completed, THEN in the Main Control Room, on H13
-P601, energize NNS
-SWG1C and NNS-SWG1B from Div III Diesel Generator as follows:
2.9.1. Place
E22-ACB04, SYNC SWITCH in NRM/BUS.
Standard Operator rotates E22-ACB04, SYNC SWITCH to NRM/BUS. Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S4 Rev. 2 RJPM-AUD-D14-S4 Rev 2 Page 7 of 11 6. *Procedure Step:
2.9.2. Close
E22-ACB04, HPCS BUS SUPPLY BRKR.
Standard Operator rotates E22-ACB04, HPCS BUS SUPPLY BRKR to trip then to close. Cue N/A Notes Results SAT UNSAT 7. Procedure Step:
2.9.3. Place
E22-ACB04, SYNC SWITCH in OFF.
Standard Operator rotates E22
-ACB04, SYNC SWITCH to OFF. Cue N/A Notes Results SAT UNSAT 8. Procedure Step:
2.10 Shutdown the HPCS Pump per SOP
-0030, High Pressure Core Spray. Standard N/A. HPCS is not running.
Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S4 Rev. 2 RJPM-AUD-D14-S4 Rev 2 Page 8 of 11 PROCEDURE NOTE Energizing ENS
-SWG1A will allow the automatic sequencing of loads on the buses. The HPCS Diesel Generator load must be maintained less than 2850 KW.
- 9. *Procedure Step:
2.11 On H13-P877, energize ENS
-SWG1A, EJS
-SWG1A, and EJS
-SWG2A as follows:
2.11.1. Place ENS SWG1A SYNCHRONIZING Switch in ALTN.
Standard Operator rotates ENS SWG1A SYNCHRONIZING Switch to ALTN. Cue N/A Notes Results SAT UNSAT 10. *Procedure Step:
2.11.2. Close ENS ACB04, ALTERNATE SUPPLY BRKR.
Standard Operator rotates hand switch for ENS ACB04, ALTERNATE SUPPLY BRKR to close. Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S4 Rev. 2 RJPM-AUD-D14-S4 Rev 2 Page 9 of 11 11. Procedure Step:
2.11.3. On V 1EGSA08, STBY BUS A VOLTS Indication, verify standby bus voltage normal.
Standard Bus voltage will indicate in normal range (green band).
Cue N/A Notes Results SAT UNSAT 12. Procedure Step:
2.11.4. Place ENS SWG1A SYNCHRONIZING Switch in OFF.
Standard Operator rotates t
-handle switch to OFF.
Cue N/A Notes Results SAT UNSAT Terminating Cue:
ENS-SWG1A is aligned to Division 3 Diesel Generator completing all critical steps satisfactory
. STOP TIME:
CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable.
- 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S16-S4 Rev. 2 RJPM-AUD-D14-S4 Rev 2 Page 10 of 11 VERIFICATION OF COMPLETI ON Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An " Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-AUD-D14-S 4 Rev 2 OPERATOR CUE SHEET Initiating Cues
- The CRS has directed you to energize ENS SWGR 1A from Division 3 Diesel Generator per AOP-50, Attachment 9, starting with step 2.5.
Initial Conditions: Station Blackout in progress.
RCIC maintaining Reactor Water level.
AOP-50, Attachment 9 Steps 2.1-2.4 are complete.
RJPM-NRC-S 1 6-S 5 Rev 1 River Bend Station Initial License Exam Page 1 of 9 Isolate Auxiliary Building CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA VALIDATION TIME: Average Time (min):
10 Actual Time (min):
LICENSE LEVEL: SRO / RO ALTERNATE PATH: YES IC: 67 with S7 EVALUATION METHOD
- EVALUATION LOCATION: X Perform Plant Simulate X Simulator Control Room
Prepared: Gabe Kimich Date: 7/8/2016 Reviewed: Danny James Date: 7/21/2016 (Operations Representative)
Approved: John Fralick Date: 8/5/2016 (Facility Reviewer)
RJPM-NRC-S16-S5 Rev. 1 RJPM-NRC-S16-S5 Rev 1 Page 2 of 9 EXAMINER INFO SHEET Task Standard:
Isolate auxiliary building (HVR AOD 143 and HVR AOD 262 manually shut) and start both trains of standby gas systems with all critical tasks completed satisfactory.
Synopsis: Auxiliary building HVAC is required to be isolated due to high radiation levels per EOP
-3 and OSP-53 Attachment 21. The ventilation system isolation is manually initiated with two dampers failing to close and both of the standby gas systems fails to automatically start (must be manually started). 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
" NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.
- 2) Initial Conditions
- The reactor scrammed one hour ago.
Auxiliary Building rad levels have raised to EOP-3 entry conditions.
Reactor pressure 390 psig.
- 3) Initiating Cues
The CRS has directed you to isolate the auxiliary building per OSP-53, Attachment 21 in order to reduce radiation levels and allow re-entry.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S16-S5 Rev. 1 RJPM-NRC-S16-S5 Rev 1 Page 3 of 9 DATA SHEET TASK Title:
Task Number K&A SYSTEM
- K&A RATING
- Restore Affected Systems to Service Following Isolation 400007004001 295034 EA1.03 4.0 /
3.9 REFERENCES
- APPLICABLE OBJECTIVES OSP-53, Attachment 21 RLP-STM-0409, Obj 6 SOP-53, Section 4.1 REQUIRED MATERIALS
- SAFETY FUNCTION:
OSP-53, Attachment 21
__9__ SOP-53, Section 4.1 LICENSE L EVEL: SRO / RO ALTERNATE PATH: Yes LOCATION: Simulator ORIGIN (Previous 2 exams): New EMERGENCY: No ENGINEERED SAFETY FEATURE: Yes LOW POWER: No SIMULATOR CONDITIONS
& SETUP: 1. IC # 67 Performed with S7
- 2. Note: GTS Reset/Lockout is labeled backwards in the computer. 2(448) GTS Fan A start and 2(466) GTS Fan B start.
- 3. P863_73a:e6 Off
- SGT Filter Train INOP
- 4. P863_73a:d6 Off
- SGT Filter Train INOP
- 5. LO_GTS_FN1A_W ON
- SGT EXH FAN A WHITE CONTROL POWER LIGHT
- 6. LO_GTS_FN1B_W ON
- SGT EXH FAN B WHITE CONTROL POWER LIGHT
- 7. DI-GTS_FN1AL RESET
- GTS FN 1 A LOCKOUT SWITCH
- 8. DI-GTS_FN1BL RESET
- GTS FN 1 B LOCKOUT SWITCH
- 9. DI_GTS_FN1AL RESET
- Delete in 1 sec on event 3
- 10. DI_GTS_FN1BL RESET
- Delete in 1 sec on event 4
- 11. Event 3: zdi2(448) GTS FN 1A Start Switch
- 12. Event 4: zdi2(466) GTS FN 1B Start Swith CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed.
Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: Isolate auxiliary building (HVR AOD 143 and HVR AOD 262 manually shut) and start both trains of standby gas systems with all critical tasks completed satisfactory.
RJPM-NRC-S16-S5 Rev. 1 RJPM-NRC-S16-S5 Rev 1 Page 4 of 9 PERFORMANCE
- START TIME:
OSP-53, EMERGENCY AND TRANSIENT RESPONSE SUPPORT PROCEDURE Attachment 21, Operating Auxiliary Building Ventilation
- 1. Isolate Auxiliary Building as follows
- 1. *Procedure Step:
1.1 Perform
the following:
Place HVR-AOD22A, ANNULUS MIX SPLY TO SGT in Man Init.
Standard HVR-AOD22A, ANNULUS MIX SPLY TO SGT hand switch rotated to Man Init. Cue N/A Notes Results SAT UNSAT 2. *Procedure Step:
Place HVR-AOD22B, ANNULUS MIX SPLY TO SGT in Man Init.
Standard HVR-AOD22B, ANNULUS MIX SPLY TO SGT hand switch rotated to Man Init. Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S5 Rev. 1 RJPM-NRC-S16-S5 Rev 1 Page 5 of 9 3. *Procedure Step:
Depress AUX BLDG TO SGT FLTR A MANUAL INITIATION 'Man Initiate' Pushbutton.
Standard AUX BLDG TO SGT FLTR A MANUAL INITIATION 'Man Initiate' Pushbutton is depressed
. Cue N/A Notes Results SAT UNSAT 4. *Procedure Step:
Depress AUX BLDG TO SGT FLTR B MANUAL INITIATION 'Man Initiate' Pushbutton.
Standard AUX BLDG TO SGT FLTR B MANUAL INITIATION 'Man Initiate' Pushbutton is depressed
. Cue N/A Notes Results SAT UNSAT ALTERNATE PATH
RJPM-NRC-S16-S5 Rev. 1 RJPM-NRC-S16-S5 Rev 1 Page 6 of 9 5. *Procedure Step:
1.2 Verify
the following dampers are closed:
HVR AOD143, DN STREAM ISOL SUPPLY HVR AOD164, UP STREAM ISOL SUPPLY HVR AOD263, SGT UPSTREAM SPLY ISOL HVR AOD264, SGT DNSTREAM SPLY ISOL HVR AOD262, AUX/CNTMT BLDG EXH ISOL HVR AOD214, AUX/CNTMT BLDG EXH ISOL HVR AOD161, ANNULUS PRESS CONT SUCT HVR AOD142, APC UP STREAM DISCH HVR AOD261, APC DN STREAM DISCH Standard The bolded dampers have to be manually closed.
Cue N/A Notes Results SAT UNSAT 6. *Procedure Step:
1.3 Verify
both divisions of GTS Start.
Standard Operator depressed GTS A(B) start and holds it until suction damper GTS
-AOD1A(B) is full open.
Cue N/A Notes RJPM-NRC-S16-S5 Rev. 1 RJPM-NRC-S16-S5 Rev 1 Page 7 of 9 Results SAT UNSAT Terminating Cue:
Isolate auxiliary building (HVR AOD 143 and HVR AOD 262 manually shut) and start both trains of standby gas systems with all critical tasks completed satisfactory.
STOP TIME:
CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable.
- 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S16-S5 Rev. 1 RJPM-NRC-S16-S5 Rev 1 Page 8 of 9 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S16-S5 Rev 1 OPERATOR CUE SHEET Initial Conditions
- The reactor scrammed one hour ago.
Auxiliary Building rad levels have raised to EOP-3 entry conditions
. Reactor pressure 390 psig.
Initiating Cues
-53, Attachment 21 in order to reduce radiation levels and allow re
-entry.
RJPM-NRC-S 1 6-S6 Rev 1 River Bend Station Initial License Exam Page 1 of 14 Transfer NPS SWG1A and NPS SWG1B from preferred to normal CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA VALIDATION TIME: Average Time (min):
15 Actual Time (min):
LICENSE LEVEL: SRO / RO ALTERNATE PATH: No IC: 65 EVALUATION METHOD
- EVALUATION LOCATION
- X Perform Plant Simulate X Simulator Control Room
Prepared: Gabe Kimich Date: 7/8/2016 Reviewed: Danny James Date: 7/21/2016 (Operations Representative)
Approved: John Fralick Date: 8/5/2016 (Facility Reviewer)
RJPM-NRC-S16-S6 Rev. 1 RJPM-NRC-S16-S6 Rev 1 Page 2 of 14 EXAMINER INFO SHEET Task Standard:
N P S-SWG1A and N P S-SWG1B are aligned to Normal completing all critical steps satisfactory
.
Synopsis: N PS SWG1A and N PS SWG1B are swapped from preferred to normal sources of power. 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situatio
- n.
- 2) Initial Conditions
- Reactor power is approximately 9
%. Fast transfer function has been verified OPERABLE by verifying STP
-302-0603 has been performed and is current.
Currently performing actions in GOP
-1, Attachment 1.
- 3) Initiating Cues
- The CRS has directed you to transfer NPS SWG1A and NPS SWG1B from preferred to normal sources of power per SOP
-4 5, Sections 5.1.1 and 5.1.2.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S16-S6 Rev. 1 RJPM-NRC-S16-S6 Rev 1 Page 3 of 14 DATA SHEET Task Title Task Number K&A SYSTEM
- K&A RATING
- Transfer NPS SWG1A From Preferred to Normal 262006001001 262001 A4.01 262001 A4.0 4 3.4 / 3.7 3.6 / 3.
7 REFERENCES
- APPLICABLE OBJECTIVES SOP-46, Rev 51 RLP-STM-0300, Obj 9 REQUIRED MATERIALS
- SAFETY FUNCTION:
SOP-00 46 , 4.16 KV SYSTEM (Sim Copy)
__6__ LICENSE LEVEL: SRO / RO ALTERNATE PATH: No LOCATION: Simulator ORIGIN (Previous 2 exams): New EMERGENCY: No ENGINEERED SAFETY FEATURE: No LOW POWER: No SIMULATOR CONDITIONS
& SETUP: 1. IC # 6 5 CRITICAL ELEMENTS:
Items marked with an "*" are Critical Steps and are required to be performed.
Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: NPS-SWG1A and NPS
-SWG1B are aligned to Normal completing all critical steps satisfactory.
RJPM-NRC-S16-S6 Rev. 1 RJPM-NRC-S16-S6 Rev 1 Page 4 of 14 PERFORMANCE
- START TIME:
SOP-004 5 Section 5.1 , Transfer of Power Source from Preferred Station Service Transformers to Normal Station Service Transformers NOTE Operation of the tap changer on RTX
-XSR1E and RTX
-XSR1F in the automatic mode or the electrically driven manual mode can be prevented if the manual operating handle is not fully inserted into its storage apparatus. With this handle not fully inserted, the tap changer will not operate in automatic or electrically driven manual mode which does not allow movement of the tap changer from its current position. The storage apparatus is designed to prevent automatic and electrically driven manual operation when the crank handle is removed, because the removed handle could be in use manually operating the tap changer.
- 1. *Procedure Step:
5.1.1. Transfer
NPS SWG1A from preferred to normal source as follows:
- 1. Turn 13.8KV SYNC SELECT Switch to NORM for NPS SWG1A.
Standard Operator placed handle in sync select notch. Then rotated handle clockwise to NORM. Cue N/A. Notes Results SAT UNSAT RJPM-NRC-S16-S6 Rev. 1 RJPM-NRC-S16-S6 Rev 1 Page 5 of 14 2. Procedure Step:
- 2. On V 1NPSA08, 13.8KV NORM SUPPLY VOLTS Indication, check voltage is in normal band.
Standard Operator verifies voltage is in normal band.
Cue N/A. Notes Results SAT UNSAT 3. Procedure Step:
- 3. Check sync scope pointer is at approximately 12 O'clock and motionless.
Standard Operator verifies sync scope is at 12 O'clock and motionless.
Cue N/A. Notes Results SAT UNSAT RJPM-NRC-S16-S6 Rev. 1 RJPM-NRC-S16-S6 Rev 1 Page 6 of 14 4. Procedure Step:
- 4. Check breaker sync permissive red light above the breaker indicating lights is on.
Standard Operator verifies breaker sync permissive red light is on.
Cue N/A. Notes Results SAT UNSAT NOTE Due to switchgear rating, both supply breakers should only remain closed for the minimum possible time and in all cases less than 15 seconds.
- 5. *Procedure Step:
- 5. Close NPS ACB09, 13.8KV NORM SUPPLY BRKR.
Standard Operator depresses NPS ACB09 breaker close pushbutton
. Cue N/A. Notes Results SAT UNSAT RJPM-NRC-S16-S6 Rev. 1 RJPM-NRC-S16-S6 Rev 1 Page 7 of 14 6. Procedure Step:
- 6. On A 1SPSA03, 13.8KV NORM SUPPLY AMPS Indication, check amperage increase.
Standard Operator verified amperage increase on A 1SPSA03, 13.8KV NORM SUPPLY AMPS Indication.
Cue N/A. Notes Results SAT UNSAT 7. *Procedure Step:
Standard Operator trip ped NPS ACB11, 13.8KV PFD SUPPLY BRKR Cue N/A. Notes Results SAT UNSAT RJPM-NRC-S16-S6 Rev. 1 RJPM-NRC-S16-S6 Rev 1 Page 8 of 14 8. Procedure Step:
- 8. Place 13.8KV SYNC SCOPE Switch to OFF for NPS SWG1A.
Standard Operator rotates 13.8KV SYNC SCOPE Switch counter clockwise to OFF. Cue N/A. Notes Results SAT UNSAT NOTE Operation of the tap changer on RTX
-XSR1E and RTX
-XSR1F in the automatic mode or the electrically driven manual mode can be prevented if the manual operating handle is not fully inserted into its storage apparatus. With this handle not fully inserted, the tap changer will not operate in automatic or electrically driven manual mode which does not allow movement of the tap changer from its current position. The storage apparatus is designed to prevent automatic and electrically driven manual operation when the crank handle is removed, because the removed handle could be in use manually operating the tap changer.
- 9. Procedure Step:
5.1.2. Transfer
NPS SWG1B from preferred to normal source as follows:
- 1. At RTX XSR1F Transformer Control Cabinet, place the Tap Changer Control Switch in LOCAL CONTROL.
- 2. Hold the MANUAL RAISE/LOWER Switch to move the tap changer to the 3 LOWER position; which is 3 steps counterclockwise from zero.
Standard Operator contacts SNEO to place the Tap Changer Control Switch in LOCAL CONTROL and the tap changer is in 3 LOWER position.
Cue Report as SNEO that the Tap Changer Control Switch is in LOCAL CONTROL and the tap changer is in 3 LOWER position
. Notes Results SAT UNSAT RJPM-NRC-S16-S6 Rev. 1 RJPM-NRC-S16-S6 Rev 1 Page 9 of 14 10. *Procedure Step:
- 3. Turn 13.8KV SYNC SELECT Switch to NORM for NPS SWG1B.
Standard Operator moves handle to NPS SWG1B switch and turn ed 13.8KV SYNC SELECT Switch to NORM for NPS SWG1B
. Cue N/A. Notes Results SAT UNSAT 11. Procedure Step:
- 4. On V 1NPSB08, 13.8KV NORM SUPPLY VOLTS Indication, check voltage is in normal band.
Standard Operator verifies voltage is in normal band.
Cue N/A. Notes Results SAT UNSAT 12. Procedure Step:
- 5. Check sync scope pointer is at approximately 12 O'clock and motionless.
Standard Operator verifies sync scope is at 12 O'clock and motionless.
Cue N/A. Notes Results SAT UNSAT RJPM-NRC-S16-S6 Rev. 1 RJPM-NRC-S16-S6 Rev 1 Page 10 of 14 13. Procedure Step:
- 6. Check breaker sync permissive red light above the breaker indicating lights is on.
Standard Operator verifies breaker sync permissive red light is on.
Cue N/A. Notes Results SAT UNSAT NOTE Due to switchgear rating, both supply breakers should only remain closed for the minimum possible time and in all cases less than 15 seconds.
- 14. *Procedure Step:
- 7. Close NPS ACB25, 13.8KV NORM SUPPLY BRKR.
Standard Operator close d NPS ACB25, 13.8KV NORM SUPPLY BRKR
. Cue N/A. Notes Results SAT UNSAT RJPM-NRC-S16-S6 Rev. 1 RJPM-NRC-S16-S6 Rev 1 Page 11 of 14 15. Procedure Step:
- 8. On A 1SPSB03, 13.8KV NORM SUPPLY AMPS Indication, check amperage increase.
Standard Operator verified amperage increase on A 1SPSA03, 13.8KV NORM SUPPLY AMPS Indication.
Cue N/A. Notes Results SAT UNSAT 16. *Procedure Step:
Standard Operator trip ped NPS ACB27, 13.8KV PFD SUPPLY BRKR. Cue N/A. Notes Results SAT UNSAT RJPM-NRC-S16-S6 Rev. 1 RJPM-NRC-S16-S6 Rev 1 Page 12 of 14 17. Procedure Step:
- 10. Place 13.8KV SYNC SELECT Switch to OFF for NPS SWG1B.
Standard Operator rotated 13.8KV SYNC SELECT Switch counter clockwise to OFF for NPS SWG1B
. Cue N/A. Notes Resul ts SAT UNSAT Terminating Cue: NPS-SWG1A and NPS
-SWG1B are aligned to Normal completing all critical steps satisfactory.
STOP TIME:
CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable.
- 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-S16-S6 Rev. 1 RJPM-NRC-S16-S6 Rev 1 Page 13 of 14 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S 1 6-S 6 Rev 1 River Bend Station Initial License Exam OPERATOR CUE SHEET Initial Conditions
- Reactor power is approximately 9
%. Fast transfer function has been verified OPERABLE by verifying STP
-302-0603 has been performed and is current.
Currently performing actions in GOP
-1, Attachment 1.
Initiating Cues
- The CRS has directed you to transfer NPS SWG1A and NPS SWG1B from preferred to normal sources of power per SOP
-45, Sections 5.1.1 and 5.1.2.
RJPM-NRC-S16-S 7 Rev 2 River Bend Station Initial License Exam Page 1 of 12 DRIVE IN IRM/SRM DETECTORS FOLLOWING A SCRAM CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA VALIDATION TIME: Average Time (min):
1 0 Actual Time (min):
LICENSE LEVEL: SRO / RO ALTERNATE PATH: No IC: 67 with S5 EVALUATION METHOD: EVALUATION LOCATION
- X Perform Plant Simulate X Simulator Control Room Prepared: Gabe Kimich Date: 7/8/2016 Reviewed: Danny James Date: 7/21/2016 (Operations Representative)
Approved: John Fralick Date: 8/5/2016 (Facility Reviewer)
RJPM-NRC-S16-S7 Rev. 2 RJPM-NRC-S16-S7 Rev 2 Page 2 of 12 EXAMINER INFO SHEET Task Standard:
SRM and IRM detectors driven full in with all critical steps completed satisfactory
. Synopsis: This task will insert the SRM and IRM detectors following a scram to monitor core power. This task is completed using operator "toolbox skills."
- 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
" NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.
- 2) Initial Conditions
- A reactor scram has just occurred from extended power operation.
SRM mode switches are in OPERATE.
- 3) Initiating Cues
- The CRS has directed you to drive in the SRM and IRM detectors (all detectors in parallel), i n accordance with AOP
-0001.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S16-S7 Rev. 2 RJPM-NRC-S16-S7 Rev 2 Page 3 of 12 DATA SHEET TASK Title:
Task Number K&A SYSTEM
- K&A RATING
- DRIVE IN SRM/IRM DETECTORS 215003001001 215003 215003 215003 215003 215004 215004 215004 A1.01 3.4/3.3 A4.03 3.6/3.4 A4.06 3.0/2.9 A4.07 3.6/3.6 A1.01 3.0/3.1 A4.04 3.2/3.2 A4.07 3.4/
3.6 REFERENCES
- APPLICABLE OBJECTIVES SOP-0074, Rev 307, Section 5.1 RLP-STM-0503 Objective 2, 10, 15 REQUIRED MATERIAL S: SAFETY FUNCTION:
SOP-0074, Rev 307, Section 5.1
__7__ LICENSE LEVEL: SRO / RO ALTERNATE PATH: No LOCATION: Simulator ORIGIN (Previous 2 exams): Bank RJPM-AUD12-S6 EMERGENCY: No ENGINEERED SAFETY FEATURE: No LOW POWER: Yes SIMULATOR CONDITIONS & SETUP: 1. IC # 67 Performed with S5.
- 2. Reactor scram occurred.
- 3. Reactor pressure 390 psig.
CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed.
Failure to successfully complete a Critical Step requires th e JPM to be evaluated as Unsatisfactory.
TASK STANDARD: SRM and IRM detectors driven full in with all critical steps completed satisfactory.
RJPM-NRC-S16-S7 Rev. 2 RJPM-NRC-S16-S7 Rev 2 Page 4 of 12 PERFORMANCE
- START TIME:
SOP-0007, Neutron Monitoring System Section 5.1, Inserting SRM/IRM Detectors
- 1. Procedure Step:
5.1.1. IF undervessel access has been permitted during a plant outage, THEN perform the following:
- 1. Verify that the CRD Removal Platform is stowed and locked in its proper position. 2. Verify that the SRM/IRM cover plates have been removed from the CRD Removal Platform.
- 3. Verify that the SRM/IRM cables are in the proper position to allow for inserting detectors.
Standard N/A. The detectors are not inserted during a plant outage.
Cue N/A Notes Results SAT UNSAT 2. *Procedure Step:
5.1.2. Depress
the SRM/IRM POWER ON Pushbutton.
Standard The SRM/IRM POWER ON Pushbutton is depressed
. Verified POWER ON light is lit.
Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S7 Rev. 2 RJPM-NRC-S16-S7 Rev 2 Page 5 of 12 3. Procedure Step:
5.1.3. Check
position indication of the detectors.
Standard Candidate located/identified the detector position indicating light and verified the detector is OUT by checking the OUT light is ON and the IN light is OFF.
Cue N/A Notes Results SAT UNSAT 4. *Procedure Step:
5.1.4. Depress
the SRM/IRM SELECT Pushbuttons for the SRM/IRM detectors to be inserted.
Standard Candidate located/identified the SRM/IRM SELECT Pushbuttons and selected all 4 SRMs and all 8 IRMs by depressing the associated pushbutton and verifying the pushbutton light illuminated indicating that it was depressed/selected.
Cue N/A Notes The standard listed here will drive in all detectors simultaneously. The candidate may elect to drive in the SRMs and IRMs separately. Either way is acceptable.
Results SAT UNSAT RJPM-NRC-S16-S7 Rev. 2 RJPM-NRC-S16-S7 Rev 2 Page 6 of 12 PROCEDURE NOTE Observation of changing indicated power levels provides verification of detector movement. 5. *Procedure Step:
5.1.5. IF driving in SRMs, THEN depress the DRIVE IN Pushbutton as necessary to maintain SRM counts greater than or equal to 1 x 10 3 and less than or equal to 1 x 10 5 CPS. Standard Candidate located/identified and depressed the DRIVE IN pushbutton and monitored SRM count rate.
Cue N/A Notes Takes approximately 3 minutes 20 seconds from full out to full in.
Results SAT UNSAT PROCEDURE CAUTION Premature down ranging of the IRM Range Switches can result in a Reactor Scram. Do not down range IRMs until the detectors are fully inserted in the core to prevent possible RPS actuation.
- 6. Procedure Step:
5.1.6. IF driving in IRMs, THEN perform the following:
- 1. Place IRM/APRM Recorder Switches to the IRM position.
Standard Candidate located/identified the IRM/APRM Recorder Switches and placed them all into the IRM position by manipulating the toggle switch to IRM.
Cue N/A Notes Not critical because the SRM detectors are already on service.
Results SAT UNSAT RJPM-NRC-S16-S7 Rev. 2 RJPM-NRC-S16-S7 Rev 2 Page 7 of 12 7. Procedure Step:
5.1.6. IF driving in IRMs, THEN perform the following:
- 2. Range IRMs as necessary to maintain power level indication greater than or equal to 15/125 and less than or equal to 75/125.
Standard N/A. SRMs are on range.
Cue N/A Notes Results SAT UNSAT 8. *Procedure Step:
5.1.7. Depress
the DRIVE IN Pushbutton.
Standard Candidate located/identified and depressed the DRIVE IN Pushbutton and monitored IRM power levels.
Cue N/A Notes Takes approximately 3 minutes 20 seconds from full out to full in.
Results SAT UNSAT RJPM-NRC-S16-S7 Rev. 2 RJPM-NRC-S16-S7 Rev 2 Page 8 of 12 9. Procedure Step:
5.1.8. Check
the DRIVE IN and DRIVING IN Indicator Lights are on. Standard Candidate located/identified and verified the DRIVE IN and DRIVING IN lights are on for all detectors.
Cue N/A Notes Results SAT UNSAT 10. Procedure Step:
5.1.9. IF the detector was out of the core, THEN check the OUT Indicator Lights go off.
Standard Candidate located/identified and verified the OUT indicating light for each detector extinguished.
Cue N/A Notes Results SAT UNSAT 11. Procedure Step:
5.1.10. WHEN the detectors are fully inserted into the core, THEN perform the following:
- 1. Check the IN Lights are on.
- 2. Check the DRIVING IN Light is off.
Standard Candidate located/identified and verified the IN indicating light for each detector was ON.
Candidate located/identified and verified the DRIVING IN indicating light for each detector was OFF.
Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S7 Rev. 2 RJPM-NRC-S16-S7 Rev 2 Page 9 of 12 12. *Procedure Step:
5.1.10. WHEN the detectors are fully inserted into the core, THEN perform the following:
- 3. Depress the DRIVE IN Pushbutton.
Standard Candidate located/identified and depressed the DRIVE IN pushbutton.
Cue N/A Notes Results SAT UNSAT 13. *Procedure Step:
5.1.10. WHEN the detectors are fully inserted into the core, THEN perform the following:
- 4. Depress the SRM/IRM SELECT Pushbuttons to de select the detector drive motors.
Standard Candidate located/identified the SRM/IRM SELECT Pushbuttons and de
-selected all 4 SRMs and all 8 IRMs by depressing the associated pushbutton and verifying the pushbutton light extinguished indicating that it was no longer depressed/de
-selected. Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S7 Rev. 2 RJPM-NRC-S16-S7 Rev 2 Page 10 of 12 14. *Procedure Step:
5.1.11. Depress SRM/IRM POWER ON Pushbutton to turn off power.
Standard Candidate located/identified and depressed the SRM/IRM POWER ON Pushbutton to turn the power off and verified the POWER ON light extinguished.
Cue N/A Notes Results SAT UNSAT Terminating Cue: SRM and IRM detectors driven full in with all critical steps completed satisfactory.
STOP TIME:
CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable.
- 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S16-S7 Rev. 2 RJPM-NRC-S16-S7 Rev 2 Page 11 of 12 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S16-S7 Rev 2 OPERATOR CUE SHEET Initial Conditions
- A reactor scram has just occurred from extended power operation.
SRM mode switches are in OPERATE.
Initiating Cues
- The CRS has directed you to drive in the SRM and IRM detectors (all detectors in parallel), i n accordance with AOP
-0001.
RJPM-NRC-S 1 6-S 8 Rev 1 River Bend Station Initial License Exam Page 1 of 10 PLACE RHR A IN SUPPRESSION POOL COOLING MODE CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA VALIDATION TIME: Average Time (min):
15 Actual Time (min):
LICENSE LEVEL: SRO / RO ALTERNATE PATH: Yes IC: 67 with S2 EVALUATION METHOD: EVALUATION LOCATION
- X Perform Plant Simulate X Simulator Control Room Prepared: Gabe Kimich Date: 7/8/2016 Reviewed: Danny James Date: 7/21/2016 (Operations Representative)
Approved: John Fralick Date: 8/5/2016 (Facility Reviewer)
RJPM-NRC-S16-S8 Rev. 1 RJPM-NRC-S16-S8 Rev 1 Page 2 of 10 EXAMINER INFO SHEET Task Standard:
RHR A aligned in suppression pool cooling and RHR A pump secured with all critical steps completed satisfactory
. Synopsis: RHR A aligned in suppression pool cooling. When flow is established the pump amps will be high and require the pump to be secured.
- 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
" NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.
- 2) Initial Conditions
- RHR "A" is filled and vented in Standby.
Suppression Pool temperature is 80ºF
.
- 3) Initiating Cues
- The CRS directs you as Unit Operator to place RHR A in Suppression Pool Cooling per SOP-0031 Section 4.6 in preparation for upcoming scheduled RCIC run
.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S16-S8 Rev. 1 RJPM-NRC-S16-S8 Rev 1 Page 3 of 10 DATA SHEET TASK Title:
Task Number K&A SYSTEM
- K&A RATING
- Place RHR A in Suppression Pool Cooling Mode with high pump amps 205012001001 219000K1.01 21900 A4.02 21900 A4.01 21900 A4.05 21900 K3.01 21900 K4.07 21900 K4.09 21900 G04 21900 A1.01 21900 G07 21900 A1.02 21900 A1.08 3.8/3.9 3.7/3.5 3.8/3.7 3.4/3.4 3.9/4.1 3.0/3.1 3.3/3.4
3.9/3.9 4.0/4.0
4.0/4.1 3.5/3.5 3.7/
3.6 REFERENCES
- APPLICABLE OBJECTIVES SOP-0031, Residual Heat Removal HLO-021-07, Obj 2, 3, 6, 8, and 11.
ARP-P601-20 ALARM RESPONSE REQUIRED MATERIALS
- SAFETY FUNCTION: SOP-0031, Residual Heat Removal
__3__ ARP-P601-20 ALARM RESPONSE LICENSE LEVEL: SRO / RO ALTERNATE PATH: Yes LOCATION: Simulator ORIGIN (Previous 2 exams): Bank RJPM-OPS-204-01A EMERGENCY: No ENGINEERED SAFETY FEATURE: No LOW POWER: Yes SIMULATOR CONDITIONS
& SETUP: Required Power:
Reactor Shutdown IC No.: 67 Performed with S2 Notes: Set up on trigger 1 the following Annunicator and meter Override on E12
-F024A control switch Annunicator Override p601_20a:a_4 RHR PUMPA OVERLOAD PRE
-TRIP WARNING t1 d00:0:30 Meter Override AO_E12-C002A-M 601-20B RHR PUMP A MOTOR AMPS MT t1 s
-130 r00:00:30 CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed.
Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: RHR A aligned in suppression pool cooling and RHR A pump secured with all critical steps completed satisfactory.
RJPM-NRC-S16-S8 Rev. 1 RJPM-NRC-S16-S8 Rev 1 Page 4 of 10 PERFORMANCE
- START TIME:
SOP-0031, Residual Heat Removal Section 4.6, Suppression Pool Cooling Mode Startup
- 1. Procedure Step:
4.6.1. IF Standby Service Water is supplying service water loads, THEN verify closed SPC
Standard N/A. Normal service water is supplying service water loads.
Cue N/A Notes Results SAT UNSAT PROCEDURE CAUTION Opening E12
-F024A(B), RHR PUMP A(B) TEST RTN TO SUP PL partially or fully, with the associated RHR Pump shutdown can cause water hammer when the pump is started. Do not allow a pump start until the loop has been filled and vented if E12
-F024A(B) has been opened with the pump shutdown.
- 2. Procedure Step:
4.6.2. Verify
the RHR Heat Exchangers are being supplied by either Normal or Standby Service Water.
Standard Operator verifies the RHR Heat Exchangers are being supplied by Normal Service Water.
Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S8 Rev. 1 RJPM-NRC-S16-S8 Rev 1 Page 5 of 10 PROCEDURE NOTE Per ER 98-0273 - 5800 gpm of Normal Service Water may be supplied to each Division of the RHR Hx's during ATWS conditions provided the guidelines outlined in the P&Ls are observed. Normal Service Water can be supplied to both RHR Heat Exchangers to support modes of operation in both loops, provided the COMBINED Normal Service Water flow does not exceed 5800 gpm.
Two Standby Service Water Pumps are required in each loop when operating the Standby Service Water System for heat removal through the RHR Heat Exchangers.
- 3. *Procedure Step:
4.6.3. On H13-P870, throttle open E12
-F068A, RHR HX A SVCE WTR RTN to establish less than or equal to 5800 gpm flow as indicated on E12 R602A, RHR HX A SVCE WTR FLOW.
Standard Operator throttles open E12
-F068A, on the P870, to establish less than or equal to 5800 gpm flow as indicated on E12 R602A, on the P601.
Cue N/A Notes Results SAT UNSAT 4. Procedure Step:
4.6.4. IF performing this Section for RHR Heat Exchanger service water flushing only, WHEN 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> have elapsed, THEN go to Step 6.3.4 to secure from flushing.
Standard N/A Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S8 Rev. 1 RJPM-NRC-S16-S8 Rev 1 Page 6 of 10 5. *Procedure Step:
Start the E12
-C002A, RHR PUMP A.
Standard Operator rotates hand switch clockwise to start the pump.
Cue N/A Notes Expected annunciator P601 F07 Div 1 ADS LOGIC LPCS/LPCI OPR PERMISSIVE.
Results SAT UNSAT 6. *Procedure Step:
4.6.6. Open E12-F024A, RHR PUMP A TEST RTN TO SUP PL.
- 1. WHEN flow exceeds 1100 gpm, THEN verify E12
-F064A, RHR PUMP A MIN FLOW TO SUP PL closes.
Standard Operator opens E12
-F024A and observes the E12
-F064A closes.
Cue N/A Notes Results SAT UNSAT 7. Procedure Step:
4.6.7. Check
running pump amps are less than or equal to 91 amps.
Standard Operator verifies running pump amps are less than or equal to 91 amps.
Cue N/A Notes When the operator verifies pump amps, they will indicate greater than 105 amps. Results SAT UNSAT RJPM-NRC-S16-S8 Rev. 1 RJPM-NRC-S16-S8 Rev 1 Page 7 of 10 ALTERNATE PATH
- 8. Procedure Step:
Per H13-P601/20A/A04 , RHR PUMP A OVERLOAD PRE
-TRIP WARNING
- 1. Verify the following:
RHR Pump A discharge flow is less than 5950 gpm.
E12-F064A, RHR PUMP A MIN FLOW TO SUP PL is closed. Standard Operator verifies pump A discharge flow is less than 5950 gpm and the E12
-F064A is closed.
Cue N/A Notes Results SAT UNSAT NOTE RHR Pump A trips if current reaches 150 amps. RHR Pump A full load motor current is 91 amps.
- 9. Procedure Step:
- 2. Reduce pump motor amps by throttling closed any of the following valves:
E12-F003A, RHR A HX OUTLET VALVE E12-F048A, RHR A HX BYPASS VALVE Standard The operator will throttle closed either the E12
-F003A or E12
-F048A. Cue N/A Notes Results SAT UNSAT RJPM-NRC-S16-S8 Rev. 1 RJPM-NRC-S16-S8 Rev 1 Page 8 of 10 10. *Procedure Step:
- 3. IF pump motor amps cannot be reduced below 105 amps AND RHR A is not needed for level control, THEN stop RHR Pump A.
Standard Operator will stop RHR Pump A.
Cue N/A Notes Results S AT UNSAT Terminating Cue: RHR A aligned in suppression pool cooling and RHR A pump secured with all critical steps completed satisfactory.
STOP TIME:
CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable.
- 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S16-S8 Rev. 1 RJPM-NRC-S16-S8 Rev 1 Page 9 of 10 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S16-S8 Rev 1 OPERATOR CUE SHEET Initial Conditions
- RHR "A" is filled and vented in Standby.
Suppression Pool temperature is 80ºF
. Initiating Cues: The CRS directs you as Unit Operator to place RHR A in Suppression Pool Cooling per SOP-0031 Section 4.6 in preparation for upcoming scheduled RCIC run
.
RJPM-NRC-S 1 6-P1 Rev 2 River Bend Station Initial License Exam Page 1 of 10 Alternating CRD Discharge Filters CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA VALIDATION TIME: Average Time (min):
20 Actual Time (min):
LICENSE LEVEL: SRO / RO ALTERNATE PATH: YES EVALUATION METHOD
- EVALUATION LOCATION
- Perform X Plant X Simulate Simulator Control Room
Prepared: Gabe Kimich Date: 7/8/2016 Reviewed: A. Willson Date: 7/21/2016 (Operations Representative)
Approved: John Fralick Date: 8/5/2016 (Facility Reviewer)
RJPM-NRC-S16-P1 Rev. 2 RJPM-NRC-S16-P1 Rev 2 Page 2 of 10 EXAMINER INFO SHEET Task Standard:
CRD pump discharge filters swapped and discharge filter B placed back in service with all critical steps completed satisfactory.
Synopsis: Operator will attempt to place CRD pump discharge filter 'A' on service. While placing '
A' on service a high D/P will occur requiring '
B' to be placed back in service.
(NOTE: The CRD pump has a low suction pressure trip, but it does not have a high discharge pressure trip, so the pump will not automatically trip when the discharge filter clogs.)
- 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
" NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.
- 2) Initial Conditions
- The reactor is critical. CRD pump discharge filter B is in service.
The out of service discharge filter A is clean.
The C11 PDIS N002, Filter Differential Pressure Indicating Switch is in operation.
- 3) Initiating Cues
-2, Section 5.
- 3.
- 4) Solicit and answer any questions the operator may have.
RJPM-NRC-S16-P1 Rev. 2 RJPM-NRC-S16-P1 Rev 2 Page 3 of 10 DATA SHEET TASK Title:
Task Number K&A SYSTEM
- K&A RATING
- Alternate CRD Discharge Filters 2 01005001001 201009001004 201001 A 2.0 5 2.9 /
2.9 REFERENCES
- APPLICABLE OBJECTIVES SOP-0002, Section 5.4 RLP-STM-0109, Obj 7, 12 REQUIRED MATERIALS
- SAFETY FUNCTION
- SOP-0002, Section 5.4
__1__ LICENSE LEVEL: SRO / RO ALTERNATE PATH: YES LOCATION: RCA ORIGIN (Previous 2 exams): NEW EMERGENCY: NO ENGINEERED SAFETY FEATURE: NO LOW POWER: NO SIMULATOR CONDITIONS
& SETUP: N/A for plant JPM CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD
- CRD pump discharge filters swapped and discharge filter B placed back in service with all critical steps completed satisfactory.
RJPM-NRC-S16-P1 Rev. 2 RJPM-NRC-S16-P1 Rev 2 Page 4 of 10 PERFORMANCE
- START TIME:
SOP-0002, CONTROL ROD DRIVE HYDRAULICS Section 5.3, Alternating Discharge Filters 1. Procedure Step:
5.3.1. Verify
the C11 PDIS N002, Filter Differential Pressure Indicating Switch is in operation.
Standard No action required. The initial conditions state this is in operation.
Cue If requested, gauge indicates 12 psid. Notes Gage is about 5 feet off of the ground. Large black gage and is about 7 feet from the right wall. Gage may actually indicate 10
-18 psid based on last time the filters have been swapped.
Results SAT UNSAT 2. *Procedure Step:
5.4.2. Perform
the following for the filter to be placed in operation.
- 1. Open C11 VF020A(B), CRD PMP DISCH FILTER D003A(B) INLET ISOL VLV. Standard Operator rotates C11 VF020A, CRD PMP DISCH FILTER D003A INLET ISOL VLV counter clockwise.
Cue Stem rises and resistance felt in the counter clockwise direction.
Hear flow noise when the valve starts to open.
Notes Results SAT UNSAT RJPM-NRC-S16-P1 Rev. 2 RJPM-NRC-S16-P1 Rev 2 Page 5 of 10 3. *Procedure Step: 2. Vent the filter as follows:
. Standard Operator rotates C11 VF022A, CRD PMP DISCH FILTER D003 A VENT VLV in the counter clockwise direction.
Cue Resistance is felt in the counter clockwise direction.
Notes Results SAT UNSAT 4. *Procedure Step:
- 2) Throttle open DER V8(V10), C11 FLTD003A(B) VENT VALVE to vent air from the filter.
Standard Operator rotates DER V8, C11 FLTD003 A VENT VALVE clockwise.
Cue After the handwheel is rotated approximately 1/2 turn counter clockwise, report air is streaming from the valve for approximately 3 seconds. Then a steady stream of water is coming from the vent valve.
Notes Results SAT UNSAT 5. *Procedure Step:
- 3) WHEN air free water is vented from filter, THEN close the following valves: DER V8(V10)
C11 VF022A(B)
Standard Operator rotates DER V8 and C11 VF022 A clockwise.
Cue Resistance felt in the clockwise direction for each valve closed
. Notes Results SAT UNSAT RJPM-NRC-S16-P1 Rev. 2 RJPM-NRC-S16-P1 Rev 2 Page 6 of 10 NOTE: Operator may call control room prior to next step to inform them that CRD filter A is about to be placed on service.
CUE: If required acknowledge CRD A filter is about to be placed on service.
- 6. *Procedure Step:
Standard Operator rotates C11 VF021 A, CRD PMP DISCH FILTER D003 A OUTLET ISOL VLV counter clockwise.
Cue Resistance felt in the counter clockwise direction.
Flow noise though the pipe. Not es Results SAT UNSAT CAUTION Backflow through the filter could damage the filter cartridge. Do not close C11-VF020A(B) before closing C11
-VF021A(B).
- 7. *Procedure Step:
5.3.3. Perform
the following for the filter being removed from service:
- 1. Close C11 VF021A(B), CRD PMP DISCH FILTER D003A(B) OUTLET ISOL VLV. Standard Operator rotates C11 VF021 B, CRD PMP DISCH FILTER D003 B OUTLET ISOL VLV clockwise.
Cue Resistance felt in the counter clockwise direction.
Notes Results SAT UNSAT RJPM-NRC-S16-P1 Rev. 2 RJPM-NRC-S16-P1 Rev 2 Page 7 of 10 8. Procedure Step:
- 2. Verify proper filter operation by observing C11 PDIS N002 is in normal band. Standard Operator verifies D/P by observing C11 PDIS N002.
Cue C11 PDIS N0 02 indicates 0
-30 psid. Raise half inch increments until 28 psid. Notes Gage is about 5 feet off of the ground, large black gage
, and is about 7 feet from the right wall.
Discharge filter high D/P alarms at 20 psid at P601 in control room.
The CRD pump has a low suction pressure trip but no discharge pressure trip. Results SAT UNSAT ALTERNATE PATH If operator calls control room for guidance, request recommendation.
Concur with recommendation to place CRD filter B back on service and state, "I concur with recommendation. We are seeing indications of header pressure slowly lowering and we could be getting accumulator faults shortly."
- 9. *Procedure Step:
Per EN-OP-120, Operator Fundamentals Program Monitoring: Identify degrading parameter and equipment trends.
Control: Anticipate the impact of component operation prior to its operation, and then verify that the expected effects occur during and following the operation.
Standard Operator rotates C11 VF021 B, CRD PMP DISCH FILTER D003 B OUTLET ISOL VLV. counter clockwise.
Cue Resistance felt in the counter clockwise direction.
C11_PDIS_N002 indicates as is.
(10-18 psid) Notes Results SAT UNSAT RJPM-NRC-S16-P1 Rev. 2 RJPM-NRC-S16-P1 Rev 2 Page 8 of 10 Terminating Cue: CRD pump discharge filters swapped and discharge filter B placed back in service with all critical steps completed satisfactory.
STOP TIME: CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable.
- 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S16-P1 Rev. 2 RJPM-NRC-S16-P1 Rev 2 Page 9 of 10 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S16-P1 Rev 2 OPERATOR CUE SHEET Initial Conditions: The reactor is critical. CRD pump discharge filter B is in service.
The out of service discharge filter A is clean.
The C11 PDIS N002, Filter Differential Pressure Indicating Switch is in operation.
Initiating Cues
-2, Section 5.3.
RJPM-NRC-S16-P 2 Rev 1 River Bend Station Initial License Exam Page 1 of 11 AOP-31, Attachment 12, ATC actions CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA VALIDATION TIME: Average Time (min):
20 Actual Time (min):
LICENSE LEVEL: SRO / RO ALTERNATE PATH: NO EVALUATION METHOD
- EVALUATION LOCATION
- Perform X Plant X Simulate Simulator Control Room
Prepared: Gabe Kimich Date: 7/8/2016 Reviewed: Scott Dallas Date: 7/21/2016 (Operations Representative)
Approved: John Fralick Date: 8/5/2016 (Facility Reviewer)
RJPM-NRC-S16-P2 Rev. 1 RJPM-NRC-S16-P2 Rev 1 Page 2 of 11 EXAMINER INFO SHEET Task Standard:
A OP-31, Attachment 12, Sections 1.1.4
-1.1.6 critical tasks completed satisfactory.
Synopsis: Operator completes ATC actions for control room evacuation due to fire at the remote shutdown panel.
- 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
" NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.
- 2) Initial Conditions: The reactor is shutdown. Crew is manning the remote shutdown panel due to smoke in the control room.
RHR is not in Shutdown cooling.
- 3) Initiating Cues
-31, (SHUTDOWN FROM OUTSIDE THE MAIN CONTROL ROOM) Sections 1.1.4
-1.1.6.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S16-P2 Rev. 1 RJPM-NRC-S16-P2 Rev 1 Page 3 of 11 DATA SHEET TASK Title:
Task Number K&A SYSTEM
- K&A RATING
- Place Division 1 Transfer Switches in EMERG 400049004001 203000 K4.14 295016 AA1.07 3.6 / 3.7 4.2 /
4.3 REFERENCES
- APPLICABLE OBJECTIVES SOP-0031 RLP-STM-200, Obj 3, 11 REQUIRED MATERIALS
- SAFETY FUNCTION
- SOP-0031, Section 1.1.4
-1.1.6 __2__ LICENSE LEVEL: SRO / RO ALTERNATE PATH: NO LOCATION: Plant outside RCA ORIGIN (Previous 2 exams): NEW EMERGENCY: YES ENGINEERED SAFETY FEATURE: NO LOW POWER: YES SIMULATOR CONDITIONS
& SETUP: N/A CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed.
Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: A OP-31, Attachment 12, Sections 1.1.4
-1.1.6 critical tasks completed satisfactory.
RJPM-NRC-S16-P2 Rev. 1 RJPM-NRC-S16-P2 Rev 1 Page 4 of 11 PERFORMANCE
- START TIME:
SOP-31, SHUTDOWN FROM OUTSIDE THE MAIN CONTROL ROOM Section 1.1.4-1.1.6 1. *Procedure Step:
1.1.4. WHEN informed by the CRS per Step 5.9, THEN At C61
-P001, REMOTE SHUTDOWN PANEL, perform the following:
- 1. Place S8, TRANSFER SWITCH FOR E12
-F027A, E12 F042A, E12 F053, in EMERG. Standard S8, TRANSFER SWITCH FOR E12
-F027A, E12 F042A, E12 F053, rotated to EMERG. Cue S8 switch has been rotated to EMERG position.
Red and green lights energize as required for the valves above the handswitch.
Notes Results SAT UNSAT 2. Procedure Step:
- 2. IF RHR A was in Shutdown Cooling, THEN place the E12
-F004A, RHR PUMP A SUP PL SUCTION VALVE Control Switch in the CLOSE position.
Standard N/A. Initial conditions state RHR A in shutdown cooling.
Cue N/A. If asked, RHR A was not in shutdown cooling.
Notes Results SAT UNSAT RJPM-NRC-S16-P2 Rev. 1 RJPM-NRC-S16-P2 Rev 1 Page 5 of 11 3. *Procedure Step:
- 3. Place the following Transfer Switches in EMERG:
- 1) S6, TRANSFER SWITCH FOR E12
-F048A, E12 F008, E12 F006A, E12 F004A Standard S6 handswitch rotate clockwise to EMERG position.
Cue You hear click sound and resistance in clockwise direction.
Red and green lights energize as required for the valves above the handswitch.
Notes Results SAT UNSAT 4. *Procedure Step:
- 3. Place the following Transfer Switches in EMERG:
- 2) S12, TRANSFER SWITCH FOR E12
-C00 2A Standard S12, TRANSFER SWITCH FOR E12
-C002A, rotated clockwise to EMERG position. Cue You hear click sound and resistance in clockwise direction.
Notes Results SAT UNSAT RJPM-NRC-S16-P2 Rev. 1 RJPM-NRC-S16-P2 Rev 1 Page 6 of 11 5. *Procedure Step:
- 3. Place the following Transfer Switches in EMERG: 3) S7, TRANSFER SWITCH FOR E12
-F068A, E12 F047A, E12 F003A, E12 F024A Standard S7, TRANSFER SWITCH FOR E12
-F068A, E12 F047A, E12 F003A, E12 F024A, is rotated clockwise to EMERG position.
Cue You hear click sound and resistance in clockwise direction. Notes Results SAT UNSAT 6. Procedure Step:
- 4. IF RHR A was in Shutdown Cooling, THEN verify that E12
-F040, RHR A TO RADWASTE DN STREAM ISOL VALVE Control Switch in the CLOSE position. Standard N/A. Initial conditions do not mention RHR A in shutdown cooling.
Cue N/A. If asked, RHR A was not in shutdown cooling.
Notes Results SAT UNSAT 7. *Procedure Step:
- 5. Place S9, TRANSFER SWITCH FOR E12
-F064A, E12 F037A, E12 F040, E12-F026A, E12
-F011A in EMERG.
RJPM-NRC-S16-P2 Rev. 1 RJPM-NRC-S16-P2 Rev 1 Page 7 of 11 Standard S9 rotated clockwise to EMERG position.
Cue You hear click sound and resistance in clockwise direction.
Notes Results SAT UNSAT PROCEDURE NOTE If the Division I Emergency Diesel Generator tripped due to a high Lube Oil or Jacket Water outlet temperature, the UO may have already placed 43
-1SWP A05 and 43
-1SWP A08 to EMERG.
- 8. *Procedure Step:
1.1.5. At RSS-PNL101, BOP REMOTE SHUTDOWN PNL, the far right panel, verify the following RSS Transfer Switches in EMERG:
- 1. 43-1SWP A05, CONTACT TRANSFER SWIT CH Standard Operator rotates handle for 43-1SWP A05, CONTACT TRANSFER SWITCH clockwise to EMERG position.
Cue You hear click sound and resistance in clockwise direction.
Notes Results SAT UNSAT 9. *Procedure Step:
1.1.5. At RSS-PNL101, BOP REMOTE SHUTDOWN PNL, the far right panel, verify the following RSS Transfer Switches in EMERG:
- 2. 43-1SWP A08, CONTACT TRANSFER SWITCH Standard Operator rotates handle for 43-1SWP A08, CONTACT TRANSFER SWITCH clockwise to EMERG position.
RJPM-NRC-S16-P2 Rev. 1 RJPM-NRC-S16-P2 Rev 1 Page 8 of 11 Cue You hear click sound and resistance in clockwise direction.
Notes Results SAT UNSAT 10. Procedure Step:
1.1.6. Report
to the CRS that Attachment 12, ATC Operator Actions is complete. Standard Operator reports Attachment 12 is complete.
Cue Acknowledge attachment 12 is complete.
Notes Results SAT UNSAT Terminating Cue: A OP-31, Attachment 12, Sections 1.1.4
-1.1.6 critical tasks completed satisfactory.
STOP TIME:
RJPM-NRC-S16-P2 Rev. 1 RJPM-NRC-S16-P2 Rev 1 Page 9 of 11 CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable.
- 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S16-P2 Rev. 1 RJPM-NRC-S16-P2 Rev 1 Page 10 of 11 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments.
Evaluator's Signature:
Date:
RJPM-NRC-S16-P 2 Rev 1 OPERATOR CUE SHEET Initial Conditions
- The reactor is shutdown.
Crew is manning the remote shutdown panel due to smoke in the control room.
RHR is not in Shutdown cooling.
Initiating Cues
-31, (SHUTDOWN FROM OUTSIDE THE MAIN CONTROL ROOM) Sections 1.1.4
-1.1.6.
RJPM-NRC-S16-P3 Rev 2 River Bend Station Initial License Exam Page 1 of 10 Place Inverter ENB
-INV01B in Service CRITICAL TIME FRAME:
Required Time (min):
NA Actual Time (min):
NA VALIDATION TIME: Average Time (min):
20 Actual Time (min):
LICENSE LEVEL: SRO / RO ALTERNATE PATH: NO EVALUATION METHOD
- EVALUATION LOCATION
- Perform X Plant X Simulate Simulator Control Room Prepared: Dave Bergstrom Date: September 11, 2013 Reviewed: A. Willson Date: July 21, 2016
(Operations Representative)
Approved: John Fralick Date: August 5, 2016 (Facility Reviewer)
RJPM-NRC-S16-P3 Rev. 2 RJPM-NRC-S16-P3 Rev 2 Page 2 of 10 EXAMINER INFO SHEET Task Standard
- ENB-INV01B is started with all critical steps completed satisfactory
. Synopsis: This task will have the applicant start an ENB inverter.
- 1) Read to the operator
- "I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow
-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.
Inform me when you have completed the task.
" NOTE: If in the Plant or the Control Room , Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.
- 2) Initial Conditions
- The plant is shut down. Inverter ENB
-INV01B has just been placed in bypass in accordance with section 4.5 of SOP
-48, 120VAC System.
- 3) Initiating Cues
- The CRS directs you to start up inverter ENB
-INV01B in accordance with SOP
-48, 120VAC System, Step 4.3 for post maintenance testing.
- 4) Solicit and answer any questions the operator may have
.
RJPM-NRC-S16-P3 Rev. 2 RJPM-NRC-S16-P3 Rev 2 Page 3 of 10 DATA SHEET TASK Title
- Task Number K&A SYSTEM
- K&A RATING
- Place Inverter ENB
-INV01 B in Service. 278014001004 262002 A4.01 2.8 /
3.1 REFERENCES
- APPLICABLE OBJECTIVES S OP-00 48, Rev 3 27 RLP-S TM-0 121, Obj 2 REQUIRED MATERIALS
- SAFETY FUNCTION:
SOP-0048, Rev 323, Section 4.3
__6__ LICENSE LEVEL: SRO / RO ALTERNATE PATH: NO LOCATION: Plant outside RCA ORIGIN (Previous 2 exams): Modified Bank: RJ PM-AUD-D14-P3 EMERGENCY: YES ENGINEERED SAFETY FEATURE: NO LOW POWER: YES SIMULATOR CONDITIONS & SETUP
- 1. NA - This is an In Plant JPM.
CRITICAL ELEMENTS:
Items marked with an "
- " are Critical Steps and are required to be performed.
Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.
TASK STANDARD: ENB-INV01B is started with all critical steps completed satisfactory.
RJPM-NRC-S16-P3 Rev. 2 RJPM-NRC-S16-P3 Rev 2 Page 4 of 10 PERFORMANCE
- START TIME:
SOP-0048, 120 VAC SYSTEM
4.3 Startup
of ENB
-INV01A(B) Inverter Side with the Inverter Operating in Maintenance Bypass for Testing PROCEDURE NOTE This Section is used to start up the inverter section of the inverter with the bypass section supplying the inverter output. Section 5.6 is used to start ENB-INV01A(B) and transfer from ENB
-INV01A1(B1).
- 1. Procedure Step:
4.3.1. Verify
ENB
-INV01A(B) is in Maintenance Bypass per Section 4.5 or 6.2. Standard NA - Applicant verified by way of initial conditions Cue NA Notes Results SAT UNSAT 2. Procedure Step:
4.3.2. On ENB-INV01A1(B1), verify BATTERY INPUT breaker is in OFF.
Standard Applicant located/identified and verified the ENB INV01B1 battery input breaker is OFF.
Cue After the applicant identifies the correct battery input breaker, indicate to the applicant that the breaker is in down position. Notes Results SAT UNSAT RJPM-NRC-S16-P3 Rev. 2 RJPM-NRC-S16-P3 Rev 2 Page 5 of 10 3. Procedure Step:
4.3.3. At VBS-TRS02A(B) verify the following:
- 1. ALTERNATE 120VAC SOURCE FROM ENB
-INV01A1(B1), is locked open with the Kirk Key removed
. 2. ALTERNATE 120VAC SOURCE FROM ENB
-INV01A(B), is locked open with the Kirk Key removed.
Standard Applicant located/identified VBS
-TRS02B and verified the two alternate sources are locked open and the Kirk Key removed.
Cue After the applicant identifies VBS-TRS02B Alternate Sources, indicate to the applicant that the metal rod is over the breaker hand switch, breaker hands switch is down, and there is nothing in the key hole
. (Should be as indicated).
Notes Results SAT UNSAT 4. Procedure Step: 4.3.4. At ENB-SWG01A(B), verify ACB 564(584), ENB INV01A(B) VITAL BUS A(B) INVERTER is racked in and closed.
Standard Applicant located/identified ENB
-INV01B and verified ACB 584 is racked in and closed.
Cue After the applicant identifies the correct breaker, indicate to the applicant that the breaker handle is up and red (CLOSED) flag present
. (Should be as indicated).
Notes Results SAT UNSAT RJPM-NRC-S16-P3 Rev. 2 RJPM-NRC-S16-P3 Rev 2 Page 6 of 10 5. Procedure Step:
4.3.5. Verify
EHS
-MCC8A(B)/BKR 3AB(3AB), ENB
-INV01A(B) 480 VAC NORMAL ENB INV01A(B) VITAL BUS INVERTER is closed.
Standard Applicant located/identified Breaker 3AB on MCC8B and verified the breaker is closed.
Cue After the applicant identifies the correct breaker, indicate to the applicant that the breaker handle is in the left position
. (Should be as indicated).
Notes Results SAT UNSAT 6.
- Procedure Step:
4.3.6. On ENB-INV01A(B), open the DC INPUT to AN1 AND AN2 breaker.
Standard Applicant located/identified the breaker for AN1 and AN2 on ENB
-INV01B and simulated opening the breaker.
Cue After the applicant identifies and simulates opening the correct breaker, indicate to the applicant that the breaker handle is down position. (Should be as indicated). Also heard a loud "clunk" when breaker was opened
. Notes Results SAT UNSAT NOTE While warming up, ENB
-INV01A(B) can take approximately 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to reach 118.5 to 123.8 VAC as indicated on V1, Voltage Output located on the front of the static switch. Per Inverter Vendor, maximum time to warm up an inverter is 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. The PRECHARGE light will go out after 5 to 10 seconds. If the light goes out before closing the BATTERY INPUT breaker, the PRECHARGE button can be depressed again.
RJPM-NRC-S16-P3 Rev. 2 RJPM-NRC-S16-P3 Rev 2 Page 7 of 10 7.
- Procedure Step:
4.3.7. On ENB-INV01A(B), depress AND hold the PRECHARGE pushbutton until the PRECHARGE light is lit.
Standard Applicant located/identified and simulated depressing and holding the PRECHARGE pushbutton.
{cue} After the cue, the applicant released the pushbutton.
Cue After the applicant depresses the pushbutton wait three seconds and inform applicant that the ORANGE light is lit.
Notes Results SAT UNSAT 8.
- Procedure Step:
4.3.8. On ENB-INV01A(B), before the PRECHARGE light goes out, close the BATTERY INPUT breaker.
Standard Applicant simulated closing the BATTERY INPUT breaker.
Cue When breaker is closed, simulate "clunk" from breaker operation and handle is in up position. Notes Results SAT UNSAT 9. Procedure Step:
4.3.9. On ENB-INV01A(B) INVERTER OUTPUT meter, observe that the inverter begins generating voltage.
Standard Applicant located/identified INVERTER OUTPUT meter on ENB
-INV01B and simulated verified voltage rising.
Cue After the applicant identifies the correct meter, indicate to the applicant that voltage is rising and then stabilizes at 120V (use a pen/pointer to show the needle is moving).
Notes Do not indicate voltage going past 120 V.
Results SAT UNSAT RJPM-NRC-S16-P3 Rev. 2 RJPM-NRC-S16-P3 Rev 2 Page 8 of 10 10.
- Procedure Step:
4.3.1 0 WHEN the voltage has stabilized, THEN on ENB-INV01A(B) close the AC INPUT TO RECTIFIER breaker.
Standard Applicant simulates closing the AC INPUT TO RECTIFIER breaker
. Cue Indicate to the applicant that voltage is stabilizes at 120V.
(use a pen/pointer to show the needle steady)
After the applicant identifies and simulates closing the correct breaker, indicate to the applicant that the breaker handle is in up position. And clunk sound when the beaker is closed. Red light on, Green light is off.
Notes Results SAT UNSAT Terminating Cue:
ENB-INV01B is started with all critical steps completed satisfactory.
This completes this JPM.
STOP TIME:
CRITERIA FOR SATISFACTORY EVALUATION
- 1. 100% of critical elements/steps identified in the JPM successfully completed.
- 2. Critical Time Frame is met if applicable
. 3. No actual safety violation (radiological or industrial) requiring evaluator intervention.
CRITERIA FOR UNSAT EVALUATION
- 1. Any critical element/step is graded as "UNSAT" 2. Critical Time Frame is not met if applicable. *
- 3. Actual safety violation (radiological or industrial) requiring evaluator intervention.
- 4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant
RJPM-NRC-S16-P3 Rev. 2 RJPM-NRC-S16-P3 Rev 2 Page 9 of 10 VERIFICATION OF COMPLETION Operator:
License (Circle one):
Follow-up Questions:
Follow-up Question Response:
Time to complete JPM:
minutes Comments / Feedback:
RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments. Evaluator's Signature:
Date:
RJPM-NRC-S16-P3 Rev 2 River Bend Station Initial License Exam OPERATOR CUE SHEET Initial Conditions
- The plant is shut down. Inverter ENB
-INV01B has just been placed in bypass in accordance with section 4.5 of SOP
-48, 120VAC System.
Initiating Cues
- The CRS directs you to start up inverter ENB
-INV01B in accordance with SOP
-48, 120VAC System, Step 4.3 for post maintenance testing.
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 1 Page 1 of 7 Facility:
River Bend Nuclear Station Scenario No.:
1 Op-Test No.: NRC LOT 201 6 Examiners: ____________________________ Operators:
_____________________________
____________________________
_____________________________
____________________________
_____________________________
Initial Conditions:
Operating at 100% power.
Inoperable Equipment:
None Turnover:
Severe Thunderstorm warning in effect for West Feliciana in effect.
All required actions per AOP
-29 (Severe Weather Operation) are complete.
Scenario Notes:
This scenario is a NEW Scenario.
Validation Time: 60 minutes
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 1 Page 2 of 7 Event No. Malf. No. Event Type f Event Description 1 HPCS004 C (BOP) TS (CRS) AOP HPCS Inadvertent Initiation. AOP 6, Condensate/Feedwater Failures. TS 3.5.1 2 MGEN005 A C (BOP) Isophase Bus Duct Cooling Fan Trips. SOP 67, Isolated Phase Bus Duct Cooling System. ARP P870 B-1 3 p808_86a:h_1 DI_EXS-VRAA C (ATC) AOP Degraded Grid. Adjust MVARs per AOP 64, Degraded Grid.
ARP 680-P808-86-H-1. 4 AO_FWS-A03-M P680_3a:c_1 C (ATC) AOP FWS Pump A motor failure (amps increasing/secure pump).
AOP 6, Condensate/Feedwater Failures. AOP 24, Thermal Hydraulics Stability Controls. ARP P680 C-1. 5 p 680_6a:a_8 p680_5a:b_10 RPS005D TS (CRS) SDV level instrument fails high 1 of 4 instruments. TS 3.3.1.1.
ARP P680-5-B-10, P680-5-A-10, P680-6-A-8 6 ED002B M (CREW) NPS-B Fault/Trip. Complete loss of feedwater.
EOP 1 7 RCIC001 E51MOVF045P C (BOP) RCIC trips due to malfunction. Restore HPCS.
EOP-2, EOP-3 8 WCS006 M (CREW) RWCU line break in the steam tunnel 100 gpm ramp for 3 minutes after mode switch taken to shutdown.
EOP-2, EOP 3 9 WCS004 WCS005 C (ATC) G33-MOV-1 and G33-MOV-4 fail to auto close. AOP 3 f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec Quantitative Attributes Table Normal Events 0 E O P Contingency Procedures Used 1 Total Malfunctions 9 Simulator Run Time 60 Malfunctions After EOP Entry 2 EOP Run Time 30 A OP Events 3 Critical Tasks 2 Major Transients 2 Reactivity Manipulations 0 E O Ps Used (Requiring measurable action) 3 Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 1 Page 3 of 7 SCENARIO ACTIVITIES:
HPCS Inadvertent Initiation
- A. After turnover and at the direction of the lead evaluator trigger Event 1. B. The BOP will override HPCS off. This will prevent further automatic initiation.
Isophase Bus Duct Cooling Fan Trips:
A. The BOP will restart Isophase Bus Duct Cooling Fan per SOP 67, Isolated Phase Bus Duct Cooling System and ARP P870-54-B-1. Degraded Grid: A. CRS will enter AOP 64 and dispatcher will notify control room to adjust MVARs.
B. MVARs will initially be 250 MVARs. ATC adjust s MVARs to 200 MVARs per AOP 64, Degraded Grid and ARP 680
-P808-86-H-1. FWS Pump A Motor Failure:
A. The ATC will recognize the increasing FW motor amps and secure the FWS Pump A per AOP 6 (Condensate/Feedwater Failures), AOP 24 (Thermal Hydraulics Stability Controls), ARP P808-86-H-1, and ARP P680-3-C-1. SDV level instrument fails high:
A. 1 of 4 SDV level instruments fails high. CRS enters TS 3.3.1.1.
NPS-B Fault/Trip, Complete loss of feedwater
,: A. Crew will manually scram the reactor due to the complete loss of feedwater. The automatic RPS scram will occur at 9.7" reactor water level if manual action is not taken first.
RCIC malfunction A. Crew will recognize RCIC malfunction and restore HPCS injection to maintain reactor water level in expanded level band.
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 1 Page 4 of 7 RWCU line break in the steam tunnel:
A. 5 minutes after automatic or manual scram, Event 7 will automatically trigger.
B. Indications of high temperatures in the steam tunnel will cause isolation signals. G33-MOV-1 and G33-MOV-4 will fail to auto close
. C. Crew will shut the failed isolation valves.
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 1 Page 5 of 7 Critical Task Number Description Basis 1 Per EOP-3, close one RWCU isolation valve (G33
-MOV-1 OR G33-MOV-4) after failure to close on group 15 isolation before completion of step 5.9 of AOP
-3 (EOP-3, SC-4) Per EOP basis, An area temperature above its maximum normal operating level is an indication that steam from a primary system may be discharging into the secondary containment. As temperatures continue to increase, the continued operability of equipment needed to carry out EOP actions may be compromised. High area temperatures also present a danger to personnel, a consideration of significance since access to the secondary containment may be required by actions specified in the EOPs. (EPSTG*0002, B 3) 2 Restore HPCS injection prior to Emergency Depressurization (EOP
-1, ALC-8). Per EOP basis, Submergence is the preferred method for cooling the core. The core is adequately cooled by submergence when it can be determined that RPV water level is at or above the top of the active fuel. All fuel nodes are then assumed to be covered with water and heat is removed by boiling heat transfer. (EPSTG*0002, B 1)
- Critical Task (As defined in NUREG 1021 Appendix D)
- Per NUREG-1021, Appendix D, If an operator or the crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a CT identified in the post
-scenario review.
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 1 Page 6 of 7 Simulator Notes:
Prior to scenario, ensure GML Fan 1 is running Note: for event 4, get to 360 amps quicker and then ramp to 440 amps slower.
Event 30 deletes amps when FWS pump is tripped.
Event 8, RCIC trips when >90% speed
. Event 29/30 deletes the leak and valve failure when valve switches are closed.
For the isophase fan trouble ARP states, "Check computer alarm typer Points GMLFC01 and GMLFC02 to determine which device is causing alarm." May need to provide screen shot to provide proper indications.
Graphic s for the SPI
-REC102 to indicate values consistent with grid.
Screen Shot for C11NC036 needs to indicate one trip unit in TRIP.
When restoring HPCS during leak, if asked to fill and vent system, expedite the process.
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 1 Page 7 of 7 SIMULATOR SET UP:
SCHEDULE FILE PICTURE DIRECTOR FILE PICTURE Provide the following:
Turnover briefing sheets and reactivity management briefing materials.
Marked up copy of AOP
-29, Severe Weather
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 1 of 1 9 Event No:
1 Event
Description:
HPCS Inadvertent Initiation After turnover and at the direction of the lead evaluator trigger Event 1.
NOTE: It is not necessary to secure the Division 3 Diesel Generator after initiation.
TIME Position Applicant's Actions or Behavior BOP o Diagnose and report HPCS initiation per:
o H13-P601/16A/A04, HPCS INITIATION LOW RX WATER LEVEL 2. o H13-P601/16A/C 02, DIV III D/G ENGINE RUNNING
. o H13-P808 / 86A / E04 , NNS-SWG1A OR 1B FAST TRANSFER BLOCKED o Dispatch SNEO to monitor running Division 3 Diesel Generator.
o Request I&C investigate HPCS inadvertent initiation.
Booth o When back panel (or I&C) requested to investigate inadvertent initiation of HPCS, (wait 5 minutes
) and report B21
-LISN673R and B21-LISN673C both failed downscale.
o Acknowledge as SNEO to monitor running Division 3 Diesel Generator.
o Acknowledge as work control for FIN team to investigate and develop troubleshooting plan IAW EN
-MA-125. BOP o Diagnose and report instrument failure per H13-P601/16A/A04, HPCS INITIATION LOW RX WATER LEVEL 2.
o Verify by two independent means the HPCS initiation was inadvertent. Then place HPCS in standby per OSP
-53, Attachment 5 Terminating and Preventing Injection from HPCS (HARDCARD):
o Verify the E22-F004, HPCS INJECT ISOL VALVE (closed) amber override light is lit.
o Stop the HPCS pump. (Trip E22-ACB02, HPCS PUMP SUPPLY BRKR.)
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 2 of 1 9 CRS o Recognize and direct BOP to restore HPCS to standby per SOP
-0030, HIGH PRESSURE CORE SPRAY SYSTEM.
o Recognize and enter Tech Spec 3.5.1 ECCS -Operating: B. High Pressure Core Spray (HPCS) System inoperable.
B.1 Verify by administrative means RCIC System is OPERABLE when RCIC is required to be OPERABLE. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> completion time.
AND B.2 Restore HPCS System to OPERABLE status. 14 days completion time. o Recognize and enter Tech Spec 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation Table 3.3.5.1
-1 3. High Pressure Core Spray System
-Low Low, Level 2
- 4 required channels per function. Conditions referenced from required action A.1: B. B. As required by Required Action A.1 and referenced in Table 3.3.5.1
-1. B.1 Declare supported feature inoperable when its redundant feature ECCS initiation capability is inoperable. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of initiation capability for feature in both divisions.
AND B.2 Declare HPCS system inoperable. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of HPCS initiation capability.
AND B.3 Place channel in trip. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> completion time.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 3 of 1 9 Event No:
2 Event
Description:
Isophase Bus Duct Cooling Fan 1 Trips At the direction of the lead evaluator trigger Event 2. TIME Position Applicant's Actions or Behavior
BOP o Diagnose and report isophase bus duct cooling fan 1 trips. References H13-P870/54A/B01 , ISOL PHASE BUS DUCT COOLING SYS FAILURE alarm. o Per ARP H13-P870/54A/B01 , check computer alarm typer Points GMLFC01 and GMLFC02 to determine which device is causing alarm.
ROLE PLAY: Use screen shot s for GML Fan Two screen shots are available:
(1) for after trip of fan 1, but before start of stby fan (fan 2)
(2) for after the start of the standby fan o Per ARP H13-P870/54A/B01 , if needed, swap to the standby fan per SOP-0067, Isolated Phase Bus Duct Cooling System.
o Start Isophase Bus Duct Cooling Fan per SOP 67, Isolated Phase Bus Duct Cooling System, section 5.1.1:
In the Main Control Room on H13
-P870, start the alternate GML fan by depressing GML
-FN 1 DUCT FAN 2, START Pushbutton.
CRS o Recognize and direct BOP to start Isophase Bus Duct Cooling Fan per SOP 67, Isolated Phase Bus Duct Cooling System, section 5.1.1
. Booth o When SNEO dispatched, wait 3 minutes and report no obvious indications of why Fan 1 tripped. Fan 2 post start checks are completed satisfactory.
o When Work Control dispatched, wait 3 minutes and report no obvious indications of why Fan 1 tripped. Troubleshooting will continue once EN-MA-125 troubleshooting plan is approved.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 4 of 1 9 Event No:
3 Event
Description:
Degraded Grid At the direction of the lead evaluator trigger Event 3. TIME Position Applicant's Actions or Behavior BOP o Recognize and report degraded grid per ARP P808-86-H-1, GRID TROUBLE alarm.
Role Play o If indications of meter SPI--REC102 are requested/viewed , Two screen shots are available:
point 03 is for grid voltage ( reading 232.455 KV )
point 04 is for grid frequency ( reading 60.07 HZ )
ATC o Diagnose and report high MVARs per AOP 64, step 5.3
( normal band = 0 and +230 MVARS
). o MVARs will raise to approximately 270 MVARs as a result of the grid transient.
CRS o Recognize and enter AOP 64 , DEGRADED GRID
. o Contact SOC to determine cause of grid transient and desired actions. Recommend lowering MVARS.
o Direct ATC to lower Generator MVARS between 0 to +230 MVARS.
Booth o SOC should ask for recommendation to correct plant conditions. When CRS recommends reducing MVARs, the SOC will concur with plan to reduce MVARs (0 to +230 MVARS)
. o Once MVARs are reduced, if requested
, SOC will report correct response.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 5 of 1 9 ATC Adjusting Generator VARS with the Voltage Regulator in Auto per SOP-80, Section 5.9
- o Verify the VOLTAGE REGULATOR MODE SELECT Switch in AUTO.
o Adjust Generator VARS to the desired output per Attachment 9, MVAR vs. MW Limits or as directed by this procedure or the Load Dispatcher by performing the following:
o IF VARS are high, THEN to lower VARS on the VOLTAGE REGULATOR AUTO ADJUST depress momentarily the LOWER Pushbutton, while monitoring VARS output on VAR
-1SPGN05, GENERATOR VARS.
o Continue to perform previous step until the desired (0 to +23 0) VARS reading is indicated on VAR
-1SPGN05, GENERATOR VARS.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 6 of 1 9 Event No:
4 Event
Description:
FWS Pump A Motor Failure At the direction of the lead evaluator trigger Event 4. Note: Once trigger is fired, the first alarm comes in at 2 minutes.
TIME Position Applicant's Actions or Behavior
ATC o Diagnose and report rising FWS
-P1A Motor amps using ARP P680-3-C-1, RX FWP 1A SUPPLY BRKR PRE
-TRIP OL. o Observe increasing motor amps using 1A RX FWP MOTOR AMPS, P680-3 (Second row, first small squint meter).
o Dispatch SNEO to investigate abnormal 1A Reactor Feed water pump indications.
o Observe Recirculation FCV runback when feed pump trips.
Booth o When SNEO dispatched to investigate abnormal 1A Reactor Feed water pump indications, wait 3 minutes and report the motor is hot to touch and no other abnormal indications.
CRS o Recognize and enter AOP 6 (Condensate/Feedwater Failures) and AOP 24 (Thermal Hydraulics Stability Controls)
. o Direct ATC to reduce power to 85% using FCVs.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 7 of 1 9 ATC Reduce reactor power to 85% using recirculation FCVs per SOP
-3, Section 5.9 Maintaining Reactor Power with Reactor Recirculation Flow: o Determine which B33
-K603A(B), RECIRC LOOP A(B) FLOW CONTROL is to be adjusted by observing Loop Flows on B33
-R612A and B 33-R612B. Both loops may have to be adjusted to obtain the desired Reactor Power while maintaining Loop Flow mismatch within specification.
o Lower Reactor Recirculation Flow by toggling momentarily B33 K603A(B) controller in the closed direction using the slow detent while observing a servo error deviation in the negative direction.
o Observe B33
-HYVF060A(B), FLOW CONTROL VALVE position, generator load, MWt, APRMs and loop flows for expected changes.
CRS o Once power is reduced to 85%, direct ATC to secure FWS-P1A , Feedwater Pump A per SOP
-9, Section 6.1 Reactor Feed Pump Shutdown. ATC o Secure FWS-P1A, Feedwater Pump A per SOP
-9, Section 6.1 Reactor Feed Pump Shutdown:
o 6.1.5 IF the capability of meeting feed flow requirements with the remaining Feedwater Pumps is uncertain, THEN make a determination as follows:
o Close FWS MOV26A, RX FWP 1A DISCH VLV for the pump being shutdown o Verify the minimum flow valve for the pump being secured is open.
o Monitor Feed Flow/Steam Flow mismatch and RPV Level to insure remaining pump(s) can maintain level.
o 6.1.7 Stop FWS P1A, RX FWP P1A
. o 6.1.8 Verify CNM H/A68A, RX FWP 1A MIN FLOW FLOW CONTROLLER is in AUTO for the Reactor Feed Pump that was secured.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 8 of 1 9 Event No:
5 Event
Description:
SDV level instrument fails high At the direction of the lead evaluator trigger Event 5. NOTE: This is for CRS Tech spec call only. Do not wait for crew actions to bypass SDV level instrument. Keylock bypass switches do not work in Mode 1.
TIME Position Applicant's Actions or Behavior ATC o Recognize and report division 2 half scram using:
o H13-P680/05A/A10 RPS TRIP LOGIC B OR D ACTIVATED o H13-P680/05A/B10 RPS SYSTEM B OR D INOPERATIVE o H13-P680/06A/A08 CRD SCRAM DISCH VOL HIGH WATER LEVEL o Division 2 RPS white lights are out (under full core display on P680). BOP o Dispatch I&C to investigate half scram.
o Requests back panel indications (booth) for failed SDV level instrumentation.
Booth o Backpanel indications have C11
-LIS N601 B offscale high and the other three are reading 0.
o When I&C dispatched to investigate Division 2 half scram, wait 5 minutes and report failed SDV level instrument high.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 9 of 1 9 CRS o Recognize 1 of 4 SDV level instruments fails high.
o Recognizes and enters Tech Spec 3.3.1.1 Reactor Protection System (RPS) Instrumentation Table 3.3.1.1
-1, 8. Scram Discharge Volume Water Level High a. Transmitter/Trip Unit
- 2 required channels per trip system. Conditions referenced from required action D.1: H A. One or more required channels inoperable.
A.1 Place channel in trip. Completion time 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
OR A.2 Place associated trip system in trip. Completion time 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 10 of 1 9 Event No:
6 Event
Description:
NPS-B Fault/Trip, Complete loss of feedwater At the direction of the lead evaluator trigger Event 6. TIME Position Applicant's Actions or Behavior ATC o Recognize and report loss of NPS
-B trip and complete loss of feedwater.
o Per AOP-0006, place C71A S1, REACTOR SYSTEM MODE SWITCH, to SHUTDOWN.
- Automatic scram on reactor water level 3 (9.7 inches) will occur in about 10 seconds.
CRS o Enter the following abnormal and emergency procedures:
o AOP-1, REACTOR SCRAM o AOP-6, CONDENSATE/FEEDWATER FAILURES o EOP-1, RPV CONTROL o Direct manual reactor scram due to complete loss of feedwater.
ATC o SCRAM Report o Mode switch is in shutdown.
o All rods are in.
o EOP 1 (RPV CONTROL) Entry Conditions:
o Level 3 o High reactor pressure
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 11 of 1 9 Event No:
7 Event
Description:
RCIC malfunction E51-F045 will automatically (Event 7) fail closed.
E51-F063 and F064 will isolate on high Main Steam Tunnel temperature due to RWCU leak in steam tunnel.
TIME Position Applicant's Actions or Behavior
BOP o Recognize the complete loss of feedwater and initiate RCIC in anticipation of and in an attempt to avoid a Level 2 initiation signal.
o Diagnose and report failure of RCIC to start. E51
-F045 fails to open.
o Dispatch SNEO to investigate and manually open E51-F045. Booth o When SNEO dispatched to investigate and manually open E51
-F045, wait 5 minutes and report valve is stuck.
CRS o Recognize and direct BOP to restore HPCS.
o Per EOP-1, direct BOP to maintain reactor water level
-20 to 51 inches wide range.
o Per EOP-1, direct ATC to maintain reactor pressure 500
-1090 psig using bypass and drain valves.
o Direct ATC to install enclosure 12, 16, 20, and 24.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 12 of 1 9 BOP o Restore HPCS per OSP
-53, Attachment 4, INITIATING HPCS:
o Verify Annunciator P601
-16A-G04, HPCS INJECTION LINE PRESSURE LOW, is not lit.
o Arm and depress HPCS MANUAL INITIATION Pushbutton.
o Verify HPCS PUMP running.
o Verify E22
-F004, HPCS INJECT ISOL VALVE, Opens.
o Verify HPCS injection flow.
o Verify E 22-F012, HPCS MIN FLOW VALVE TO SUPPRESSION POOL, Closes. o Per EOP-1, maintain reactor water level
-20 to 51 inches wide range.
Critical Task: Restore HPCS injection prior to Emergency Depressurization.
ATC o Per EOP-1, maintain reactor pressure 500
-1090 psig using bypass and drain valves.
o Install enclosure 16 and 24.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 13 of 1 9 CRS o Recognize and direct ATC to verify level 3 and level 2 isolations and initiations.
o Recognize and enter EOP
-0002, Primary Containment Control:
o Drywell Temperature o Suppression Pool Level o Containment Pressure ATC o Verify level 3 and level 2 reactor water level initiations and isolations.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 14 of 1 9 Event No:
8 Event
Description:
RWCU line break in the steam tunnel 5 minutes after the reactor scram (AUTOMATIC) or at the direction of the lead evaluator (MANUAL), trigger Event 8
. NOTE: SP suction swap will occur with rising SP level. SP level steadies out at approximately 20 feet 3 inches. Main Steam Line Tunnel Temperatures Max Safe 200F Isolation 173F Max Normal 144F TIME Position Applicant's Actions or Behavior ATC o Diagnose and report leak in the main steam tunnel using:
o P601-21-A-1, DIV I RCIC ISOL STM SPLY PRESS LOW o P601-21-A-6, RCIC ISOLATION MS TNL HI AMBIENT TEMP o P601-21-B-1, DIV II RCIC ISOL STM SPLY PRESS LOW o P601-21-A-3, RCIC PUMP DISCHARGE FLOW LOW o P601-21-B-3, RCIC TURBINE STEAM SPLY WATER DRAIN TRAP LVL HI CRS o Recognize and enter EOP-3, (SECONDARY CONTAINMENT AND RADIOACTIVITY RELEASE CONTROL) and EOP-2 (PRIMARY CONTAINMENT CONTROL)
. o Recognize and direct ATC to verify high steam tunnel temperature isolations per AOP
-3, Automatic Isolations.
o Directs BOP to install enclosure 20 for DW cooling.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 15 of 1 9 ATC o Per EOP-3, indications of high temperatures in the steam tunnel will cause isolation signals.
Main Steam Line Tunnel Temperature High: 173°F Group 2, 6, 7, 15, and 16 valves isolate.
o Verify Group 15 Valves closed per AOP
-3: o G33 F004 o G33 F054 o G33 F039 o G33 F034 o G33 F001 o G33 F053 o G33 F040 o G33 F028 o Recognize and report G33-MOV-1 and G33-MOV-4 fail ed to auto close. o Manually close failed isolation valves.
Critical Task: Close one RWCU isolation valve (G33
-MOV-1 OR G33-MOV-4) after failure to close on group 15 isolation before completion of step 5.9 of AOP
-3 Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 16 of 1 9 BOP Enclosure 20, DEFEATING DRYWELL COOLING ISOLATION INTERLOCKS o OBTAIN EOP-0005 ENCL 20 keys (2) o 3.2 VERIFY Normal Service Water pressure on SWP
-PI124, SVCE SPLY HDR PRESSURE (H13
-P870) OR Standby Service Water pressure on SWP
-PR50A(B), STBY CLG TOWER LVL & PUMP DISCH PRESS RECORDER (H13
-P870) as applicable is greater than Containment AND Drywell pressure on CMS
-PR2A(B), DRYWELL PRESSURE (H13 P808) o 3.3 PLACE Control Switches for all tripped Drywell Unit Coolers to OFF. (H13
-P863) o 3.4 PLACE the following keylock switches in the EMERGENCY position AND VERIFY the red lights illuminate.
Switch Name Panel No. o DW CLG ISOL INTLK BYP H13-P851 o DW CLG ISOL INTLK BYP H13-P852 NOTE DIV I AND II H2 Analyzers will no longer auto start.
o 3.5 START DIV I AND II H2 Analyzers. (H13
-P808) o 3.6 IF any drywell temperature on CMS-TR41A or B, DRYWELL ATMOS TEMP (H13
-P808) is or has been greater than 200 °F, THEN notify the CRS/OSM that this enclosure cannot be completed.
CAUTION Restoration of Service Water to Drywell unit coolers following isolation, if any drywell temperature on CMS-TR41A or B is or has been greater than 200 °F, can result in piping failure due to voiding and subsequent water hammer. Drywell UC Supply and Return Valves should NOT be reopened if any drywell temperature on CMS
-TR41A or B is or has been greater than 200 °F.
NOTE o Service Water should only be aligned and Drywell Unit Coolers started if a minimum of two (2) units can run. (Ref. CR
-RBS-2011-00346)
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 17 of 1 9 BOP o 3.7 IF a minimum of two (2) Drywell Unit Coolers can be started, THEN perform the following:
o OPEN the following valves: (H13
-P870) o SWP-MOV4A DRYWELL UC SUPPLY o SWP-MOV5A DRYWELL UC RETURN o SWP-MOV4B DRYWELL UC SUPPLY o SWP-MOV5B DRYWELL UC RETURN o VERIFY closed the following: (H13
-P877) o EJS-ACB25 NHS-MCC102A SPLY BRKR o EJS-ACB66 NHS-MCC102B SPLY BRKR o 3.8 IF a minimum of two (2) Drywell Unit Coolers can be started, THEN START Drywell Unit Coolers as directed by the CRS.
o 3.9 Monitor Stby Cooling Tower Level on SWP
-PR50A (B) (H13
-P870) at the frequencies shown on the Stby Cooling Tower Inventory Losses During Post DBA table.
o 3.10 IF Stby Cooling Tower Level lowers to below the minimum water level of the Stby Cooling Tower Inventory Losses During Post DBA table, THEN reclose the valves opened in Step 3.7 above.
o 3.11 IF Stby Cooling Tower inventory continues to lower below the minimum water level, THEN provide makeup water within 10 days per SOP-0042 or AOP
-0004.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Page 18 of 1 9 TERMINATION Once at least one RWCU isolation valve is shut and reactor water level is being controlled in band or as directed by Lead Evaluator:
Take the simulator to Freeze and turn horns off.
Stop and save the SBT report and any other recording devices.
Instruct the crew to not erase any markings or talk about the scenario until after follow
-up questions are asked.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 1 Offgoing OSM:
Oncoming OSM:
Off-Going Shift
_______________________
_____ ___________________
_____ (Print) KCN (Print) KCN N D Date PART I - TO BE REVIEWED PRIOR TO ASSUMING THE SHIFT UNIT STATUS MODE 1 RX POWER 100%
EVOLUTIONS (COMPLETED / IN PROGRESS / PLANNED); GENERAL INFORMATION Severe Thunderstorm warning in effect for West Feliciana in effect. All required actions per AOP-29 (Severe Weather Operation) are complete.
SIGNIFICANT LCO STATUS None EQUIPMENT STATUS None Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 2 Page 1 of 5 Facility:
River Bend Nuclear Station Scenario No.:
2 Op-Test No.: NRC LOT 201 6 Examiners: ____________________________ Operators:
_____________________________
____________________________
_____________________________
____________________________
_____________________________
Initial Conditions:
Operating at 100% power.
Inoperable Equipment:
None Turnover:
Restore 3-element control for feedwater. I&C has completed maintenance and retest.
Severe Thunderstorm warning in effect for West Feliciana in effect.
All required actions per AOP
-29 are complete.
Main Turbine experienced increased (approximately 1 mil higher than normal) turbine vibrations on previous shift.
Scenario Notes:
This scenario is a NEW Scenario.
Validation Time: 60 minutes
.
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 2 Page 2 of 5 Event No. Malf. No. Event Type f Event Description 1 N (ATC) Restore 3-element control per SOP
-9, Section 4.10 2 ED004J RCS015B C (ATC) TS (CRS) AOP R (ATC) NJS-J malfunction. MFP A trip. FCV runback. B FCV fails to runback. Recirculation flow mismatch. AOP 2 (MAIN TURBINE AND GENERATOR TRIPS) AOP 6 (Condensate /
Feedwater failures). TS 3.4.1 Reset FCV Runback IAW ARP. Increase flow to increase margin away from restricted region.
3 FWS012 DTM-AOV41A C (BOP) Loss of extraction steam. ARP 870 H09, AOP-7 4 MSS005 J C (BOP) TS (CRS) AOP SRV (47 C) stuck open.
AOP-35. TS 3.5.1 and 3.6.5.3 5 TMS003 M (CREW) Main Turbine Vibrations increase to manual scram level.
-53, AOP-2, EOP-1. 6 CRD014 M (CREW) Hydraulic ATWS 65%. EOP 1A (RPV Control, ATWS).
EOP 2 7 SLC002A/B C (BOP) SLC Pump Failure.
8 E12MOVF064AP E12MOVF064BP C (BOP) Failure of RHR A/B min flow valve to auto close. f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec Quantitative Attributes Table Normal Events 1 E OP Contingency Procedures Used 1 Total Malfunctions 8 Simulator Run Time 60 Malfunctions After EOP Entry 2 EOP Run Time 30 A OP Events 2 Critical Tasks 3 Major Transients 2 Reactivity Manipulations 1 E O Ps Used (Requiring measurable action) 2 Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 2 Page 3 of 5 SCENARIO ACTIVITIES:
Restore 3-element control A. After turnover the ATC will restore 3
-element control for feedwater control using SOP-9, Section 4.10.
NJS-J malfunction:
A. F W P A will trip. An automatic FCV runback will occur. The B FCV fails to runback.
A large Recirculation flow mismatch will result. B. The ATC will manually runback the B FCV to eliminate the flow mismatch per AOP 6 (Condensate / Feedwater failures)
. C. The CRS will enter TS 3.4.1. D. ATC will reset FCV Runback IAW ARP. Increase flow to increase margin away from restricted region. Loss of Extraction Team
-870-53-H09. The ARP operator actions include referencing AOP
-7, Loss of FW Heating. The drain will fail to automatically open and the BOP will manually open DTM-AOV41A, 1ST PT EXTRACTION LINE DRAIN CONTROL VLV
. SRV (47C) stuck open:
A. SRV (47C) will open. Per AOP-35, SRV Stuck Open, the valve will shut when the hand switch is manually taken to close.
Main Turbine Vibrations:
A. Vibrations continue to increase to 12 mils which require a manual scram and turbine trip per OSP
-53. ATWS: A. After the ATC manually scrams the reactor, a 65% Hydraulic ATWS will occur automatically. B. The crew will install EOP attachments and drive the control rods in.
SLC Pump Failure:
A. The first SLC pump started will have an automatic malfunction resulting in a failure to inject.
B. The second SLC pump will operate normally and inject boron as required.
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 2 Page 4 of 5 Failure of RHR A or B min flow valve to Auto Clos e: A. The crew will establish Suppression Pool Cooling per OSP 53, Attachment 12.
B. The min flow valve will fail to auto close when the test return valves are opened and require crew to manually close the minimum flow valve.
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 2 Page 5 of 5 Critical Task Number Description Bas i s 1 Per EOP-1A, RLA-13, terminate and prevent all injection sources except boron injection, CRD and RCIC prior to exceeding HCTL
. With RPV injection terminated, RPV level and reactor power decrease at the maximum possible rate allowed by boiloff. Failure to completely stop RPV injection flow (with the exception of CRD, RCIC, and boron injection) would delay the reduction in core inlet subcooling, thus increasing the potential for flux oscillations. (EPSTG*0002, B 37) 2 ***Per EOP-1A, RQA-4, inject SLC prior to suppression pool temperature reaching 110F. A scram failure event with reactor power above 5% coupled with an MSIV isolation, however, may result in rapid heatup of the suppression pool due to the steam discharged from the RPV via SRVs. The challenge to containment thus becomes the limiting factor which defines the second of the two possible conditions requiring initiation of boron injection.
If suppression pool temperature and RPV pressure cannot be maintained below the Heat Capacity Temperature Limit, emergency depressurization will be required. To avoid depressurizing the RPV with the reactor at power, it is desirable to shut down the reactor prior to reaching the Heat Capacity Temperature Limit. Suppression pool
temperature of 110ºF represents the minimum Boron Injection Initiation Temperature (BIIT).
The suppression pool temperature at which a reactor scram is required by plant Technical Specifications (110ºF).
River Bend Station uses the suppression pool temperature at which a reactor scram is required by plant Technical Specifications in place of a curve that is a function of reactor power for simplicity. (EPSTG*0002, B 59) 3 Per EOP-1A, RQA-2, commence driving control rods in prior to exiting EP
-1A. Positive confirmation that the reactor will remain shutdown under all conditions is best obtained by determining that no control rod is withdrawn beyond the Maximum Subcritical Banked Withdrawal Position (MSBWP). The MSBWP is the greatest banked rod position at which the reactor will remain shutdown under all conditions. For the current fuel design and core load, the MSBWP is all control rods fully inserted. (EPSTG*0002, B 2)
- Critical Task (As defined in NUREG 1021 Appendix D)
- Per NUREG-1021, Appendix D, If an operator or the crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a CT identified in the post
-scenario review.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 1 of 24 Event No:
1 Event
Description:
Restore 3-element control Normal evolution completed by ATC after turnover.
TIME Position Applicant's Actions or Behavior ATC Per SOP-9, Section 4.10 Single Element to Three Element Control Transfer: o Verify feedwater flow is greater than 10% or 1.31 x 10 6 lbm/hr. o Verify RPV level is stable and being controlled automatically by C33 R600, FW REG VALVES MASTER FLOW CONTROLLER.
o Place C33 R600, FW REG VALVES MASTER FLOW CONTROLLER in MANUAL.
o Depress 3 ELEM on the SINGLE ELEMENT THREE ELEMENT Select Switch. o Place C33 R600, FW REG VALVES MASTER FLOW CONTROLLER in AUTO as follows:
o Adjust tape set 2 inches above actual vessel level and observe the deviation signal is positive.
o Lower tape set 2 inches below actual vessel level and observe the deviation signal is negative.
o Match tape set to actual vessel level in order to null the deviation signal. o WHEN the level signal is nulled, THEN depress the AUTO Pushbutton and check green light above the pushbutton is on.
o Readjust C33 R600, FW REG VALVES MASTER FLOW CONTROLLER Tape Set to maintain the reactor level requested by the OSM/CRS.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 2 of 24 Event No:
2 Event
Description:
NJS-J malfunction At the direction of the lead evaluator
, trigger Event 2. TIME Position Applicant's Actions or Behavior BOP o Diagnose and report NJS
-J malfunction per:
o H13-P808 / 86A / B05 , NJS-LDC1A-M/U&V LOAD CENTER GROUND FAULT o H13-P808 / 86A / G05 , NJS-LDC1J BLOWN FUSE o H13-P808 / 86A / G07 , NJS-LDC1J OR 1K UNDERVOLTAGE (RED) o H13-P808 / 86A / H04 , NJS-LDC DIST BRKRS AUTO TRIP o Dispatch SNEO and electrical maintenance to investigate loss of NJS
-J. Booth o When SNEO dispatched to investigate loss of NJS
-J, wait 3 minutes and report 86 device (overcurrent) is actuated on feeder breaker.
o When electrical dispatched to investigate loss of NJS
-J, wait 10 minutes and report 86 device (overcurrent) is actuated on feeder breaker and tagout is being written to complete troubleshooting per EN-MA-125. o When directed to investigate Alarm on GML Panel 101 (p680-15-A6), report alarm GML
-PNL101/2-A04, DIFF'L SEAL OIL PRESS LOW is in Alarm; operator actions have been taken and all oil pressures are normal. Alarm is a due to loss of power.
- ATC o Diagnose and report feedwater pump A trip and B Recirculation FCV fails to runback per:
o H13-P680 / 03A / A01 , RX FW PUMP BREAKERS AUTO TRIP o H13-P680 / 03A / D01 , RX FWP 1A DC OIL PUMPS RUNNING o H13-P680/04A/A03 , FCV A RUNBACK RFP TRIP o H13-P680/04A/A09, FCV B RUNBACK RFP TRIP
- NOT LIT o Loop A/B Flow (C51-R614 Red A/ Blue B, Bottom right on vertical section Insert 4) has a large mismatch.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 3 of 24 CRS o Recognize and enter the following AOPs:
o AOP 6, Condensate / Feedwater failures o AOP 24, THERMAL HYDRAULIC STABILITY CONTROLS o Direct ATC to balance recirculation loop flows due to failure of B Recirculation FCV.
o The CRS will enter TS 3.4.1.
3.4.1 Recirculation
Loops Operating
A. Recirculation loop jet pump flow mismatch not within limits.
A.1 Shutdown one recirculation loop. Completion 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
ATC o Runback B Recirculation FCV per H13-P680/04A/A09 , FCV B RUNBACK RFP TRIP
Verify both Reactor Recirc flow control valves close to approximately 60% drive flow position: (Operator manually run s back B Recirc FCV until flow mismatch is less than 10%.)
o Lower Reactor Recirculation Flow by toggling momentarily B33 K603B controller in the closed direction using the slow detent while observing for a servo error deviation in the negative direction.
o Observe B33
-HYVF060AB, FLOW CONTROL VALVE position, generator load, MWt, APRMs and loop flows for expected changes. Booth o When RE is contacted about monitor region entry, request crew raise power using Recirc flow control valves to approximately 51.8 Mlbm/hr. o Role Play as RE with the printed RMP
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 4 of 24 CRS o Direct ATC to reset FCV runback per ARP H13-P680/04A/A03 , FCV A RUNBACK RFP TRIP
- o Direct ATC to raise power 2% using Recirc flow control valves to approximately 47.9 Mlbm/hr.
ATC Reset FCV runback per ARP H13-P680/04A/A03 , FCV A RUNBACK RFP TRIP: o Adjust B33
-K603A, RECIRC LOOP A FLOW CONTROL station to obtain zero % LIMITER ERROR.
o Adjust B33
-K603B, RECIRC LOOP B FLOW CONTROL station to obtain zero % LIMITER ERROR.
o Perform the following to reset the cavitation interlock:
o Depress the CAVITAITION INTLK RECIRC PMP A RESET pushbutton and verify alarm H13
-P680/04A/A03, FCV A RUNBACK RFP TRIP resets. o Depress the CAVITAITION INTLK RECIRC PMP B RESET pushbutton and verify alarm H13
-P680/04A/A09, FCV B RUNBACK RFP TRIP resets. o IF the alarms do not reset, THEN re-perform steps 2.a
- c, as needed, to reset the runback alarm(s).
Raise Power as follows:
o Raise Reactor Recirculation Flow by toggling momentarily B33 K603B controller in the open direction using the slow detent while observing for a servo error deviation in the positive direction.
o Observe B33
-HYVF060AB, FLOW CONTROL VALVE position, generator load, MWt, APRMs and loop flows for expected changes.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 5 of 24 Event No:
3 Event
Description:
Loss of Extraction Steam At the direction of the lead evaluator, Trigger Event
- 3. Note: Crew may review actions per SOP
-10, but no actions required at this time.
TIME Position Applicant's Actions or Behavior
BOP o Recognize and report FEEDWATER & POINT HEATERS EXTREME HIGH LVL alarm (870 H09). Reference ARP
-870-53-H09. o Diagnose the 1 st Pt Htr E1A is the feedwater heater with the extreme high l e v e l. o Per ARP-870-53-H09, verify auto close ESS-MOV-3A, HP TURB EXT STM TO 1ST PT WTR E1A ISOL VLV and MANUALLY OPEN DTM-AOV41A, 1ST PT EXTRACTION LINE DRAIN CONTROL VLV.
-0007, Loss of Feedwater Heating.
Booth o When WMC requested, after 5 minute delay, report First Point A Heater level instrument seems to be broken and will need further troubleshooting.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 6 of 24 Event No:
4 Event
Description:
SRV (47C) stuck open At the direction of the lead evaluator, trigger event
-F047C is stuck open, which is not a low-low set valve open per ARP:
o H13-P601/19A/A09 , MAIN STEAM SAFETY RELIEF VALVE OPEN o H13-P601/19A/B09 , ADS/SRV VALVE LEAKING CRS o Recognize and enter AOP
-35, SAFETY RELIEF VALVE STUCK OPEN. o Direct per AOP
-35, 5.5.51 At H13-P601, take the control switch to OFF. o Recognize and enter Tech Spec 3.5.1, EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM; ECCS
- Operating Condition E, One ADS Valve inoperable.
Restore ADS valve to OPERABLE status 14 days.
o Recognize and enter Tech Spec 3.6.5.3 Drywell Isolation Valves
Condition A, One or more penetration flow paths with one drywell isolation valve inoperable.
A.1 Isolate the affected penetration flow path by use of at least one closed and de
-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
AND A.2 Verify the affected penetration flow path is isolated. Prior to entering Mode 2 or 3 from Mode 4, if not performed within the previous 92 days.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 7 of 24 BOP o Announce the following over the Gaitronics:
o Attention in the plant. "Safety Relief Valve Open, all personnel evacuate the Containment. Personnel evacuate to WMC OR describe location
." o At H13-P601, place SRV control switch to OPEN.
o Refer to EIP 001, Classification of Emergencies, for possible applicability.
o Reduce reactor power to equal to or less than 90%.
o WHEN reactor power is equal to or less than 90%, THEN attempt to close the open SRV as follows:
o At H13-P601, take the control switch to OFF.
o Alarm H13-P601/19A/F08 , DIV I ADS/SRV CONTROL SWITCH IN OFF POSITION, comes in.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 8 of 24 Event No:
5 Event
Description:
Main Turbine Vibrations At the direction of the lead evaluator trigger Event 5. As turbine vibrations increase it takes 90 seconds for the alarm to come in after the trigger.
TIME Position Applicant's Actions or Behavior BOP o Vibrations continue to increase to 12 mils which require a manual scram and turbine trip per OSP
-53, AOP-2 o Diagnose and report rising main turbine vibrations per:
o P870 Insert 53 (Yokogawa on right) bearing vibrations going up.
o H13-P870/54A/D08, TURBINE HIGH VIBRATION ATC o Recognize and report rising main turbine vibrations per:
o P680 CRT1 (Computer screen to left of full core display) bearing vibrations going up. (Number turns red at 7 mils)
CRS o Recognize and direct BOP to make Turbine Vibrations a critical parameter.
o Brief crew to manually scram the reactor if main turbine vibrations reach 1 0 mils per OSP
-53 (EMERGENCY AND TRANSIENT RESPONSE SUPPORT) and AOP
-2 (MAIN TURBINE AND GENERATOR TRIPS).
o Direct ATC to manually scram the reactor and trip the main turbine when main turbine vibrations reach 10 mils.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 9 of 24 ATC o At 1 0 mils, manually scram reactor per AOP
-1 (Reactor Scram):
o Place C71A S1, REACTOR SYSTEM MODE SWITCH, to SHUTDOWN. o Check all Control Rods are fully inserted.
o IF all Control Rods are not fully inserted, THEN perform one OR both of the following steps to insert control rods:
o Arm and depress C71A S3A, B, C, and D, MANUAL SCRAM Pushbuttons.
o IF any Control Rods are not fully inserted, THEN arm and depress both C11C S1A and B, ARI CHANNEL A and B MANUAL INITIATION, Pushbuttons.
o Manually trip main turbine.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 10 of 24 Event No:
6 Event
Description:
ATWS After the ATC manually scrams the reactor, a 65% Hydraulic ATWS will occur automatically.
Note: Once the scram is reset it takes approximately 13 minutes to drain the scram discharge volume in order to scram and drive rods.
Enclosure actions are listed at the back of the scenario guide.
TIME Position Applicant's Actions or Behavior ATC ATWS Report o Mode Switch in shutdown. Scram pushbuttons and ARI not effective.
o Reactor Power 65
%. Hydraulic block ATWS.
o Turbine manually tripped due to main turbine vibrations.
o MSIVs are open.
o EOP 1 entry conditions: Power >5% scram required.
-1, RPV Control.
o Recognize and enter EOP-1A, RPV Control, ATWS o Directs ATC to trip both reactor recirc pumps.
o Directs ATC to verify ARI initiation.
o Directs BOP to terminate and prevent injection from HPCS.
o Directs ATC to trip the MainTurbine and evacuate Turbine Building IAW OSP-53 and AOP
-2. o Directs BOP to install Enclosures 16 and 24.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 11 of 24 ATC Trips both reactor recirc pumps.
o Depress the STOP pushbutton for B33
-C001A(B) RECIRC PUMP A(B) MOTOR BREAKER 5A(B).
o Verify B33
-C001A(B) RECIRC PUMP A(B) MOTOR BREAKER 5A(B) opens and pump coasts down to 0% speed.
o Open NJS-ACB305(029) by depressing the TRIP pushbutton for B33-S001A(B) LFMG A(B) MOT BRKR 1A(B).
Verifies ARI initiation:
o Verify light indication on ARI/RPT shows initiation.
OR o Arm and depress ATS ARI/RPT MAN TRIP Channel 1 and CHANNEL 2 pushbuttons.
o Per AOP-2, makes plant announcement to evacuate the Turbine Building. BOP Per OSP-0053, Attachment 5 (HARDCARD)
- o Override Injection / Initiate HPCS o Verify E22
-F004 amber override light is lit. o Stop the HPCS pump. o Notify the CRS that injection from HPCS has been terminated and prevented.
Inhibits ADS:
o Places ADS INHIBIT switches to the INHIBIT position.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 12 of 24 CRS o Directs ATC to terminate and prevent all injection in the RPV except boron injection, CRD and RCIC to maintain RPV level
-60 to -140 inches wide range.
o Directs ATC to stabilize RPV pressure 9 6 0-1090 psig using SRVs, Bypass valves, and drains
. o Directs ATC to maintain RPV pressure 800-1090 psig using SRVs, Bypass valves, and drains
. ATC o Terminate and prevent injection from condensate/feedwater.
o Place the Master Controller in Manual and drive all Feed Reg
valves full closed; place the Startup Feed Reg valve in Manual and drive it full closed.
o Intentionally lowers water level to maintain
-60 to -140 inches wide range. Critical Task: Terminate and prevent all injection into the RPV except boron injection, CRD and RCIC prior to exceeding HCTL
. o Maintain RPV pressure 800
-1090 psig using SRVs, Bypass valves, and drains.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 13 of 24 CRS o Directs SLC injection prior to SP temperature reaches 110F.
Critical Task: Before Suppression Pool temperature reaches 110F, inject boron (SLC). (EOP
-1A, Step RQA
-4/5) o Directs BOP to maximize CRD.
o Directs Enclosures 12 for ARI and 24 installed.
o Directs ATC to Drive and rods per Enclosure 14.
Booth o Install EOP Enclosures as requested.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 14 of 24 Event No:
7 Event
Description:
SLC Pump Failure The first SLC pump started will have an automatic malfunction resulting in a failure to inject.
TIME Position Applicant's Actions or Behavior CRS o Direct BOP to inject SLC per OSP
-53, Attachment 13 Initiating Standby Liquid Control.
-53, Attachment 13 Initiating Standby Liquid Control:
o Place SLC PUMP A(B) (NOT BOTH), control switch to RUN.
o Perform the following:
o Verify the following:
o SQUIB CONTINUITY A(B), light goes Off.
o C41-F001A(B), SLC PUMP A(B) SUCT VLV, Opens.
o C41-C001A(B), SLC PUMP A(B), Starts.
- SLC pump will have red light indicating pump start, but discharge pressure (P601
-19, C41-R600, meter on right next to SLC pump A switch) will indicate very low due to pump shaft shear. o IF any required actions do not occur, THEN perform the following:
o Place SLC PUMP A(B), control switch to STOP.
o Repeat steps 1 and 2 for the Alternate pump.
o Notify CRS of SLC injection status.
o Verify IAS
-MOV106 is Open. (Enclosure 16 may be required).
o Record SLC Tank Level. gallons
_____________
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 15 of 24 Event No:
8 Event
Description:
RHR Min flow valve fails to close in Suppression Pool Cooling TIME Position Applicant's Actions or Behavior CRS o Direct Suppression Pool Cooling using RHR A and B.
BOP o Per OSP 53, Attachment 12, Establishing Suppression Pool Cooling:
o Verify the selected system is not required for adequate core cooling.
o Throttle E12
-F068A(B), RHR HX A(B) SVCE WTR RTN, not to exceed 5800 gpm flow.
o Start/Verify Running RHR PUMP A(B).
o Verify E12
-F042A(B), RHR PUMP A(B) LPCI INJECT ISOL VALVE, Closed. o Verify E12
-F053A(B), RHR PUMP A(B) SDC INJECTION VALVE, Closed. o Open/Verify Open E12
-F024A(B), RHR PUMP A(B) TEST RTN TO SUP PL. o Verify E12
-F064A(B), RHR PUMP A(B) MIN FLOW TO SUP PL, Closed. This will fail to auto close and requires manual operation.
o Close E12-F048A(B), RHR A(B) HX BYPASS VALVE, when auto open signal has cleared.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 16 of 24 Event No:
Event
Description:
ATWS continued TIME Position Applicant's Actions or Behavior BOP Maximize CRD per OSP
-53 hardcard:
o Start any available, non
-running CRD pump as follows:
o Start C11-C001AP(BP), CRD AUX OIL PUMP A(B). o Verify C11-C001A(B), CRD PUMP A(B), white control power available light on. o Start C11-C001A(B), CRD PUMP A(B). o Place CRD HYDRAULICS FLOW CONTROLLER, in MANUAL and raise signal to 100%. o Fully Open C11-F003, CRD DRIVE WATER PRESS CONTROL VALVE. o Verify IAS-MOV106 is Open. IF IAS-MOV106 is not open, AND an ATWS condition exists, THEN notify the CRS that EOP Enclosure 16 is required. CRS o When attachments are installed, direct ATC to scram and drive rods.
Critical task: Commence driving control rods in prior to exiting E O P-1A. o Recognize and enter EOP
-2, Primary Control per:
o DW temperature o Suppression Pool Temperature o Suppression Pool Level o Containment Temperature o Containment Pressure
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 17 of 24 ATC Inserts Control Rods by Scram and normal lnsert drive by:
Manual Scram:
Reset Scram signal (Division 1 only)
Allow Scram Discharge Volume to drain Arm and depress Manual Scram pushbuttons.
(Division 1 only)
Normal Drive Reset Scram signal (Division 1 only)
Select control rod Select gang drive mode depress IN TIMER SKIP pushbutton until control rods indicate 00 Critical task: Commence driving control rods in prior to exiting E O P-1A.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 18 of 24 Event
Description:
Enclosure 12 DEFEATING RPS AND ARI LOGIC TRIPS NOTE: It takes approximately 13 minutes after the scram is reset to drain the SDV to clear the alarm.
TIME Position Applicant's Actions or Behavior CRS o Direct BOP to install enclosure 12.
BOP NOTE For non-ATWS events complete Steps 3.1 through 3.4 only. ARI should only be defeated during ATWS events.
DEFEAT Containment Instrument Air isolation interlocks per EOP
-0005 ENCL 16, to supply air to the Scram Valves.
o 3.2 OBTAIN EOP
-0005 ENCL 12 keys, four (4).
o 3.3 DEFEAT the RPS trip logic by placing the following switches in the EMERGENCY position AND VERIFY the red lights illuminate:
Switch No.
Panel No. o C71A-S15A RPS LOGIC TRIP DISABLE H13-P691 o C71A-S15B RPS LOGIC TRIP DISABLE H13-P692 o C71A-S15C RPS LOGIC TRIP DISABLE H13-P693 o C71A-S15D RPS LOGIC TRIP DISABLE H13-P694 o 3.4 IF DEFEATING the RPS trip logic only, THEN RESET the reactor SCRAM AND ARI. (H13 P680) o 3.5 DEFEAT ARI logic trip as follows:
o 3.5.1 Location: H13-P632 Bay A
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 19 of 24 (Note: Booth Actions required for the following relays)
NOTE All ARI relays are on the right side of the bay.
REMOVE Relays:
o C11C-K2B (3rd row of relays from door, 3rd relay from top) o C11C-K3B (3rd row of relays from door, 4th relay from top) o C11C-K4B (3rd row of relays from door, 5th relay from top) o C11C-K5B (3rd row of relays from door, 6th relay from top) o C11C-K2A (4th row of relays from door, 3rd relay from top) o C11C-K3A (4th row of relays from door, 4th relay from top) o C11C-K4A (4th row of relays from door, 5th relay from top) o C11C-K5A (4th row of relays from door, 6th relay from top) o 3.6 -P680) o 3.7 -P680) o 3.8 (F010 & F180) AND SCRAM DISCH VOL DRAIN VLVS (F011 & F181). (H13
-P680) o 3.9 CRD SCRAM DISCH VOL HIGH WATER LEVEL
P680-06A-A08 o THEN initiate a manual SCRAM.
o 3.10 motion is observed, THEN Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 20 of 24 Event No:
6 Event
Description:
Enclosure 14 CONTROL ROD INSERTION DATA SHEET TIME Position Applicant's Actions or Behavior CRS o Direct ATC to drive rods using Enclosure 14 until rod block occurs.
ATC o 3.3 Verify Control Rod Pattern Sequence "A" is selected.
o 3.4 Fully INSERT control rods by group, starting with Group 10, using IN TIMER SKIP pushbutton.
Skip control rods which do not fully INSERT.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 21 of 24 Event No:
6 Event
Description:
Enclosure 16 INTERLOCKS TIME Position Applicant's Actions or Behavior CRS o Direct installation of Enclosure 16.
BOP o VERIFY Instrument Air Header Pressure pressure on IAS
-PI105 (H13
-P870) is greater than Containment pressure on CMS
-PR2A(B). (H13
-P808) o 3.2 OBTAIN EOP
-0005 ENCL 16 key, one (1) o 3.3 PLACE the following switch in the EMERGENCY position AND VERIFY the red light illuminates:
o Switch Name Panel No. 3.3.1 CONTMT INST AIR ISOL INTLK BYP H13-P851 o 3.4 VERIFY open IAS
-MOV106, INST AIR OUTBD ISOL. (H13
-P870)
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 22 of 24 Event No:
6 Event
Description:
Enclosure 24 DEFEATING RPV LOW LEVEL 1 MSIV AND MSL DRAINS ISOLATION INTERLOCKS TIME Position Applicant's Actions or Behavior CRS o Direct installation of Enclosure 24.
BOP o DEFEAT Containment Instrument Air Isolation interlocks per EOP
-0005 ENCL 16 to supply air to the inboard MSIVs.
o 3.2 OBTAIN EOP-0005 ENCL 24 keys (4) o 3.3 PLACE the following keylock switches in the EMERGENCY position AND VERIFY the red lights illuminate.
o Switch No.
Panel No. o B21H-S78A RPV LO LVL 1 MSIV AND MSL DR ISOL INTLK BYP H13-P691 o B21H-S78B RPV LO LVL 1 MSIV AND MSL DR ISOL INTLK BYP H13-P692 o B21H-S78C RPV LO LVL 1 MSIV AND MSL DR ISOL INTLK BYP H13-P693 o B21H-S78D RPV LO LVL 1 MSIV AND MSL DR ISOL INTLK BYP H13-P694 o 3.4 OPEN MSIVs and MSL drains as directed by the CRS.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Page 23 of 24 TERMINATION Once crew has established rod movement, reactor water level is being controlled in band, or as directed by Lead Evaluator:
Take the simulator to Freeze and turn horns off.
Instruct the crew to not erase any markings or talk about the scenario until after follow-up questions are asked.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 2 Offgoing OSM:
Oncoming OSM:
Off-Going Shift
_______________________
_____ ___________________
_____ (Print) KCN (Print) KCN N D Date PART I - TO BE REVIEWED PRIOR TO ASSUMING THE SHIFT UNIT STATUS MODE 1 RX POWER 100%
EVOLUTIONS (COMPLETED / IN PROGRESS / PLANNED); GENERAL INFORMATION Restore 3-element control for feedwater. I&C has completed maintenance and retest.
Severe Thunderstorm warning in effect for West Feliciana in effect. All required actions per AOP-29 are complete.
Main Turbine experienced increased (approximately 1 mil higher than normal) turbine vibrations on previous shift.
SIGNIFICANT LCO STATUS None EQUIPMENT STATUS None Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 4 Page 1 of 6 Facility:
River Bend Nuclear Station Scenario No.:
4 Op-Test No.: NRC LOT 201 6 Examiners: ____________________________ Operators:
_____________________________
____________________________
_____________________________
____________________________
_____________________________
Initial Conditions:
Operating at 4% power.
Inoperable Equipment:
None Turnover: Per SOP-7, start CNM-P1B,Section 5.1, and secure CNM
-P 1C, Section 6.1 Continue withdrawing rods to achieve mode 1 using RMP-RBS-19-TRG-01 starting on Step 066
. Severe Thunderstorm warning in effect for West Feliciana in effect.
All required actions per AOP
-29 are complete.
Scenario Notes:
This scenario is a NEW Scenario. Validation Time: 60 minutes
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 4 Page 2 of 6 Event No. Malf. No. Event Type f Event Description 1 N (ATC/BOP) Swap Condensate Pumps per SOP-7, start CNM-P1B,Section 5.1, and secure CNM
-P 1C, Section 6.1 2 R (ATC) Withdraw rods for mode change. Crew will withdraw 3 rods per Reactivity Management Plan.
3 p877_32a:e_1 TS (CRS) Division 2 Diesel Generator Air Leak per P877
-32A-E01, TS 3.8.3 and 3.8.1.
4 NMS006E C (ATC) IRM E fails upscale. Bypass IRM. Reset the 1/2 scram ARP P680-6-C-10. 5 CCS001B CCS003C C (BOP) AOP CCS pump trip. Standby fails to auto start. AOP
-12 (Loss of Turbine Plant Component Cooling Water) 6 RMS005C HVFAOD102 104 AND 122 C (BOP) AOP Rad monitor fails. HVF
-AOD-104, HVF-AOD-122 and HVF
-AOD-102 fail to auto close. EOP-3, AOP-3 7 NMS007A TS (CRS) IRM A fails downscale. ARP P680 C-9. 8 ED001 DG00 2 B DG002C RCS007 M Station Blackout. Loss of offsite power. Loss of feed.
Reactor scram. Division 2 and 3 DGs fail. EOP 1. Drywell leak 200 gpm, EOP-2 9 DG006A C (BOP) Division 1 DG voltage is low and needs to be raised in order to energize the bus.
10 RCIC002 DI_E51-MIDA C (ATC) RCIC manual initiation fails. RCIC must be manually aligned per hardcard.
f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec Quantitative Attributes Table Normal Events 1 E OP Contingency Procedures Used 1 Total Malfunctions 7 Simulator Run Time 60 Malfunctions After EOP Entry 2 EOP Run Time 30 A OP Events 2 Critical Tasks 2 Major Transients 1 Reactivity Manipulations 1 E O Ps Used (Requiring measurable action) 3 Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 4 Page 3 of 6 SCENARIO ACTIVITIES:
Swap Condensate Pumps A. Per SOP-7, start CNM
-P1B,Section 5.1, and secure CNM
-P 1C, Section 6.1 Withdraw rods for mode change A. ATC will continue with the rod withdraw to transition to mode 1.
Division 2 DG Air Leak A. BOP recognizes Division 2 Diesel Generator Air Leak per P877
-32A-E01. Dispatches SNEO to investigate alarm and reports low air pressure and air leak.
B. CRS enters TS 3.8.3 and 3.8.1.
IRM E fails upscale
- A. The ATC will bypass IRM E per ARP P680-6-C-10. B. The ATC will reset the half scram per ARP P680 A-9. CCS pump trip
- A. The running CCS pump will trip and the standby pump fails to start.
B. The Unit Operator will manually start the standby CCS pump per AOP
-12 (Loss of Turbine Plant Component Cooling Water)
. Rad monitor fails
- A. The Fuel Building Exhaust Rad monitor fails and HVF-AOD-104, HVF-AOD-122 and HVF-AOD-102 fail to auto close. ARP-RMS-DSP230/4GE005 B. The Unit Operator manually closes the three dampers. IRM A fails downscale
- 1.
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 4 Page 4 of 6 Station Blackout
- A. A loss of offsite power will result in a complete loss of feed and an automatic reactor scram on low reactor water level. Division 2 and 3 Diesel Generators will malfunction. A slow drywell leak will occur.
Division 1 Diesel Generator fails to energize ENS
-SWGR1A: A. Upon the loss of offsite power, Event 8 will automatically trigger
. B. The Division 1 Diesel Generator will fail to reach voltage required to automatically energize ENS
-SWGR1A. C. The crew will manually raise diesel voltage and energize ENS
-SWGR1A. RCIC manual initiation fails
- A. Manual initiation of RCIC using the manual pushbutton will not work, Event 9 will automatically trigger
. B. The crew will manually align RCIC per the hard card (OSP-53).
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 4 Page 5 of 6 Critical Task Number Description Bas i s 1 Per E O P-1, RL-1, adjust division 1 voltage to energize ENS SWGR A within 10 minutes. If shutdown, then once fill and vent of LP ECCS systems are complete, restart and power ENS SWGR A prior to auto trip on high temperature.
Diesel Generator is needed to restore vital switchgear electrical power for AC control power during a station blackout.
The third bullet "Emergency diesel generators" applies because electrical power supplied by a
diesel generator may be required to operate RPV injection systems under emergency conditions.
The statement "which should have-but did not" encompasses conditions for which automatic action should have occurred but failed to. In such a case, manual operator action to initiate the appropriate action is required. (EPSTG*0002, B 9) 2 Per E O P-1, ALC-8, manually start RCIC prior to emergency depressurization
. Emergency depressurization is not performed while RPV water level is above the top of the active fuel because the core will remain adequately cooled as long as RPV water level remains above the Minimum Steam Cooling RPV Water Level.
(EPSTG*0002, B 29) Submergence is the preferred method for cooling the core. The core is adequately cooled by submergence when it can be determined that RPV water level is at or above the top of the active fuel. All fuel nodes are then assumed to be covered with water and heat is removed by boiling heat transfer.
- Critical Task (As defined in NUREG 1021 Appendix D)
- Per NUREG-1021, Appendix D, If an operator or the crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a CT identified in the post
-scenario review.
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 4 Page 6 of 6 Simulator Notes:
Provide and mark up GOP 1 and reactivity plan.
Possible Remote Actions:
CRD006 Reset CRDM high Temperature ECCS003 LPCS pump breaker (control power fuses)
ECCS004 RHR A pump breaker (control power fuses)
ECCS005 RHR B pump breaker (control power fuses)
ECCS006 RHR C pump breaker (control power fuses)
IAS009 Diesel Air Compressor
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 1 of 2 2 Event No:
1 Event
Description:
Swap Condensate Pumps After turnover the ATC and BOP will swap Condensate Pumps per SOP
-7. Initially CNM
-P1A and P1C are running which are both powered from the same switchgear. Starting P1B and securing P1C increases reliability.
TIME Position Applicant's Actions or Behavior CRS o Directs ATC and BOP to coordinate and swap Condensate pumps, start CNM-P1B and secure CNM
-P1C. BOP o Open CNM AOV43B, PUMP 1B DISCH VENT for the pump to be started. ATC o Start CNM P1B, CNDS PUMP 1 B. o Verify associated CCS MOV67B, CNDS PMP 1B MOT CLR and CCS MOV68B, CNDS PMP 1B BRG CLR are open for the pump started.
o Open associated CNM MOV3B, CNDS PUMP 1B DISCH.
o WHEN CNM MOV3B, CNDS PUMP 1B DISCH is full open, THEN depress the STOP pushbutton.
BOP o Close CNM AOV43B, PUMP 1B DISCH VENT for the pump just started. o Dispatch SNEO to locally verify breaker relay trip flags are reset for Condensate Pump started in Step 5.1.
- 8. Booth o When SNEO dispatched, wait 1 minute and report CNM
-1B breaker relay trip flags are reset.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 2 of 2 2 ATC o Depress the CLOSE pushbutton for CNM MOV3C, CNDS PUMP 1 C DISCH. o WHEN pump motor current lowers below 100 amps, THEN stop CNM P1C, CNDS PUMP 1C.
o WHEN CNM MOV3C, CNDS PUMP 1C DISCH is full closed, THEN depress the STOP pushbutton.
o Verify associated CCS MOV67C, CNDS PMP 1C MOT CLR close for pump stopped.
o Verify associated CCS MOV68C, CNDS PMP 1C BRG CLR close for pump stopped.
o Dispatch SNEO to locally verify breaker relay trip flags are reset for Condensate Pump stopped in Step 6.1.6
. Booth o When SNEO dispatched, wait 1 minute and report CNM
-1C breaker relay trip flags are reset.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 3 of 2 2 Event No:
2 Event
Description:
Normal Rod withdrawal After swapping Condensate Pumps, the ATC will continue with the rod withdraw to transition to mode 1. The rods will be withdrawn one notch at a time. After two rods are withdrawn (or at the direction of the Lead Examiner) the booth will manually trigger the event for the diesel air leak.
TIME Position Applicant's Actions or Behavior CRS o Directs ATC to continue rod withdrawal to transition to Mode 1.
ATC o At H13 P680, on the ROD SELECT MODULE, select the rod to be moved. Rods to be moved from 00-04: o 16-41 o 40-41 o 40-17 o 16-17 o Depress SELECTED GROUP button to check positions of control rods within group are correct prior to movement.
o Check that a Rod Withdrawal Block or Inhibit does not exist.
o On H13 P680, depress and hold C11A S334, WITHDRAW Pushbutton until the IN indicator is lit or the start of rod motion is observed. o Check that the new rod notch position displayed is the next highest even number.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 4 of 2 2 Event No:
3 Event
Description:
Division 2 Diesel Generator Air Leak After four rods are withdrawn the booth will manually trigger event 3 for the event for the diesel air leak.
TIME Position Applicant's Actions or Behavior BOP o Recognizes and reports Division 2 Diesel Generator trouble per:
o H13-P877/32A/E01 , DIESEL GENERATOR EGS
-EG1B SYSTEM TROUBLE o Dispatch a SNEO to investigate diesel trouble alarm.
Booth o When SNEO dispatched to investigate the diesel trouble alarm, wait 2 minutes and report the following:
o starting air pressure in both banks is 140 psig and slowly lowering.
o The air compressors are running and I can hear a n air leak. o The following alarms are in on the EGS
-PNL3B: EGS-PNL3B / D-10 , START AIR RECEIVER PRESS LOW EGS-PNL3B / E-5 , DSL START AIR PRESS LOW
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 5 of 2 2 CRS o Recognize and enter Tech Spec 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air E. One or more DGs with diesel fuel oil, lube oil, or starting air subsystem not within limits for reasons other than Condition A, B, C, or D. (SR 3.8.3.4 Verify each required DG air start receiver pressure is greater than or equal to 160 psig for DGs 1A and 1B.)
E.1 Declare associated DG inoperable. Immediately.
o C. One required DG inoperable.
C.1 Perform SR 3.8.1.1 for OPERABLE required offsite circuits. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> completion time and once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
AN D C.2 Declare required features supported by the inoperable DG inoperable when the redundant required features are inoperable. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery of condition C concurrent with inoperability of redundant required features.
AND C.3.1 Determine OPERABLE DG are not inoperable due to common cause failure. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
OR C.3.2 Perform SR 3.8.1.2 for OPERABLE DGs. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
AND C.4 Restore required DG to OPERABLE status. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from discovery of an inoperable division III DG and 14 days and 17 days from discovery of failure to meet LCO.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 6 of 2 2 Event No:
4 Event
Description:
IRM E fails upscale At the direction of the lead evaluator trigger Event 4. TIME Position Applicant's Actions or Behavior ATC o Diagnose and report IRM E failed upscale per
- o H13-P680/06A/C10 , IRM UPSCALE
. o H13-P680/05A/A09 , RPS TRIP LOGIC A OR C ACTIVATED o H13-P680/06A/A02 , NEUTRON MONITORING SYSTEM o H13-P680/06A/A09 , IRM UPSCALE TRIP OR INOP RPS CHAN A o UP light lit for IRM Channel E (Insert 6, apron section).
o Report no single rod scram.
CRS o Recognize and direct ATC to bypass IRM E and reset half scram per H13-P680/05A/A09, RPS TRIP LOGIC A OR C ACTIVATED o May enter a tracking LCO for 3.3.1.1.
Booth o If back panel indications requested, IRM E indicates full upscale. All other IRM indications are normal and steady.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 7 of 2 2 ATC o Bypass IRM E and reset RPS A per ARP H13-P680/05A/A09, RPS TRIP LOGIC A OR C ACTIVATED
- o Take the bypass joystick to IRM E position.
o On H13-P680, reset any potential reactor scram signals by placing the following switches momentarily to RESET then back to NORMAL:
o C71A-S5A, SCRAM RESET LOGIC A o Check the following indicating lights are on:
o RPS DIV 1 SCRAM SOV VALVES OPEN CR1A and CR1B o RPS DIV 2 SCRAM SOV VALVES OPEN CR2A and CR2B o RPS DIV 3 SCRAM SOV VALVES OPEN CR3A and CR3B o RPS DIV 4 SCRAM SOV VALVES OPEN CR4A and CR4B
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 8 of 2 2 Event No:
5 Event
Description:
CCS pump B trip At the direction of the lead evaluator trigger Event 5. A & B Pumps are initially running with C pump in standby.
TIME Position Applicant's Actions or Behavior BOP o Diagnose and report the running CCS pump trip and the standby pump fail to automatically start per: o H13-P870/55A/E01 (RED), TURB CMPNT CLG WATER PUMP BRKR AUTO TRIP o H13-P870/55A/E02 , TURB CMPNT CLG WATER PUMP LOW DISCH PRESS CRS o Recognize and direct the BOP to manually start the standby CCS pump C per H13-P870/55A/E01 (RED), TURB CMPNT CLG WATER PUMP BRKR AUTO TRIP
. o Recognize and enter AOP
-12, Loss of Turbine Plant Component Cooling Water.
BOP Start the standby CCS P1AC, TPCCW PUMP and verify the following per H13-P870/55A/E01
- o CCS P1C, TPCCW PUMP starts.
o CCS MOV15C, TPCCW PUMP DISCH VLV opens.
o CCS P1C, TPCCW PUMP MOTOR AMPS are normal.
o Alarm H13-P870/55A/E02 , TURB CMPNT CLG WATER PUMP LOW DISCH PRESS clears. o Refers to AOP
-12. Booth o TBO, investigate B CCS pump trip. No obvious indications for trip.
o TBO report post start checks on C CCS pump SAT.
o If SNEO requested to investigate B CCS pump breaker, wait 3 minutes and report no indications of trip.
o If SNEO requested, wait 3 minutes and report reports normal surge tank level.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 9 of 2 2 Event No:
6 Event
Description:
Fuel Building Exhaust Rad monitor fails At the direction of the lead evaluator trigger Event 6. TIME Position Applicant's Actions or Behavior BOP o The Fuel Building Exhaust rad monitor fails and HVF
-AOD-104, HVF-AOD-122 and HVF
-AOD-102 fail to auto close.
o Diagnose and report RMS
-RE5A failed upscale per:
o ARP-RMS-DSP230/4GE005, FUEL BUILD STACK / VENT EXHAUST A o H13-P863/75A/H01 (2 red stripes), DIV 1 FUEL BLDG EXH PAM GASEOUS RADN ALARM CRS o Per H13-P863/75A/H01, directs BOP to verify automatic actions.
o Recognize and enter AOP
-3, Automatic Isolations and direct BOP to verify group 13 valves.
o Recognize and enter EOP
-3, Secondary Containment and Radioactivity Control, until crew determines isolation was caused by a failed instrument not actual plant conditions.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 10 of 2 2 BOP Per H13-P863/75A/H01, verify the following automatic actions occur:
- Dampers fail to automatically close.
o *HVF-AOD102, FUEL BLDG EXH FAN INLT closes o H13-P863/75A/E02 , FUEL BLDG EXHAUST AIR LOW FLOW o *HVF-AOD104, FUEL BLDG EXH ISOL closes o *HVF-AOD122, FUEL BLDG AIR SPLY ISOL closes o H13-P863/75A/C02 , FUEL BLDG SUPPLY AIR LOW FLOW o HVF-AOD37A, FUEL BLDG ALT AIR SPLY opens o HVF-AOD20A, FILTER 2A INLET opens o HVF-AOD31A, FAN 3A DISCH opens o HVF-FN3A, EXH FLTR TRAIN starts o HVF-FN8A/B, FUEL BLDG EXH FAN A/B trips o HVF-ACU1FN1A/B, FUEL BLDG SPLY FAN A/B trips BOP Per AOP-3, verify group 13 isolation valves:
- Dampers fail to automatically close.
o *HVF-AOD122, FUEL BLDG AIR SPLY ISOL o *HVF-AOD102, FUEL BLDG EXH INLET ISOL o *HVF-AOD104, FUEL BLDG EXH OUTLET ISOL o HVF-AOD101, FUEL BLDG AIR SPLY INLET ISOL o HVF-AOD112, FUEL BLDG EXH INLET ISOL o HVF-AOD137, FUEL BLDG EXH OUTLET ISOL
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 11 of 2 2 Event No:
7 Event
Description:
IRM A fails downscale At the direction of the lead evaluator, trigger Event 7. TIME Position Applicant's Actions or Behavior ATC o Diagnose and report IRM A fails downscale per:
o H13-P680/06A/C09 , IRM DOWNSCALE o H13 P680/07A/C01 , CONTROL ROD WITHDRAWAL BLOCK o DOWN light lit for IRM A.
CRS o Recognize and enter Tech Spec 3.3.1.1 Reactor Protection System (RPS) Instrumentation Table 3.3.1.1
-1 1. Intermediate Range Monitors.
- b. Inop. 3 Required Channels per trip system.
A. One or more required channels inoperable.
A.1 Place channel in trip. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
OR A.2. Place associated trip system in trip. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 12 of 2 2 Event No:
8 Event
Description:
Station Blackout
& Recirc leak At the direction of the lead evaluator trigger Event 8. TIME Position Applicant's Actions or Behavior BOP o Diagnose and report:
o Loss of offsite power.
o Station Blackout.
o Division 2 Diesel Generator trip.
o Division 3 Diesel Generator fails to start. CRS o Recognize and enter:
o EOP-1, RPV Control o AOP-1, Reactor Scram o AOP-4, Loss of Offsite Power OR AOP-50, Station Blackout o Direct BOP to perform Enclosure 7 for injection into RPV with Fire System. ATC SCRAM REPORT o Mode Switch is in shutdown.
o All rods are in.
o EOP-1 (RPV CONTROL) Entry Conditions:
o Level 3 Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 13 of 2 2 Event No:
9 Event
Description:
Division 1 Diesel Generator fails to energize ENS
-SWGR1A Upon the loss of offsite power, Event 9 will automatically trigger
. TIME Position Applicant's Actions or Behavior BOP o Diagnose and report Division 1 Diesel Generator running with low voltage, therefore, did not automatically energize ENS
-SWGR1A. CRS o Recognize and direct ATC to raise Division 1 Diesel Generator voltage and energize ENS
-SWGR1A. BOP o Raise Division1 Diesel Generator voltage. (When voltage is raised to >3814 VAC, the Division 1 Diesel Generator will automatically energize ENS-SWGR1A.) Critical Task:
Adjust division 1 voltage to energize ENS SWGR A within 10 minutes. If shutdown, then once fill and vent of LP ECCS systems are complete, restart and power ENS SWGR A prior to auto trip on high temperature. Diesel Generator is needed to restore vital switchgear electrical power for AC control power during a station blackout.
Booth o Acknowledge SNEO request to monitor Division 1 EDG.
o If SNEO dispatched to investigate Division 2 EDG trip, wait 3 minutes and report control air leak from control cabinet.
o If requested to remove control power fuses for HPCS, wait 3 minutes and report fuses removed.
o If SNEO dispatched to locally start division 3 EDG, wait 10 minutes and report inability to locally start division 3 EDG.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 14 of 2 2 CRS o Recognize and enter A OP-16. o Direct BOP to split SSW to isolate division 2 SSW.
BOP o Per AOP-16, Section 5.2.6 Operate the following valves to isolate SSW Division II and place redundant SSW Division I in service:
o CLOSE SWP-MOV73B, HVR
-UC5 SUPPLY SWP-MOV74B, HVR
-UC5 RETURN o CLOSE SWP-MOV77B, HPCS D/G SUPPLY SWP-MOV506B, HPCS D/G RETURN o CLOSE SWP-MOV4B, DRYWELL UC SUPPLY SWP-MOV5B, DRYWELL UC RETURN o OPEN SWP-MOV73A, HVR
-UC5 SUPPLY SWP-MOV74A, HVR
-UC5 RETURN o OPEN SWP-MOV77A, HPCS D/G SUPPLY SWP-MOV506A, HPCS D/G RETURN o OPEN SWP-MOV4A, DRYWELL UC SUPPLY SWP-MOV5A, DRYWELL UC RETURN
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 15 of 2 2 Event No:
10 Event
Description:
RCIC manual initiation fails Manual initiation of RCIC using the manual pushbutton will not work, Event 10 will automatically trigger. (The collar to rotate to arm fails to arm.)
TIME Position Applicant's Actions or Behavior ATC o Diagnose and report RCIC fails to manually initiate. The ARM collar is not working.
The crew will manually align RCIC per the SOP-35, RCIC Section 4.2 (or per OPS-53 hardcard): o Start E51-C002C, GLAND SEAL COMPRESSOR.
o Open E51-F045, RCIC STEAM SUPPLY TURBINE STOP VALVE.
o Verify the following valves are closed:
o E51-F025, RCIC STM SPLY DR POT UP STREAM ISOL VALVE o E51-F026, RCIC STM SUPLY DR POT DN STREAM ISOL VALVE o E51-F004, RCIC TURB EXH DR POT UP STREAM ISOL VALVE o E51-F005, RCIC TURB EXH DR POT DN STREAM ISOL VALVE o Verify E51-F019, RCIC MIN FLOW VLV TO SUPPRESSION POOL is closed. o To inject into the vessel perform the following:
o Open E51-F013, RCIC INJECT ISOL VALVE.
o Verify closed E51
-F022, RCIC TEST BYPASS VLV TO CST.
o Verify closed E51
-F059, RCIC TEST RETURN VLV TO CST.
o WHEN it is required to control RPV water level with RCIC, THEN Go To Section 5.7:
o Open E51-F013, RCIC INJECT ISOL VALVE o Close the following valves o E5 1-F022, RCIC TEST BYPASS VLV TO CST o E51-F059, RCIC TEST RETURN VLV TO CST o Verify E51
-F019, RCIC MIN FLOW VLV TO SUPPRESSION POOL is closed. Critical Task:
Manually start RCIC prior to emergency depressurization
.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 16 of 2 2 ATC o Per OSP-53, assume both level control and pressure control.
o Open 1 SRV to begin cool down. Once pressure is less than 700# band will be 500 to 700#.
o Maintain level between
-5 and +15 inches is ideal for shrink and swell during SRV cycles.
CRS o CRS: establish bands of -20 to 51 inches with RCIC for level and 500 to 1090# with SRVs for pressure. Assign STP
-050-0700 for cool down.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 17 of 2 2 : Event
Description:
Station Blackout continued.
TIME Position Applicant's Actions or Behavior CRS o Assign AOP-0004 "Loss of Offsite Power" time critical actions to the ATC. o Enter EOP-2, Primary Containment Control o Drywell Temperature o Containment Pressure BOP o Perform time critical / other important task based on priority / availability:
o Start Suppression Pool cooling (30 minutes) o Verify proper operation of ventilation system and secure redundant trains (20 minutes) o Install enclosure 20 and start drywell cooling o AOP-0010 for loss of RPS (after alt EPAs are reset) o Secure EBOP (15minutes post turbine stop concurrent with LOCA) o Restart Radiation Monitors (ATC/3rd Operator) o ATC should dispatch the o ACR to start Diesel Air compressor o Control Building to reset Alt EPA bkrs and then to monitor D/G
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 18 of 2 2 Event
Description:
Enclosure 7.
TIME Position Applicant's Actions or Behavior CRS o Direct BOP to perform Enclosure 7 to align injection into RPV with fire system. BOP o OBTAIN EOP
-0005 ENCL 7 key OR opening device, one (1) o 3.2 VERIFY Diesel fire pumps running (Auxiliary Control Room, 1CES
-PNL4) o 3.3 CLOSE the following Standby Service Water valves: (H13
-P870) o -MOV96A, NORM SVCE WTR RETURN o -MOV96B, NORM SVCE WTR RETURN o -MOV57A, NORM SVCE WTR SUPPLY o -MOV57B, NORM SVCE WTR SUPPLY o SWP-MOV55A, STBY CLG TOWER 1 INLET o -MOV55B, STBY CLG TOWER 1 INLET o 3.4 VERIFY E12
-C002B, RHR PUMP B is secured. (H13
-P601) o 3.5 VERIFY CLOSED E12
-F024B, RHR PUMP B TEST RTN TO SUP PL. (H13-P601)
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 19 of 2 2 BOP o 3.6 OPEN (UNLOCK if necessary) the following Fire Protection/Service Water Inlet Valves.
o SWP-V965) o 1. FPW-V818, SWP BACKUP TO CB HOSE RACKS ISOLATION VALVE
AND o 2. SWP-V961, SVCE WTR SUPPLY TO FIRE PROTECTION IN CONTROL BLDG ISOL VLV o g EL 74 ft. SW corner each side of Check Valve SWP
-V973) o 1. FPW-V396, ISOLATION VALVE FOR SWP BACKUP TO FUEL BLDG HOSE RACKS AND o 2. SWP-V971, DIV 2 STBY SWP TO FUEL BLDG FIRE PROT ISOL VLV o Valve SWP-V964) o 1. FPW-V321, SWP BACKUP TO RB AND AUX BLDG HOSE RACKS ISOLATION VALVE AND o 2. SWP-V968, SVCE WTR TO FIRE PROTECTION MAN ISOL VLV o 3.7 IF Reactor Pressure is below 150 psig, o THEN VERIFY OPEN E12
-F042B, RHR PUMP B LPCI INJECT ISOL VALVE, (H13
-P601) OR o OPEN E12-F053B, RHR PUMP B SDC INJECTION VALVE (H13
-P601) defeating isolation interlocks per EOP
-0005 ENCLOSURE 32 if necessary.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 20 of 2 2 BOP o 3.8 IF unable to open E12
-F042B, RHR PUMP B LPCI INJECT ISOL VALVE OR E12-F053B, RHR PUMP B SDC INJECTION VALVE AND Containment Flooding is required THEN o OPEN E12-F024B, RHR PUMP B TEST RTN TO SUP PL. (H13
-P601) OR o OPEN E12-F037B, RHR B TO UPPER POOL FPC ASSIST (H13
-P601) defeating isolation interlocks if necessary as follows:
o 3.8.1 OBTAIN EOP
-0005 ENCL 22 jumper kit from the Control Room Emergency Locker.
o 1. INSPECT kit for 1 jumper.
o 3.8.2 Location: H13
-P618 Bay B o Affected Relay: E12A
-K135B (Top row of agastat relays, 1st relay from left) o 1. REMOVE relay E12A
-K135B. o 2. Jumper No. 1 o JUMPER Terminal M1 on relay block E12A-K135B o to o Terminal R1 on relay block E12A
-K135B o 3.9 OPEN E12
-F094, UP STREAM SVCE WATER CONTMT FLOOD VALVE. (H13
-P601) o 3.10 OPEN E12
-F096, DN STREAM SVCE WATER CONTMT FLOOD VALVE. (H13
-P601) o 3.11 VERIFY OPEN E12
-F027B, RHR PUMP B OUTBD ISOLATION VALVE. (H13-P601) o 3.12 As reactor pressure decreases, VERIFY service water flow commences to the RPV or containment as indicated on E12
-P601)
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Page 21 of 2 2 TERMINATION Once reactor water level is being controlled in band, or as directed by Lead Evaluator:
Take the simulator to Freeze and turn horns off.
Instruct the crew to not erase any markings or talk about the scenario until after follow-up questions are asked.
Save SBT data.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 4 Offgoing OSM:
Oncoming OSM:
Off-Going Shift
_______________________
_____ ___________________
_____ (Print) KCN (Print) KCN N D Date PART I - TO BE REVIEWED PRIOR TO ASSUMING THE SHIFT UNIT STATUS MODE 2 RX POWER 4%
EVOLUTIONS (COMPLETED / IN PROGRESS / PLANNED); GENERAL INFORMATION Severe Thunderstorm warning in effect for West Feliciana in effect. All required actions per AOP-29 are complete.
- 1. Per SOP-7, start CNM
-P1B,Section 5.1, and secure CNM
-P 1C, Section 6.1
- 2. Continue withdrawing rods to achieve mode 1 using RMP-RBS-19-TRG-01 starting on Step 066
. SIGNIFICANT LCO STATUS None EQUIPMENT STATUS None Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 3 (Spare) Page 1 of 6 Facility:
River Bend Nuclear Station Scenario No.:
3 (Spare) Op-Test No.: NRC LOT 201 6 Examiners: ____________________________ Operators:
_____________________________
____________________________
_____________________________
____________________________
_____________________________
Initial Conditions:
Operating at 100% power.
Inoperable Equipment:
None Turnover:
Severe Thunderstorm warning in effect for West Feliciana in effect.
All required actions per AOP
-29 are complete.
RPS B power supply is on alternate due to repairs to B RPS MG set.
RPS B normal power supply is available and tags are being cleared.
Swap CRD pumps STP-203-6305 is in progress commence on step 7.6.3.
Scenario Notes:
This scenario is a NEW Scenario.
Validation Time: 60 minutes
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 3 (Spare) Page 2 of 6 Event No. Malf. No. Event Type f Event Description 1 N (BOP) Swap CRD pumps per SOP-2 2 HPCS001 Event 1 N (BOP) TS (CRS) HPCS STP. HPCS pump trip.
STP-203-6305. TS 3.5.1. ARP P601-16-B-3, P601-16-F-5, and P601 G-4. 3 ED0040 C (BOP/ATC)
TS (CRS) AOP Loss of alternate RPS power supply. Power supply switched back to normal and half scram reset.
AOP 10 (Loss of RPS Bus). ARP P877 C-3, P877-32-E-1, P877-32-E-2, P877-32-F-2, P877-32-G-1, P877-32-H-3, and P877 H-4. TS 3.3.8.2, EOP-3 4/5 RCS005A RCS002A C (ATC) AOP R (ATC) Recirc pump seal leak, pump trip, (isolate recirc loop
). ARP P680-4-E-5. GOP-4. AOP-24. Exit restricted region (insert rods or increase recirc flow) 6 MSC006 M (CREW) THI increases and requires manual scram. ARP P680-6-C-1, P680-7-A-5, P680-7-A-6, P680-7-B-5, and P680 B-6. AOP-1. EOP-1. 7 ED001 Delay 2:30 RCIC001 T8, Ev 8 ED003I, Delay 2:30 M (CREW) Loss of offsite power. Loss of feedwater.
RCIC trips on overspeed. Failure of Division 2 DG to energize ENS SWGR-1B. Recirc loop rupture.
8 RHR009A C (ATC) RHR 'A' pump fails to auto start 9 LPCS002 delete on event 9 C (ATC) LPCS injection valve fails to auto open f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec Quantitative Attributes Table Normal Events 2 E OP Contingency Procedures Used 1 Total Malfunctions 5 Simulator Run Time 60 Malfunctions After EOP Entry 2 EOP Run Time 30 A OP Events 2 Critical Tasks 3 Major Transients 2 Reactivity Manipulations 1 E O Ps Used (Requiring measurable action) 2 Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 3 (Spare) Page 3 of 6 SCENARIO ACTIVITIES:
Swap CRD Pumps A. Crew will swap CRD pumps per SOP
-0002. This is a normal evolution that is not faulted. HPCS pump trip
- A. After turnover the Unit Operator will perform STP-203-6305. During the performance of the STP the HPCS pump will automatically trip (Event 1). The Unit operator should secure HPCS STP lineup per ARP P601-16-B-3, P601-16-F-5, and P601-16-G-4. B. CRS should enter TS 3.5.1. EJS SWGR B lockout:
A. After the Unit Operator secures HPCS, CRS enters TS 3.5.1, and/or at the direction of the lead evaluator trigger Event 2. B. The E JS SWGR B lockout will result in loss of alternate RPS power supply and a division 2 half scram.
C. The Unit Operator will switch the power supply back to normal and the ATC will reset the half scram. AOP 10 (Loss of RPS Bus). ARP P877 C-3, P877-32-E-1, P877-32-E-2, P877-32-F-2, P877-32-G-1, P877-32-H-3, and P877 H-4. D. The CRS will enter TS 3.8.4 and 3.8.9
. Recirculation pump seal leak: A. After the Unit Operator swaps the RPS power supply and has completed AOP
-10 through step 13 of Attachment 2, the ATC resets the Division 2 half scram , the CRS enters TS 3.8.4 and 3.8.9 , and/or at the direction of the lead evaluator trigger Event 3. B. The A Recirculation pump #1 seal will degrade.
C. After the crew diagnosis of the seal failure and/or at the direction of the lead evaluator , trigger Event 4 to trip the Recirculation Pump.
D. The ATC may be required to reduce flow to < 33 kgpm and monitor for THI. ARP P680-4-E-5. GOP-4. AOP-24. The ATC will also isolate tripped recirc pump and take actions to exit restricted region (insert rods or increase recirc flow).
E. The CRS will enter TS 3.5.1.
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 3 (Spare) Page 4 of 6 Thermal Hydraulic Instability:
A. After the ATC reduces flow to < 33 kgpm, the CRS enters TS 3.5.1, and/or at the direction of the lead evaluator trigger Event 5. B. THI power swings get bigger and require a manual scram. ARP P680 C-1, P680-7-A-5, P680-7-A-6, P680-7-B-5, and P680 B-6. AOP-1. AOP-24. EOP-1. Loss of offsite power
& Recirc leak
- A. After the manual scram, Event 6 will automatically occur
. B. The loss of offsite power will result in a loss of all feedwater. RCIC will trip on overspeed. The Division 2 DG will fail to energize ENS SWGR-1B. C. When RCIC trips, recirc leak will develop leading to lowering reactor water level.
D. Due to a loss of all high pressure injection sources, the crew will be forced to emergency depressurize and inject with Division 1 low pressure ECCS systems.
RHR 'A' pump fails to auto start: A. The RHR A pump will fail to auto start after automatic initiation. Automatic trigger Event 7. B. The crew will manually start the RHR 'A' pump to assist restoring reactor water level.
RHR alone will not be enough to restore reactor water level. LPCS will be required as well. LPCS injection valve fails to auto open: A. The LPCS injection valve will fail to open after automatic initiation and emergency depressurization. Automatic trigger Event 8. B. The crew will manually open the LPCS injection valve to assist restoring reactor water level. LPCS alone will not be enough to restore reactor water level. RHR will be required as well.
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 3 (Spare) Page 5 of 6 Critical Task Number Description Bas i s 1 Per AOP-24, 4.2, Mode switch to shutdown immediately after Division 1 and 2 PERIOD BASED DETECTION SYSTEM HI-HI DECAY RATIO alarms are in (P680
-07A-A6 and B6)
. It is possible for the Critical Power Ratio Safety Limit to be violated during a Thermal Hydraulic Instability Event, even if the peak
-to-peak power oscillations are less than 10%.
(AOP-24, 1.9) 2 Per E O P-1, ALC-11 & 1 4 , Emergency Depressurize prior to
-211 inches compensated fuel zone.
Emergency RPV depressurization (signaled by Step ALC-11) permits injection from low head systems, maximizes the total injection flow, and minimizes the flow through any primary system break. If it is believed that available injection sources are capable of restoring and maintaining RPV water level above the Minimum Steam Cooling RPV Water Level following RPV depressurization, the blowdown may be performed as soon as RPV level reaches the top of the active fuel.
(EPSTG*0002, B 29) 3 Per EO P-1, RL-2 & 3, Manually start RHR A pump and open LPCS injection valve p rior to entering SAPs (restore and maintain reactor water level >
-211 inches). The primary action of Step RL
-3 defines the range in which RPV level should be established and maintained, and specifies the preferred systems to use in doing so.
Maintaining RPV water level below the high end of the identified control band preserves the availability of RCIC. RPV level above the low end of the identified control band permits the scram to be reset (barring the existence of other scram signals), and allows the use of the normal shutdown cooling system to establish and maintain cold shutdown conditions.
Submergence is the preferred method for cooling the core. The core is adequately cooled by submergence when it can be determined that RPV water level is at or above the top of the active fuel. All fuel nodes are then assumed to be covered with water and heat is removed by boiling heat transfer.
(EPSTG*0002, B 4)
- Critical Task (As defined in NUREG 1021 Appendix D)
- Per NUREG-1021, Appendix D, If an operator or the crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a CT identified in the post
-scenario review.
Appendix D Scenario Outline Form ES-D-1 NRC 2016 Scenario 3 (Spare) Page 6 of 6 Simulator Notes:
RPS B in alternate using the key switch in the back.
Set up the IC rod line to ensure when the recirc pump trips the crew is deep in the restricted region.
Make the recirc loop rupture big enough not to be turned by RHR alone.
Event 1 E22-MOVF011 red light on zdi5(856)
Event 10 remove MSC006 5 seconds after mode switch Event 9 LPCS injection valve (5) to open zdi5(538)
T9, RCS001 to 20 on event 9 Event 7, Mode switch not in run Event 8, RCIC turb >90% speed.
Event 30, Narrow range <0, T30 reacotr recirc loop rupture RCS001A to 10. Ramp 2 minutes.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 1 of 20 Event No:
1 Event
Description:
CRD Pump Swap Note: Crew will be starting CRD Pump A and securing CRD pump B TIME Position Applicant's Actions or Behavior BOP o Alternating CRD Pumps o NOTE o Precaution and Limitation 2.18 should be referenced prior to alternating CRD Pumps.
o Perform the following steps for the CRD Pump to be started.
o Check that the oil level for CRD Pump A(B) and its associated gear box is normal.
o Close C11 VF014A(B), CRD PMP A(B) DISCH STOP CHECK VLV
. o 3. Vent the CRD Pump A(B) casing using C11 VF109A(B), CRD PUMP A(B) CASING VENT VLV.
o Start C11 C001AP(BP), CRD AUX OIL PUMP A(B).
o Verify white light comes on for C11 C001A(B), CRD PUMP A(B).
o Start C11 C001A(B), CRD PUMP A(B) AND immediately perform the following:
o Slowly open C11 VF014A(B), CRD PMP A(B)
DISCH STOP CHECK VLV. o Verify CRD Pump A(B) is operating properly.
o Check that CRD System flow has stabilized.
o Perform the following steps for the CRD Pump to be stopped:
o Close C11 VF014A(B), CRD PMP A(B) DISCH STOP CHECK VLV.
o Stop C11 C001A(B), CRD PUMP A(B).
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 2 of 20 Event No:
1 Event
Description:
HPCS pump trip After turnover the Unit Operator will perform STP
-203-6305. During the performance of the STP the HPCS pump will automatically trip (Event 1). Pump trips 45 seconds after the E22
-F011 is taken to the open position (red light on)
TIME Position Applicant's Actions or Behavior BOP o Perform STP
-203-6305, HPCS QUARTERLY PUMP AND VALVE OPERABILITY TEST:
o 7.6.3 Start E22
-C001, HPCS PUMP.
o Expected alarm H13
-P808 / 86A /
E04, NNS-SWG1A OR 1B FAST TRANSFER BLOCKED o 7.6.4 Check E22
-F012, HPCS MIN FLOW VALVE TO SUPPRESSION POOL, auto opens.
o 7.6.5 Simultaneously throttle open E22
-F010, HPCS TEST BYPASS VLV TO CST, AND E22
-F011, HPCS TEST RETURN VALVE TO CST, equal amounts to establish the Reference Value of 5050 gpm as indicated on E22
-R603, HPCS FLOW.
(bottom right meter) o 7.6.6 Check E22
-F012 auto closes.
o Diagnose and report HPCS Pump trip per o H13-P601/16A/B03, DIV III 4KV BUS AUTO TRIP o H13-P601/16A/F05, HPCS PUMP MOTOR OVERCURRENT o H13-P601/16A/G04, HPCS INJECTION LINE PRESSURE LOW CRS o Recognize and direct BOP to secure HPCS STP lineup.
o Recognize and enter Tech Spec 3.5.1 ECCS -Operating B. High Pressure Core Spray (HPCS) System inoperable.
B.1 Verify by administrative means RCIC System is OPERABLE when RCIC is required to be OPERABLE. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> completion time.
AND B.2 Restore HPCS System to OPERABLE status. 14 days completion time.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 3 of 20 BOP o Secure HPCS lineup by closing E22
-F010 and E22
-F011. Booth o If SNEO requested, at the HPCS pump there are no obvious indications for cause of pump trip.
o If SNEO dispatched to breaker, wait 3 minutes and report trip flags present. 86 lockout device is present.
o Acknowledge request for work control to protect RCIC.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 4 of 20 Event No:
3 Event
Description:
Loss of RPS Bus B Alternate After the Unit Operator secures HPCS, CRS enters TS 3.5.1, and/or at the direction of the lead evaluator trigger Event 3. The lights will be manually flickered to add realism of lightning strike and grid transient.
TIME Position Applicant's Actions or Behavior Booth o Flicker lights when event is initiated
. o After event is triggered, call control room and report from security that a lightning strike in the switchyard was observed.
o When directed to investigate loss of Alternate RPS B, wait 3 minutes and report both EPA breakers have trip flags present but remain closed. o If status of B MG set is requested, report B MG set is running and ready to be loaded. Tags have been removed.
BOP o Diagnose and report loss of alternate RPS power supply
. ATC o Diagnose and report loss of division 2 RPS and division 2 half scram per: o H13-P680/05A/A06 , LOSS OF RPS B
- ALT PWR SUPPLY o H13-P680/05A/A10 , RPS TRIP LOGIC B OR D ACTIVATED o The division 2 white lights are out.
BOP o Diagnose and report Division 2 isolation and loss of division 2 RPS per:
o H13-P601/18A/E03 , 120 VAC RPS LOGIC "D" POWER FAILURE o H13-P601/18A/G04 , DIV 2 & 3 NSSSS ISOLATION o H13-P601/19A/F03 , TURB BLDG DIV 2 HIGH TEMP OR INOP o H13-P601/19A/G01 , TURB BLDG DIV 4 HIGH TEMP OR INOP o H13-P601/19A/H03 , AIR TEMP MON R608 DRYWELL AMBIENT HIGH TEMP Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 5 of 20 CRS o Recognize and enter TS 3.3.8.2 RPS Electric Power Monitoring
3.3 INSTRUMENTATION
3.3.8.2 LCO 3.3.8.2 Two RPS electric power monitoring assemblies shall be OPERABLE for each inservice RPS motor generator set or alternate power supply. Reactor Protection System (RPS) Electric Power Monitoring A. One or both inservice power supplies with both electric power monitoring assemblies inoperable
. B.1 Remove associated inservice power supply(s) from service.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> CRS o Recognize and enter AOP 10 (Loss of RPS Bus).
o Direct BOP to transfer RPS B to Normal Supply per SOP
-79, Section 5.2 and AOP
-10, Attachment 2.
o Once power is restored to RPS B, direct ATC to reset division 2 half scram per AOP
-10, Attachment 2, Step 7.
ATC o Reset the half-scram. o Place C71A
-S5B, SCRAM RESET LOGIC B and C71A
-S5D, SCRAM RESET LOGIC D in RESET to reset the half scram per AOP-10, Attachment 2, Step 7
. Booth o When requested, backpanel reset NI cabinet power supply.
o When requested, backpanel sway control room lighting from EJS B to EJS A (Breaker 053).
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 6 of 20 CRS o May prioritize the order of restoration of AOP
-10 if desired.
o Enters EOP
-3 for annulus pressure until crew verifies actual entry conditions are not present per H13-P863/72A/A01 , ANNULUS PRESSURE HIGH. BOP Transfer RPS B to Normal Supply per SOP
-79, Section 5.2 and AOP
-10, Attachment 2:
o At H13-P610, verify power is available from the MG Set as indicated by GEN. B NORM FEED AVAIL white indicating light.
o On H13-P610, place the POWER TRANSFER Switch in NORM B. o Reset the following as applicable:
o At H13-P670 and P672, Neutron Monitoring Cabinets, depress S1, RESET Pushbutton for RPS B, located in the power supply section on the lower section of the cabinet.
o Reset the half
-isolation: o B21H-S33, INBD ISOLATION SEAL
-IN RESET Pushbutton o B21H-S32, OUTBD ISOLATION SEAL
-IN RESET Pushbutton o Check appropriate RPS Trip Logic annunciator clears:
o For RPS Bus B, P680
-05A-A10, RPS TRIP LOGIC B OR D ACTIVATED o At H13-P870, reopen the following isolation valves:
o CCP-MOV144, RR PUMP CLG UP STREAM RTN o CCP-MOV158, CONTMT RTN INBD ISOL o At H13-P670, Neutron Monitoring Cabinets, depress S1, RESET Pushbutton for RPS B, located in the power supply section on the lower section of the cabinet. o At H13-P672, Neutron Monitoring Cabinets, depress S1, RESET Pushbutton for RPS B, located in the power supply section on the lower section of the cabinet.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 7 of 20 BOP o Place control switches for all tripped Drywell Unit Coolers to OFF.
o At H13-P877, close the following breakers:
o EJS-ACB49, NORM CHGR 1B SPLY BRKR (NO POWER) o EJS-ACB50, NHS
-MCC101 SPLY BRKR o EJS-ACB66, NHS
-MCC 102B SPLY BRKR o EJS-ACB77, IHS
-CHGR 1D SPLY BRKR o At H13-P870, reopen the following isolation valves:
o SWP-MOV4B, DRYWELL UC SUPPLY o SWP-MOV5A, DRYWELL UC RETURN o DFR-AOV101, RB FLOOR DR INBD ISOL (NO POWER) o DER-AOV126, RB EQUIP DR INBD ISOL (NO POWER) o WCS-MOV178 BW TK DR INBD ISOL o Start additional Drywell Unit Coolers as needed per SOP
-0060, Drywell Cooling. o At H13-P863, reopen the following isolation valves:
o HVN-MOV129, CHW SPLY SHUTOFF VLV o HVN-MOV102, CHW RTN INBD ISOL o HVN-MOV130, CHW RTN SHUTOFF VLV o JRB-SOV15, SUPPLY AIR ISOL VLV (NO POWER) o JRB-SOV25, SUPPLY AIR ISOL VLV (NO POWER)
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 8 of 20 BOP o At H13-P863, perform the following to reset HVK-MOV10B, CHW SURGE TK B NORM MKUP:
o Place HVK-MOV10B, CHW SURGE TK B NORM MKUP Control Switch in CLOSE.
(NO POWER) o Place HVK-MOV10B, CHW SURGE TK B NORM MKUP Control Switch in AUTO.
(NO POWER) o At H13-P808, reopen the following isolation valves:
o RCS-MOV61B, FCV B ACTUATOR LEAKOFF o RCS-MOV60B, FCV B RETURN ISOL VLV o RCS-MOV59B, FCV B CLOSING SPLY VLV o RCS-MOV58B, FCV B OPENING SPLY VLV o At H13-P601, reopen the following isolation valves:
o B33-F019, REACTOR WATER UPSTREAM ISOL VLV (NO POWER) o B21-F016, MSL WARMUP HDR INBD CONTMT ISOL VLV o B21-F085, MSL WARMUP HDR SHUTOFF VALVE
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 9 of 20 Event No:
3 Event
Description:
A Recirculation pump seal leak After the Unit Operator swaps the RPS power supply and has completed AOP
-10 through step 13 of Attachment 2, the ATC resets the Division 2 half scram, the CRS enters TS 3.8.4 and 3.8.9
, and/or at the direction of the lead evaluator trigger Event 3
. After the crew diagnosis of the seal failure and/or at the direction of the lead evaluator, trigger Event 4 to trip the Recirculation Pump.
TIME Position Applicant's Actions or Behavior ATC o Diagnose and report the A Recirculation pump #1 seal degrading: o H13-P680/04A/E05, RECIRC PUMP A SEAL STAGING HIGH/LOW FLOW o #2 PRESS SEAL CAVITY, B33
-R602A, Pressure equalizes with #1 PRESS SEAL CAVITY pressure.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 10 of 20 Event No:
4 Event
Description:
Recirculation pump A trip After the crew diagnosis of the seal failure and/or at the direction of the lead evaluator, trigger Event 4 to trip the Recirculation Pump.
TIME Position Applicant's Actions or Behavior ATC o Diagnose and report recirc pump trip per:
o H13-P680/04A/A01 , RECIRC MOTOR A TRIP o H13-P680/04A/B01 , RECIRC MOTOR A LOCKOUT/TRIP o H13-P680/05A/C03 , RECIRC PUMP SUPPLY BRKR 4A OVERCURRENT o H13-P680 / 03A / B08 , REACTOR HIGH/LOW WATER LEVEL CRS o Recognize and enter:
o AOP-24, THERMAL HYDRAULIC STABILITY CONTROLS o GOP-4, SINGLE LOOP OPERATION o Direct ATC to perform actions per AOP-24, section 4.3. o If flow is not within limits, direct ATC to reduce recirculation loop flow to <33 kgpm, per GOP
-4 (28.1 kgpm)
. o Direct ATC to secure Recirc Pump A per SOP
-3.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 11 of 20 ATC AOP-24, 4.3 Determine power/flow region using Attachment 1, RBS Dual Loop Operation Power/Flow Maps OR Attachment 2, RBS Single Loop Operation Power/Flow MapsEnter GOP-0004, Single Loop Operation.
o IF entry into the Restricted Region is unexpected, THEN perform the following:
o IF both channels of PBDS are inoperable, THEN immediately place the reactor mode switch in the SHUTDOWN position.
o NOTE o With only one Recirc Pump in operation, GOP 0004, Single Loop Operation Precautions and Limitations should be referenced prior to raising Recirc flow.
o Immediately exit this region by performing the following actions:
o Insert Control Rods using the Shutdown Control Rod Sequence Package or as specified by Reactor Engineering, OR o Raise recirculation flow by opening Recirc FCVs o Per the RMP, step 002, the following control rods will be moved from position 10 to position 00 o 20-37 o 36-37 o 36-21 o 20-21 Note: When the third rod per the Reactivity Management Plan is inserted or when one of the recirc flow control valves have been adjusted to raise flow, THI will be inserted.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 12 of 20 ATC Shutdown the Recirc Pump A per SOP
-3: o Close B33-F067A(B), RECIRC PUMP A(B) DISCH VLV, for the pump that was shutdown to permit the pump to come to a complete stop and prevent reverse rotation.
o WHEN at least 5 minutes have elapsed, THEN open B33
-F067A(B), RECIRC PUMP A(B) DISCH VLV to permit the flow of reactor coolant through the pump loop to maintain it within 50*F of the running loop.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 13 of 20 Event No:
5 Event
Description:
Thermal Hydraulic Instability When the crew takes action to exit the restricted region, the booth will trigger Event 5.
Takes approximately 1 minute for the alarm to come in after the event is triggered.
TIME Position Applicant's Actions or Behavior ATC Diagnose and report indications of THI per:
o H13-P680/06A/C01 , APRM UPSCALE o H13-P680/07A/A05 , DIV 1 PERIOD BASED DETECTION SYSTEM HI DECAY RATIO o H13-P680/07A/A06 , DIV 1 PERIOD BASED DETECTION SYSTEM HI
-HI DECAY RATIO o H13-P680/07A/B05 , DIV 2 PERIOD BASED DETECTION SYSTEM HI DECAY RATIO o H13-P680/07A/B06 , DIV 2 PERIOD BASED DETECTION SYSTEM HI
-HI DECAY RATIO o APRM power oscillations getting larger.
CRS o Recognize THI and enter:
o AOP-1, REACTOR SCRAM o AOP-24, THERMAL HYDRAULIC STABILITY CONTROLS o EOP-1, RPV CONTROL o Direct ATC to place the mode switch in SHUTDOWN, per AOP
-24, 4.2.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 14 of 20 ATC o Per AOP-24, 4.2 IF core thermal hydraulic instability is observed THEN place the reactor mode switch in the SHUTDOWN position.
o Per EN-OP-115 (Conduct of Operations), 5.2 Conditions Requiring An Immediate Manual Reactor Scram: Licensed operators SHALL immediately insert a manual scram whenever any of the following conditions occurs: Core theral
-hydraulic instability is observed.
Critical Task: Mode switch to shutdown immediately after Division 1 and 2 PERIOD BASED DETECTION SYSTEM HI
-HI DECAY RATIO alarms are in (P680
-07A-A6 and B6).
Scram report:
o Mode switch is in shutdown.
o All rods are in
. o EOP Entry Conditions: Level 3.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 15 of 20 Event No:
6 Event
Description:
Loss of offsite power & Recirc leak:
2 minutes after the manual scram, LOP will occur and small Recirc leak commences. On level 3 the recirc leak will get larger to drive the crew to emergency depressurization. When the first Low Pressure ECCS injection source is commenced, the recirc leak will get larger to ensure RHR A and LPCS are both required for injection to restore reactor water level.
Note: All 1.68 psid actions for isolation and initiations will have to be re
-performed when LOP occurs.
TIME Position Applicant's Actions or Behavior BOP o Diagnose and report:
o Loss of offsite power.
o RCIC overspeed trip during startup. o Division 1 DG will start and energize ENS SWGR
-1A. o Division 2 DG will start but fails to energize ENS SWGR
-1B. ATC o Diagnose and report:
o Loss of offsite power.
o Loss of all feed and condensate.
CRS o Recognize and enter EOP 1 for level 3 and 1.68 psid drywell pressure.
o Recognize and direct ATC to verify Level 2 and 3 initiations, isolations and diesel generators.
o If RPV level cannot be restored and maintained between 10 inches and 51 inches, then restore and maintain RPV level above
-162 inches using Table L
-2 Alternate Injection Subsystems if necessary.
o Recognize and direct BOP to maximize CRD flow and inject SLC.
o Direct ATC to install Enclosures 32, 22, 6, 7, and 35.
o Assign level band
-20 to 51 inches on RCIC.
o Assign pressure band 500
-1090 psig on SRVs.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 16 of 20 ATC o Verify Level 2 and 3 initiations, isolations and diesel generators.
BOP INITIATING STANDBY LIQUID CONTROL o Place SLC PUMP A(B) (NOT BOTH), control switch to RUN. o Verify the following:
o SQUIB CONTINUITY A(B), light goes Off. o C41-F001A(B), SLC PUMP A(B) SUCT VLV, Opens. o C41-C001A(B), SLC PUMP A(B), Starts. o Notify CRS of SLC injection status.
o Verify IAS-MOV106 is Open. (Enclosure 16 may be required).
MAXIMIZING CRD (Recognizes no power to maximize CRD) o Start any available, non-running CRD pump as follows:
o Start C11-C001AP(BP), CRD AUX OIL PUMP A(B). o Verify C11-C001A(B), CRD PUMP A(B), white control power available light on. o Start C11-C001A(B), CRD PUMP A(B). o Place CRD HYDRAULICS FLOW CONTROLLER, in MANUAL and raise signal to 100%. o Fully Open C11-F003, CRD DRIVE WATER PRESS CONTROL VALVE. o Verify IAS-MOV106 is Open. IF IAS-MOV106 is not open, AND an ATWS condition exists, THEN notify the CRS that EOP Enclosure 16 is required.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 17 of 20 CRS o If RPV level cannot be restored and maintained above
-162 inches , then go to alternate level control.
o Recognize when RPV level cannot be restored and maintained above
-187 inches, emergency depressurization is required.
o Direct ATC to open 7 ADS/SRVs. ATC Inhibits ADS:
o Places both ADS INHIBIT switches to the INHIBIT position.
o Open 7 ADS/SRVs Critical Task: Emergency Depressurize prior to
-18 7 inches compensated fuel zone.
CRS o Direct ATC to maintain RPV level
-20 to 51 inches, using RHR A through SDC injection valve E12-F053A and LPCS.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 18 of 20 Event No:
7 Event
Description:
RHR 'A' pump fails to automatically start The RHR A pump will fail to auto start after automatic initiation. Automatic trigger Event 7. TIME Position Applicant's Actions or Behavior ATC o Diagnose and report RHR A pump fail to auto start.
o Manually start RHR A pump.
Critical Task: Manually start RHR A pump and open LPCS injection valve prior to entering SAPs (restore and maintain reactor water level >
-211 inches).
CRS o Recognize RHR A pump fail to auto start and direct ATC to manually start RHR A pump.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 19 of 20 Event No:
8 Event
Description:
LPCS injection valve fails to automatically open The LPCS injection valve will fail to open after automatic initiation and emergency depressurization. Automatic trigger Event 8. TIME Position Applicant's Actions or Behavior ATC o Diagnose and report LPCS injection valve fails to auto open.
o Manually open LPCS injection valve.
Critical Task: Manually start RHR A pump and open LPCS injection valve prior to entering SAPs (restore and maintain reactor water level >
-211 inches).
CRS o Recognize LPCS injection valve fails to auto open.
o Direct ATC to manually open LPCS injection valve.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Page 20 of 20 TERMINATION Once reactor water level is being restored, or as directed by Lead Evaluator:
Take the simulator to Freeze and turn horns off.
Instruct the crew to not erase any markings or talk about the scenario until after follow-up questions are asked.
Save SBT data.
Appendix D Scenario Outline Form ES-D-2 NRC 2016 Scenario 3 Offgoing OSM:
Oncoming OSM:
Off-Going Shift
_______________________
_____ ___________________
_____ (Print) KCN (Print) KCN N D Date PART I - TO BE REVIEWED PRIOR TO ASSUMING THE SHIFT UNIT STATUS MODE 1 RX POWER 100%
EVOLUTIONS (COMPLETED / IN PROGRESS / PLANNED); GENERAL INFORMATION Severe Thunderstorm warning in effect for West Feliciana in effect. All required actions per AOP-29 are complete.
RPS B power supply is on alternate due to repairs to B RPS MG set. RPS B normal power supply is available and tags are being cleared.
CRD pumps need to be swapped for maintenan ce per SOP-2. Steps 5.1.1 1
-3 are complete (Perform this prior to STP)
. STP-203-6305 is in progress commence on step 7.6.3.
SIGNIFICANT LCO STATUS None EQUIPMENT STATUS None ES-301 Transient and Event Checklist Form ES-301-5 FACILITY: RBS DATE OF EXAM: 09/
12/201 6 OPERATING TEST NO.:
NRC 301-1 A P P L I C A N T E V E N T T Y P E Scenarios 1
Tues 2
Wed 3 (Spare) 4
Thurs T O T A L M I N I M U M(*) CREW POSITION CREW POSITION CREW POSITION CREW POSITION R I U S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P R1 RX 0 1 1 0 NOR 0 1 1 1 I/C 3,4,9 3,4,7,8 7 4 4 2 MAJ 6,8 5,6 4 2 2 1 TS 0 0 2 2 R2 RX 3 1 1 1 0 NOR 1 1 1 1 1 I/C 2 4,5 8,9 5 4 4 2 MAJ 5,6 7 3 2 2 1 TS 0 0 2 2 R3 RX 2 1 1 1 0 NOR 1 1 1 1 1 I/C 3,4,7,8 3 5 4 4 2 MAJ 5,6 7 3 2 2 1 TS 0 0 2 2 I1 RX 3 1 1 1 0 NOR 1 1 1 1 1 I/C 1-4, 7,9 2 7 4 4 2 MAJ 6,8 5,6 4 2 2 1 TS 1,5 2 0 2 2 Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns
. 4. For licenses that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO
-I applicants in either the ATC or BOP position to best evaluate the SRO
-I in manipulating controls.
ES-301 Transient and Event Checklist Form ES-301-5 FACILITY:
RBS DATE OF EXAM: 09/12/2016
OPERATING TEST NO.:
NRC 301-1 A P P L I C A N T E V E N T T Y P E Scenarios 1
Tues 2
Wed 3 (Spare) 4
Thurs T O T A L M I N I M U M(*) CREW POSITION CREW POSITION CREW POSITION CREW POSITION R I U S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P I2 RX 3 2 2 1 1 0 NOR 1 1 2 1 1 1 I/C 1-4, 7,9 2 3-6, 8,9 7 4 4 2 MAJ 6,8 5,6 7 5 2 2 1 TS 1,5 2,6 4 0 2 2 U1 RX 3 1 1 1 0 N OR 1 1 1 1 1 I/C 1,2,7 2-4, 7,8 8 4 4 2 MAJ 6,8 5,6 4 2 2 1 TS 2,4 2 0 2 2 U2 RX 3 1 1 1 0 NOR 1 1 1 1 1 I/C 1,2,7 2-4, 7,8 8 4 4 2 MAJ 6,8 5,6 4 2 2 1 TS 2,4 2 0 2 2 RX 1 1 0 NOR 1 1 1 1 I/C 1-4, 8,9 3,4,8,9 2,3 4 4 2 MAJ 6,7 6,7 6,7 2 2 1 TS 2,3 0 2 2 Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions tha t provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns
. 4. For licenses that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO
-I applicants in either the ATC or BOP position to best evaluate the SRO
-I in manipulating controls.
RBS 2016-09 NRC Exam Page 1 of 2 ES-301 Competencies Checklist Form ES-301-6 Facility:
RBS Date of Examination:
0 9/12/20 1 6 Operating Test No.:
NRC 301-1 APPLICANTS RO S RO-I SRO-U 1 RO SRO-I SRO-U 2 RO 1 SRO-I SRO-U RO 2 SRO-I SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 4 1 2 4 1 2 4 1 2 4 Interpret/Diagnose Events and Conditions 1,2, 6-8 2-8 1,2, 6-8 2-8 3,4,5,6,8,9 3-8 3,4, 5,6,8,9 3,5,6,8,9, 10 Comply With and Use Procedures (1) 1,2, 6-8 2-8 1,2, 6-8 2-8 3,4, 5,6,8,9 3-8 3,4, 5,6,8,9 3,5,6,8,9, 10 Operate Control Boards (2) 1,2, 6-8 N/A 1,2, 6-8 N/A 3,4, 5,6,8,9 3-8 3,4, 5,6,8,9 3,5,6,8,9, 10 Communicate and Interact ALL ALL ALL ALL ALL ALL ALL ALL Demonstrate Supervisory Ability (3)
N/A 1-8 N/A 1-8 N/A N/A N/A N/A Comply With and Use Tech. Specs. (3) 1,5 2,4 1,5 2,4 N/A N/A N/A N/A Notes: (1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO
-U. (3) Only applicable to SROs.
Instructions:
Check the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
(This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES
-303-1 and ES-303-3.)
RBS 2016-09 NRC Exam Page 2 of 2 ES-301 Competencies Checklist Form ES-301-6 Facility:
RBS Date of Examination:
09/12/201 6 Operating Test No.: NRC 301-1 APPLICANTS RO 3 SRO-I SRO-U RO SRO-I 1 SRO-U RO SRO-I 2 SRO-U RO SRO-I SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 4 1 2 4 1 2 4 Interpret/Diagnose Events and Conditions 3-8 1,2,4,7, 8 1-9 1,2, 3,5, 6 1-9 1,2, 3,5, 6 1-10 Comply With and Use Procedures (1) 3-8 1,2,4,7, 8 1-9 1,2, 3,5, 6 1-9 1,2, 3,5, 6 1-10 Operate Control Boards (2) 3-8 1,2, 4,7, 8 N/A 1,2, 3,5, 6 N/A 1,2, 3,5, 6 N/A Communicate and Interact ALL ALL ALL ALL ALL ALL ALL Demonstrate Supervisory Ability (3)
N/A N/A 1-9 N/A 1-9 N/A 1-10 Comply With and Use Tech. Specs. (3)
N/A N/A 1,5 N/A 1,5 N/A 3,7 Notes: (1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO
-U. (3) Only applicable to SROs.
Instructions:
Check the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
(This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES
-303-1 and ES-303-3.)