ML090700228
| ML090700228 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/11/2009 |
| From: | Apger G W Operations Branch IV |
| To: | Douet J R Entergy Operations |
| References | |
| 50-416/09-301 | |
| Download: ML090700228 (265) | |
Text
Revision 0 11/13/2006 ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination:
2 March 2009 Examination Level (circle one)
RO / SRO Operating Test Number: Administrative Topic (see Note)
Type Code* Describe activity to be performed Conduct of Operations
N Perform Daily Operations Log Surveillance for SLC Operability.
GJPM-OPS-ADM04 K/A 2.1.25: 2.8
Conduct of Operations
N/A Equipment Control
N Prepare a Tagout Tags Sheet for a Protective Tag out Clearance.
GJPM-OPS-ADM01 K/A 2.2.13: 3.6
Radiation Control
M Identify Entry/Exit Requirements for accessing a High Radiation Area / Contamination Area.
GJPM-OPS-RP01 K/A 2.3.1: 2.6; 2.3.4: 2.5
Emergency Procedures/Plan
N Loss of Shutdown Cooling - Determine time to 200°F GJPM-OPS-ADM03 K/A 2.4.11 3.4 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 (D) irect from bank ( 3 for ROs; 4 for SROs & RO retakes (N) ew or (M) odified from bank ( 1) (P) revious 2 exams ( 1; randomly selected) (S) imulator
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-RP01 Revision: 0
Page: 1 of 11
Rtype:
QA Record
Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE: ADMINISTRATIVE JPM RWP Review New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES
- NA REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/14/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-RP01 Revision: 0
Page: 2 of 11 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operati on and data collection is at the discretion of the Evaluator.
- 4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam.
These activities are not required for JPMs conducted in the Simulator.
- 5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE.
Details can be found in Att. 2 of the Electrical Safety Rulebook and Gene ral Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
- 6. Obtain Shift Management's permission before opening any control panel or compartment.
Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-RP01 Revision: 0
Page: 3 of 11 RWP Review Setting: Classroom Type: RO Task: Determine requirements for entry into a High Radiation Area / Contamination Area K&A: Generic 2.3.1 - 2.6/3.0; 2.3.4 - 2.5/3.1 Safety Function: Determination of health physics requirements for space entry (ADHR Pump Room) [10CFR55.45a (9)] Time Required: 15 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): EN-RP-100 (Revision 3), EN-RP-105 (Revision 4)
Handout(s): Copy of the RWP for access to the area
- Manipulations: N/A # Critical Steps: 1 Group : N/A
Simulator Setup/Required Plant Conditions: None Safety Concerns: None Initial Condition(s): The reactor is operating at 100% power. An inspection of the ADHR Heat Exchanger is needed. You have no open wounds. A copy of the RWP for access to the area is provided.
Initiating Cue(s): Determine the health physics requirements for access to the area.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-RP01 Revision: 0
Page: 4 of 11
RWP Review Notes: 1. None Task Overview
- Determination of health physics requirements for space entry.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-RP01 Revision: 0
Page: 5 of 11 RWP Review Tasks : Critical steps are underlined, italicized, and denoted by an (*)
REFERS to procedure EN-RP-100, Section 3.0 and 5.3 for requirements: entry into a High Radiation Area and a Contamination Area.
Standard: The operator refers to the appropriate sections of the needed procedure.
Cue: Notes:
- DETERMINES the following requirements are needed for entry into a High Radiation Area (Step [17], Section 5.3, Procedure EN-RP-100).
- 1) Be briefed and sign in RWP# 20XX-1005.
- 3) Be provided with or accompanied by one or more of the following or similar as
specified in site technical specifications:
A radiation monitoring device which continuously indicates the radiation dose rate in the area; OR A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the
dose rate levels in the area have been established and personnel have been made knowledgeable of them; OR An individual qualified in Radiation Protection procedures who is equipped with a radiation dose rate monitoring device. This individual
shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the RP supervision in the Radiation Work Permit
- 4) Ensure that after entering/exiting the High Radiation Area (HRA), the HRA
barricade and posting are in place.
Standard: The operator identifies all of the entry requirements.
Cue: Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-RP01 Revision: 0
Page: 6 of 11
- DETERMINES the following requirements are needed for entry into a Contamination Area (Step [21], Section 5.3, Procedure EN-RP-100).
- 2) Sign on RWP# 20XX-1005.
- 3) Use Single PCs.
- 4) Exit at the location of the step-off pad.
- 5) Remove all protective clothing prior to exiting a contaminated area.
- 6) Perform, as a minimum, a hand-and-foot frisk, as soon as practicable upon exiting the contamination area.
- 7) Perform a whole body frisk using a whole body contamination monitor or a frisker before personnel don any clothing not worn in a contaminated area.
Standard: The operator documents 6 of the 7 entry requirements.
Cue:
Notes:
Task Standard(s)
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-RP01 Revision: 0
Page: 7 of 11 RWP Review Follow-Up Questions & Answers
Comments:
Page: 8 of 11 RWP Review Give this page to the student
Initial Condition(s): The reactor is operating at 100% power. An inspection of the ADHR Heat
Exchanger is needed. You have no open wounds. A copy of the RWP for access to the area is provided.
Initiating Cue(s): Determine the health physics requirements for access to the area.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM03 Revision: 0
Page: 1 of 7
Rtype:
QA Record
Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE: Loss of Shutdown Cooling, Time to 200°F Determination JPM New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES
- NA REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/14/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM03 Revision: 0
Page: 2 of 7 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operati on and data collection is at the discretion of the Evaluator.
- 4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam.
These activities are not required for JPMs conducted in the Simulator.
- 5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE.
Details can be found in Att. 2 of the Electrical Safety Rulebook and Gene ral Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
- 6. Obtain Shift Management's permission before opening any control panel or compartment.
Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM03 Revision: 0
Page: 3 of 7 Loss of Shutdown Cooling, Time to 200°F Setting: Classroom Type: RO Task: Interpret Time to 200°F Curves from Inadequate Decay Heat Removal ONEP, 05-1-02-III-1 K&A: 205000 A1.06- 3.7/3.7; A2.05- 3.5/3.7; Generic 2.4.11- 3.4/3.6 Safety Function: Estimation of time to reach 200°F following loss of shutdown cooling [10CFR55.45a (7)] Time Required: 15 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): 05-1-02-III-1, Section 3.3 and Attachment I Handout(s): None # Manipulations: N/A # Critical Steps: 1 Group : N/A
Simulator Setup/Required Plant Conditions: None Safety Concerns: None Initial Condition(s): The reactor was in Mode 4 with the following conditions: Reactor coolant temperature is 120°F. Reactor vessel coolant level is 24 inches below the vessel flange. RHR A is lined up and providing shutdown cooling. The reactor has been refueled recently, and the reactor vessel head has been retensioned following this. The mode of the reactor was changed to Mode 3 fifty days ago. The recirculation pumps are secured. A large leak at RHR System valve F008 is reported. Neither RHR nor ADHRS is available due to the situation. RWCU is available.
Initiating Cue(s): Determine the time available before reactor coolant temperature reaches 200°F.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM03 Revision: 0
Page: 4 of 7 Loss of Shutdown Cooling Time to 200°F Notes: 1. None Task Overview
- Estimate time to reach 200°F following loss of shutdown cooling.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM03 Revision: 0
Page: 5 of 7 Loss of Shutdown Cooling Time to 200°F
Tasks : Critical steps are underlined, italicized, and denoted by an (*)
- DETERMINES that the approximate time to boil is 3.8-4 hours.
Standard: The operator determines using procedure 05-1-02-III-1 Attachment I, Figure 3 that there are about 3.8-4 hours to 200°F .
Cue: End of task.
Notes:
Task Standard(s)
- Determine the time to 200°F in the reactor following the loss of shutdown cooling IAW
05-1-02-III-1.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM03 Revision: 0
Page: 6 of 7 Loss of Shutdown Cooling Time to 200°F Follow-Up Questions & Answers
Comments:
Page 7 of 7 Loss of Shutdown Cooling Time to 200°F Give this page to the student
Initial Condition(s): The reactor was in Mode 4 with the following conditions: Reactor coolant temperature is 120°F Reactor vessel coolant level is 24 inches below the vessel flange RHR A is lined up and providing shutdown cooling. The reactor has been refueled recently, and the reactor vessel head has been
retensioned following this. The mode of the reactor was changed to Mode 3 fifty days ago The recirculation pumps are secured. A large leak at RHR System valve F008 is reported. Neither RHR nor ADHRS is available due to the situation. RWCU is available
Initiating Cue(s): Determine the time available before reactor coolant temperature reaches 200°F.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM04 Revision: 0 Page: 1 of 20 Rtype:
QA Record Number of pages Date Initials Page 1 of 20 TRAINING PROGRAM:
OPERATOR TRAINING TITLE: ADMINISTRATIVE JPM Daily Operations Log Surveillance for SLC Operability Requirements New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES: N/A REVIEW / APPROVAL (Print Name):
TEAR Approval (TEAR # ) Prepared By: Kyle Grillis 2/14/09
- Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
- Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL) RETURNED FOR CORRECTIONS (DATE/INITIAL) RETURN RECEIPT (DATE/INITIAL) FINAL ACCEPTANCE BY RM (DATE/INITIALS)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM04 Revision: 0 Page: 2 of 20 Page 2 of 20 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs: 1) "Full open" = "red light on, green light off" 2) "Full closed" = "red light off, green light on" b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction" 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.
- 4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator. 5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE.
Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
- 6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area.
Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM04 Revision: 0 Page: 3 of 20 Page 3 of 20 Task: Daily Operations Log Surveillance for SLC Operability Requirements Setting: Classroom Type: RO Task: Determine SLC Boron Solution Operability Requirements K&A: 211000 Generic 2.1.25 - 2.8/3.1; 2.2.12 - 3.0/3.4 Safety Function: Determine operability of SLC system [10CFR55.45a (4), (13)] Time Required: 15 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): 06-OP-1000-D-0001, Daily Operations Log Handout(s): 06-OP-1000-D-0001, Daily Operations Log, Att. I, Data Sheet I (partial for items 38,39,40) # Manipulations: N/A # Critical Steps: 4 Group : N/A
Simulator Setup/Required Plant Conditions: None Safety Concerns: None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM04 Revision: 0 Page: 4 of 20 Page 4 of 20 Initial Condition(s): The plant is operating in Mode 1, 100% power, at 0830 on March 1.
Initiating Cue(s): Plant Chemistry has just completed sampling and analysis of the SLC Tank contents. You have been directed to complete Daily Operations Log surveillance, 06-OP-1000-D-0001 for SLC operability requirements with the information provided. Annotate any notifications that need to be made based on the results.
To support this, the following information is provided:
Air sparging of the SLC tank started at 0730 on March 1, and was completed at 0754 on March 1.
The Operations staff has been notified that the sample is complete.
Control Room Instrument 1C41R601 on 1H13-P601 reads 4825 gallons.
Local instrument 1C41R001 on 1H22-P011 reads 4700 gallons.
Local Transmitter 1C41-TIC-R002 indicates 90 0F after the sparging evolution.
The M&TE pyrometer used to obtain all hand held temperature readings was a Fluke model 51K, Instrument number 12345, with a calibration due date of 1 MAY 2009.
SLC Tank temperature obtained with the hand held pyrometer was 78°F.
SLC piping temperatures obtained with the hand held pyrometer were: Point A = 78°F, Point B = 80°F, Point C = 78°F, Point D = 81°F
No level alarms are in for the SLC tank.
SLC tank boron concentration was determined to be 13.8% by Plant Chemistry.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM04 Revision: 0 Page: 5 of 20 Page 5 of 20 Task: Daily Operations Log Surveillance for SLC Operability Requirements Notes: 1. None Task Overview
- Complete the Daily Operations Log surveillance 06-OP-1000-D-0001 for SLC operability requirements with the information provided. Annotate any notifications that need to be made based on the results.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM04 Revision: 0 Page: 6 of 20 Page 6 of 20 Task: Daily Operations Log Surveillance for SLC Operability Requirements Tasks : Critical steps are underlined, italicized, and denoted by an (*)
- COMPLETE item 38 of Attachment I, Data Sheet I of procedure 06-OP-1000-D-0001 (Revision 125). The operator determines SLC Tank temperature versus boron concentration meets the Technical Specification requirement.
Standard: The operator determines SLC Tank temperature versus boron concentration is in the "Normal Operation" region of TS Figure 3.1.7-2, given in the step.
Cue: Notes:
- COMPLETE item 39 of Attachment I, Data Sheet I of procedure 06-OP-1000-D-0001 (Revision 125) using the level indication from 1C41-R001 on 1H22-P011. The operator determines SLC Tank boron concentration versus volume indicated by the required instrument, 1C41R001 on 1H22-P011, does NOT meet the Technical Specification requirement.
Standard: The operator determines SLC Tank temperature versus boron concentration is in the "Unacceptable Operation" region of TS Figure 3.1.7-1, given in the step. (Even though the SLC Tank level indicator in the control room, 1C41-R601, yields an acceptable reading, it may not be used to satisfy the surveillance requirement without engineering justification.)
Cue:
Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM04 Revision: 0 Page: 7 of 20 Page 7 of 20
- COMPLETE item 40 of Attachment I, Data Sheet I of procedure 06-OP-1000-D-0001 (Revision 125). The operator determines SLC Piping temperatures versus boron concentration meets the Technical Specification requirement.
Standard: The operator determines SLC Piping temperatures versus boron concentration is in the "Normal Operation" region of TS Figure 3.1.7-2, given in the step.
Cue: None Notes:
- Immediately informs the Shift Supervisor item 39 is unacceptable.
Standard: The operator informs the Shift Supervisor Tech Spec acceptance criteria is not met for item 39.
Cue: None Notes:
Complete surveillance data package cover sheet.
Standard: The operator checks Partial procedure completed, TechSpec Acceptance Criteria Unacceptable, and All other steps acceptable and signs and dates Test performed by on the data package cover sheet.
Cue: End of JPM
Notes:
Task Standard(s)
- Complete the Daily Operations Log surveillance 06-OP-1000-D-0001 for SLC operability requirements.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EALXX Revision: 0 Page: 8 of 20 Page 8 of 20 Task: Daily Operations Log Surveillance for SLC Operability Requirements
Follow-Up Questions & Answers
Comments:
Page 9 of 20 Daily Operations Log Surveillance for SLC Operability Requirements Give this page to the student Initial Condition(s): The plant is operating in Mode 1, 100% power, at 0830 on June 1.
Initiating Cue(s): Plant Chemistry has just completed sampling and analysis of the SLC Tank contents. You have been directed to complete Daily Operations Log surveillance, 06-OP-1000-D-0001 for SLC operability requirements with the information provided. Annotate any notifications that need to be made based on the results.
To support this, the following information is provided:
Air sparging of the SLC tank was completed at 0754 on March 1.
The Operations staff has been notified that the sample is complete.
Local instrument 1C41R001 on 1H22-P011 reads 4700 gallons.
Control Room Instrument 1C41R601 on 1H13-P601 reads 4825 gallons.
Local Transmitter 1C41-TIC-R002 indicates 90 0F after the sparging evolution.
The M&TE pyrometer used to obtain all hand held temperature readings was a Fluke model 51K, Instrument number 12345, with a calibration due date of 1 MAY 2009.
SLC Tank temperature obtained with the hand held pyrometer was 78°F.
SLC piping temperatures obtained with the hand held pyrometer were: Point A = 78°F, Point B = 80°F, Point C = 78°F, Point D = 81°F
No level alarms are in for the SLC tank.
SLC tank boron concentration was determined to be 13.8% by Plant Chemistry.
GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Daily Operating Logs No.: Revision: 125 Page: 2 06-OP-1000-D-0001 Page 11 of 20
1.0 PURPOSE
1.1 To provide a method of completing surveillance requirements as required by Technical Specifications (Tech Spec), Technical Requirements Manual (TRM),
or Offsite Dose Calculation Manual (ODCM) that are daily or more frequent in nature.
1.2 Changes
required for implementation of 1994 TSIP were incorporated in Revision 100. For historical reference this statement should not be deleted. 2.0 PRECAUTIONS AND LIMITATIONS 2.1 A channel check shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
2.2 All panel numbers are prefixed by 1H13 unless otherwise designated.
2.3 The "Tech Spec" column on the data sheets is used to list not just Tech Spec surveillance requirements but is also used to list all surveillance requirements from other source documents such as TRM, ODCM, or other source documents.
3.0 REQUIRED
MATERIAL AND TEST EQUIPMENT 3.1 Hand-held temperature measuring device (Fluke 51K or equivalent instrument with minimum 2.5 deg. F accuracy to meet TS SR 3.1.7.2 and SR 3.1.7.3)
3.2 Fluke
8600A or Fluke 45 (Attachment IV only)
4.0 PREREQUISITES
AND PLANT CONDITIONS
4.1 This procedure will be performed in all Plant modes. Each item may indicate the specific Plant mode(s) applicable to that item.
5.0 INSTRUCTIONS
5.1 Each data sheet should be page checked before use. Shift Supervisor should sign Section 2.2 to ensure that the page check has been completed and all pages are included and Operations Tech Spec/TRM/ODCM required actions data entered on applicable data sheet for actions other than hourly or continuous fire watch.
5.2 Obtain
Shift Supervisor's permission to perform this procedure. Performer to record Test Start Time on Data Package Cover Sheet.
5.3 Each shift will initiate the logs to be performed during that shift by filling in the brought forward readings from the previous shift.
GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Daily Operating Logs No.: Revision: 125 Page: 3 06-OP-1000-D-0001 Page 12 of 20 NOTE The Daily Operating Log consists of: Attachment I All Mode 1, 2, 3 requirements Attachment II All Mode 4 requirements Attachment III All Mode 5 requirements Attachment IV Steam Tunnel Temperatures (Backup Method) Attachment V Mode 3 Early Drain down of UCP Attachments I, II and III contain three data sheets: Data Sheet I Mid-Shift 24-hr and 4-hr requirements Data Sheet II Day Shift 12-hr and 4-hr requirements Data Sheet III Evening Shift 12-hr and 4-hr requirements Attachment IV contains one data sheet: Data Sheet I As Required 12-hr requirements for Steam Tunnel Temperatures (Backup Method)
Attachment V contains two data sheets Data Sheet I Day Shift 12-hr requirements Data Sheet II Evening Shift 12-hr requirements 5.4 Each data sheet lists the due and late times. Applicable readings must be taken between the due and late times to ensure continuity of compliance with Technical Specifications SR 3.0.2.
5.4.1 If it is discovered that an item was not completed by its late time, then the associated component must be declared Inoperable (Inop) per Technical Specification SR 3.0.1. Alternately, Tech Spec SR 3.0.3 may be entered to allow time to perform the Surveillance. Whenever a surveillance requirement exceeds its late date, refer to 01-S-06-5, Reportable Events or Conditions.
5.4.2 Readings
should not be taken before due time to maintain proper frequency intervals.
- a. An exception may be made while preparing for a plant mode change.
5.4.3 After
initial performance of an attachment data sheet outside the due and late times, applicable data sheet must be performed again between the next scheduled due and late times to restore the required schedule.
GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Daily Operating Logs No.: Revision: 125 Page: 4 06-OP-1000-D-0001 Page 13 of 20 NOTE Example of Step 5.4: Evening shift, mode 4, Startup is scheduled to start at 1600. In addition to performing Attachment II, Data Sheet III, the shift performs Attachment I, Data Sheets I and III to meet the mode 1, 2 and 3 surveillance requirements for Startup. Attachment I, Data Sheet I must be re-performed on the next sequential Mid-shift.
When required to perform attachments outside their due and late times to meet surveillance requirements for mode changes, then performance of Data Sheets I and II (or III) of any attachment satisfies all daily surveillance requirements for that mode.
5.5 Each data sheet contains both channel check items and Tech Spec items. Identification of channel checks and Tech Spec items will be indicated in the criteria column.
5.6 A channel check shall consist of at least the following:
5.6.1 If an indicator is available:
- a. Compare with indications on similar instruments that perform and monitor the same function. (Comparison criteria will be provided in the channel check criteria block.)
- b. Compare indication to existing plant condition.
- c. If an indication has no similar instruments to compare with, then compare indication with previous readings. (Comparison criteria will be provided in the channel check criteria block.)
- d. Indication should be checked for erratic behavior (spiking, oscillations not indicative of measured parameter, etc.).
5.6.2 Trip units for the same function should be in the same state. (Either all tripped or all reset; an exception could be plant conditions in which the monitored parameter is between trip and reset points.)
5.6.3 Reset
any trip unit found in gross fail. Instrument fails channel check only if gross fail cannot be reset.
GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Daily Operating Logs No.: Revision: 125 Page: 5 06-OP-1000-D-0001 Page 14 of 20 5.7 If any item fails to meet channel check requirements of Step 5.
6, the following actions must be taken:
NOTE Failure to meet the channel check requirements does not automatically make an instrument Inop, but serves only as the initiation point at which an investigation should begin to determine if there is something wrong with the instrument.
5.7.1 Notify
Shift Supervisor immediately.
5.7.2 Shift
Supervisor will initiate an immediate investigation to determine cause for not meeting the channel check requirements.
5.7.3 The item will be circled and a note placed in the "Comments" section explaining what form of investigation was performed and its results. (Even if no reason is found for the item not meeting the channel check requirement, a note stating "No Reason Found. Reading Returned to Normal" should be made.)
5.7.4 The investigation shall include at least the following:
- a. A check of plant parameters which could cause the suspected indication
- b. A determination of instrument operability
5.7.5 If at any time during the investigation an instrument is determined to be Inop, then declare that instrument Inop and take any required Tech Spec action.
5.7.6 If the investigation is continued past shift change, it shall be included in the shift turnover, and a note describing results of the item's investigation placed in the new shift log's "Comments" section.
5.7.7 If two sequential channel checks for an item fail to meet the channel check requirements and the investigation has not revealed the reason by the late time of the second channel check, then initiate a CR on the affected instrument per Reference 6.2 and describe the channel check criteria and that the instrument has failed two successive channel checks.
5.8 All Tech Spec items will have their Acceptance Criteria provided in the Tech Spec Criteria block.
5.9 If any item fails to meet its Tech Spec Acceptance Criteria, the following actions must be taken:
5.9.1 Refer
to the referenced Tech Spec for any required action.
5.9.2 Circle
the reading and place a note in the "Comments" section to indicate LCO number or why an LCO was not written.
Deleted: 5 GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Daily Operating Logs No.: Revision: 125 Page: 5 06-OP-1000-D-0001 Page 15 of 20 5.9.3 If any area temperature exceeds Tech Spec limits, initiate a CR, in addition to other deficiency documents, to investigate equipment qualification.
GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Daily Operating Logs No.: Revision: 125 Page: 6 06-OP-1000-D-0001 Page 15 of 20 5.10 The Mid-shift will route the previous day's logs to the Operations Surveillance Coordinator after recording the brought forward readings.
5.11 If the plant unexpectedly changes modes during a shift before all the surveillances have been completed, note in the "Comments" section why the readings are incomplete and list the applicable attachment data sheet performed for the new mode.
5.12 A licensed operator must review and sign the applicable data sheet each shift.
5.13 If temporary M&TE is required to obtain a reading, such as room temperature, CTMT pool temperature, etc., record M&TE number and Cal Due Date on respective page in "Comments" section.
5.14 Perform Attachment IV when the computer is unavailable to obtain Containment and/or Auxiliary Building Steam Tunnel Temperatures. Once temperature is determined per Attachment IV, then record temperature(s) on applicable data sheets.
5.15 Notify Shift Supervisor upon completion of applicable data sheet. Shift Supervisor's signature is required on Data Package Cover Sheet.
6.0 REFERENCES
6.1 GGNS Technical Specifications 6.2 NMM EN-LI-102, Corrective Action Process
6.3 IPC 90/1324
6.4 MNCR 0298-89 6.5 MNCR 0072-91
6.6 IR 91-01-01 (01-S-06-5 Attachment II Corrective Action)
6.7 QDR 0203-92 6.8 MNCR 0048-93
6.9 QDR 0062-93
6.10 GGNS Technical Requirements Manual
6.11 Administrative Procedure 01-S-06-5, Reportable Events or Conditions.
6.12 GIN 96-02158 D/G Room Temp 120 F 6.13 GIN 96-01203 RPV Flange 50 psig 6.14 MNCR 0291-95, CTMT/DW Exh Vent Rad Monitor Channel A Criteria Extension 6.15 DCP 91/0113 6.16 DCP 88/0249 6.17 GGCR 1998-0850-00 Deleted: ¶ GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Daily Operating Logs No.: Revision: 125 Page: 7 06-OP-1000-D-0001 Page 16 of 20 6.18 ER 98/0550 6.19 CR 1999-1957 6.20 ER 99/0545 6.21 CR 2001-1951 6.22 CR 2001-1952 6.23 ER 1996-0086 6.24 ER 2001-0259 6.25 ER 1996-0086 6.26 CR 2002-2321 6.27 CR 2003-3725 6.28 CR 2003-3225 6.29 ER 2001-0190 6.30 ER 1999-0217
6.31 CR 2006-1662
6.32 LDC 2003-037
6.33 LDC 2005-022 6.34 GGNS Offsite Dose Calculation Manual 6.35 EC-0433
6.36 CR 2007-04123
Page 17 of 20 GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE X QA RECORD 06-OP-1000-D-0001 Revision: 125 NON-QA RECORD INITIALS Attachment I Page 1 of 84 NUMBER OF PAGES DATE RELATED DOCUMENT Model WO # 50290153 NUMBER = XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Daily Operating Logs Data Sheet I (Mid-shift) Modes 1, 2, and 3 Technical Specifications: As listed on data sheets
1.0 IMPACT
STATEMENT
1.1 There
should be no impact on plant operations during the performance of this test. The procedure gathers data and verifies instrument operability as required by various Tech Specs.
2.0 PROCEDURE
2.1 Plant
Mode is (circle one): 1 2 3
2.2 Procedure
page checked Performer (Effective Pages 1-21)
2.3 Test Start Time / /
Performer Date / Time
2.4 Radiation
Protection Review N/A RWP # N/A
3.0 TEST RESULTS
3.1 Test Completion: (Check one in each category)
Entire procedure completed [ ] Partial procedure completed [ ] Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable [ ] All other steps/data Acceptable [ ] Unacceptable [ ]
3.2 Comments
3.3 Test performed by: Date/Time /
3.4 Reviewed
by Licensed Operator
4.0 DEFICIENCIES
CR Issued #
LCO Entered # WR Issued #
5.0 APPROVAL
All appropriate deficiency documents are initiated for any Unacceptable Item. Yes [ ] N/A [ ]
Shift Supv/Manager Date
Comments:
CONCURRENCE
Operations Management Date
GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1000-D-Revision: 125 Attachment I Page 18 of 84 Page XRef DATA SHEET I (Continued)
DAILY OPERATING LOGS 24-HR REQUIREMENTS DUE 2000 LATE 0200 SAFETY RELATED Page 18 of 20 INST/PARAMETER TECH SPEC INDICATION CRITERIA 38. HAND HELD TEMP SR 3.1.7.2 INST # _____________ TECH SPEC MEASURING (Fluke 51K or equivalent with MIN: 75°F DEVICE accuracy of 2.5 deg. F) MAX: 125°F CAL DUE DATE __________
TECH SPEC SAT TRIGGER TEMP ______°F UNSAT ________ IF < 75°F ENTER LCO SLC TANK SR 3.1.7.5 3.1.7 IN MODES 1 & 2. TEMPERATURE CONCENTRATION ______ % WHEN TEMPERATURE IS RESTORED TO 75 F, NOTIFY CHEMISTRY TO (From Chemistry Dept) PERFORM TS SR 3.1.7.5 WITHIN 24 HOURS. /
WHO NOTIFIED TIME NOTIFIED BY
Comments:
GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1000-D-Revision: 125 Attachment I Page 19 of 84 Page XRef DATA SHEET I (Continued)
DAILY OPERATING LOGS 24-HR REQUIREMENTS DUE 2000 LATE 0200 SAFETY RELATED Page 19 of 20 INST/PARAMETER TECH SPEC INDICATION CRITERIA 39. C41-LI-R001 SR 3.1.7.1 H22-P011 TECH SPEC AVAILABLE VOLUME SLC VOLUME WITHIN THE LIMITS OF FIGURE 3.1.7-1. IND VOL _______ GAL IF CONC > 15.2% Plot Volume BY WEIGHT, ENTER CONCENTRATION ________ % TS 3.1.7. (From Chemistry Dept) IND VOL < 5088 GAL
Comments:
GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1000-D-Revision: 125 Attachment I Page 20 of 84 Page XRef DATA SHEET I (Continued)
DAILY OPERATING LOGS 24-HR REQUIREMENTS DUE 2000 LATE 0200 SAFETY RELATED Page 20 of 20 INST/PARAMETER TECH SPEC INDICATION CRITERIA 40. HAND HELD TEMP SR 3.1.7.3 TEMP (all in °F) TECH SPEC MEASURING DEVICE A_____ B_____ C_____ D_____ MIN: 75°F PIPE HEAT TRACE TECH SPEC INST # ____________
MAX: 125°F TRIGGER (Fluke 51K or equivalent with SR 3.1.7.9 accuracy of 2.5 deg. F) IF TEMP < 75°F CAL DUE DATE ENTER LCO 3.1.7 CONCENTRATION % IN MODES 1 & 2. (From Chemistry Dept) PERFORM SR 3.1.7.9 WITHIN 24 HRS HEAT TRACE POWER AECM 90/0012 "POWER AVAILABLE" LIGHT LIT AFTER TEMPERATURE IS P110A: YES / NO RESTORED TO 75F. P110B: YES / NO POWER AVAIL TO ONE DIVISION OF HEAT TRACE Comments:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM01 Revision: 0
Page: 1 of 15
Rtype:
QA Record
Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE: ADMINISTRATIVE JPM Standby Diesel Generator Starting Air System Desiccant Changeout Tagout New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES
- N/A REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/14/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM01 Revision: 0
Page: 2 of 15 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operati on and data collection is at the discretion of the Evaluator.
- 4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam.
These activities are not required for JPMs conducted in the Simulator.
- 5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE.
Details can be found in Att. 2 of the Electrical Safety Rulebook and Gene ral Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
- 6. Obtain Shift Management's permission before opening any control panel or compartment.
Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM01 Revision: 0
Page: 3 of 15 Task: Standby Diesel Generator Starting Air System Desiccant Changeout Tagout Setting: Classroom Type: RO Task: Perform Preparer responsibilities for Protective Clearance Preparation K&A: 264000 Generic 2.2.13 - 3.6/3.8 Safety Function: 6 Time Required: 15 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): EN-OP-102, EN-OP-102-1, Drawings M1070A; E1110-25,26,33; E0658-13 Handout(s): Completed Work Impact Statement, partially completed Tagout Request Form, completed Tagout Cover Sheet, Blank copy of
Tagout Tags Sheet, Dwgs M1070A; E1110-25,26,33; E0658-13
- Manipulations: N/A # Critical Steps: 1 Group : N/A Simulator Setup/Required Plant Conditions: None Safety Concerns: None Initial Condition(s): The plant is operating in Mode 1, 100% power.
The next sequential tag serial number is "01".
Initiating Cue(s): You have been directed to prepare a tag out in preparation for the changeout of desiccant
in the Standby Diesel Generator 11 backup St arting Air Dryer. Use the drawings and forms provided.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM01 Revision: 0
Page: 4 of 15 Task: Standby Diesel Generator Starting Air System Desiccant Changeout Tagout Notes: 1. None Task Overview
- Prepare a tag out in preparation for the changeout of desiccant in the Standby Diesel Generator 11 backup Starting Air Dryer.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM01 Revision: 0
Page: 5 of 15 Task: Standby Diesel Generator Starting Air System Desiccant Changeout Tagout
Tasks : Critical steps are underlined, italicized, and denoted by an (*)
- COMPLETE Attachment 9.3 of procedure EN-OP-102-01, documenting the required components and their required positions for the tagout. (Tagging sequence and tag type are not critical.)
Standard: The operator prepares the Attachment as indicated on the attached key by an asterisk (*) in the tag serial number field.
Cue:
Notes: See attached Evaluator Key Task Standard(s)
- Correctly prepare a Tagout Tags Sheet (EN-OP-102 Attachment 9.3) in preparation for the changeout of desiccant in the Standby Diesel Generator 11 IAW EN-OP-102.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM01 Revision: 0
Page: 6 of 15 Task: Standby Diesel Generator Starting Air System Desiccant Changeout Tagout Follow-Up Questions & Answers
Comments:
DO NOT GIVE THIS PAGE TO THE STUDENT N ON-Q UALITY R ELATED EN-OP-102-01 REV. 4 NUCLEAR MANAGEMENT
MANUAL I NFORMATIONAL U SE PAGE 7 OF 24 Protective and Caution Tagging Forms & Checklist Page 7 of 15 A TTACHMENT 9.3 T AGOUT T AGS S HEET C LEARANCE: ___MANUAL___________
TAGOUT: ________________
Tag Serial No. Tag Type Equipment Equipment Description
Equipment Location Place. Seq. Placement Configuration Place. 1st Verif Date/Time Place. 2nd Verif Date/Time Rest. Seq. Restoration Configuration Rest. 1st Verif Date/Time Rest. 2nd Verif Date/Time Placement/R emoval Tag Notes XXX1 Danger 52-1L113-7 Lighting Panel Breaker to Battery Charger for DG11 Diesel Driven Air
Compressor 1P75C013A D SL-133 1 OFF XXX2 Danger 1P75M026A Handswitch for Starting Air Dryer #2 and Aftercooler D012A B013A D SL-133 1 OFF XXX3
- Danger Battery Positive (+) Lea d D G11 Diesel Driven Air Compressor 1P75C013A Battery D SL-133 2 Lifted XXX4
- Danger Battery Negative (-) Lead D G11 Diesel Driven Air Compressor 1P75C013A Battery D SL-133 2 Lifted XXX5
- Danger 1P75F177A Starting Air Storage Tank 1P75A001A Inlet Valve D SL-133 3 Closed DO NOT GIVE THIS PAGE TO THE STUDENT N ON-Q UALITY R ELATED EN-OP-102-01 REV. 4 NUCLEAR MANAGEMENT
MANUAL I NFORMATIONAL U SE PAGE 7 OF 24 Protective and Caution Tagging Forms & Checklist Page 8 of 15 Tag Serial No. Tag Type Equipment Equipment Description
Equipment Location Place. Seq. Placement Configuration Place. 1st Verif Date/Time Place. 2nd Verif Date/Time Rest. Seq. Restoration Configuration Rest. 1st Verif Date/Time Rest. 2nd Verif Date/Time Placement/R emoval Tag Notes XXX6 Danger 1P75F176A U nloader Isolation Valve for 1P75C013A D SL-133 3 Closed XXX7
- Danger 52-111342 Breaker to DG11 Diesel Driven Air Compressor Aftercooler 1P75B013A D SL-133 4 Off XXX8
- Danger 52-1P11314 Power Panel Breaker to DG11 Starting Air Dryer #2 1P75D012A D SL-133 4 Off A TTACHMENT 9.3 T AGOUT T AGS S HEET XXX9
- Danger 1P75FX252A Starting Air Dryer D012A Test Connection D SL-133 4 Open XX10 Danger 1P75C013A Starter switch for DG11 Diesel Drive n A ir Compressor 1P75C013A D SL-133 1 Position 0 C LEARANCE: ___MANUAL___________
TAGOUT: ________________
Page 9 of 15 Standby Diesel Generator Starting Air System Desiccant Changeout Tagout Give this page to the student Initial Condition(s): The plant is operating in Mode 1, 100% power.
The next sequential tag serial number is "01".
Initiating Cue(s): You have been directed to prepare a tag out in preparation for the changeout of desiccant
in the Standby Diesel Generator 11 backup St arting Air Dryer. Use the drawings and forms provided.
N ON-Q UALITY R ELATED EN-OP-102-01 REV. 4 NUCLEAR MANAGEMENT MANUAL I NFORMATIONAL U SE PAGE 6 OF 24 Protective and Caution Tagging Forms & Checklist Page 10 of 15 A TTACHMENT 9.2 T AGOUT C OVER S HEET Clearance: __MANUAL____________ Tagout: _____________________
Component to be worked:
P75-AIRDRY-1P75D012A STANDBY DIESEL START AIR DRYER DSL-133 -1D310
==
Description:==
ISOLATE 1P75D012A IN ORDER TO REPLACE DESSICANT
Placement Inst:
This tagout will isolate and de-ernergize Div 1 Diesel Driven Air Compressor 1P75C013A.
References:
M1070A; E1110-25,26,33; E0658-13
Hazards:
NONE Restoration Inst:
Post-maintenance testing and recovery method required; maintenance leak test requires running the diesel driven air compressor to pressurize the air dryer.
Attribute Description Attribute Value High Energy System Concerns NO Tech Spec Impact? Enter EOS# or None N/A Compensatory Actions Req?
NO Locked Components?
NO Fire Protection Impairment?
NO Equip Drain / Vent rig required?
NO Scaffold Required?
NO Is an LCO start time required?
NO Tech Spec Impact on System Restoration?
NO Component Deviation Required?
NO 50.59 Screening Attached N/A Crew Assigned Walk down Yes Walk down complete?
Reason this tag was created?
Scheduled work Tagout prepare issues:
No issues Work Order Number Description XXXXXX REPLACE DESSICANT IN 1P75D012A Status Description User Verification Date Prepared Prepared Technical Reviewed Reviewed Approved Approved Tags Verified Hung Tags Verified Hung Removal Approved Removal Approved Tags Verified Removed Tags Verified Removed
Give this page to the student N ON-Q UALITY R ELATED EN-OP-102-01 REV. 4 NUCLEAR MANAGEMENT
MANUAL I NFORMATIONAL U SE PAGE 7 OF 24 Protective and Caution Tagging Forms & Checklist Page 11 of 15 A TTACHMENT 9.3 T AGOUT T AGS S HEET C LEARANCE: ___MANUAL___________
TAGOUT: ________________
Tag Serial No. Tag Type Equipment Equipment Description
Equipment Location Place. Seq. Placement Configuration Place. 1st Verif Date/Time Place. 2nd Verif Date/Time Rest. Seq. Restoration Configuration Rest. 1st Verif Date/Time Rest. 2nd Verif Date/Time Placement/R emoval Tag Notes
Give this page to the student N ON-Q UALITY R ELATED EN-OP-102-01 REV. 4 NUCLEAR MANAGEMENT
MANUAL I NFORMATIONAL U SE PAGE 7 OF 24 Protective and Caution Tagging Forms & Checklist Page 12 of 15 A TTACHMENT 9.3 T AGOUT T AGS S HEET C LEARANCE: ___MANUAL___________
TAGOUT: ________________
Tag Serial No. Tag Type Equipment Equipment Description
Equipment Location Place. Seq. Placement Configuration Place. 1st Verif Date/Time Place. 2nd Verif Date/Time Rest. Seq. Restoration Configuration Rest. 1st Verif Date/Time Rest. 2nd Verif Date/Time Placement/R emoval Tag Notes
Give this page to the student QUALITY RELATED EN-WM-105 REV.0 NUCLEAR MANAGEMENT
MANUAL INFORMATIONAL USE PAGE xx OF 48 ATTACHMENT 9.2 IMPACT TEMPLATE Sheet 1 of 1
____________________/___________
____________________/___________
PLANNER DATE REVIEWER DAT E WORK SCOPE:
Replace desiccant in Div I DG Diesel Driv en Air Compressor Starting Air Dryer 1P75D012A.
COMPONENT MODE: ( ) INSV ( X )OOSV ( ) AVAILABLE
PLANT MODES & CONDITIONS:
Plant may be in any condition. Starting Air Dryer and associated Diesel Driven Air Compressor must be secured and isolated. Starting Air Dr yer 1P75D012A must be depressurized.
EFFECTS ON ASSOCIATED SYSTEM AND COMPONENTS:
DG11 Diesel Driven Air Compressor will be out of se rvice. The Motor Driven Air Compressor will be available to maintain DG11 Starting Air Storage Tanks pressurized.
PRE-MAINTENANCE ACTIVITIES:
None POST-MAINTENANCE ACTIVITIES:
None DOES THE ACTIVITY HAVE THE POTENTIAL TO SCRAM/TRIP THE PLANT: ( ) YES ( X ) NO
SECURITY/FIRE/CONTROL ROOM ENVELOPE BARRIER BREACH: ( ) YES ( X ) NO
RPS AFFECTED: ( ) YES ( X ) NO
ESF/EFSAS AFFECTED: ( ) YES ( X ) NO
ALARMS/COMPUTER POINTS AFFECTED (IF YES, LIST ON ATTACHED SHEET) ( ) YES ( X ) NO Page 13 of 15 Give this page to the student Page 14 of 15 QUALITY RELATED EN-WM-105 REV.4 NUCLEAR MANAGEMENT
MANUAL INFORMATIONAL USE PAGE xx OF 48 ATTACHMENT 9.3 OPERATIONAL IMPACT TEMPLATE Sheet 1 of 1
OPERATIONAL IMPACT
____________________/___________
____________________/___________
SRO DATE REVIEWER D ATE TECHNICAL SPECIFICATIONS:
NONE LIMITING CONDITIONS FOR OPERATIONS:
NONE REACTIVITY IMPACT (REQUIRED):
NONE POTENTIAL SYSTEM/COMPONENT EFFECTS:
This work only affects DG11 Diesel Driven Air Compressor subsystem. The Motor Driven Air Compressor will be available to maintain DG11 Starting Air Storage Tanks pressurized.
ACTUAL OR POTENTIAL MEASURE OR CONTINGENCY ACTION REQUIRED:
If the DG11 Motor Driven Air Compressor fails to function, a low starting air pressure will result in a DG11 Trouble alarm in the main control room. The asso ciated ARIs contain the necessary contingencies for that condition.
Give this page to the student N ON-QUALITY RELATED EN-OP-102-01 REV. 4 NUCLEAR MANAGEMENT
MANUAL INFORMATIONAL U SE PAGE 14 OF 24 Protective and Caution Tagging Forms & Checklist Page 15 of 15 ATTACHMENT 9.10 TAGOUT REQUEST Tagout Request Instructions The Tagging Requestor is responsible for providing detailed information on the work scope/condition and should recommend boundaries to provide for equipment and personnel
safety. Work Order #
Task # Mark # Requester Ext. / Pager 999999 1 Smith 555 1. Provide a detailed description of the maintenance activity and the reference drawing numbers:
Replace desiccant in Div I DG Diesel Driv en Air Compressor Starting Air Dryer 1P75D012A.
P&ID M1070A
- 2. If known, provide a previous Clearance/Tagout number which provides the required protection:
Fluid systems: Yes No Valve Work Back Seat Yes No MOV Open Closed Air- Water- Steam- Oil- Test & Maintenance Tag 3. Fluid Components To Be Tagged and Required Position:
Isolation Valves (Any Gags, Brakes, or Flanges required):
Drain/Vent Valves:
Special Instructions: Need system depressurized to change the desiccant 4. Electrical Components To Be Tagged and Required Position: Yes No Control Switches:
Breakers:
Tag on Breaker Tag to be moved to Door
Fuses/Leads to Pulled/Lifted:
Grounds/Ground Locations:
Special Instructions: Maintenance leak test required after desiccant is replaced.
ES-301 Administrative Topi cs Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination:
2 March 2009 Examination Level (circle one) RO /
SRO Operating Test Number:
Administrative Topic (see Note)
Type Code* Describe activity to be performed Conduct of Operations
N Perform SRO review of the Daily Jet Pump Surveillance.
GJPM-SRO-ADM01 K/A 2.1.33: 4.0
Conduct of Operations
M Review the Plant Chemistry Report and determine any required actions GJPM-SRO-ADM03 K/A 2.1.25: 3.1; 2.1.34: 2.9
Equipment Control
N Perform Tag Reviewer re view of Protective Tag out Clearance.
GJPM-OPS-ADM02 K/A 2.2.13: 3.8
Radiation Control
M Review Liquid Radwaste Discharge Permit.
GJPM-SRO-ADM02 K/A 2.3.6: 3.1
Emergency Procedures/Plan
M Given plant conditions, determine entry into the Site Emergency Plan and complete the initial notification form. ATWS GJPM-OPS-EAL25 K/A 2.4.41: 4.1; 2.4.38:
4.0; 2.4.40: 4.0 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 (D) irect from bank ( 3 for ROs; 4 for SROs & RO retakes (N) ew or (M) odified from bank ( 1) (P) revious 2 exams ( 1; randomly selected) (S) imulator Revision 0 11/13/2006 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EAL25 Revision: 0
Page: 1 of 9
Rtype:
QA Record
Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE: EMERGENCY EVENT CLASSIFICATION JPM ATWS New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES
- NA REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/14/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EAL25 Revision: 0
Page: 2 of 9 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operati on and data collection is at the discretion of the Evaluator.
- 4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam.
These activities are not required for JPMs conducted in the Simulator.
- 5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE.
Details can be found in Att. 2 of the Electrical Safety Rulebook and Gene ral Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
- 6. Obtain Shift Management's permission before opening any control panel or compartment.
Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EAL25 Revision: 0
Page: 3 of 9 Task : EMERGENCY EVENT CLASSIFICATION Setting: Simulator Type: SRO Task: SRO-A&E-015 K&A: 2.4.41 - 2.3/4.1; 2.4.38: 2.2/4.0; 2.4.40: 2.3/4.0 Safety Function: Emergency event classification for SROs [10CFR55.45a (11)] Time Required: 15 minutes Time Critical: YES Faulted: No Performance: Actual Reference(s): 10-S-01-1, Activation of the Emergency Plan; 10-S-01-6, Notification of offsite Agencies and Plant On-Call Emergency Personnel
Handout(s): None # Manipulations: N/A # Critical Steps: 2 Group : N/A Simulator Setup/Required Plant Conditions: None Safety Concerns: None Initial Condition(s): All the initial conditions for this JPM are identical to the scenario you just participated in.
Initiating Cue(s): Based on the scenario you just participated in:
Seal Steam Pressure Controller failure. RPS MG Set B trip. Reactor Recirc Flow Control Valve A failing open. Bus 16AB lockout. ATWS Classify the event and complete section 3, 4, and 6 of the attached Emergency Plan Notification Form, EPP-06-01.
This is a time critical JPM.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EAL25 Revision: 0
Page: 4 of 9 Task : EMERGENCY EVENT CLASSIFICATION Notes: 1. None Task Overview
- Event classification JPM in accordance with the Emergency Preparedness Plan.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EAL25 Revision: 0
Page: 5 of 9 Task : EMERGENCY EVENT CLASSIFICATION
Tasks : Critical steps are underlined, italicized, and denoted by an (*)
- Classify the event as a SITE AREA EMERGENCY Standard: Candidate reviews 10-S-01-1 Att. I and classifies the event as EAL SS3. Cue: Notes:
- Complete an Emergency Notification Form as the SRO for the event.
Standard: Candidate correctly completes sections 3, 4, and 6 of an Emergency Notification Form per 10-S-01-6.
Cue:
Notes: See attached evaluator key.
Task Standard(s)
- Within 15 minutes, classifies the event as an SITE AREA EMERGENCY in accordance with EAL SS3 . Then , c orrectly completes the attached Emergency Plan Notification Form, EPP-06-01.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EAL25 Revision: 0
Page: 6 of 9 Task : EMERGENCY EVENT CLASSIFICATION Follow-Up Questions & Answers
Comments:
REV. 17 (08/08) JPM Page 7 of 9 EMERGENCY NOTIFICATION FORM
- 1. THIS IS GRAND GULF NUCLEAR STATION WITH MESSAGE NUMBER
- 2. A. TIME DATE B. COMMUNICATOR: C. TEL NO. 601-437-KEY - Do NOT Give to Student
- 3. EMERGENCY CLASSIFICATION:
A. NOTIFICATION OF UNUSUAL EVENT C. SITE AREA EMERGENCY E. TERMINATED B. ALERT D. GENERAL EMERGENCY
- 4. CURRENT EMERGENCY CLASSIFICATION DECLARATION TIME: DATE: TERMINATION TIME: DATE: 5. RECOMMENDED PROTECTIVE ACTIONS:
A. No Protective Actions Recommended At This Time (Go to item 6).
B. EVACUATE ALL sectors to 2 miles. EVACUATE sectors to 5 miles.
SHELTER the remainder of the 10 mile EPZ with the exception of areas previously recommended for evacuation.
OR EVACUATE ALL sectors to 2 miles. EVACUATE sectors to 10 miles.
SHELTER the remainder of the 10 mile EPZ with the exception of areas previously recommended for evacuation.
OR Shelter ___________________________________________________________
C. Consider prophylactic use of Potassium Iodide in accordance with State Plans.
- 6. INCIDENT DESCRIPTION/UPDATE/COMMENTS/EAL#:
Failure of the reactor protection system to shut dow n the reactor and manual reactor shutdown was not successful. Reactor power > 4%. / SS3
- 7. REACTOR SHUTDOWN?
NO YES TIME: DATE:
- 8. METEROLOGICAL DATA
- NOT AVAILABLE AT THIS TIME (Go to item 9)
A. WIND DIRECTION FROM Degrees at MPH B. SECTORS AFFECTED (A-R) C. STABILITY CLASS (A-G)
D. PRECIPITATION: None Rain Sleet Snow Hail Other 9. RELEASE INFORMATION
- A. NO RELEASE (Go to item 13)
B. A RELEASE is occurring BELOW federally approved operating limits. (Go to item 9E)
C. A RELEASE is occurring ABOVE federally approved operating limits. (Go to item 9E)
D. A RELEASE OCCURRED BUT STOPPED (Go to item Go to item 9E)
E. Release started at _________ (time)
Release stopped at __________ (time) Re lease Duration ________hrs (Actual o r Expected)
- 10. TYPE OF RELEASE:
A. Radioactive Gases B. Radioactive Airborne Particulates C. Radioactive Liquids (Go to item 13)
- 11. RELEASE RATE: A. NOBLE GASES Ci/s B. IODINES Ci/s
- 12. ESTIMATE OF PROJECTED OFF-SITE DOSE
- A. Projections for hours based on: Field Data Plant Data
B. TEDE - WB DOSE COMMITMENT(mRem) C. CDE - THYROID DOSE COMMITMENT (mRem)
Site Boundary 5 miles Site Boundary 5 miles
2 miles 10 miles 2 miles 10 miles Student enters current time
and date 13. MESSAGE APPROVED BY: TITLE: EMERGENCY DIRECTOR OFFSITE EMERGENCY COORDINATOR Return to communicator instructions line J Reviewed Sections (3,4,6) Sections(5,7,8,9,10,11,12) TSC Coord/
EOF Admin Dir RPM/REMInit Init PAR Chan ge Time EPP 06-01 REV. 17 (08/08) JPM Page 8 of 9 Give this page to the student
Initial Condition(s): All the initial conditions for this JPM are identical to the scenario you just participated in.
Initiating Cue(s): Based on the scenario you just participated in:
Seal Steam Pressure Controller failure. RPS MG Set B trip. Reactor Recirc Flow Control Valve A failing open. Bus 16AB lockout. ATWS Classify the event and complete section 3, 4, and 6 of the attached Emergency Plan Notification Form, EPP-06-01.
This is a time critical JPM.
REV. 17 (08/08) JPM Page 9 of 9 EMERGENCY NOTIFICATION FORM
- 4. THIS IS GRAND GULF NUCLEAR STATION WITH MESSAGE NUMBER
- 5. A. TIME DATE B. COMMUNICATOR: C. TEL NO. 601-437-
- 6. EMERGENCY CLASSIFICATION:
A. NOTIFICATION OF UNUSUAL EVENT C. SITE AREA EMERGENCY E. TERMINATED B. ALERT D. GENERAL EMERGENCY
- 4. CURRENT EMERGENCY CLASSIFICATION DECLARATION TIME: DATE: TERMINATION TIME: DATE: 6. RECOMMENDED PROTECTIVE ACTIONS:
D. No Protective Actions Recommended At This Time (Go to item 6).
E. EVACUATE ALL sectors to 2 miles. EVACUATE sectors to 5 miles.
SHELTER the remainder of the 10 mile EPZ with the exception of areas previously recommended for evacuation.
OR EVACUATE ALL sectors to 2 miles. EVACUATE sectors to 10 miles.
SHELTER the remainder of the 10 mile EPZ with the exception of areas previously recommended for evacuation.
OR Shelter ___________________________________________________________
F. Consider prophylactic use of Potassium Iodide in accordance with State Plans.
- 6. INCIDENT DESCRIPTION/UPDATE/COMMENTS/EAL#:
- 7. REACTOR SHUTDOWN?
NO YES TIME: DATE:
- 8. METEROLOGICAL DATA
- NOT AVAILABLE AT THIS TIME (Go to item 9)
A. WIND DIRECTION FROM Degrees at MPH B. SECTORS AFFECTED (A-R) C. STABILITY CLASS (A-G)
D. PRECIPITATION: None Rain Sleet Snow Hail Other 9. RELEASE INFORMATION
- A. NO RELEASE (Go to item 13)
B. A RELEASE is occurring BELOW federally approved operating limits. (Go to item 9E)
C. A RELEASE is occurring ABOVE federally approved operating limits. (Go to item 9E)
D. A RELEASE OCCURRED BUT STOPPED (Go to item Go to item 9E)
E. Release started at _________ (time)
Release stopped at __________ (time) Re lease Duration ________hrs (Actual o r Expected)
- 10. TYPE OF RELEASE:
A. Radioactive Gases B. Radioactive Airborne Particulates C. Radioactive Liquids (Go to item 13)
- 11. RELEASE RATE: A. NOBLE GASES Ci/s B. IODINES Ci/s
- 12. ESTIMATE OF PROJECTED OFF-SITE DOSE
- A. Projections for hours based on: Field Data Plant Data
B. TEDE - WB DOSE COMMITMENT(mRem) C. CDE - THYROID DOSE COMMITMENT (mRem)
Site Boundary 5 miles Site Boundary 5 miles
2 miles 10 miles 2 miles 10 miles
- 13. MESSAGE APPROVED BY: TITLE: EMERGENCY DIRECTOR OFFSITE EMERGENCY COORDINATOR Return to communicator instructions line J
EPP 06-01 Reviewed Sections (3,4,6) Sections(5,7,8,9,10,11,12) TSC Coord/
EOF Admin Dir RPM/REMInit Init PAR Chan ge Time ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM01 Revision: 0
Page: 1 of 12
Rtype:
QA Record
Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE: ADMINISTRATIVE JPM Daily Jet Pump Surveillance Review New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES
- N/A REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/14/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADMXX Revision: 0
Page: 2 of 12 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operati on and data collection is at the discretion of the Evaluator.
- 4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam.
These activities are not required for JPMs conducted in the Simulator.
- 5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE.
Details can be found in Att. 2 of the Electrical Safety Rulebook and Gene ral Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
- 6. Obtain Shift Management's permission before opening any control panel or compartment.
Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADMXX Revision: 0
Page: 3 of 12 Task: Daily Jet Pump Surveillance Review Setting: Classroom Type: SRO Task: Perform SRO responsibilities for a Daily Jet Pump Surveillance review K&A: 202001 Generic 2.2.12 - 3.0/3.4; 2.1.33 - 3.4/4.0 Safety Function
- 1 Time Required: 15 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): 06-RE-1B33-D-0001 Handout(s): Copy of Data Sheet I and II from procedure 06-RE-1B33-D-0001 documenting the results of the surveillance
- Manipulations: N/A # Critical Steps: 4 Group : N/A
Simulator Setup/Required Plant Conditions: None Safety Concerns: None Initial Condition(s): The plant is operating in Mode 1, 100% power.
Initiating Cue(s): Reactor engineering has just completed the attached jet pump surveillance, 06-RE-1B33-D-0001. You are to review the surveillance and determine if any operability criteria is not met and complete section 5.0 of the attached surveillance.
Note: You can assume all mathematical calculations have been performed correctly.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADMXX Revision: 0
Page: 4 of 12 Task: Jet Pump Surveillance Review Notes: 1. None Task Overview
- Review the results from the daily jet pump surveillance. Annotate any changes needed on the form itself. Document if any notifications need to be made based on the results at the end of the forms.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADMXX Revision: 0
Page: 5 of 12 Task: Jet Pump Surveillance Review Tasks : Critical steps are underlined, italicized, and denoted by an (*)
FINDS that "Flow" is not circled for Step 5.1.2a, although it is initialed and is indicated by the information provided elsewhere in the form.
Standard: The applicant marks that "Flow" should be circled for Step 5.1.2a on Data Sheet I.
Cue:
Notes:
- Determines Jet Pump 5 does not meet the criterion for individual jet pump flow being within 10% of its normal.
Standard: The applicant finds Jet Pump 5 Flow deviation recorded in step 5.1.3c is greater than 10% of its normal and therefore does not meet the criteria of step 5.1.4a(1).
Cue:
Notes:
- Determines the Core Flow criteria are not met for not being within 10% of its normal. Standard: The applicant finds core flow percent deviation recorded in step 5.1.3 l is greater than 10% of its normal and therefore does not meet the criteria of step 5.1.4a(3). Cue:
Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADMXX Revision: 0
Page: 6 of 12
- Determines the jet pumps are not operable.
Standard: The applicant determines 2 of the 3 criterion listed in step 5.1.4a are not met; therfore, the jet pump operability criterion of step 5.1.4b is not met.
Cue:
Notes:
- Corrects marking of the TEST RESULTS section and correctly marks the APPROVAL section of the surveillance data package cover sheet.
Standard: The applicant corrects section 3.0 TEST RESULTS to indicate "Tech Spec Acceptance Criteria" and "All other steps/data" are Unacceptable and checks the "Tech Spec Operability Requirements Unacceptable" block of section 5.0.
Cue:
Notes:
Task Standard(s)
- Complete the review of the daily jet pump surveillance IAW 06-RE-1B33-D-0001.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADMXX Revision: 0
Page: 7 of 12 Task: Daily Jet Pump Surveillance Review Follow-Up Questions & Answers
Comments:
Page 8 of 12 Daily Jet Pump Surveillance Review Give this page to the student Initial Condition(s): The plant is operating in Mode 1, 100% power.
Initiating Cue(s): Reactor engineering has just completed the attached jet pump surveillance, 06-RE-1B33-D-0001. You are to review the surveillance and determine if any operability criteria is not met and complete section 5.0 of the attached surveillance.
Note: You can assume all mathematical calculations have been performed correctly.
Page 9 of 12 GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE
X QA RECORD
06-RE-1B33-D-0001 Revision 111 RT = B6.61
NON-QA RECORD Attachment I Page 1 of 4 INITIALS NUMBER OF PAGES DATE Page RELATED DOCUMENT RTYPE B6.61 NUMBER =
XRef 002202 SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Jetpump Functional Test
Technical Specifications: SR 3.4.3.1 and TRM SR TR3.4.1.1
1.0 IMPACT
STATEMENT
1.1 Performance
of this procedure may have no impact on plant operations.
2.0 REFERENCES
2.1 Plant
MODE is (circle one): 1 2 3 4 5
2.2 Permission
to begin the test John Smith / 3/02/09 Shift Supervisor Date
2.3 Test Start Time: Bilbo Baggins / 3/02/09 / 0845 Performer's signature Date Time
3.0 TEST RESULTS
3.1 Test Completion: (Check one in each category.)
Entire procedure completed [X] Partial procedure completed[ ]
Tech Spec Acceptance Criteria Acceptable [X] Unacceptable [ ]
All other steps/data Acceptable [X] Unacceptable [ ]
3.2 TCNs in effect during performance (list): None
3.3 Comments
None .
3.4 Test performed by Bilbo Baggins Date/Time 3/02/09 / 0945
4.0 DEFICIENCIES
CR Issued #
MAI Issued #
LCO Entered #
5.0 APPROVAL
Tech Spec Operability Requirements Acceptable [ ] Unacceptable [ ]
Shift Supv/Mgr Date (MUST NOT BE SAME AS PERFORMER)
Comments:
CONCURRENCE Reactor Engineering Superintendent Date
GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-RE-1B33-D-0001 Revision 111 Attachment II Page 10 of 4
Page RTYPE B6.61 XRef 002202 Page 10 of 12 DATA SHEET I JETPUMP FUNCTIONAL TEST SAFETY RELATED
Step 4.1 Attachment I prerequisite met: Yes No BB (Circle as appropriate) Initial
Step 5.1.2a Data recorded using: %P Flow BB (Circle as appropriate) Initial
(Note: If %P used then Attachment II must be included.)
Recirculation Jetpump Percent Deviation JETPUMP Loop A Normal Percentage From Normal (Step 5.1.2a) (Step 5.1.3a) (Step 5.1.3c)
JP1 4.95 8.360 5.263 JP2 5.01 8.464 5.230 JP3 4.88 8.515 1.886 JP4 4.85 8.431 2.268 JP5 4.90 7.900 10.267 JP6 4.89 8.293 4.827 JP7 4.90 8.163 6.715 JP8 4.74 8.139 3.534 JP9 4.90 8.609 1.186 JP10 4.66 8.078 2.556 JP11 4.66 8.690
-4.667 JP12 4.55 8.359
-3.231
Step 5.1.3b Loop A Total: 56.25 Mlb/hr
GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-RE-1B33-D-0001 Revision 111 Attachment II Page 11 of 4
Page RTYPE B6.61 XRef 002202 Page 11 of 12 DATA SHEET I (Continued)
JETPUMP FUNCTIONAL TEST SAFETY RELATED Recirculation Jetpump Percent Deviation JETPUMP Loop A Normal Percentage From Normal (Step 5.1.2a) (Step 5.1.3a) (Step 5.1.3c)
JP13 4.95 8.426 4.438 JP14 4.83 8.271 3.816 JP15 4.85 8.365 3.075 JP16 4.90 8.595 1.351 JP17 4.40 8.155
-4.081 JP18 4.52 8.379
-4.099 JP19 4.68 8.235 1.032 JP20 4.57 8.091 0.413 JP21 4.61 8.298
-1.235 JP22 4.55 8.575
-5.669 JP23 4.78 8.360 1.648 JP24 4.82 8.249 3.878 Step 5.1.3b Loop B Total: 56.25 Mlb/hr
Step 5.1.4a(1)
Flow Acceptance Criteria met for both Loop A and B: Yes No BB (Circle as appropriate) Initial
(%DEV Flow <
+ 10%)
GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-RE-1B33-D-0001 Revision 111 Attachment II Page 12 of 4
Page RTYPE B6.61 XRef 002202 Page 12 of 12 DATA SHEET II JETPUMP FUNCTIONAL TEST LOOP/CORE FLOW CHECKS SAFETY RELATED LOOP FLOWS Loop A Loop B Step 5.1.2b Measured Loop Drive Flow 43000 gpm 43000 gpm Step 5.1.2c FCV Position/Recirc Pump Speed 80% / Fast 80% / Fast Step 5.1.2e Reactor CTP 100%
Step 5.1.3d Loop Drive Flow Criterion 44000 gpm 43000 gpm Step 5.1.3e Loop Flow Multiplier 1.000 1.000 Step 5.1.3f Established Loop Drive Flow 44000 gpm 43000 gpm Step 5.1.3g Percent Deviation (%DEV) 2 0
Step 5.1.4a(2)
Flow Acceptance Criteria met: Yes No BB (Circle as appropriate) Initial
(%DEV < + 10%) CORE FLOWS Step 5.1.2d Measured Total Core Flow 97 Mlb/hr Step 5.1.3h Measured Total Drive Flow 88000 gpm Step 5.1.3i Core Flow Criterion 108 Mlb/hr Step 5.1.3j Core Flow Multiplier 1.000 Step 5.1.3k Established Total Core Flow 108 Mlb/hr Step 5.1.3l Percent Deviation (%DEV) 10.2%
Step 5.1.4a(3)
Flow Acceptance Criteria met:
Yes No BB (Circle as appropriate) Initial
(%DEV < + 10%) $ Step 5.1.4b Tech Spec Acceptance Criteria met: Yes No BB (Circle as appropriate) Initial
(At least 2 out of 3 Flow Acceptance Criteria met)
Volumetric Loop Flow
$ Step 5.1.5a Tech Spec Acceptance Criteria met: Yes No N/A (Circle as appropriate) Initial (Flow < 44,600 gpm, for single loop operation)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM03 Revision: 0
Page: 1 of 9
Rtype:
QA Record
Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE: ADMINISTRATIVE JPM Plant Chemistry Report Review New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES
- N/A REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/14/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM03 Revision: 0
Page: 2 of 9 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operati on and data collection is at the discretion of the Evaluator.
- 4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam.
These activities are not required for JPMs conducted in the Simulator.
- 5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE.
Details can be found in Att. 2 of the Electrical Safety Rulebook and Gene ral Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
- 6. Obtain Shift Management's permission before opening any control panel or compartment.
Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM03 Revision: 0
Page: 3 of 9 Task: Plant Chemistry Report Review Setting: Classroom Type: SRO Task: Identify required actions for plant chemistry levels in excess of administrative limits K&A: 256000 Generic 2.1.25 - 2.8/3.1; 2.1.34 - 2.3/2.9; 2.4.4 - 4.0/4.3; 2.4.11 - 3.4/3.6 Safety Function
- 2 Time Required: 20 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): Condensate High Conductivity, 05-1-02-V-12; EPRI Water Chemistry Guidelines, 01-S-08-29 Handout(s): Completed copy of 01-S-08-29 Att. VI
- Manipulations: N/A # Critical Steps: 1 Group : N/A Simulator Setup/Required Plant Conditions: None Safety Concerns: None Initial Condition(s): A plant startup is in progress in Operational Mode 2. Reactor Power is 9% at 950 psig. Preparations are being made for Main Turbine/Generator roll up. There is no inoperable equipment.
Initiating Cue(s): Plant Chemistry has just completed the required sampling of Condensate, Feedwater and Reactor Water in preparation for entry into Mode 1 and for exceeding 10% power.
You are the SRO. Review the Chemistry data and determine the course of action for plant operations. Include any required Tech Spec/TRM actions.
SEE THE CHEMISTRY VALUES ON 01-S-08-29 ATT. IV, PROVIDED.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM03 Revision: 0
Page: 4 of 9 Task: Plant Chemistry Report Review Notes: 1. None Task Overview
- Review the results from the Plant Chemistry Report. Identify any actions required by plant procedures, including any Tech Spec/TRM requirements.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM03 Revision: 0
Page: 5 of 9 Task: Plant Chemistry Report Review
Tasks : Critical steps are underlined, italicized, and denoted by an (*)
Compares data from 01-S-08-29 Att. VI to Technical Requirements Manual 6.4.1 Chemistry requirements of TRM Table 6.4.1-1 for Mode 2.
Standard: The applicant identifies Reactor Coolant Chemistry requirements of TRM 6.4.1 are met.
Cue:
Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM03 Revision: 0
Page: 6 of 9
- Compares data from 01-S-08-29 Att. VI to the limits of ONEP 05-1-02-V-12 and identifies the required actions.
Standard: The applicant determines the conductivity of Condensate Pump Discharge (CPD) exceeds the limit of 05-1-02-V-12 step 3.6 and identifies the following actions are required (steps 3.6.1 through 3.6.6):
MANUALLY SCRAM the reactor.
CLOSE E51-F010, RCIC PMP SUCT FM CST.
OPEN E51-F031, RCIC PMP SUCT FM SUPP POOL.
INITIATE RCIC for Reactor level control.
WHEN RCIC and CRD can maintain Reactor water level, THEN TRIP running Reactor Feedwater pumps.
CLOSE 1B21-F065A and B to isolate feedwater to reactor vessel.
CLOSE MSIV's and MSL drain valves and OPERATE SRV's for Reactor pressure control.
PLACE hotwell level controller N19-R004 on 1H22-P171 in Manual at 50% to isolate hotwell from CST and CRD.
CLOSE/CHECK CLOSED N19-F008, CNDS MU BYP VLV and N19-F013, CNDS REJECT BYP valve to reduce CST contamination Cue:
Notes: RCIC is available as given in the initial condition of no inoperable equipment.
Task Standard(s)
- Candidate has determined the actions for out of limits Chemistry in accordance with 05-
1-02-V-12.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM03 Revision: 0
Page: 7 of 9 Task: Plant Chemistry Report Review Follow-Up Questions & Answers
Comments:
Page 8 of 9 Plant Chemistry Report Review Give this page to the student Initial Condition(s): A plant startup is in progress in Operational Mode 2. Reactor Power is 9% at 950 psig. Preparations are being made for Main Turbine/Generator roll up. There is no inoperable equipment.
Initiating Cue(s): Plant Chemistry has just completed the required sampling of Condensate, Feedwater and Reactor Water in preparation for entry into Mode 1 and for exceeding 10% power.
You are the SRO. Review the Chemistry data and determine the course of action for plant operations. Include any required Tech Spec/TRM actions.
SEE THE CHEMISTRY VALUES ON 01-S-08-29 ATT. IV, PROVIDED.
Page 9 of 9
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM02 Revision: 0
Page: 1 of 24
Rtype:
QA Record
Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE: ADMINISTRATIVE JPM LIQUID RADWASTE DISCHARGE PERMIT REVIEW New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES
- N/A REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/14/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM02 Revision: 0
Page: 2 of 24 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operati on and data collection is at the discretion of the Evaluator.
- 4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam.
These activities are not required for JPMs conducted in the Simulator.
- 5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE.
Details can be found in Att. 2 of the Electrical Safety Rulebook and Gene ral Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
- 6. Obtain Shift Management's permission before opening any control panel or compartment.
Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM02 Revision: 0
Page: 3 of 24 Task: Liquid Radwaste Discharge Permit Review Setting: Classroom Type: SRO Task: Perform SRO review of a Batch Liquid Radwaste Discharge Permit K&A: 2.3.6: 3.1 Safety Function
- 9 Time Required: 15 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): 01-S-08-11, Radioactive Discharge Controls; 06-CH-SG17-P-0041, Radwaste Release Pre-Relealease Analysis Handout(s): LRW Discharge Permit with 06-CH-SG17-P-0041 Att. I completed and 01-S-08-11 Att. I with Parts 1, 2, and 3 completed
with errors
- Manipulations: N/A # Critical Steps: 1 Group : N/A
Simulator Setup/Required Plant Conditions: None Safety Concerns: None Initial Condition(s):
The Radwaste Specialist has presented a Batch Liquid Radwaste Discharge Permit to you for
Shift Manager approval.
Initiating Cue(s): You are the Shift Manager. Review the Batch Liquid Radwaste Discharge Permit and identify 5 critical deficiencies.
The discharge does not exceed any TRM/Standing Order limits.
REFER TO THE LRW DISCHARGE PERMIT, PROVIDED.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM02 Revision: 0
Page: 4 of 24 Task: Liquid Radwaste Discharge Permit Review Notes: 1. None Task Overview
- This task is to perform the SRO review of the Batch Liquid Radwaste Discharge Permit performed by the Shift Manager to authorize a controlled release of liquid radwaste. Five errors have been introduced on the Discharge Permit.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM02 Revision: 0
Page: 5 of 24 Task: Liquid Radwaste Discharge Permit Review
Tasks : Critical steps are underlined, italicized, and denoted by an (*)
- Reviews the Batch Liquid Radwaste Discharge Permit package provided per the requirements of 01-S-08-11 to determine if the discharge is allowable.
Standard: Reviews the data recorded in Parts 1, 2, and 3 of the LRW Discharge Permit provided using 01-S-08-11 and identifies at least 4 of the 5 following errors:
In Part 1, the "Radwaste monitor background reading" is above the limit In Part 2, the "Effluent Monitor Alarm Setpoint" is incorrect In Part 2, the "Effluent Monitor Alarm Setpoint" is incorrect In Part 3, the "Minimum Blowdown Flow Rate Setpoint" is incorrect In Part 3, the "Maximum Tank Discharge Flow Rate Setpoint" is incorrect Cue: Notes: all values recorded in Parts 1, 2, and 3 derive from pages 1 and 2 of the computer generated Liquid Pre-Release Permit Report in 06-CH-SG17-P-0041 Att I
Task Standard(s)
- Candidate has identified at least 4 of the 5 errors in the Liquid Radwaste Discharge Permit parts 1, 2, and 3.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-SRO-ADM02 Revision: 0
Page: 6 of 24 Task: Liquid Radwaste Discharge Permit Review Follow-Up Questions & Answers
Comments:
Page 7 of 24 DO NOT GIVE TO STUDENT EVALUATOR COPY Scientific notation conversion errors, should be a factor
of 10 higher Must be less than 1 0,800 Page 8 of 24 DO NOT GIVE TO STUDENT EVALUATOR COPY Values listed are voltage settings for
the respective setpo in ts Page 9 of 24 Liquid Radwaste Discharge Permit Review
Give this page to the student Initial Condition(s):
The Radwaste Specialist has presented a Batch Liquid Radwaste Discharge Permit to you for Shift Manager
approval.
Initiating Cue(s):
You are the Shift Manager. Review the Batch Liquid Radwaste Discharge Permit and identify 5 critical deficiencies.
The discharge does not exceed any TRM/Standing Order limits.
REFER TO THE LRW DISCHARGE PERMIT PACKAGE, PROVIDED.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM02 Revision: 00
Page: 1 of 13
Rtype:
QA Record
Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE: ADMINISTRATIVE JPM Standby Diesel Generator Starting Air System Desiccant Changeout Tagout Review New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES
- N/A REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/14/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM02 Revision: 00
Page: 2 of 13 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operati on and data collection is at the discretion of the Evaluator.
- 4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam.
These activities are not required for JPMs conducted in the Simulator.
- 5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE.
Details can be found in Att. 2 of the Electrical Safety Rulebook and Gene ral Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
- 6. Obtain Shift Management's permission before opening any control panel or compartment.
Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM02 Revision: 00
Page: 3 of 13 Task: Standby Diesel Generator Starting Air System Desiccant Changeout Tagout Review Setting: Classroom Type: SRO Task: Perform Reviewer responsibilities for Protective Clearance preparation K&A: 264000 Generic 2.2.13 - 3.6/3.8 Safety Function
- 6 Time Required: 15 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): EN-OP-102, EN-OP-102-1, Drawings M1070A; E1110-25,26,33; E0658-13 Handout(s): Completed Work Impact Statement, partially completed Tagout Request Form, completed Tagout Cover Sheet, completed Tagout
Tags Sheet, Dwgs M1070A; E1110-25,26,33; E0658-13
- Manipulations: N/A # Critical Steps: 1 Group : N/A
Simulator Setup/Required Plant Conditions: None Safety Concerns: None Initial Condition(s): The plant is operating in Mode 1, 100% power.
Initiating Cue(s): You have been been provided the tagout package for the changeout of desiccant in the Standby Diesel Generator 11 backup Starting Air Dryer. Use the procedure, forms, and drawings provided to determine if it is adequate.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM02 Revision: 00
Page: 4 of 13
Task: Standby Diesel Generator Starting Air System Desiccant Changeout Tagout Review Notes: 1. None Task Overview
- Review the provided tagout package for the changeout of desiccant in the Standby Diesel Generator 11 backup Starting Air Dryer. Use the procedure, forms, and drawings provided to determine if it is adequate.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM02 Revision: 00
Page: 5 of 13 Task: Standby Diesel Generator Starting Air System Desiccant Changeout Tagout Review
Tasks : Critical steps are underlined, italicized, and denoted by an (*)
- Identify the following three errors:
- 1) Electrical error (Attachment 9.3, tag XXX3 breaker should be 52-111342, not 52-111432)
- 2) Mechanical valve error (Attachment 9.3, placement sequence for tag
XXX7,which vents the piping, should be after tags XXX5 and XXX6, which
isolate the piping.)
- 3) Tag omission (Battery leads for Diesel Driven Compressor 1P75C013A should
be lifted)
Standard: The operator marks and corrects the errors as needed.
Cue:
Notes:
Task Standard(s)
- Review the tag out in preparation for the changeout of desiccant in the Standby Diesel Generator 11 IAW EN-OP-102.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-ADM02 Revision: 00
Page: 6 of 13 Task: Standby Diesel Generator Starting Air System Desiccant Changeout Tagout Review Follow-Up Questions & Answers
Comments:
Page: 7 of 13 Standby Diesel Generator Starting Air System Desiccant Changeout Tagout Review Give this page to the student Initial Condition(s): The plant is operating in Mode 1, 100% power.
Initiating Cue(s): Find attached the tagout package for the changeout of desiccant in the Standby Diesel
Generator 11 backup Starting Air Dryer. eSOMS is out of service. You are to review the
tagout package to ensure it is adequate for the desicant changeout. Note any
discrepancies you find on the tagout sheet.
Give this page to the student N ON-Q UALITY R ELATED EN-OP-102-01 REV. 4 NUCLEAR MANAGEMENT
MANUAL I NFORMATIONAL U SE PAGE 6 OF 24 Protective and Caution Tagging Forms & Checklist Page: 8 of 13 A TTACHMENT 9.2 T AGOUT C OVER S HEET Clearance: __MANUAL____________ Tagout: _____________________
Component to be worked:
P75-AIRDRY-1P75D012A STANDBY DIESEL START AIR DRYER DSL-133 -1D310
==
Description:==
ISOLATE 1P75D012A IN ORDER TO REPLACE DESSICANT
Placement Inst:
This tagout will isolate and de-ernergize Div 1 Diesel Driven Air Compressor 1P75C013A.
References:
M1070A; E1110-25,26,33; E0658-13
Hazards:
NONE Restoration Inst:
Post-maintenance testing and recovery method required; maintenance leak test requires running the diesel driven air compressor to pressurize the air dryer.
Attribute Description Attribute Value High Energy System Concerns NO Tech Spec Impact? Enter EOS# or None N/A Compensatory Actions Req?
NO Locked Components?
NO Fire Protection Impairment?
NO Equip Drain / Vent rig required?
NO Scaffold Required?
NO Is an LCO start time required?
NO Tech Spec Impact on System Restoration?
NO Component Deviation Required?
NO 50.59 Screening Attached N/A Crew Assigned Walk down Yes Walk down complete?
Reason this tag was created?
Scheduled work Tagout prepare issues:
No issues Work Order Number Description XXXXXX REPLACE DESSICANT IN 1P75D012A Status Description User Verification Date Prepared Prepared Bilbo Baggins 3-3-09 Technical Reviewed Reviewed Approved Approved Tags Verified Hung Tags Verified Hung Removal Approved Removal Approved Tags Verified Removed Tags Verified Removed
Give this page to the student N ON-Q UALITY R ELATED EN-OP-102-01 REV. 4 NUCLEAR MANAGEMENT
MANUAL I NFORMATIONAL U SE PAGE 7 OF 24 Protective and Caution Tagging Forms & Checklist Page: 9 of 13 A TTACHMENT 9.3 T AGOUT T AGS S HEET C LEARANCE: ___MANUAL___________
TAGOUT: ________________
Tag Serial No. Tag Type Equipment Equipment Description
Equipment Location Place. Seq. Placement Configuration Place. 1st Verif Date/Time Place. 2nd Verif Date/Time Rest. Seq. Restoration Configuration Rest. 1st Verif Date/Time Rest. 2nd Verif Date/Time Placement/R emoval Tag Notes XXX1 Danger 52-1L113-7 Lighting Panel Breaker to Battery Charger for DG11 Diesel Driven Air
Compressor 1P75C013A D SL-133 1 Off XXX2 Danger 1P75M026A Handswitch for Starting Air Dryer #2 and Aftercooler D012A B013A D SL-133 1 Off XXX3 Danger 52-111432 Breaker to DG11 Diesel Driven Air Compressor Aftercooler 1P75B013A D SL-133 4 Off XXX4 Danger 52-1P11314 Power Panel Breaker to DG11 Starting Air Dryer #2 1P75D012A D SL-133 4 Off XXX5 Danger 1P75F177A Starting Air Storage Tank 1P75A001A Inlet Valve D SL-133 3 Closed Give this page to the student N ON-Q UALITY R ELATED EN-OP-102-01 REV. 4 NUCLEAR MANAGEMENT
MANUAL I NFORMATIONAL U SE PAGE 7 OF 24 Protective and Caution Tagging Forms & Checklist Page: 10 of 13 A TTACHMENT 9.3 T AGOUT T AGS S HEET C LEARANCE: ___MANUAL___________
TAGOUT: ________________
Tag Serial No. Tag Type Equipment Equipment Description
Equipment Location Place. Seq. Placement Configuration Place. 1st Verif Date/Time Place. 2nd Verif Date/Time Rest. Seq. Restoration Configuration Rest. 1st Verif Date/Time Rest. 2nd Verif Date/Time Placement/R emoval Tag Notes XXX6 Danger 1P75F176A U nloader Isolation Valve for 1P75C013A D SL-133 3 Closed XXX7 Danger 1P75FX252A Starting Air Dryer D012A Test Connection D SL-133 2 Open XXX8 Danger 1P75C013A Starter switch for DG11 Diesel Drive n A ir Compressor 1P75C013A D SL-133 1 Position 0
Give this page to the student QUALITY RELATED EN-WM-105 REV.0 NUCLEAR MANAGEMENT
MANUAL INFORMATIONAL USE PAGE xx OF 48 ATTACHMENT 9.2 IMPACT TEMPLATE Sheet 1 of 1
____________________/___________
____________________/___________
PLANNER DATE REVIEWER DAT E WORK SCOPE:
Replace desiccant in Div I DG Diesel Driv en Air Compressor Starting Air Dryer 1P75D012A.
COMPONENT MODE: ( ) INSV ( X )OOSV ( ) AVAILABLE
PLANT MODES & CONDITIONS:
Plant may be in any condition. Starting Air Dryer and associated Diesel Driven Air Compressor must be secured and isolated. Starting Air Dr yer 1P75D012A must be depressurized.
EFFECTS ON ASSOCIATED SYSTEM AND COMPONENTS:
DG11 Diesel Driven Air Compressor will be out of se rvice. The Motor Driven Air Compressor will be available to maintain DG11 Starting Air Storage Tanks pressurized.
PRE-MAINTENANCE ACTIVITIES:
None POST-MAINTENANCE ACTIVITIES:
None DOES THE ACTIVITY HAVE THE POTENTIAL TO SCRAM/TRIP THE PLANT: ( ) YES ( X ) NO
SECURITY/FIRE/CONTROL ROOM ENVELOPE BARRIER BREACH: ( ) YES ( X ) NO
RPS AFFECTED: ( ) YES ( X ) NO
ESF/EFSAS AFFECTED: ( ) YES ( X ) NO
ALARMS/COMPUTER POINTS AFFECTED (IF YES, LIST ON ATTACHED SHEET) ( ) YES ( X ) NO Page: 11 of 13
Give this page to the student Page: 12 of 13 QUALITY RELATED EN-WM-105 REV.4 NUCLEAR MANAGEMENT
MANUAL INFORMATIONAL USE PAGE xx OF 48 ATTACHMENT 9.3 OPERATIONAL IMPACT TEMPLATE Sheet 1 of 1
OPERATIONAL IMPACT
____________________/___________
____________________/___________
SRO DATE REVIEWER D ATE TECHNICAL SPECIFICATIONS:
NONE LIMITING CONDITIONS FOR OPERATIONS:
NONE REACTIVITY IMPACT (REQUIRED):
NONE POTENTIAL SYSTEM/COMPONENT EFFECTS:
This work only affects DG11 Diesel Driven Air Compressor subsystem. The Motor Driven Air Compressor will be available to maintain DG11 Starting Air Storage Tanks pressurized.
ACTUAL OR POTENTIAL MEASURE OR CONTINGENCY ACTION REQUIRED:
If the DG11 Motor Driven Air Compressor fails to function, a low starting air pressure will result in a DG11 Trouble alarm in the main control room. The asso ciated ARIs contain the necessary contingencies for that condition.
Give this page to the student N ON-QUALITY RELATED EN-OP-102-01 REV. 4 NUCLEAR MANAGEMENT
MANUAL INFORMATIONAL U SE PAGE 14 OF 24 Protective and Caution Tagging Forms & Checklist Page: 13 of 13 ATTACHMENT 9.10 TAGOUT REQUEST Tagout Request Instructions The Tagging Requestor is responsible for providing detailed information on the work scope/condition and should recommend boundaries to provide for equipment and personnel
safety. Work Order #
Task # Mark # Requester Ext. / Pager 999999 1 Smith 555 1. Provide a detailed description of the maintenance activity and the reference drawing numbers:
Replace desiccant in Div I DG Diesel Driv en Air Compressor Starting Air Dryer 1P75D012A.
P&ID M1070A
- 2. If known, provide a previous Clearance/Tagout number which provides the required protection: undetermined Fluid systems: Yes No Valve Work Back Seat Yes No MOV Open Closed Air- Water- Steam- Oil- Test & Maintenance Tag 3. Fluid Components To Be Tagged and Required Position:
Isolation Valves (Any Gags, Brakes, or Flanges required):
undetermined Drain/Vent Valves: undetermined Special Instructions: Need system depressurized to change the desiccant and need to run the DD
compressor to do a maintenance leak test when work is complete 4. Electrical Components To Be Tagged and Required Position: Yes No Control Switches:
Breakers:
Tag on Breaker Tag to be moved to Door
Fuses/Leads to Pulled/Lifted: undetermined Grounds/Ground Locations:
Special Instructions:
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Grand Gulf Nuclear Station Date of Examination:
2 March 2009 Exam Level (circle one)
RO / SRO-I / SRO-U Operating Test Number:
Control Room Systems
@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code* Safety Function a. 202001 Recirculation System - Startup idle Recirculation Pump w/ High Vibration requiring manual pump trip.
S; N; A; L 1 b. 209002 High Pressure Core Spray System - Operate HPCS in CST-to-CST mode w/failure of HPCS minimum flow valve S; D; A 2 ESF c. 264000 Emergency Generators - Parallel of Emergency Generator (with load) to the grid S; N 6 ESF d. 400000 Component Cooling Water System - Rotate CCW pumps w/CCW pump trip S; B; A 8 e. 217000 Reactor Core Isolation Cooling System - Operate RCIC for RPV pressure control w/failure of RCIC turbine speed controller S; N; A 3 f. 219000 RHR/LPCI: Suppression Pool Cooling Mode
- Secure RHR from Containment Spray mode to Suppression Pool Cooling mode w/trip of ECCS pump requiring manual RHR alignment to LPCI
mode S; N; A 5 ESF g. 201005 Rod Control and Information System
- Bypass a Control Rod in the RACS C; D 7 h. 239003 Main Steam Isolation Valve Leakage Control System
- Start the Outboard MSIV LCS w/ blower failure requiring start of the Inboard MSIV LCS C; N; A 9 ESF In-Plant Systems
@ (3 for RO; 3 for SRO-I; 3or2 for SRO-U)
- i. 211000 Standby Liquid Control System - Perform SLC Pump A Monthly Surveillance R; N 1 j. 262002 Uninterruptible Power Supply (A.C./D.C.)
- Start up Static Inverter 1Y81 D 6 k. 286000 Fire Protection System - Align Fire Water for injection to the reactor via LPCS and RHR C per EP Attachment 26 R; E; L; D 8 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol Room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 Revision 2 2/22/2007 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Grand Gulf Nuclear Station Date of Examination:
2 March 2009 Exam Level (circle one)
RO / SRO-I / SRO-U Operating Test Number:
Control Room Systems
@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code* Safety Function a. 202001 Recirculation System - Startup idle Recirculation Pump w/ High Vibration requiring manual pump trip.
S; N; A; L 1 b. 209002 High Pressure Core Spray System - Operate HPCS in CST-to-CST mode w/failure of HPCS minimum flow valve S; D; A 2 ESF c. 264000 Emergency Generators - Parallel of Emergency Generator (with load) to the grid S; N 6 ESF d. 400000 Component Cooling Water System - Rotate CCW pumps w/CCW pump trip S; B; A 8 e. 217000 Reactor Core Isolation Cooling System - Operate RCIC for RPV pressure control w/failure of RCIC turbine speed controller S; N; A 3 f. 219000 RHR/LPCI: Suppression Pool Cooling Mode
- Secure RHR from Containment Spray mode to Suppression Pool Cooling mode w/trip of ECCS pump requiring manual RHR alignment to LPCI
mode S; N; A 5 ESF g. 201005 Rod Control and Information System
- Bypass a Control Rod in the RACS C; D 7 h. N/A In-Plant Systems
@ (3 for RO; 3 for SRO-I; 3or2 for SRO-U)
- i. 211000 Standby Liquid Control System - Perform SLC Pump A Monthly Surveillance R; N 1 j. 262002 Uninterruptible Power Supply (A.C./D.C.)
- Start up Static Inverter 1Y81 D 6 k. 286000 Fire Protection System - Align Fire Water for injection to the reactor via LPCS and RHR C per EP Attachment 26 R; E; L; D 8 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol Room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 Revision 2 2/22/2007 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Grand Gulf Nuclear Station Date of Examination:
2 March 2009 Exam Level (circle one)
RO / SRO-I /
SRO-U Operating Test Number:
Control Room Systems
@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code* Safety Function a. N/A b. N/A c. N/A d. N/A e. 217000 Reactor Core Isolation Cooling System - Operate RCIC for RPV pressure control w/failure of RCIC turbine speed controller S; N; A 3 f. 219000 RHR/LPCI: Suppression Pool Cooling Mode
- Secure RHR from Containment Spray mode to Suppression Pool Cooling mode w/trip of ECCS pump requiring manual RHR alignment to LPCI
mode S; N; A 5 ESF g. N/A h. N/A In-Plant Systems
@ (3 for RO; 3 for SRO-I; 3or2 for SRO-U)
- i. 211000 Standby Liquid Control System - Perform SLC Pump A Monthly Surveillance R; N 1 j. 262002 Uninterruptible Power Supply (A.C./D.C.)
- Start up Static Inverter 1Y81 D 6 k. 286000 Fire Protection System - Align Fire Water for injection to the reactor via LPCS and RHR C per EP Attachment 26 R; E; L; D 8 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol Room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 Revision 2 2/22/2007 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3314 Revision: 0
Page: 1 of 10
Rtype:
QA Record
Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE: B33 JOB PERFORMANCE MEASURES Reactor Recirc System Startup New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES
- NA REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/11/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3314 Revision: 0
Page: 2 of 10 Generic Instructions
- 1. Standards and cues for valve operation: a. MOVs:
- 1) "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red light is (energized or de-energized) and its green light is (energized or de-energized)".
- b. Manual valves
- 1) "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direc tion until resistance is felt." 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.
- 4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam.
These activities are not required for JPMs conducted in the Simulator.
- 5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securi ng shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
- 6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3314 Revision: 0
Page: 3 of 10 B33 Task 14: Reactor Recirc System Startup (Alternate Path) Setting: Simulator Type: RO Task: CRO-B33(1)-002 K&A: 202001: A4.01 - 3.7/3.7 Safety Function: Recirculation System Time Required: 25 minutes Time Critical: No Faulted: YES Performance: Actual Reference(s): 04-1-01-B33-1 section 4.1, ARI 04-1-02-1H13-P680-3A-E4 Handout(s): Copy of 04-1-01-B33-1 section 4.1 marked up to show all steps are complete up to the step 4.1.2b(15) for starting Recirc Pump A
- Manipulations: 9 # Critical Steps: 2 Group: 2 Simulator Setup/Required Plant Conditions
- Reset to any Mode 4 IC with Recirc Pumps A and B shut down and in standby. Start Unit 1 Instrument Air Compressor Place Recirc FCV "A" in the MIN-ED (20%) position Align RWCU blowdown to Radwaste. Raise tap setting for bus 11HD to 7.2 kV Insert malfunction rr014a at 100 Insert remote function C86009X at 20 Safety Concerns: None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3314 Revision: 0
Page: 4 of 10 Initial Condition(s): The plant is in Mode 4.
The pump seal for Recirc Pump A was replaced during the plant shutdown, and Recirc Pump A is ready to be returned to operation.
All steps within Sections 4.1.1 and 4.1.2a of 04-1-01-B33-1 are complete, and steps of Section 4.1.2b are complete up to step 4.1.2b(15). Recirc Pump A is
ready to start.
Initiating Cue(s): The CRS has directed you to start Recirc Pump A per the SOI.
The vibration engineer is monitoring the pump start on Control Building, 148'
elev. The CRS will notify RE and I&C to evaluate if venting of the jet pump flow transmitters is required after the pump is started.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3314 Revision: 0
Page: 5 of 10 B33 Task 14: Reactor Recirc System Startup (Alternate Path) Notes 1. Unless otherwise indicated, all controls a nd indications for this task are on panel 1H13-P680-3A - C. 2. This task begins at Step 4.1.2b(15) of 04-1-01-B33-1.
Task Overview This task begins the process of placing the Reactor Recirculation System in service during plant startup by starting the "A" Recirc pump in slow speed. The fault in this task is that Recirc Pump A vibration will increase immediately after pump start. The range for vibration indication available to the operator is limited to 20 mils maximum. The operator will request an extended reading taken from remote equipment used by the vibration monitoring engineer. The vibration engineer will report vibration levels in excess of the limit of 25 mils listed in the ARI and will recommend pump shutdown. The operator will trip Recirc Pump A in accordance with ARI 04-1-02-1H13-
P680-3A-E4 step 4.1b(2).
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3314 Revision: 0
Page: 6 of 10 B33 Task 14: Reactor Recirc System Startup (Alternate Path) Tasks : Critical steps are underlined, italicized, and denoted by an (*)
- Starts Recirc Pump A Standard: Depresses the START pushbutton on the TRANS TO LFMG/START handswitch for Recirc Pump A Cue: As Indicated Notes:
Observes the proper low speed start sequence for Recirc Pump A.
Standard: Monitors the following on P680:
CB-5A, RECIRC PMP A FDR 252-1103, closes. CB1-A LFMG A FDR, 152-1308, closes. RECIRC PMP A AMPS and RECIRC PMP RPM rise. Checks that CB-5A RECIRC PUMP A FDR 252-1103, opens at approximately 1700 rpm and pump starts coasting down. Checks that CB-2A, LFMG A GEN FDR 252-1103A, closes between 360-470 rpm and pump speed stabilizes.
Cue: Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3314 Revision: 0
Page: 7 of 10 Responds to RECIRC PMP A VIBR HI alarm.
Standard: Silences and acknowledges alarm and refers to ARI P680-3A-E4. Calls up PDS computer display for Recirc Pump A vibration and observes some readings are pegged high at 20 mils.
Cue: Notes: The P846 indicator in the computer room and its respective PDS indications are pegged high upscale during the alarming condition of 20 mils. To monitor vibration levels above 20 mils, the Vibration Engineer or Computer Engineering uses the RMSS computer or 0-scope in the lower Computer Room. Requests vibration engineer to monitor Recirc Pump A vibration.
Standard: Requests assistance per step 3.1 of ARI P680-3A-E4 to detrmine the actual amplitude of the vibration.
Cue: As the vibration engineer, report vibration indications from multiple probes are reading above 25 mils and you recommend securing Recirc
Pump A. Notes:
- Trips Recirc Pump A
Standard: Depresses TRIP pushbutton on CB-2A LFMG A MTR FDR 2A, 252-1103A, handswitch on 1H13-P680.
Cue: Notes: The operator may trip CB-1A after CB-2A is tripped, but this is not required for the JPM.
When Recirc Pump A is tripped by the operator, the evaluator will end the JPM.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3314 Revision: 0
Page: 8 of 10 Task Standard(s)
- Recirc Pump A has been secured.
Name: _________________________________Time Start: _______Time Stop: _______
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3314 Revision: 0
Page: 9 of 10 B33 Task 14: Reactor Recirc System Startup (Alternate Path)
Follow-Up Questions & Answers
Comments:
Page: 10 of 10 Reactor Recirc System Startup Give this page to the student Initial Condition(s): The plant is in Mode 4.
The pump seal for Recirc Pump A was replaced during the plant shutdown, and Recirc Pump A is ready to be returned to operation.
All steps within Sections 4.1.1 and 4.1.2a of 04-1-01-B33-1 are complete, and steps of Section 4.1.2b are complete up to step 4.1.2b(15). Recirc Pump A is
ready to start.
Initiating Cue(s): The CRS has directed you to start Recirc Pump A per the SOI.
The vibration engineer is monitoring the pump start on Control Building, 148'
elev. The CRS will notify RE and I&C to evaluate if venting of the jet pump flow transmitters is required after the pump is started.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E22102 Revision: 01
Page: 1 of 10
Rtype:
QA Record Number of pages Date Initials TRAINING PROGRAM:
OPERATIONS TRAINING TITLE: Operating HPCS in the Test Return Mode New Material Minor Revision Major Revision REASON FOR REVISION: change setup to have SSW C running; editorial changes.
THIS DOCUMENT REPLACES
- GJPM-OPS-E22102 Rev. 0 REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/14/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E22102 Revision: 01
Page: 2 of 10 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.
- 4. Obtain Shift Management's permission before opening any control panel door or instrument cover.
5 It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator. 6. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating pr ocedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E22102 Revision: 01
Page: 3 of 10 E22-1 Task 2: Operating HPCS in the Test Return Mode (Alternate Path)
Setting: Simulator Type: RO Task: CRO-E22-008, 010 K&A: 209002: A1.01-3.6/3.7; A4.01 - 3.7/3.7 Safety Function: High Pressure Core Spray System Time Required: 19 minutes Time Critical: No Faulted: Yes Performance: Actual Reference(s): 04-1-01-E22-1/5.2 and 5.3; 04-1-01-P41-1/4.5 Handout(s): None # Manipulations: 9 # Critical Steps: 5 Group: 1 Simulator Setup: Reset to any IC Insert Malf e22186d (E22-F012 breaker trip upon valve opening) Start SSW C pump and open P41F011
Safety Concerns: None Initial Condition(s): HPCS is in Standby SSW C is operating Initiating Cue(s): You have been directed to start the HPCS pump in CST-to-CST mode per 04-1 E22-1 section 5.2. The Shift Manager has authorized this evolution per Precaution and Limitation 3.28
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E22102 Revision: 01
Page: 4 of 10 E22-1 Task 2: Operating HPCS in the Test Return Mode (Alternate Path)
Notes 1. All operations and verifications take place on panels P601 and P870 in the Simulator.
Task Overview This task requires the ability to manually start the only ECCS-qualified high pressure injection system. The system auto-starts during LOCA conditions. Under certain conditions, however, the EOPs direct the operator to override the system off. If and when it is needed later in the event, the operator must manually re-start HPCS and align it for injection into the RPV, controlling its flowrate to maintain RPV level within a certain band. This task demonstrates the ability to operate HPCS in the "test return" mode, which puts HPCS flow in a loop from and to the Condensate Storage Tank, one of its two suction sources. HPCS is operated in this mode for surveillance and post-maintenance testing. HPCS minimum flow valve E22-F012 will fail in the closed position when it tries to
auto-open.
o Upon recognition of failure, the candidate should shut down HPCS pump.
Tasks : critical steps are underlined, italicized and denoted by (*)
Place the HPCS MOV TEST switch in the TEST position.
Standard: Places the HPCS MOV TEST switch on P601 in the TEST position by turning the switch clockwise until it snaps into position.
Cue: None Notes: Precaution and Limitation 3.17
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E22102 Revision: 01
Page: 5 of 10 Open HPCS/RCIC TEST RTN TO CST isolation valves.
Standard: Checks open P11-F064 and P11-F065 by observing the valves' position indicating lamps on P870 (red light on, green light off).
Cue: None Notes:
Directs local operator to close F305, Injection Valve Equalization.
Standard: Directs local operator to close F305 and awaits report of status.
Cue: The local operator reports that valve E22-F305 is full closed.
Notes:
- Start the HPCS pump.
Standard: Starts the HPCS pump by turning its handswitch on P601 in the clockwise direction until the switch clicks and displays a red target.
Cue: None Notes:
Check HPCS pump running.
Standard: Checks the status lamps above the pump's handswitch on P601: red light on, green light off.
Cue: None Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E22102 Revision: 01
Page: 6 of 10 Check HPCS motor current.
Standard: Observes HPCS motor current on meter E22-R616 on P601. Verifies current < 434 amps.
Cue: None Notes:
Check HPCS minimum flow valve opens.
Standard: Checks HPCS min flow valve E22-F012 auto-opens when HPCS discharge pressure increases above 130 psig as observed on indicator HPCS PMP DISCH PRESS E22-PI-R601 on panel P601.
Cue: None Notes:
- Observes minimum flow valve loses power and fails to open.
Standard: When HPCS discharge pressure is observed to be greater than 130 psig as indicated by E22-PI-R601 with system flow less than 1200 gpm as indicated by E22-R603 on panel P601, observes E22-F012 fails to open as indicated by de-energized
red and green lights, HPCS SYS OOSVC alarm (1H13-P601-16A-H5), and status light HPCS MOV OVRLD/PWR LOSS.
Cue: The CRS directs a controlled shutdown of HPCS, using 04-1-01-E22-1 section 5.3, and SSW C using 04-1-01-P41-1 section 4.5.
Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E22102 Revision: 01
Page: 7 of 10
- Stop the HPCS pump.
Standard: Stops the HPCS pump by turning its handswitch on P601 in the counter-clockwise direction until the switch clicks and displays a green target.
Cue: If asked, another operator will generate a CR and WR.
Notes:
Directs the local operator to open HPCS discharge valve disc equalizing valve E22-F305. Standard: Directs the local operator to open E22-F305.
Cue: The local operator reports that valve E22-F305 is full open.
Notes:
Verify HPCS jockey pump is running.
Standard: Verifies that the HPCS jockey pump is operating by observing its energized red status light and de-energized green status light on panel P601.
Cue: None Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E22102 Revision: 01
Page: 8 of 10
- Close SSW C return valve.
Standard: Closes P41-F011 by rotating its handswitch on panel P870-5C in the counter-clockwise position and observing its red status light de-energizes and its green status light energizes.
Cue: None Notes:
- Stop SSW Pump C.
Standard: Stops HPCS Service Water Pump P41-C002 by rotating its handswitch on panel P870-5C in the counter-clockwise position and observing its red status light de-energizes and its green status light energizes.
Cue: None Notes:
When SSW C Pump is stopped, the evaluator will end the JPM Task Standard(s)
- The HPCS pump is started for full test return flow, CST-to-CST, then, when E22F012 loses power, HPCS is shut down IAW SOI 04-1-01-E22-1 and SSW C is shut down IAW SOI 04-
1-01-P41-1.
Name: _________________________________Time Start: _______Time Stop: _______
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E22102 Revision: 01
Page: 9 of 10 E22-1 Task 2: Operating HPCS in the Test Return Mode (Alternate Path)
Follow-Up Questions & Answers
Comments:
Page: 10 of 10 Operating HPCS in the Test Return Mode Give this page to the student
Initial Condition(s): HPCS is in Standby SSW C is operating
Initiating Cue(s): You have been directed to start the HPCS pump in CST-to-CST mode per 04-1 E22-1 section 5.2. The Shift Manager has authorized this evolution per Precaution and Limitation 3.28.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P7520 Revision: 0
Page: 1 of 9
Rtype:
QA Record Number of pages Date Initials TRAINING PROGRAM:
OPERATIONS TRAINING TITLE: Parallel Offsite Power via ESF-21 to Bus 15AA New Material Minor Revision Major Revision REASON FOR REVISION
- N/A THIS DOCUMENT REPLACES
- N/A REVIEW / APPROVAL (Print Name):
Prepared By:
- Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P7520 Revision: 0
Page: 2 of 9 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.
- 4. Obtain Shift Management's permission before opening any control panel door or instrument cover.
5 It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator. 6. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating pr ocedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P7520 Revision: 0
Page: 3 of 9 Task: Transfer Vital Bus Loads from Standby Diesel Generator to Offsite Power Setting: Simulator Type: RO Task: Restore offsite power to bus 15AA following a LOSP K&A: 264000 A4.05 - 3.6/3.7 Safety Function: 6 Electrical - AC Electrical Distribution and Emergency Generators Time Required: 15 minutes Time Critical: No Alternate Path: No Performance: Actual Reference(s): 05-1-02-I-4, Section 3.1 (Step 3.1.12) 04-1-01-R21-1, Section 4.1 04-1-01-P75-1, Sections 4.3 and 4.4
Handout(s): none # Manipulations: 6 # Critical Steps: 4 Group: 1 Simulator Setups: Reset to any IC Open the feeder from ESF 11 to bus 15AA Restore the auxiliary building and restore other plant systems, as desired to minimize
distractions Safety Concerns: None Initial Condition(s): A loss of ESF-11 supplying bus 15AA occurred. Standby Diesel Generator 11 started and is supplying loads on the 15AA Bus. ESF-11 is unavailable.
Initiating Cue(s): You have been directed to parallel ESF-21 to bus 15AA per Section 4.3 of procedure 04-1-01-P75-1. All precautions and limitations of 04-1-01-P75-1 for this evolution have been verified to be met.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P7520 Revision: 0
Page: 4 of 9 Task: Parallel Offsite Power via ESF-21 to Bus 15AA Notes 1. All controls will be from panel 1H13-P864 in the Main Control Room.
Task Overview:
This JPM begins with DG11 carrying ESF bus 15AA following a loss of power to the bus. The operator will establish the proper conditions for the diesel generator and reconnect offsite power to bus 15AA from ESF Transformer 21.
Tasks : critical steps are underlined, italicized and denoted by (*)
VERIFY that Standby Diesel Generator 11 is running with Diesel Output breaker 152-
1508 Closed carrying ESF Bus 15AA load.
Standard: The operator verifies the parameters available to confirm that the diesel generator is running, carrying load, and that the breaker is closed.
Cue: Notes:
NOTE: The following operations are performed on 1H13-P864, unless otherwise noted.
SELECT phase of Bus 15AA voltage to be monitored with BUS 15AA VOLT SEL handswitch as indicated on voltmeter R21-R615A.
Standard: The operator selects the correct handswitch and moves it to any position other than OFF.
Cue: Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P7520 Revision: 0
Page: 5 of 9
- PLACE Offsite Power Source ESF-21 Breaker SYNCH FEEDER 152-1501 handswitch in the ON position.
Standard: The operator selects the correct handswitch and moves it to the correct position.
Cue: Notes:
- DEFEAT Standby Diesel Generator 11 Output breaker parallel interlock by placing keylocked DG 11 PRL CONT handswitch in the PRL position (spring return to OFF).
Standard: The operator places the correct handswitch in the correct position.
Cue: Notes:
ADJUST Standby Diesel Generator 11 RUNNING VOLTS DIV 1 about 50 volts above INCOMING VOLTS DIV 1 with AUTO VOLT SETPOINT CONT DG 11 handswitch.
Standard: The operator adjusts the diesel generator voltage 50 volts above the incoming voltage with the correct handswitch.
Cue: Notes:
- ADJUST Standby Diesel Generator 11 speed to bring frequency within range of Offsite System frequency by using MAN GOV CONT DG 11 handswitch so that synchroscope indicator is rotating slowly in the SLOW direction (counterclockwise).
Standard: The operator adjusts the diesel generator frequency as described using the correct handswitch.
Cue: Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P7520 Revision: 0
Page: 6 of 9 NOTE: Diesel Generator Output voltage is being maintained in AUTO control, but a
check should be kept on Diesel Ge nerator Output voltage and frequency.
ALLOW the synchroscope indicator to make a few revolutions to ensure frequency stability (once in the correct direction - counterclockwise) (There may be a need to
adjust diesel generator speed to obtain pr oper rotation of synchroscope indicator.).
Standard: The operator observes the synchroscope indicator for at least three revolutions to assess frequency stability.
Cue: Notes:
NOTE: Adjusting diesel generator speed in the lower direction can cause the parallel circuitry to reset due to low frequency. This may cause the generator output breaker
to trip on closure of the offsite feeder breaker. If generator under frequency alarm annunciates or ready-to-load light extinguishes or if it is uncertain as to how low generator frequency became, place the DG 11 PRL CONT handswitch back to PRL position after generator frequency has stabilized at approximately 60 Hz.
CAUTION: Do not close an Offsite Power Source breaker with synchroscope indicator standing still if bus is powered from diesel generator.
- CLOSE Offsite Power Source ESF-21 Breaker 152-1501 WHEN Standby Diesel Generator 11 speed is such that synchroscope indicator is moving slowly in the SLOW direction (counterclockwise) and is approximately five minutes before the 12 o' clock position. Standard: The operator closes breaker 152-1501 by rotating BUS 15AA FDR FM ESF XFMR 21 handswitch clockwise to CLOSE at the appointed synchroscope position. This action may be repeated, if necessary, if the closing attempt is unsuccessful.
Cue: Notes: The next step is the verification of breaker 152-1501 closing.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P7520 Revision: 0
Page: 7 of 9 OBSERVE BREAKER CLOSING lights immedi ately after closing Offsite Power Source ESF-21 breaker 152-1501 to ensure breaker is closed.
Standard: The operator observes the red light illuminates on 152-1501 handswitch BUS 15AA FDR FM ESF XFMR 21. If the breaker does not close, the operator releases
the handswitch.
Cue: Notes:
PLACE Offsite Power Source ESF-21 Breaker SYNCH FEEDER 152-1501 handswitch in the OFF position as soon as Standby Diesel Generator 11 load has
stabilized.
Standard: The operator rotates the handswitch to the OFF position after diesel generator load has stabilized.
Cue:
Notes:
When the SYNCH handswitch for breaker 152-1501 is placed in OFF, the evaluator will end the JPM Task Standard(s)
- Offsite Power has been paralleled to bus 15AA IAW SOI 04-1-01-P75-1 section 4.3.
Name: _________________________________Time Start: _______Time Stop: _______
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P7520 Revision: 0
Page: 8 of 9 Task: Parallel Offsite Power via ESF-21 to Bus 15AA Follow-Up Questions & Answers
Comments:
Page: 9 of 9 Parallel Offsite Power via ESF-21 to Bus 15AA Give this page to the student
Initial Condition(s): A loss of ESF-11 supplying bus 15AA occurred.
Standby Diesel Generator 11 started and is supplying loads on the 15AA Bus.
ESF-11 is unavailable.
Initiating Cue(s): You have been directed to parallel ESF-21 to bus 15AA per Section 4.3 of procedure
04-1-01-P75-1.
All precautions and limitations of 04-1-01-P75-1 for this evolution have been verified to be met.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision: 01
Page: 1 of 8 Rtype:
QA Record
Number of pages Date Initials GJPM-OPS-P4271.00 Page 1 of 8 TRAINING PROGRAM:
OPERATIONS TRAINING
- LESSON PLAN TITLE:
ROTATE CCW PUMPS APPROXIMATE TIME REQUIRED:
10 Minutes
PREREQUISITES:
NONE SUPPORTING LESSONS:
NONE New Material Minor Revision Major Revision THIS DOCUMENT REPLACES: GJPM-OPS-P4271 Rev. 0 REASON FOR REVISION: Editorial enhancements REVIEW / APPROVAL (Print Name):
Electronic Approval (TEAR #
) Prepared By:
Kyle Grillis 2/14/09 Preparer Date Reviewed By:
Technical Reviewer (e.g., SME, line management)
Date Instructional Adequacy Determined By:
ITPL (Rev 0); Qualified Instructor (All other revisions)
Date Approved By:
++Discipline Training Supervisor Date Effective Date:
- Date ++Indicates that the LP has been reviewed by the Training Supervi sor for inclusion of Management Expectations and items reference d on the Training Development Review Worksheet FLEET/REGIONAL PROGRAM CONCURRENCE:
Fleet ENS ENN Not Applicable ANO PNPS CNPS RBS ECH VY GGNS WF3 IPEC WPO JAF
- Indexing Information GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision: 01
Page: 2 of 8 GJPM-OPS-P4271.00 Page 2 of 8 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the
intended place on the gauge.
- 3. Other methods of simulating control, operation and data collection is at the discretion of the
Evaluator.
- 4. Obtain Shift Management's permission before opening any control panel door or instrument cover.
5 It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the
evaluator give the candidate previously prepared copi es of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator. 6. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performe r should be aware that working on or near energized equipment requires, at a minimum, wearing 100% co tton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses.
Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the
Electrical Safety Rulebook and General Operating pr ocedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision: 01
Page: 3 of 8 GJPM-OPS-P4271.00 Page 3 of 8 P42 Task 71: Rotate CCW Pumps (Alternate Path)
Setting: Simulator Type: RO Task: CRO-P42-007; CRO-P42-004 K&A: 400000 2.1.30: 3.9/3.4; 2.1.31: 4.2/
3.9; A4.01: 3.1/3.0; A2.01: 3.3/3.4 295018 AK3.04: 3.3/3.3; AA1.01: 3.3/3.4 Safety Function: Plant Service Systems (8) Time Required: 10 minutes Time Critical: No Faulted: YES Performance: Perform Reference(s): SOI 04-1-01-P42-1 section 5.2; ONEP 05-1-02-V-1 section 3.1.1 Handout(s): SOI 04-1-01-P42-1; ONEP 05-1-02-V-1
- Manipulations: 4 # Critical Steps: 4 Group #: 2 Simulator Setup/Required Plant Conditions: Initialize the simulator to any IC. Insert Malfunction p42151c CCW Pump C Trip on TRIGGER 1.
Ensure CCW Pumps 'A' and 'C' are operating with CCW Pump 'B' in Standby.
Safety Concerns
- None Equipment Needed:
None.
Initial Condition(s)
- Electrical Maintenance has requested Component Cooling Water (CCW) Pump A be secured in preparation for tagout and preventive maintenance.
CCW Pumps A and C are currently in operation.
Initiating Cue(s)
- You have been directed to rotate CCW pumps to have CCW Pumps B and C operating, with CCW Pump A secured, per SOI 04-1-01-P42-1 section 5.2.
An operator is standing by at the CCW pumps ready to rotate pumps.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision: 01
Page: 4 of 8 GJPM-OPS-P4271.00 Page 4 of 8 P42 Task 71: Rotate CCW Pumps (Alternate Path)
Notes 1. None. Task Overview: This task is to rotate CCW Pumps per SOI. During the evolution, a trip will occur on one of the operating CCW pumps requiring the restart of the non-operating CCW pump per the Loss of CCW ONEP. This is an Alternate Path JPM. This is a task that is coordinated from the control room.
Tasks: Critical steps are underlined, italicized, and denoted by (*).
Remove Standby pump (CCW Pump 'B') from STANDBY by placing its handswitch to STOP. Standard: Candidate places CCW Pump 'B' handswitch to STOP.
Cue: Notes: Switch on H13-P870 section 8C.
Observes White Standby light for CCW Pump 'B' go off.
Standard: Candidate observes White Standby light for CCW Pump 'B' turns off. Cue:
Notes: Indication is on H13-P870 section 8C.
- Start CCW Pump 'B'.
Standard: Candidate starts CCW Pump 'B'. Cue: Notes: Switch on H13-P870 section 8C.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision: 01
Page: 5 of 8 GJPM-OPS-P4271.00 Page 5 of 8 Contact the local operator to close P42-F016A CCW Pump 'A' discharge valve.
Standard: Candidate contacts the local operator to close P42-F016A CCW Pump 'A' discharge valve.
Cue: CCW Pump 'A' discharge valve P42-F016A is closed. Notes:
- Stop CCW Pump 'A'.
Standard: Candidate stops CCW Pump 'A'. Cue:
Notes: Switch is on H13-P870 section 5C.
SIMULATOR OPERATOR: When CCW Pump
'A' is stopped, ensure TRIGGER 1 is activated, CCW Pump 'C' Trip.
Cue: Evaluator: after the trip annunciator comes into alarm, inform the candidate as the local operator that a small amount of water is spraying from CCW Pump 'B' pump seal on CCW Pump 'C', No water is spraying on pump 'A'.
Cue: The Control Room Supervisor directs you to take actions per the Loss of CCW ONEP.
The next two items may be performed in either order.
- Contact the local operator to open P42-F016A CCW Pump 'A' discharge valve.
Standard: Candidate contacts the local operator to open P42-F016A CCW Pump 'A' discharge valve.
Cue: CCW Pump 'A' discharge valve P42-F016A is open. Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision: 01
Page: 6 of 8 GJPM-OPS-P4271.00 Page 6 of 8
- Start CCW Pump 'A'.
Standard: Candidate starts CCW Pump 'A'. Cue: Notes: Switch on H13-P870 section 5C.
Once CCW Pump A has been started, the evaluator will terminate the JPM.
Task Standard(s)
CCW Pumps 'A' and 'B' are operating with discharge valves open.
Name: __________________________________ Time Start: _______ Time Stop: _______
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision: 01
Page: 7 of 8 GJPM-OPS-P4271.00 Page 7 of 8 P42 Task 71: Rotate CCW Pumps (Alternate Path)
Follow-Up Questions & Answers
Comments:
Page 8 of 8 Rotate CCW Pumps Give this page to the student
Initial Condition(s)
- Electrical Maintenance has requested Component Cooling Water (CCW) Pump A be secured in preparation for tagout and preventive maintenance.
CCW Pumps A and C are currently in operation.
Initiating Cue(s)
- You have been directed to rotate CCW pumps to have CCW Pumps B and C operating, with CCW Pump A secured, per SOI 04-1-01-P42-1 section 5.2.
An operator is standing by at the CCW pumps ready to rotate pumps.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5105 Revision: 0
Page: 1 of 9
Rtype:
QA Record Number of pages Date Initials TRAINING PROGRAM:
OPERATIONS TRAINING TITLE: Start RCIC for RPV Pressure Control New Material Minor Revision Major Revision REASON FOR REVISION: new JPM THIS DOCUMENT REPLACES
- N/A REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/14/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5105 Revision: 0
Page: 2 of 9 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.
- 4. Obtain Shift Management's permission before opening any control panel door or instrument cover.
5 It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator. 6. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating pr ocedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5105 Revision: 0
Page: 3 of 9 Start RCIC for RPV Pressure Control (Alternate Path)
Setting: Simulator Type: RO Task: Operate RCIC in recirc mode to control decay heat K&A: 217000 A4.01 - 3.7/3.7; A2.10 - 3.1/3.1 Safety Function: 4 Time Required: 15 minutes Time Critical: No Alternate Path: Yes Performance: Actual Reference(s): 04-1-01-E51-1, Section 5.2 04-1-01-P41-1, Section 4.2
Handout(s): # Manipulations: 11 # Critical Steps: 6 Group: 1 Simulator Setups: Reset to any IC at rated pressure Insert a scram and ensure level is maintained between Level 2 and Level 8 by other systems Insert malfunction e51044 at 0 Insert overrides ao_1e51r605 at 1567 and ao_1e51r601 at 23.72 on an auto trigger On PhD Expert, assign the auto trigger to trigger file e51f045 Safety Concerns: None Initial Condition(s): A scram occurred from rated power approximately 30 minutes ago. SSW Subsystem A has been placed in operation per procedure 04-1-01-P41-1. The plant is being controlled per EP-2.
Initiating Cue(s): You have been directed to perform a controlled start RCIC to place it in CST to CST mode for RPV Pressure Control, and attempt to stabilize RPV pressure. Use procedure 04-1-01-E51-1, Section 5.2.2. Section 5.2.1 has been completed. Other operators are responsible for RPV water level control and for monitoring Suppression Pool temperature.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5105 Revision: 0
Page: 4 of 9 Start RCIC for RPV Pressure Control (Alternate Path)
Task Overview:
This task is to start and operate RCIC iin the CST-to-CST mode to aid in decay heat removal/pressu re control. When RCIC is started, a speed controller failure will occur, causing RCIC to be unable to maintain speed above 200 rpm, the minimum for proper lubrication by the shaft driven oil pump. The operator will be required to trip RCIC to prevent turbine
damage. This is an Alternate Path JPM.
Notes 1. All controls will be from panel 1H13-P601 and 1H13-P870 in the Main Control Room.
Tasks : critical steps are underlined, italicized and denoted by (*)
START RCIC RM FAN COIL UNIT using RCIC RM FAN COIL UNIT handswitch on 1H13-P870-1C.
Standard: The operator selects the correct handswitch, starts the fan coil unit, and receives appropriate indication.
Cue: Notes:
Verify SSW Subsystem A is in operation in accordance with SOI 04-1-01-P41-1 on P870. Standard: The operator checks that SSW Subsystem A is started.
Cue: If asked, SSW Subsystem A is in operation per SOI 04-1-01-P41-1.
Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5105 Revision: 0
Page: 5 of 9 NOTE: The operator should not perform steps a or e in Section 5.2.2.
Directs local operator to close F268, PRESS LOCK ISOL FOR F013 Standard: Directs local operator to close F268 and awaits report of RCIC status.
Cue: E51F268, PRESS LOCK ISOL FOR F013, is closed Notes:
- SHIFT RCIC FLO CONT to MANUAL.
Standard: Shifts RCIC FLO CONT E51-R600 to manual control on P601.
Cue: Notes:
- REDUCE RCIC FLO CONT output to minimum.
Standard: Reduces RCIC flow controller output to minimum by depressing the CLOSE pushbutton on RCIC FLO CONT E51-R600 until the red output needle is all the way to the left.
Cue: Notes:
Standard: Opens valve F046 using it handswitch on P601.
Cue: Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5105 Revision: 0
Page: 6 of 9 START Turbine Gland Seal compressor.
Standard: Starts RCIC Turbine Gland Seal compressor using RCIC GL SEAL COMPR handswitch on P601.
Cue: Notes:
Standard: Opens F095 using its handswitch on P601.
Cue: Notes:
NOTE: Valve FO95 will close 15 seconds after valve F045 begins to OPEN.
Standard: The operator waits approximately 6 seconds after opening F095, then opens F045 using its handswitch on P601.
Cue: Notes: It is acceptable for the operator to mentally count to six instead of mechanically measuring six seconds.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5105 Revision: 0
Page: 7 of 9 INCREASE turbine speed to develop greater than 2000 rpm using RCIC FLO CONT in MANUAL.
Standard: Attempts to adjust turbine speed as needed by depressing the OPEN /
CLOSE pushbuttons on RCIC FLO CONT E51-R600 and notices speed cannot be maintained above 2000 rpm even with maximum controller output demanded, indicated by the red output needle being fully to the right.
Cue: If asked as the SRO, direct the operator to trip RCIC.
Notes:
- Secures steam to the RCIC turbine by depressing the RCIC TURB TRIP pushbutton or by RCIC TURB TRIP/THROT VLV handswitch to Close on P601.
Standard: Depresses the RCIC TURB TRIP pushbutton or rotates RCIC TURB TRIP/THROT VLV handswitch to Close on P601.
Cue: Notes:
When the operator closes the Turbine Trip/Throttle Valve, the evaluator will end the JPM Task Standard(s)
- RCIC was manually started, but when speed above 2000 rpm could not be maintained, RCIC Turbine Trip/Throttle Valve was closed.
Name: _________________________________Time Start: _______Time Stop: _______
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5105 Revision: 0
Page: 8 of 9 Start RCIC for RPV Pressure Control Follow-Up Questions & Answers
Comments:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5105 Revision: 0
Page: 9 of 9 Start RCIC for RPV Pressure Control Give this page to the student Initial Condition(s): A scram occurred from rated power approximately 30 minutes ago.
SSW Subsystem A has been placed in operation per procedure 04-1-01-P41-1.
The plant is being controlled per EP-2.
Initiating Cue(s):
Initiating Cue(s): You have been directed to perform a controlled start RCIC to place it in CST to CST mode for RPV Pressure Control, and attempt to stabilize RPV pressure. Use procedure 04-1-01-E51-1, Section 5.2.2. Section 5.2.1 has been completed.
Other operators are responsible for RPV water level control and for monitoring Suppression Pool temperature.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1225 Revision: 0
Page: 1 of 9
Rtype:
QA Record Number of pages Date Initials TRAINING PROGRAM:
OPERATIONS TRAINING TITLE: Shift Residual Heat Removal (RHR) A System from Containment Spray to Suppression Pool Cooling Mode New Material Minor Revision Major Revision REASON FOR REVISION
- N/A THIS DOCUMENT REPLACES
- N/A REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 02/14/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1225 Revision: 0
Page: 2 of 9 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.
- 4. Obtain Shift Management's permission before opening any control panel door or instrument cover.
5 It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator. 6. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating pr ocedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1225 Revision: 0
Page: 3 of 9 Shift RHR System from Containment Spray to Suppression Pool Cooling Mode Setting: Simulator Type: RO Task: Shift RHR from Containment Spray mode to Suppression Pool Cooling mode K&A: 226000 A4.03 - 3.5/3.4; A4.18 - 3.8/3.8 Safety Function: 5, Containment Integrity - RHR: Containment Spray and Suppression Pool Cooling Modes Time Required: 20 minutes Time Critical: No Alternate Path: Yes Performance: Actual Reference(s): 04-1-01-E12-1, Att. VI Handout(s): NA # Manipulations: 4 # Critical Steps: 5 Group: 1 Simulator Setups: Reset to an IC 164 (password protected) Inset malfunction e21050 LPCS Pump Trip on a manual trigger
Safety Concerns: None Initial Condition(s): A LOCA in the drywell is in progress. Emergency Depressurization has been performed. RHR is in Containment Spray Mode. LPCS, LPCI B, and LPCI C injecting for RPV level control.
Initiating Cue(s): You have been directed to realign RHR Loop A from Containment Spray to Suppression Pool Cooling mode, with cooling maximized, using 04-1-01-E12-1 Att.
VI (hard card for Suppression Pool Cooling).
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1225 Revision: 0
Page: 4 of 9 TASK: Shift RHR A System from Containment Spray to Suppression Pool Cooling Mode Notes 1. All controls will be from panels 1H13-P601 in the Main Control Room.
Task Overview:
RHR A is operating in Containment Spray Mode under Post-LOCA conditions. The other three low pressure ECCS systems are maintaining reactor water level. The candidate will
realign RHR A valves to place Suppression Pool Cooling A in service, without securing RHR A pump. When Suppression Pool Cooling A has been maximized, LPCS pump will trip, and the candidate will realign RHR A to LPCI mode for RPV level control.
Tasks : critical steps are underlined, italicized and denoted by (*)
Verify SSW A is in service to RHR A Heat Exchanger.
Standard: Checks SSW is in service by observing the following on H13-P870:
SSW A Pump running
P41-F001A, SSW PMP A DISCH VLV is Open
P41-F005A, SSW LOOP A RTN TO CLG TWR A is Open
P41-F014A, SSW INL TO RHR HX A is Open
P41-F006A, SSW PMP A RECIRC VLV is Closed . Cue: Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1225 Revision: 0
Page: 5 of 9 Verify open E12-F003A, RHR HX A OUTL VLV.
Standard: The operator verifies E12-F003A is open by observing its position indicating meter on H13-P601.
Cue: Notes:
- Resets Containment Spray A logic.
Standard: Depresses the CTMT SPR A RESET pushbutton on P601, and observes the logic white light extinguish and verifies E12-F028A, CTMT SPRAY A SPARGER INJ VLV on P601, closes Cue:
Notes:
- Opens E12-F024A, RHR A TEST RTN TO SUPP POOL
. Standard: The operator opens E12-F024A using its handswitch on P601.
Cue:
Notes: Opening of F024A causes LPCI A Mode of RHR to be inoperable, but this is not required to be communicated to the SRO under these Post-LOCA conditions
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1225 Revision: 0
Page: 6 of 9 NOTE: When the evaluator is ready, activate malfunction e21050, LPCS Pump Trip. Reactor water level will begin to fall.
- Recognizes and reports LPCS Pump Trip. Standard: Acknowledges and reports alarm 1H13-P601-21A-A7, LPCS PMP TRIP.
Cue: As the SRO direct the operator to align RHR A for LPCI mode and inject to the RPV to stabilize reactor water level Notes:
NOTE: Sequence of the next two steps is not critical.
- Closes E12-F024A, RHR A TEST RTN TO SUPP POOL.
Standard: Closes E12-F024Ausing its handswitch on P601.
Cue:
Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1225 Revision: 0
Page: 7 of 9
- Opens E12-F042A, RHR A INJ SHUTOFF VLV. Standard: The operator opens E12-F042A, receiving feedback that it is open.
Cue: Notes:
When E12-F042A is open with E12-F024A is fully closed, the evaluator will end the JPM.
Task Standard(s)
- RHR Loop A was placed in Suppression Pool Cooling mode per SOI 04-1-01-E12-1 Att VI and then realigned to LPCI mode.
Name: _________________________________Time Start: _______Time Stop: _______
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1225 Revision: 0
Page: 8 of 9 TASK: Shift RHR A System from Containment Spray to Suppression Pool Cooling Mode Follow-Up Questions & Answers
Comments:
Page 9 of 9 Shift RHR A System from Containment Spray to Suppression Pool Cooling Mode Give this page to the student Initial Condition(s): A LOCA in the drywell is in progress. Emergency Depressurization has been performed. RHR is in Containment Spray Mode. LPCS, LPCI B, and LPCI C injecting for RPV level control.
Initiating Cue(s): You have been directed to realign RHR Loop A from Containment Spray to Suppression Pool Cooling mode, with cooling maximized, using 04-1-01-E12-1 Att.
VI (hard card for Suppression Pool Cooling).
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C11216 Revision: 00
Page: 1 of 9
Rtype:
QA Record
Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE: Bypass a Control Rod in RACS New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: NEW JPM THIS DOCUMENT REPLACES
- N/A REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/13/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C11216 Revision: 00
Page: 2 of 9 Generic Instructions
- 1. Standards and cues for valve operation: a. MOVs:
- 1) "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red light is (energized or de-energized) and its green light is (energized or de-energized)".
- b. Manual valves
- 1) "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direc tion until resistance is felt."
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.
- 4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam.
These activities are not required for JPMs conducted in the Simulator.
- 5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securi ng shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
- 6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C11216 Revision: 00
Page: 3 of 9 C11(2) Task 14: Bypass a Control Rod in RACS Setting: Control Room Type: RO Task: CRO-C11(2)-014 K&A: 201005 A2.033.2/3.2; A2.04: 3.2/3.2; A2.06: 3.2/3.2; A2.07: 3.2/3.2 Safety Function: 1/7 Time Required: 20 minutes Time Critical: No Faulted: No Performance: SIMULATE Reference(s): 04-1-01-C11-2 Handout(s): 04-1-01-C11-2
- Manipulations: 2 # Critical Steps: 4 Group #: 2 Simulator Setup/Required Plant Conditions
- Permission to open Control Room Back Panel Cabinets from the Control Room
Supervisor or Shift Manager
Safety Concerns
- Do NOT allow candidate to manipulate Control Room controls. Only point and
discuss.
Initial Condition(s)
- Reactor startup is in progress. Rod Pattern Controller is in effect. Control Rod 20-09 has caused a control rod block due to the rod position out of
pattern. Reactor Engineering has been consulted and concurs with bypassing the control rod. Requirements of Engineering Procedure 17-S-02-400 have been met.
Initiating Cue(s)
- The Control Room Supervisor gives you the key to the RACS cabinets. You have been directed to bypass control rod 20-09 in both Rod Action Control
Cabinets per 04-1-01-C11-2 section 5.1. Anaother operator will complete Attachment V of 04-1-01-C11-2 in parallel with your performing the rod bypass.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C11216 Revision: 00
Page: 4 of 9 C11(2) Task 14: Bypass a Control Rod in RACS Notes 1. All Control Room operations will be on panels P651 and 652.
Task Overview This task is to bypass control rod positions in RACS 1 and 2 to allow Control Rod Movement to place the control rod in a specific position regardless of the Rod Pattern
Controller. This is done when a control rod is out of position with regard to the Rod Pattern
Controller to allow the rod to be put in pattern allowing Control Rod Blocks to be cleared.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C11216 Revision: 00
Page: 5 of 9 C11(2) Task 14: Bypass a Control Rod in RACS Tasks: Critical steps are underlined, italicized, and denoted by an (*)
Sequence within a division is critical. Performance of RACS 1 or 2 first is
NOT critical. If the candidate bypasses the rod in RACS 1 first, he then
needs only to identify RACS 2, and vice versa.
- Determine the binary address of control rod 20-09 is 00110 00011 Standard: Using Figure 1b of 04-1-01-C11-2 determines the binary address of control rod 20-09 is 00110 00011.
Cue: Acknowledge the binary address given by the candidate.
Notes: Candidate may also use chart in panel RACS 1 P651 (RACS 2 P652).
RACS 1 Unlock the cover to the binary switches on RACS 1 panel H13-P651 (RACS 2 P652)
Standard: Unlocks the cover to the binary switches on panel H13-P651 (RACS 2 P652) Cue: cover is unlocked Notes: DO NOT OPEN THE COVER!
- On a Bypass Card selects binary code 00110 00011 Standard: On a Bypass Card selects binary code 00110 00011 by placing address switches (from top to bottom) 3, 4, 9, and 10 to the right. Switches 1, 2, 5, 6, and 7 should be to the left.
Cue: The switches are in the positions you indicated.
Notes: See attached drawing
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C11216 Revision: 00
Page: 6 of 9
- Place the bypass card bypass switch to BYPASS Standard: Place the bypass card bypass switch to the right BYPASS and observes the red LED illuminate on the top of the card.
Cue: Red LED on Notes: Bypass switch is the top switch. The rod is now bypassed in RACS 1 (2) when this step is complete. . RACS 2
- Identifies RACS 2 at panel H13-P652 (RACS 1 at panel H13-P652)
Standard: Candidate indicates the rod bypass performed in RACS 1 (2) will be repeated in RACS 2 (1) by identifying H13-P652 (P651) as housing RACS 2 (1).
Cue: When the candidate identifies the second RACS cabinet, the evaluator will end the JPM Notes:
Task Standard(s)
- Control Rod 20-09 has been bypassed in RACS 1, and the candidate has identified the
location of RACS 2.
Name: ______________________________ Time Start: ______ Time Stop: _______
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C11216 Revision: 00
Page: 7 of 9 C11(2) Task 14: Bypass a Control Rod in RACS Follow-Up Questions & Answers
Comments:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C11216 Revision: 00
Page: 8 of 9
EVALUATOR KEY Do NOT give this page to Candidate!
Binary Address Depicted for Rod 20-09 00110 00011 BYPASS SWITCH "ON" - Right "OFF" - Left (shown in OFF)
Page 9 of 9 Bypass a Control Rod in RACS Give this page to the student
Initial Condition(s)
- Reactor startup is in progress. Rod Pattern Controller is in effect. Control Rod 20-09 has caused a control rod block due to the rod position out of
pattern. Reactor Engineering has been consulted and concurs with bypassing the control
rod. Requirements of Engineering Procedure 17-S-02-400 have been met.
Initiating Cue(s)
- The Control Room Supervisor gives you the key to the RACS cabinets.
You have been directed to bypass control rod 20-09 in both Rod Action Control
Cabinets per 04-1-01-C11-2 section 5.1.
Another operator will complete Attachment V of 04-1-01-C11-2 in parallel with your performing the rod bypass.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E3201 Revision: 0
Page: 1 of 14
Rtype:
QA Record Number of pages Date Initials TRAINING PROGRAM:
OPERATIONS TRAINING TITLE: Place Main Steam Isolation Valve Leakage Control System (MSIVLCS) in Service New Material Minor Revision Major Revision REASON FOR REVISION
- N/A THIS DOCUMENT REPLACES
- N/A REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/16/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E3201 Revision: 0
Page: 2 of 14 Generic Instructions
- 1. Standard cues for valve operation: a. MOVs:
- 1) "Full open" = "red light on, green light off"
- 2) "Full closed" = "red light off, green light on"
- b. Manual valves
- 1) "Full open" = "you feel resistance in the counter-clockwise direction"
- 2) "Full closed" = "you feel resistance in the clockwise direction"
- 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.
- 4. Obtain Shift Management's permission before opening any control panel door or instrument cover.
5 It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator. 6. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating pr ocedure 04-S-04-2 (Operation of Electrical Circuit Breakers)
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E3201 Revision: 0
Page: 3 of 14 Place Main Steam Isolation Valve Leakage Control System (MSIVLCS) in Service Setting: Control Room Type: RO Task: Place MSIV LCS in service K&A: 239003 A4.01- 3.2/3.2 Safety Function: 9, Radioactivity Release Time Required: 30 minutes Time Critical: No Alternate Path: Yes Performance: Actual Reference(s): 04-1-01-E32-1, Section 5.1, 5.2 and 5.4
Handout(s): # Manipulations: 12 # Critical Steps: 9 Group: 2 Simulator Setup / Required Plant Condiitons: Main control room and backpanels are accessible Safety Concerns: None Initial Condition(s): A LOCA has occurred. It has been approximately 30 minutes since the initiation of the event. All MSIVs are closed. All MSL Drain MOVs are closed. SGTS has been placed in service. MSIVLCS Outboard and Inboard subsystems are in Standby. Steam line pressure is 10 psig and lowering. OUTBD MSIV LCS PERM annunciator 1H13-P601-17A-G6 is On.
Initiating Cue(s): You have been directed to start the Outboard Main Steam Isolation Valve Leakage Control System (MSIVLCS). Use procedure 04-1-01-E32-1, Section 5.2.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E3201 Revision: 0
Page: 4 of 14 Place Main Steam Isolation Valve Leakage Control System (MSIVLCS) in Service Notes All controls will be from panels 1H13-P654, P655, and P601 in the Main Control Room.
Task Overview This task is to start the Outboard MSIV LCS. When the Outboard system is started, air blower E32-C003F will be simulated to fail to start. The Outboard MSIV LCS will be secured, and the Inboard MSIV LCS will be started
Tasks : Critical steps are underlined, italicized and denoted by (*)
NOTE: All handswitches and indicators are on 1H13-P654, unless otherwise noted.
CHECK that the 120 VAC POWER AVAILABLE light is illuminated (Start Section 5.2.2). Standard: Verifies the 120 VAC POWER AVAILABLE available lite is illuminated on P654.
Cue: White light is on.
Notes:
CLOSE MSL SHUTOFF VLV B21-F098A.
Standard: The operator closes B21-F098A using its handswitch on P601.
Cue: Green light is on, red light is off.
Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E3201 Revision: 0
Page: 5 of 14 CLOSE MSL SHUTOFF VLV B21-F098B.
Standard: The operator closes B21-F098B using its handswitch on P601.
Cue: Green light is on, red light is off.
Notes:
CLOSE MSL SHUTOFF VLV B21-F098C using its handswitch on P601.
Standard: The operator closes B21-F098C using its handswitch on P601.
Cue: Green light is on, red light is off.
Notes:
CLOSE MSL SHUTOFF VLV B21-F098D using its handswitch on P601.
Standard: The operator closes B21-F098D using its handswitch on P601.
Cue: Green light is on, red light is off.
Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E3201 Revision: 0
Page: 6 of 14 NOTE: E32-F008 and F009 will open if steam line pressure is initially 28.9 psia.
CUE: When asked, Main Steam Line Pressure trip unit 1E32-PIS-N657 indicates 25 psia.
- PLACE INITIATE OUTBD SYSTEM handswitch to OPER.
Standard: The operator rotates INITIATE OUTBD SYSTEM handswitch to OPER on P654. Cue: Handswitch is in OPER.
Notes:
- VERIFIES that the following occurs (Section 5.2.2, Substeps d. and e.):
- 1) 1E32-C002B, OUTBOARD AIR BLOWER starts
- 2) 1E32-C002F, OUTBOARD AIR BLOWER starts (in JPM it fails to start)
- 5) 1E32-F006, OUTBOARD BLEED VALVE is open
- 6) 1E32-F007, OUTBOARD BLEED VALVE is open Standard: The operator verifies that the outboard depressure and bleed valves are closed as indicated by the Note provided (with initial conditions); 1E32-C002B starts, and 1E32-C002F fails to start.
Cue: 1) 1E32-C002B, OUTBOARD AIR BLOWER - red light on, green light off
- 2) 1E32-C002F, OUTBOARD AIR BLOWER -
green light on, red light off
- 5) 1E32-F006, OUTBOARD BLEED VALVE - red light on, green light off
- 6) 1E32-F007, OUTBOARD BLEED VALVE - red light on, green light off
Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E3201 Revision: 0
Page: 7 of 14 INFORMS Control Room Supervisor that Outboard MSIVLCS is not operational.
Standard: The operator provides the information to the CRS, and acknowledges the new order.
Cue: The CRS acknowledges the information, and directs the applicant to secure the Outboard MSIVLCS per 04 01-E32-1 Section 5.4, THEN start the Inboard MSIVLCS per 04-1-01-E32-1 Section 5.1.
Notes:
NOTE: All handswitches and indicators are on 1H13-P654, unless otherwise noted.
- PLACE INITIATE OUTBD SYSTEM handswitch to OFF.
Standard: The operator places INITIATE OUTBD SYSTEM handswitch on P654 in the OFF position.
Cue: Handswitch is in OFF.
Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E3201 Revision: 0
Page: 8 of 14 VERIFIES that the following occurs:
- 1) 1E32-C002B, OUTBOARD AIR BLOWER stops
- 2) 1E32-C002F, OUTBOARD AIR BLOWER stops (remains stopped)
- 3) 1E32-F006, OUTBOARD BLEED VALVE close
- 4) 1E32-F007, OUTBOARD BLEED VALVE close (Note: There is no check in the procedure for the valve position of 1E32-F006 and -
F007.)
Standard: The operator verifies that the outboard bleed valves are closed and air blower fans 1E32-C002B and C002F are secured.
Cue: 1) 1E32-C002B, OUTBOARD AIR BLOWER
- green light on, red light off
- 2) 1E32-C002F, OUTBOARD AIR BLOWER - green light on, red light off
- 5) 1E32-F006, OUTBOARD BLEED VALVE - green light on, red light off
- 6) 1E32-F007, OUTBOARD BLEED VALVE - green light on, red light off Notes: There is procedure step for checking the valve positions of 1E32-F008 and F009.
CHECK CLOSED B21-F147A MSL DR LINE LEAK CONT on H13-P601-19C.
Standard: The operator checks closed B21-F147A MSL DR LINE LEAK CONT on P601. Cue: Green light on, red light off.
Notes:
CHECK CLOSED B21-F147B MSL DR LINE LEAK CONT on H13-P601-19C.
Standard: The operator checks closed B21-F147B MSL DR LINE LEAK CONT on P601. Cue: Green light on, red light off.
Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E3201 Revision: 0
Page: 9 of 14 Inboard System Start Up NOTE: All prerequisites in section 5.1.1 are met as initial conditions.
NOTE: All handswitches and indicators are on 1H13-P655, unless otherwise noted.
CHECK that the amber PERMISSIVE TO INITIATE SYS A, E, J, & N MSIV LCS lights are illuminated.
Standard: Checks the PERMISSIVE TO INITIATE SYS A, E, J, & N MSIV LCS lights are illuminated on P655.
Cue: PERMISSIVE TO INITIATE SYS A, E, J and N amber lights are all On Notes:
CHECK "INBD MSIV LCS PERM" annunciator 1H13-P601-17A (D6) is illuminated.
Standard: The operator verifies INBD MSIV LCS PERM annunciator on P601 is on.
Cue: Annunciatior is sealed in.
Notes:
CHECK SYSTEM A, E, J, & N white POWER AVAILABLE lights are illuminated.
Standard: The operator verifies inboard system A, E, J, & N white POWER AVAILABLE lights on P655 are on.
Cue: POWER AVAILABLE lights A, E, J, and N are on.
Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E3201 Revision: 0
Page: 10 of 14
- PLACE SYSTEM A INITIATION handswitch to OPER.
Standard: The operator SYSTEM A INITIATION handswitch to OPER on P655.
Cue: Handswitch is in OPER.
Notes:
- PLACE SYSTEM E INITIATION handswitch to OPER.
Standard: The operator SYSTEM E INITIATION handswitch to OPER on P655.
Cue: Handswitch is in OPER.
Notes:
- PLACE SYSTEM J INITIATION handswitch to OPER.
Standard: The operator SYSTEM J INITIATION handswitch to OPER on P655.
Cue: Handswitch is in OPER.
Notes:
- PLACE SYSTEM N INITIATION handswitch to OPER.
Standard: The operator SYSTEM N INITIATION handswitch to OPER on P655.
Cue: Handswitch is in OPER.
Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E3201 Revision: 0
Page: 11 of 14 ENSURE the following:
- 1) 1E32-F001A, -E, -J, -N INBOARD VALVES Open
- 2) 1E32-F002A, -E, -J, -N INBOARD VALVES Open
Standard: Checks that the following valves open:
E32-F001A E32-F001E E32-F001J E32-F001N E32-F002A E32-F002E E32-F002J E32-F002N Cue: For all listed valves - red light on, green light off.
Notes:
- OPEN B21-F147A MSL DR LINE LEAK CONT.
Standard: The operator opens B21-F147A with handswitch MSL DR LINE LEAK CONT on P601.
Cue: Red light on, green light off Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E3201 Revision: 0
Page: 12 of 14
- OPEN B21-F147B MSL DR LINE LEAK CONT.
Standard: The operator opens B21-F147B with handswitch MSL DR LINE LEAK CONT on P601.
Cue: Red light on, green light off Notes:
CUE: When the operator has completed the above step, the evaluator will end the JPM
.
Task Standard(s)
- Inboard MSIVLCS is in service IAW SOI 04-1-01-E32-1 section 5.1, and Outboard MSIV LCS is shutdown IAW 04-1-01-E32-1 section 5.4.
Name: _________________________________Time Start: _______Time Stop: _______
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-E3201 Revision: 0
Page: 13 of 14 Place Main Steam Isolation Valve Leakage Control System (MSIVLCS) in Service Follow-Up Questions & Answers
Comments:
Page: 14 of 14 Place Main Steam Isolation Valve Leakage Control System (MSIVLCS) in Service Give this page to the student Initial Condition(s): A LOCA has occurred. It has been approximately 30 minutes since the initiation of the event. All MSIVs are closed. All MSL Drain MOVs are closed. SGTS has been placed in service. MSIVLCS Outboard and Inboard subsystems are in Standby. Steam line pressure is 10 psig and lowering. OUTBD MSIV LCS PERM annunciator 1H13-P601-17A-G6 is On.
Initiating Cue(s): You have been directed to start the Outboard Main Steam Isolation Valve Leakage Control System (MSIVLCS). Use procedure 04-1-01-E32-1, Section 5.2.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C4106 Revision: 0
Page: 1 of 12
Rtype:
QA Record
Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE: STANDBY LIQUID CONTROL PUMP A MONTHLY OPERABILITY SURVEILLANCE New Material Minor Revision Major Revision Cancellation REASON FOR REVISION
- THIS DOCUMENT REPLACES
- REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/13/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C4106 Revision: 0
Page: 2 of 12 Generic Instructions
- 1. Standards and cues for valve operation:
- a. MOVs: i. "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red
light is (energized or de-energized) a nd its green light is (energized or de-energized)".
- b. Manual valves
- i. "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direction until resistance is felt." 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operation a nd data collection is at the discretion of the Evaluator.
- 4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s).
This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator. 5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may
require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Ope ration of Electrical Circuit Breakers)
- 6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration mu st be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C4106 Revision: 0
Page: 3 of 12 C41 Task 6: Standby Liquid Control Pump A Monthly Operability Setting: Plant (Inside CAA)
Type: NLO Task: Perform SLC A Monthly Pump Run Surveillance K&A: 211000 A1.09 Safety Function
- 1 Time Required: 60 minutes Time Critical: No Faulted: No Performance: Simulated Reference(s): 06-OP-1C41-M-0001 Handout(s): 06-OP-1C41-M-0001
- Manipulations: 14 # Critical Steps: 12 Group : 1
Simulator Setup/Required Plant Conditions: SLC @ Area 11/185' and 10/166' is accessible with rad levels ALARA
Safety Concerns: No climbing. Point up or down while you explain what you are going to do.
Initial Condition(s)
- SLC is in standby An operator is stationed at the SLC drain station in the Aux. Bldg. to monitor drum level. Two 55 gallon drums are stationed in the Aux Bldg. An operator is stationed at the local SLC control panel. An operator is available to monitor SLC test tank level during performance of
test. Plant is in Mode 1 Makeup water is available Initiating Cue(s)
- You have been directed to perform the SLC Pump A Monthly Operability test in accordance with 06-OP-1C41-M-0001 for SLC Pump A only. All prerequisites have been met.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C4106 Revision: 0
Page: 4 of 12 C41 Task 6: Standby Liquid Control Pump A Monthly Operability Notes: 1. Evaluator should act as communications liaison with the Control Room.
Task Overview:
This task simulates the ability to perform the SLC Pump A Monthly Operability Test.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C4106 Revision: 0
Page: 5 of 12 C41 Task 6: Standby Liquid Control Pump A Monthly Operability Tasks : Critical steps are underlined, italicized, and denoted by an (*)
Closely monitor the SLC drain drums to ensure drained solution does not overflow into the Floor Drains.
Standard: None Cue: The evaluator will act as the drain station operator Notes:
Station an operator at SLC local panel (1H22-P011) to start and stop pump.
Standard: The candidate establishes an operator at panel P011.
Cue: The evaluator will act as the operator to start and stop the pump Notes:
Station an operator at the SLC test tank level gauge to monitor and control level during the test..
Standard: The candidate establishes an operator at the SLC test tank level gauge.
Cue: The evaluator will act as the operator to maintain SLC tank level.
Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C4106 Revision: 0
Page: 6 of 12 Notify the Auxiliary Building side operator to open P48-F007 and F008, Aux. Bldg.-
side SLC drain isolation valves Standard: Simulates contacting the Auxiliary Building side operator.
Cue: Acting as the Auxiliary Building op erator the evaluator reports that P48-F007 and F008 are open.
Notes:
- Open 1C41-F031.
Standard: the 1C41-F031 handwheel in the counter-clockwise direction until resistance is felt
. Cue: Resistance is felt in the counter-clockwise direction.
Notes:
Notify the Shift Supervisor that both SLC A and B are inoperable.
Standard: Simulates contacting the Control Room.
Cue: Acting as the Shift Supervisor, the evaluator reports that information was received.
Notes:
- To fill the test tank, open 1C41-F014, Makeup Water valve.
Standard: Simulates turning the 1C41-F014 handwheel in the counter-clockwise direction until resistance is felt
. Cue: Resistance is felt in the counter-clockwise direction.
Notes: Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C4106 Revision: 0
Page: 7 of 12 Open 1C41-F806 to vent the suction side of SLC A pump.
Standard: Simulates turning the 1C41-F806 handwheel in the counter-clockwise direction until water flows from the vent
. Cue: Water is flowing from the vent.
Notes:
Close 1C41-F806.
Standard: Simulates turning the 1C41-F806 handwheel in the clockwise direction until until resistance is felt.
Cue: Resistance is felt in the clockwise direction and test tank level is in the proper operating band. Inform the candidate level in the test tank is 44 inches.
Notes:
- Close 1C41-F014, Test Tank Makeup Water valve.
Standard: Simulates turning the 1C41-F014 handwheel in the clockwise direction until resistance is felt
. Cue: Resistance is felt.
Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C4106 Revision: 0
Page: 8 of 12
- Open 1C41-F016, Recirc to Test Tank.
Standard: Simulates turning the 1C41-F016 handwheel in the counter-clockwise direction until resistance is felt
. Cue: Resistance is felt.
Notes:
- Open 1C41-F017, Recirc to Test Tank.
Standard: Simulates turning the 1C41-F017 handwheel in the counter-clockwise direction until resistance is felt
. Cue: Resistance is felt.
Notes:
- Open 1C41-F220, Recirc to Test Tank.
Standard: Simulates turning the 1C41-F220 handwheel in the counter-clockwise direction until resistance is felt
. Cue: Resistance is felt.
Notes:
Verify oil level in SLC A pump is between the upper two marks in the sightglass.
Standard: Verifies SLC A pump oil level.
Cue: As indicated.
Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C4106 Revision: 0
Page: 9 of 12 Verify gear box oil level in SLC A pump satisfies the requirements of PRECAUTION 2.11.
Standard: Check Precaution 2.11 and verifies gearbox oil level of SLC A pump.
Cue: As indicated.
Notes:
Close or check closed gauge isolation T valve for PI-R003.
Standard: Simulates turning handwheel on T valve for PI-R003 in clockwise direction until resistance if felt.
Cue: Resistance if felt.
Notes:
Start SLC A pump.
Standard: Simulates contacting the operator at the local SLC panel.
Cue: Acting as the operator at the local SLC panel, the evaluator reports that SLC A pump is running.
Notes:
If desired, Open gauge isolation T valve for PI-R003.
Standard: Simulates turning handwheel on T valve for PI-R003 in counter-clockwise direction until resistance if felt.
Cue: If asked, state opening the T-valve is not desired. Or, if the candidate opens the T-valve, state resistance is felt and the guage is responding.
Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C4106 Revision: 0
Page: 10 of 12 Verify the SLC A Pump recirculates wate r to the test tank by observing flow of >40 gpm indicated on 1C41-FI-R050.
Standard: Checks flow rate indicated on 1C41-FI-R050.
Cue: Indicated flow is >40 gpm.
Notes:
Visually inspect SLC piping up to 1C41-F004A for leaks.
Standard: Inspects for leaks.
Cue: If asked, leakage from the pump stuffing box is 8-10 drops/minute. Other than that, state no leakage is indicated.
Notes: After the candidate completes the check for leaks, the evaluator will end the JPM
Task Standard(s)
06-OP-1C41-M-0001, Standby Liquid Control Operability, has been performed through step 5.2.4g for SLC Pump A leaving SLC Pump A running in recirc to the SLC Test
Tank.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C4106 Revision: 0
Page: 11 of 12 C41 Task 6: Standby Liquid Control Pump A Monthly Operability Follow-Up Questions & Answers
Comments:
Page 12 of 12 Standby Liquid Control Pump A Monthly Operability Give this page to the student
Initial Condition(s)
- SLC is in standby An operator is stationed at the SLC drain station in the Aux. Bldg. to monitor drum level. Two 55 gallon drums are stationed in the Aux Bldg. An operator is stationed at the local SLC control panel. An operator is available to monitor SLC test tank level during performance of
test. Plant is in Mode 1 Makeup water is available
Initiating Cue(s)
- You have been directed to perform the SLC Pump A Monthly Operability test in accordance with 06-OP-1C41-M-0001 for SLC Pump A only. All prerequisites have been met.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-1 Revision: 03
Page: 1 of 10
Rtype:
QA Record
Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE: STARTUP STATIC INVERTER 1Y81 New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: editorial enhancements THIS DOCUMENT REPLACES: GJPM-OPS-L62-1 rev. 02 REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/13/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-1 Revision: 03
Page: 2 of 10 Generic Instructions
- 1. Standard cues for valve operation:
- a. MOVs: i. "Full open" = "red light on, green light off" ii. "Full closed" = "red light off, green light on" b. Manual valves
- i. "Full open" = "you feel resistance in the counter-clockwise direction" ii. "Full closed" = "you feel resistance in the clockwise direction" 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.
- 4. Obtain Shift Management's permission before opening any control panel door or instrument cover.
- 5. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time
should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam.
These activities are not required for JPMs conducted in the Simulator. 6. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE.
Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure
04-S-04-2 (Operation of Electrical Circuit Breakers)
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area.
Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-1 Revision: 03
Page: 3 of 10 L62 Task 1: Startup Static Inverter 1Y81 Setting: Plant (Outside CAA)
Type: NLO Task: NLO-L62-002 K&A: 262002 2.1.30: 3.9/3.4; A4.01: 2.8/3.1 Safety Function: Electrical (6) Time Required: 15 minutes Time Critical: No Faulted: Yes Performance: Simulate Reference(s): SOI 04-1-01-L62-1 Section 4.1, Attachment III Handout(s): SOI 04-1-01-L62-1, Attachment III
- Manipulations: 6 # Critical Steps: 7 Group #: 1 Simulator Setup/Required Plant Conditions: Area 25A elevation 148' accessible. Shift Manager/ Control Room Supervisor permission to conduct JPMs.
Safety Concerns
- 1. Do NOT allow candidate to manipulate plant equipment.
- 2. Due to Protected Train concerns may substitute Inve rter 1Y79 or 1Y80. If this is done review the SOI for the alternate circuit breaker numbers.
Equipment Needed:
None.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-1 Revision: 03
Page: 4 of 10 Initial Condition(s)
- Inverter 1Y81 is shutdown with both Battery Input breaker CB1 and Inverter Output breaker CB2 Open. The Alternate Source is supplying the loads for 1Y81.
DC Bus 11DL is energized and circuit breaker 72-11L04 is closed. The Manual Bypass Switch for Inverter 1Y81 is selected to Alternate Source To Load. The Alternate (AC) Power feeder breaker 52-164226 is closed. The Alternate Source AC Input breaker CB4 is open.
Initiating Cue(s)
- You have been directed to startup Inverter 1Y81 and transfer the loads to the Normal Source per SOI 04-1-01-L62-1 section 4.1.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-1 Revision: 03
Page: 5 of 10 L62 Task 1: Startup Static Inverter 1Y81 Notes 1. If Division 2 is the Protected Train, an alternate Static Inverter may be substituted.
Task Overview:
This task is to startup a BOP Static Inverter and transfer the Uninterruptable Power Supply loads to the inverter per the SOI.
Tasks: Critical steps are underlined, italicized, and denoted by (*).
Static Inverter 1Y81 is located in the RPS 'B' Motor Generator Room 148' elevation Control Building.
Check Alternate (AC) Power and Primary (DC) Power feeder breakers are closed.
Standard: Candidate checks Alternate (AC) Power and Primary (DC) Power feeder breakers are closed.
Cue: Breakers are in the closed position.
Notes: Given in Initial Conditions may not be checked further, this is acceptable.
Check REVERSE POLARITY light is off.
Standard:
Candidate checks REVERSE POLARITY light is off.
Cue: Light is off.
Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-1 Revision: 03
Page: 6 of 10
- Depress PRECHARGE pushbutton until Precharge light comes on.
Standard: Candidate depresses PRECHARGE pushbutton until Precharge light comes on.
Cue: Precharge light is on.
Note: The next step should be preformed within 10 seconds of the precharge light being illuminated.
- Close BATTERY INPUT breaker.
Standard: Candidate closes the BATTERY INPUT breaker CB1.
Cue: Breaker indicates closed.
Notes: Observes the following indications: DC INPUT voltmeter reads 125 volts. Both AC OUTPUT voltmeters indicate 125 +/- 5 volts. AC OUTPUT frequency meter reads 60 +/-0.06 Hz.
Standard: Candidate confirms the above indications.
Cue: As the candidate checks an indication give them the following indication:
DC INPUT- 125VDC, AC OUTPUT VOLT- 125 VAC, AC OUTPUT FREQ- 60 HZ Notes:
- Close ALTERNATE SOURCE AC INPUT breaker.
Standard:
Candidate closes ALTERNATE SOURCE AC INPUT breaker CB4.
Cue: Breaker closed.
Notes: If asked by the operator, the Manual Bypa ss Switch is in the ALTERNATE SOURCE TO LOAD position.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-1 Revision: 03
Page: 7 of 10
- Transfer the Manual Bypass Switch to NORMAL OPERATION position.
Standard: Candidate transfers the Manual Bypass Switch to NORMAL OPERATION position.
Cue: Switch is in Normal Operation position.
Notes: Large two position barrel switch.
- Close INVERTER OUTPUT breaker.
Standard: Candidate closes INVERTER OUTPUT breaker CB2.
Cue: Breaker closed.
Notes: If asked cue the candidate the Alternate Source is still supplying the load.
Observes the following indications: PRECHARGE light is on. INVERTER SUPPLYING LOAD light is OFF. INSYNC light is on. All other lights are off. Both AC OUTPUT ammeters indicate positive values.
Standard: Candidate confirms the above indications.
Cue: INFORM the candidate the indications are as above.
Notes:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-1 Revision: 03
Page: 8 of 10
- Recognizes INVERTER SUPPLYING LOAD light being Off is not expected.
Standard:
Candidate recognizes that INVERTER SUPPLYING LOAD light should be ON, and consults the procedure for needed action.
Cue: None
Notes: Once the inverter output breaker was closed, the static switch should have automatically transferred back to the normal supply (inverter supplying the load).
- Depress INVERTER TO LOAD pushbutton.
Standard:
Candidate depresses INVERTER TO LOAD pushbutton.
Cue: INVERTER SUPPLYING LOAD light is on.
Notes:
If asked cue the candidate the Control Room annunciator for Inverter Trouble has cleared.
If asked cue the candidate another operator will clear Caution Tags.
Task Standard(s)
Inverter 1Y81 has been started and load transferred to the Normal supply of the Inverter powering load
per 04-1-01-L62-1 section 4.1.
Name: __________________________________ Time Start: _______ Time Stop: _______
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-1 Revision: 03
Page: 9 of 10 L62 Task 1: Startup Static Inverter 1Y81
Follow-Up Questions & Answers
Comments:
Page: 10 of 10 Startup Static Inverter 1Y81 Give this page to the student
Initial Condition(s)
- Inverter 1Y81 is shutdown with both Battery Input breaker CB1 and Inverter Output breaker CB2 Open. The Alternate Source is supplying the loads for 1Y81.
DC Bus 11DL is energized and circuit breaker 72-11L04 is closed. The Manual Bypass Switch for Inverter 1Y81 is selected to Alternate Source To Load. The Alternate (AC) Power feeder breaker 52-164226 is closed. The Alternate Source AC Input breaker CB4 is open.
Initiating Cue(s)
- You have been directed to startup Inverter 1Y81 and transfer the loads to the Normal Source per SOI 04-1-01-L62-1 section 4.1.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP26 Revision: 02
Page: 1 of 13
Rtype:
QA Record
Number of pages Date Initials TRAINING PROGRAM:
OPERATOR TRAINING TITLE: Align Fire Water to LPCS and RHR C per EP Attachment 26 New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: major editorial changes, new format THIS DOCUMENT REPLACES: GJPM-NLO-EP026 Rev 01 REVIEW / APPROVAL (Print Name):
Prepared By:
Kyle Grillis 2/13/09 **Preparer Date Ops Review
++: Technical Reviewer (e.g., SME, line management) Date Validated By:
Training Representative Date Approved By:
+Discipline Training Supervisor Date Approval Date:*
- Indexing Information ** The requirements of the Training Material Checklist have been met.
+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenc ed on TQJA-201- DD06, Training Material Checklist.
++ Indicates that Operations has reviewed and approved this material for exam use.
FLEET/REGIONAL PROGRAM CONCURRENCE
TO RM INITIAL RECEIPT
BY RM (DATE/INITIAL)
RETURNED FOR
CORRECTIONS (DATE/INITIAL)
RETURN RECEIPT (DATE/INITIAL)
FINAL ACCEPTANCE
BY RM (DATE/INITIALS)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP26 Revision: 02
Page: 2 of 13 Generic Instructions
- 1. Standards and cues for valve operation:
- a. MOVs: i. "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red
light is (energized or de-energized) a nd its green light is (energized or de-energized)".
- b. Manual valves
- i. "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direction until resistance is felt." 2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.
- 3. Other methods of simulating control, operation a nd data collection is at the discretion of the Evaluator.
- 4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s).
This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator. 5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may
require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Ope ration of Electrical Circuit Breakers)
- 6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).
- 7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).
- 8. During activities within the CAA, consideration mu st be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.
Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP26 Revision: 02
Page: 3 of 13 Task: Align Fire Water to LPCS and RHR C per EP 6 Setting: Plant (Inside CAA)
Type: NLO Task: Align Firewater to LPCS and RHR C per EP Attachment 26 K&A: 286000 A1.05: 3.2/3.2; 295031 EA 1.08: 3.8/3.9; 2.1.30: 3.9/3.4; 2.4.35: 3.3/3.5 Safety Function
- 2,8 Time Required: 20 minutes Time Critical: No Faulted: No Performance: Simulated Reference(s): 05-S-01-EP-1 Attachment 26 Handout(s): 05-S-01-EP-1 Attachment 26
- Manipulations: 6 # Critical Steps: 12 Group : 2 Simulator Setup/Required Plant Conditions: Auxiliary Building 119' elev., Areas 9/10 are accessible with rad levels ALARA
Safety Concerns: No climbing is allowed. .
Initial Condition(s)
- A LOCA has occurred. The reactor is shutdown with RPV level still lowering. The SRO with the Command Function is implementing EP-2 actions.
Initiating Cue(s)
- The SRO with the Command Function has directed you to obtain EP-2 Attachment 26, Injection into RPV with Fire Protection Water System, and align Fire Water for
injection through LPCS and RHR 'C'. Plant Services is dispatching a ladder and extra fire hoses to the area.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP26 Revision: 02
Page: 4 of 13 Task: Align Fire Water to LPCS and RHR C per EP 6 Notes: 1. Fire hoses and nozzles are not to be disturbed during task performance.
Task Overview:
This task simulates routing and connecting fire hoses from hose stations to test connections on ECCS injection piping in the Auxiliary Building.
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP26 Revision: 02
Page: 5 of 13 Task: Align Fire Water to LPCS and RHR C per EP 6 Tasks : Critical steps are underlined, italicized, and denoted by an (*)
Sequence for which path is aligned first is not critical. Path 3 may be aligned before path 2. Within a path, the only portion of the sequence
that is critical is that the fire hose is connected before either the hose station valve or the pair of injection line test connection valves is
opened.
Locate a copy of EP Attachment 26.
Standard: Candidate describes location of the dedicated copy of Attachment 26 in a box on top of the Control Room Emergency Locker.
Cue: When the candidate describes the location of the box containing the EP attachments, hand the candidate the JPM copy of Attachment 26 Notes:
Ensures at least one fire pump is running
.
Standard: The candidate contacts a control room operator and requests him to start at least one fire pump on H13-P862 by depressing its remote START pushbutton on
SH13-P862.
Cue: The Motor Driven Fire Pump is running.
Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP26 Revision: 02
Page: 6 of 13 Ensures a pathway for Fire Water is aligned to the Auxiliary Building header.
Standard: The candidate contacts a control room operator and requests him to ensure open at least one of the following sets of valves:
P64-F282A AND F282B, FIRE WTR SPLY HDR #1 TO AUX BLDG on 1H13-P870.
P64-F283A AND F283B, FIRE WTR SPLY HDR #2 TO AUX BLDG on 1H13-P870.
P64-FA10A, FIRE HDR #1 BYP AUX BLDG ISOL on 1H13-P862.
P64-FA10B, FIRE HDR #2 BYP AUX BLDG ISOL on 1H13-P862.
Cue: P64-F282A AND F282B are open.
Notes:
Obtains spanner wrench
Standard: Describes the location where a spanner wrench may be obtained.
Cue: You have a spanner wrench.
Notes: The procedure states spanner wrenches can be obtained at the most convenient fire breakout locker. They may also be obtained from the Fire Truck House, tool room, and some hose stations.
RHR C, Pathway 2 Locate HOSE STATION 13B.
Standard: Locates hose station 13B (Area 9 El. 119' by stairwell)
. Cue: Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP26 Revision: 02
Page: 7 of 13
- Remove nozzle from existing hose on Hose Station 13B
. Standard: Describes removal of the nozzle from the hose on hose station 13B using common technique for right hand threads.
Cue: The nozzle is removed Notes:
- Attach an additional 50 feet of hose.
Standard: Locates a 50 foot section of hose (provided by Plant Services in the Initial Conditions) and connects it to the hose on the hose reel of HS-13B using common technique for right hand threads.
Cue: When asked, tell the candidate as Plant Services that a 50 foot section of hose has been placed on the floor beneath hose station 13B. After the candidate
describes connecting the hose section, state the hose section is attached Notes:
- Route and attach hose to RPV fill connection 1E12-F056C/F057C.
Standard: Locates 1E12-F056C/F057C in the piping penetration room Area 9/10 and describes routing the hose from hose station 13B into the room and connecting it to the special fitting at E12-F057 using common technique
for right hand threads..
Cue: The hose is connected Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP26 Revision: 02
Page: 8 of 13
- Slowly open Hose Station 13B isolation valve SP64-FA12V
. Standard: Describes slowly opening Hose Station 13B isolation valve SP64-FA12V by turning the valve handle CCW.
Cue: The hose is pressurized and you feel resistance.
Notes:
- Slowly open fill connection inboard valve 1E12-F056C.
Standard: Describes slowly opening fill connection 1E12-F056C by turning the valve handle CCW.
Cue: You feel resistance Notes:
- Slowly open fill connection outboard valve 1E12-F057C.
Standard: Describes slowly opening fill connection 1E12-F057C by turning the valve handle CCW.
Cue: You feel resistance and hear flow.
Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP26 Revision: 02
Page: 9 of 13 LPCS, Pathway 3 Locate HOSE STATION 14B.
Standard: Locates hose station 14B (Area 9 El. 119' outside of switchgear room)
. Cue: Notes:
- Remove nozzle from existing hose on Hose Station 14B
.
Standard: Describes removal of the nozzle from the hose on Hose Station 14B using common technique for right hand threads.
Cue: The nozzle is removed Notes:
- Route hose to the piping/penetration room.
Standard: Locates 1E21-F013/F014 in the piping penetration room Area 9/10 and describes routing the hose from hose station 14B into the room.
Cue: The hose is in place Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP26 Revision: 02
Page: 10 of 13
Standard: Describes connecting the hose from hose station 14B into the room and connecting it to the special fitting at E21-F014 using common technique
for right hand threads.
Cue: The hose is connected Notes:
- Slowly open Hose Station 14B isolation valve SP64-FA13B
.
Standard: Describes slowly opening Hose Station 13B isolation valve SP64-FA13B by turning the valve handle CCW.
Cue: The hose is pressurized and you feel resistance.
Notes:
- Slowly open fill connection inboard valve 1E21-F013.
Standard: Describes slowly opening fill connection 1E21-F013 by turning the valve handle CCW.
Cue: You feel resistance Notes:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP26 Revision: 02
Page: 11 of 13
- Slowly open fill connection outboard valve 1E21-F014.
Standard: Describes slowly opening fill connection 1E21-F014 by turning the valve handle CCW.
Cue: You feel resistance and hear flow. (End of JPM)
Notes:
Task Standard(s)
Fire Water has been aligned to RHR C, pathway 2, and to LPCS, pathway 3, in accordance with 05-S-01-EP-1 Attachment 26.
Name: ___________________________ Time Start: _______ Time Stop: _______
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP26 Revision: 02
Page: 12 of 13 Task: Align Fire Water to LPCS and RHR C per EP 6 Follow-Up Questions & Answers
Comments:
Page 13 of 13 Align Fire Water to LPCS and RHR C per EP Attachment 26 Give this page to the student
Initial Condition(s)
- A LOCA has occurred. The reactor is shutdown with RPV level still lowering. The SRO with the Command Function is implementing EP-2 actions.
Initiating Cue(s)
- The SRO with the Command Function has directed you to obtain EP-2 Attachment 26, Injection into RPV with Fire Protection Water System, and align Fire Water for
injection through LPCS and RHR 'C'. Plant Services is dispatching a ladder and extra fire hoses to the area.
Appendix D Scenario Outline Form ES-D-1 Scenario 1 Facility: GRAND GULF NUCLEAR STATION Scenario No.:
1 Op-Test No.:
030209 Examiners: _________________________ Operators:__________________________ _________________________ __________________________
_________________________ __________________________
Objectives: To evaluate the candidates' ability to operate the facility in response to the following evolutions:
- 1. Rotate EHC pumps.
- 2. Recognize and respond to indications of a Seal Steam Pressure Controller failure. 3. Respond to RPS MG Set B trip.
- 4. Recognize and respond to Reactor Reci rc Flow Control Valve A failing open.
- 5. Respond to bus 16AB lockout.
- 6. Respond to an ATWS.
- 7. Respond to a SSW C Pump trip.
Initial Conditions:
Reactor Power is at 73 %.
INOPERABLE Equipment None Turnover: The plant is at 73% power during startup. Power ascension is temporarily suspended to place EHC pump C in service and re move EHC pump A from operation in accordance with SOI 04-1-01-N3 2-1. No out of service equipment and EOOS is green. Division 1 work week is in effect.
REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 1 of 20
Appendix D Scenario Outline Form ES-D-1 Scenario 1 REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 2 of 20 Event No. Malf. No.
Event Type* Event Description 1 N(BOP) Rotate EHC pumps - start C and secure A (SOI 04-1 N32-1 section 5.1) 2 ms255 C(ACRO) Recognize and respond to indi cations of a Seal Steam Pressure Controller failure. (ARI 1H13-P680-10A-E7) 3 c71077b C(ACRO) Respond to RPS MG Set B trip (05-1-02-III-2) 4 di_1b33k603ac
C(ACRO) Recognize and respond to Recirc FCV A Controller
Failure (FCV Opens) 5 r21139f C(BOP) Respond to ESF bus 16AB lockout (ONEP 05-1-02-I-4)
6 c11164 @ 10
M (ALL) Respond to an ATWS (EP-2A)
7 p41149 C(BOP) Respond to SSW C Pump trip * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks
- Upon recognition of ATWS conditions, perform actions to insert control rods by scramming and/or driving.
- When conditions are met in EP-2A, terminate and prevent injection to exercise power/level control, and re-establish injection to control RPV level in accordance with EP-2A.
Appendix D Simulator Operation Form ES-D-2 Scenario 1 CREW TURNOVER The plant is at 73% power during startup at se ction 6.5 of IOI 03-1-01
-2 and step 177 of the control rod movement sequence.
The target control rod pa ttern has not been reached.
Power ascension is temporarily suspended to place EHC pump C in service and remove EHC pump A from operation. Immediately fo llowing turnover, the BO P operator is to perform the EHC pump rotation in accordance with SOI 04-1-01-N32-1 section 5.1.
There is no out of service equipment, and EOOS is green.
A Division 1 work week is in effect.
SIMULATOR SETUP Start the process from a new simulator load. Reset to IC-124 (password protected).
Verify or perform the following:
IC: 124 OOS: none Active malfunctions: c11164 @ 10%
SDV Block c41f001a_i SLC A suction valve power loss on stroke p41149 SSW C Pump trip
Active overrides none Pending overrides di_1b33k603ac fast_open Recirc FCV A Failure Open (TRG 4)
Pending malfunctions:
ms255 @ 27 Seal Steam Pressure Controller Fail Low (TRG 2) c71077b RPS B MG Set Trip (TRG 3) r21139f Bus 16AB Lockout (TRG 5) Trigger files:
none BAT/CAEP files:
hpuastart.cae Restarts Recirc FCV A HPU on P634 (TRG 10)
REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 3 of 20
Appendix D Simulator Operation Form ES-D-2 Scenario 1 SIMULATOR SETUP (Continued)
Startup all PDS / SPDS scr eens. Clear any graphs and trends off of SPDS.
Setup cyclops display and verify it is functional.
Ensure the correct control rod movement sequence is available at the P680.
Mark IOI for startup to 73% power 03-1-01-02 Attachment II through Step 6.4 completed, as appropriate.
Place/position turnover guide, red tag, and LCO paperwork as applicable.
Erase all temporary markings from control room panels, posted operator aids, switch covers, and indicators.
Erase all prior markings from procedures and hard cards expected to be referenced by the crew during this scenario.
Advance all chart recorders and ensure all pens are inking properly.
(APRM chart recorders must be turned on and settings for scales on pens 0 - 125 scale)
REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 4 of 20
Appendix D Simulator Operation Form ES-D-2 Scenario 1 SIMULATOR OPERATION Once simulator is reinitialized and setup complete take the simulator out of Freeze.
Once the Crew has taken control, note the simulator time.
EHC Pump Rotation Provide role play as local operator verify ing EHC pump C discharge pressure is normal after it is started.
The local operator observes discharge pressure on EHC Fluid pump C, just started, is approximately the same as the other runni ng pumps by monitoring applicable local pressure indicators:
CF PMP A, 1N32-PI-R006A (low pressure) 1N32-PI-R018A (high pressure)
CF PMP B, 1N32-PI-R006B (low pressure) 1N32-PI-R018B (high pressure)
CF PMP C, 1N32-PI-R006C (low pressure) 1N32-PI-R018C (high pressure)
When the lead evaluator is ready to proceed, activate TRIGGER 2, (Seal Steam Pressure Controller Failure)
Respond to Seal Steam Pressure Controller Failure (Low)
The ACRO should announce 1H13-P680-10A-E7 TURB SS PRESS LO and check seal steam pressure on P680. The operator may place the seal steam controller in manual on P680 and attempt manual control using the rais e pushbutton, but this will be unsuccessful. The operator will manually control turbine s eal steam header pressure at approximately
20"wc using the bypass valve around the failed pr essure control valve via MN TURB SSCV BYP VLV F105 JOG OPEN/CLOSE pushbuttons on 1H13-P680
REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 5 of 20
Appendix D Simulator Operation Form ES-D-2 Scenario 1 SIMULATOR OPERATION (Continued)
When the lead evaluator is ready to proceed, activate TRIGGER 3, (RPS B MG Set Trip)
RPS B MG Set Trip (05-1-02-III-2)
The ACRO should announce alarms RX SCRAM TRIP and HCU TROUBLE and recognize
a half scram exists on RPS B. ACRO will di agnose the half scram is due to loss of RPS B power because no scram signals are annunciated.
The CRS will enter 05-1-02-III-2 Loss of One or Both RPS Busses ONEP and direct R PS B power be transferred to the alternate supply. The BOP operator will transfer RPS B to Alternate via a backpanel handswitch per the ONEP, and the ACRO will rese t the division 2 half scram. The CRS should enter TR 3.1.5 Conditions A and B for HCU Accumulator Instrumentation since any accumulator pressure or moisture condition would hav e been masked by the sealed-in HCU trouble alarm, which was caused by the power monitoring circuit under half scram conditions.
Cue: When dispatched report RPS B MG Set feels warmer than norma l to the touch, and its breaker, 52-142229, is tripped.
When ONEP actions have been completed and the lead evaluator is ready to proceed, initiate TRIGGER 4, (Recirc FCV A Fail Open)
Recirc FCV A Controller Failure (FCV Opens)
No alarms directly identifying this failure will be received. The ACRO will observe a rise in power, generator output, feedw ater controller output, and/or core flow and diagnose positive reactivity addition. If the ACRO recognizes Recirc FCV A failing open before the valve is fully open, he will trip the FCV HPU by arming and depressing the HPU A SHUTDOWN pushbutton on P680. Because of the resulting difference in Recirc loop flows, the CRS will enter TS 3.4.1 Conditi on A, which requires the Recirc loop flow mismatch to be restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
When the problem with FCV A is reported corrected, the crew will restore the Recirc loop flow mismatch to within the limit by closing FCV A.
Cues: After the CRS has addressed TS for mismatched Recirc loop flows, as I&C
report the problem has been corrected and the FCV can be operated as
desired. As Reactor Engineering advise the crew to match Recirc loop flows by closing FCV A to matc h the position of FCV B.
If necessary, restart HPU using Tr igger 10 (runs file hpuastart.cae)
REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 6 of 20
Appendix D Simulator Operation Form ES-D-2 Scenario 1 SIMULATOR OPERATION (Continued)
When the lead evaluator is ready to proceed, Initiate Trigger 5, Bus 16AB Lockout.
The BOP operator will repor t loss of power to Division 2 bus. The CRS will enter Loss of AC Power ONEP 05-1-02-I-4. After DG12 does not restore bus power within the normal timeframe, as indicated by receipt of DIV 2 LSS SYS FAIL alarm, P864-2A-H1, the BOP operator will attempt to close the feeder from ESF transformer 21 and/or 12. He will then report bus 16AB is locked out. Due to the lo ss of power to Division 2 equipment, the CRS will enter ONEPs for air operated isolation valv e closures, CRD pump trip, loss of fuel pool cooling, loss of cooling water. If core flow is greater than 67 Mlbm/hr, the ACRO will lower core flow to 67 Mlbm/hr in accordance with loss of PSW ONEP 05-1-02-V-11. Plant Service Water isolation valves to the auxiliary building failing closed will result in rising temperatures of TBCW and CCW. Due to risi ng TBCW temperature, Generator Seal Oil temperature will not be able to be maintained bel ow the limit of 125°F, and a manual scram will be required per Loss of TBCW ONEP 05-1-02-V-2.
Cues: As electricians, report there is pr obable bus bar damage to bus 16AB.
ATWS When the ACRO places the RMS to Shutdown to scram the reactor, he will recognize and report that rods did not fully insert and diagn ose a hydraulic block of the scram discharge volume exists. The CRS will enter EP-2A and di rect actions to insert rods. Power will be above 4% requiring the ACRO to terminate feedwat er injection to lower level to -70" to -
130" in order to reduce power. The BOP operator will terminate and prevent injection from ECCS. Bypass valves will be available to automatically control pressure. The BOP operator will attempt SLC initiation and will be fo rced to call for Alternate Boron Injection.
After EP Attachments 18 and 19 are installed, control rod insertion via repetitively scramming will be possible. Then after Attachment 20 is inst alled, control rods can be driven in.
EP Attachments that may be requested Time to install Att 12 - Defeat RHR Shutdown Cooling interlocks 6 minutes Att 18 - Defeat ATWS ARI 5 minutes Att 19 - Defeat RPS 5 minutes Att 20 - Defeat RCIS 5 minutes Att 8 - Defeat MSIV Le vel 1 Isolation 9 minutes Att 1 - Defeat RCIC High Supp P ool Level Suction Transfer 8 minutes Att 2 - Defeat RCIC Low Steam S upply Pressure Isolation 8 minutes Att 3 - Defeat all RCIC Isolations 8 minutes Att 28 - Alternate Boron Injection Not modeled REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 7 of 20
Appendix D Simulator Operation Form ES-D-2 Scenario 1 REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 8 of 20 Standby Service Water (SSW) C Pump Trip When HPCS is initiated and overridden, SSW Pump C will trip.
The BOP operator will check for proper operation of HPCS support systems, DG13 and SSW C, and will recognize the failure of SSW C. He will advise the SRO, and because DG13 will be running without cooling water, he will shut down DG13 by depressing its emergency stop pushbutton on P601 per SOI 04-1-01-P81-1 section 6.6.
TERMINATION
Once Control Rods are being inserted and as directed by the Lead Evaluator, terminate the scenario by placing the simulator in freeze and turning the "horns" off.
Critical Tasks
- Upon recognition of ATWS conditions, perform ac tions required to insert control rods by scramming and/or driving.
- When conditions are met in EP-2A, terminate and prevent injection to exercise power/level control, and re-establish injection to control RPV level in accordance with EP-2A.
Emergency Classification Site Area Emergency per EAL Failure of RPS SS3.
Appendix D Operator Actions Form ES-D-2 Scenario 1 Op-Test No.: _
030209____ Scenario No.: __
1___ Event No.: ___
1__ Event
Description:
Rotate EHC Pumps A and C (SOI 04-1-01-N32-1 section 5.1)
Time Position Applicant's Actions or Behavior
BOP Places STANDBY EHC Fluid pump into operation by first depressing CF PMP C START pushbutton, then depressing C AUTO pushbutton.
Directs local operator to observe that discharge pressure on EHC Fluid pump just started is approximately the same as t he other running pumps by monitoring applicable local pressure indicators:
CF PMP A, 1N32-PI-R006A (low pressure) 1N32-PI-R018A (high pressure)
CF PMP B, 1N32-PI-R006B (low pressure) 1N32-PI-R018B (high pressure)
CF PMP C, 1N32-PI-R006C (low pressure) 1N32-PI-R018C (high pressure)
Shuts down EHC pump A by depressing CF PMP A STOP pushbutton on 1H13-P680-10C. Waits approximately 30 seconds, then depresses CF PMP A AUTO pushbutton.
Observes that CF PRESS HP SIDE and CF PRESS LP SIDE remain at greater than 455 psig and 175 psig respectively on 1H13-P680-10B.
Clears annunciator "CF PMP SWITCH TO AUTO", 1H13-P680-10A (C-5).
REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 9 of 20
Appendix D Operator Actions Form ES-D-2 Scenario 1 Op-Test No.: __
030209___ Scenario No.: __
1___ Event No.: ___
2__ Event
Description:
Seal Steam Pressure Controller failure. (ARI 1H13-P680-10A-E7) Time Position Applicant's Actions or Behavior ACRO Recognizes and reports TURB SS PRESS LO (1H13-P680-10A-E7) and notes seal steam pressure decreasing and seal steam control valves N33-F505A/
B closing on P680 meters.
CRS Directs manually controlling s eal steam pressure using the seal steam pressure control bypass valve per ARI P680-10A-E7 step 3.6.
ACRO Controls turbine seal steam header pressure at approximately
19.6"wc by throttling open the bypass valve around the failed pressure control valve via MN TURB SSCV BYP VLV F105
JOG OPEN/CLOSE pushbuttons on 1H13-P680 CRS Directs checking condenser vacuum BOP Monitors and reports c ondenser vacuum as directed CRS Notifies Duty Mgr and Ma intenance of the seal steam pressure control failure REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 10 of 20
Appendix D Operator Actions Form ES-D-2 Scenario 1 Op-Test No.: __
030209___ Scenario No.: __
1___ Event No.: ___
3__ Event
Description:
RPS MG Set B trip (05-1-02-III-2)
Time Position Applicant's Actions or Behavior ACRO Announces Half Scram and HCU Trouble alarms on P680. Diagnoses condition is due to loss of RPS B power.
CRS Enters 05-1-02-III-2 Loss of One or Both RPS Busses ONEP
and direct RPS B power be transfe rred to the alternate supply BOP Transfers RPS B to Alternate by placing MG SET B TRANSFER switch on Panel 1H13-P610 to ALT "B." per 05-1-02-III-2 step 3.1.3 ACRO Resets Division 2 half scram using HS-M601 B and D on Panel P680 by placing switches momentarily to reset per 05-1-02-III-2 step 3.1.4 BOP May request status of MSIV so lenoid lights and amp meters from the simulator operator (these indicators are not modeled) CRS Sends operator to check status of RPS MG Set B and normal
supply EPA breakers CRS Enters TR 3.1.5 Conditions A and B for HCU Accumulator
Instrumentation for the time t he half-scram exis ted due to the HCU accumulator trouble alarm being sealed in and masking any actual low pressure/high moisture condition.
CRS Notifies Duty Mgr and Maintenan ce of RPS MG set B failure.
REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 11 of 20
Appendix D Operator Actions Form ES-D-2 Scenario 1 Op-Test No.: __
030209___ Scenario No.: __
1___ Event No.: ___
4__ Event
Description:
Recirc FCV A Controller Failure (FCV Opens)
Time Position Applicant's Actions or Behavior ACRO Recognizes and reports a rise in power, generator output, feedwater controller output, and/or core flow and diagnoses positive reactivity addition is due to Recirc FCV A failing open ACRO Trips the FCV HPU by arming and depressing the HPU A SHUTDOWN pushbutton on P680.
CRS Notifies Reactor Engineering of reactivity event and to check
thermal limits and margin to preconditioning envelope CRS The CRS will enter TS 3.4.1 Condition A due to Recirc loop flow mismatch CRS Notifies Duty Mgr and Ma intenance of event. Directs Maintenance to restore operability of FCV A.
CRS When the problem with FCV A is reported corrected, CRS conducts reactivity brief for closing FCV A to restore the Recirc loop flow mismat ch to within the limit.
CRS Directs restarting one subloop on FCV A HPU (note: HPUs are not physically modeled in the simulator, so the simulator
operator performs this)
CRS Directs ACRO to match Recirc loop flows by slowly closing FCV A ACRO Closes Recirc FCV A using m anual loop A flow controller on P680 in slow detent REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 12 of 20
Appendix D Operator Actions Form ES-D-2 Scenario 1 Op-Test No.: __
030209___ Scenario No.: __
1___ Event No.: ___
5__ Event
Description:
ESF Bus 16AB lockout (ONEP 05-1-02-I-4)
Time Position Applicant's Actions or Behavior BOP Recognizes and reports loss of power to Division 2 bus. After DG12 does not restore bus power within the normal
timeframe, as indicated by re ceipt of DIV 2 LSS SYS FAIL alarm, P864-2A-H1, the BOP operator will attempt to close the feeder from ESF transforme r 21 and/or 12. He will then report bus 16AB is locked out.
CRS Enters Loss of AC Power ONEP 05-1-02-I-4. Directs building operator and electrical maintenance to investigate 16AB
lockout. BOP Recognizes and reports isolation valves failing closed due to
loss of power CRS Enters Automatic Isolations ONEP 05-1-02-III-5 and Loss of PSW ONEP 05-1-02-V-11. Directs monitoring PSW, TBCW, CCW, and Generator Seal Oil temperatures.
ACRO If core flow is greater than 67 Mlbm/hr, the ACRO will lower core flow to 67 Mlbm/hr in accordance with loss of PSW
ONEP 05-1-02-V-11.
ACRO/ BOP Demands PDS computer displays for Loss of PSW/CCW/TBCW ONEPS BOP Reports CRD pump B trip. Starts CRD pump A on P601 per CRD Malfunctions ONEP 05-1-02-IV-1 step 2.1.2:
Places CRD SYS FLO CONT in MANUAL and reduces output to zero. Starts standby CRD pump. Adjusts CRD SYS FLO CONT to 54-66 gpm after charging pressure is normal. Returns CRD SYS FLO CONT to AUTO with tapeset at 54-66 gpm.
REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 13 of 20
Appendix D Operator Actions Form ES-D-2 Scenario 1 Time Position Applicant's Actions or Behavior ACRO Recognizes and reports P680 alarms indicating loss of Spent Fuel Pool Cooling CRS Enters Inadequate Decay Heat Removal ONEP 05-1-02-III-1, directs monitoring Spent Fuel Pool temperature ACRO/ BOP Reports cooling water temperatures rising, Seal Oil
temperature approaching 125°F CRS Declares total loss of PSW/TBCW due to rising cooling
water/seal oil temperatures.
Directs manual scram per 05 02-V-11 step 3.2.5a ACRO Places RMS in Shutdown. Provides scram report: All control rods not fully inserted Reactor power above 4% Indications of SDV hydraulic block Reactor level being controlled by FW control system Reactor pressure being controlled by EHC control system REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 14 of 20
Appendix D Operator Actions Form ES-D-2 Scenario 1 Op-Test No.: __
030209___ Scenario No.: __
1___ Event No.: ___
6__ Event
Description:
Time Position Applicant's Actions or Behavior CRS Enters EP-2A. Directs ARI-RPT initiation BOP Initiates ARI/RPT by arming/depressing ARI/RPT INIT channel 1 and channel 2 pushbuttons on P680 CRS Directs ADS inhibited BOP Inhibits ADS by plac ing channel A and Channel B handswitches to INHIBIT on P601 CRS Directs HPCS initiated and overridden.
BOP Initiates and overrides HPCS by holding handswitch for E22-F004 in CLOSE while arming
/depressing HPCS MAN INIT pushbutton and then placing HPCS pump handswitch to stop on P601.
ACRO Aligns Startup Level Control per 04-1-01-N21-1 Att. VII:
On P680, closes the following valves: N21-F009A, FW HTR 6A OUTL VLV N21-F009B, FW HTR 6B OUTL VLV.
On P870, opens the following valves: N21-F001, SU FCV OUTL ISOL VLV. N21-F010A, HP FW HTR STRNG A SU OUTL VLV.
N21-F010B, HP FW HTR STRNG B SU OUTL VLV.
On P680, verifies the following valves are closed: N21-F513, X WTR LVL SU CONTR Valve (via controller 1C34-LK-R602) N21-F510, FW CU RECIRC VLV N21-F040, FW S U BYP VLV REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 15 of 20
Appendix D Operator Actions Form ES-D-2 Scenario 1 Time Position Applicant's Actions or Behavior ACRO Recovers a RFP per 04-1-01-N21-1 Att. VI at P680: (may be delayed if Level 9 was reached due to HPCS injection)
Restarts the 'A' AC lube oil pump for RFPT to be restarted by depressing STOP then AUTO for the oil pump. Opens RFP A(B) DISCH VLV N21-F014A(B).
Depresses the RFPT A(B) TRIP RESET pushbutton.
Raises pump speed using the RAISE pushbutton until governor position is approx. 60%
or as required to obtain discharge pressure approx. 250 psig above reactor pressure.
Adjusts N21-F513, RX WTR LVL SU CONT valve, as necessary in MANUAL to mainta in desired Reactor level. N21-F040 and/or N21-F009A(B) may be OPEN/CLOSED as necessary to augment flow.
CRS Directs BOP to monitor/control reactor pressure 800-1060 psig using turbine/bypass valves CRS Orders installation of Attachments 8 of EP-2.
CRS** Directs terminating condensate
/feedwater injection to a band of -70" to -130" wide range.
ACRO** Terminates feedwater injection by closing startup level control valve N21-F513 on P680. When reactor level decreases below
-70" WR, injects by opening t he startup level control valve and attempts to stabilize level in the middle of the prescribed band,
-100" WR. Controls Feedwater to maintain level in band.
REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 16 of 20
Appendix D Operator Actions Form ES-D-2 Scenario 1 Time Position Applicant's Actions or Behavior CRS Directs preventing low pressure ECCS injection BOP Prevents LP ECCS injection by arming/depressing Div 1 and Div 2 ECCS INIT pushbuttons and placing handswitches for LPCS, RHR A, RHR B, RHR C pumps to STOP and injection
valves to CLOSE Verifies associated manual override alarms
seal in on P601.
BOP Reports reactor Level 2 as level lowers and resulting isolation BOP Reports drywell pressure 1.23 psig due to DW Purge Compressor operation and resulting isolation CRS Directs restoring instrument air to containment following L2 /
high drywell pressure isolation BOP** Reopens P53-F001 on P870 (section 3C) following Level 2/High DW Pressure isolation BOP At P807, restores isolations as directed using 05-1-02-III-5 Att. II:
Opens P44-F121, F118, F122, F117 (section 3C) Opens P72-F121, F122, F125 (section 3C)
CRS Orders Standby Liquid Control initiated prior to Suppression Pool Temperature reaching 110 F. BOP When ordered, initiates Standby Liquid Control using 04 01-C41-1 Att. I (hard card)
BOP When SLC A is initiated, identifies the failure of SLC pump A suction valve manifested by P 601 status light and loss of valve position indication. Reports SLC A suction valve failure and SLC B unavailable due to previous bus 16AB lockout.
CRS Orders implementation of 8 Alternate Boron Injection.
REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 17 of 20
Appendix D Operator Actions Form ES-D-2 Scenario 1 Time Position Applicant's Actions or Behavior CRS Directs CRD flow maximized BOP Maximizes CRD flow: Places CRD SYS FLO CONT C11-R600 in MANUAL. USING CRD SYS FLOW CONT C11-R600, fully opens C11-F002A(B), CRD FLO CONT VLV. Fully opens C11-F003, CRD DRIVE WTR PRESS CONT VLV CRS ** Orders installation of Attachments 18, 19, and 20 of EP-2.
CRS When Attachments 18, 19, and 20 are reporte d installed, directs resetting scram and maximizing CRD drive water p ressure. ACRO Resets RPS A by placing RPS Div 1 and 3 Reset switches to RESET on P680.
BOP Maximizes CRD drive water pr essure by fully closing C11-F003, CRD DRIVE WTR PRESS CONT VLV on P601 BOP ** Inserts Control Rods by scramming rods using RPS A scram arm/depress pushbuttons and/or by selecting control rods on RC&IS and depressing IN TIMER SKIP pushbutton on P680.
REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 18 of 20
Appendix D Operator Actions Form ES-D-2 Scenario 1 REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 19 of 20 Op-Test No.: __
030209___ Scenario No.: __
1___ Event No.: ___
7__ Event
Description:
SSW Pump C Trip (04-1-01-P81-1)
Time Position Applicant's Actions or Behavior BOP After initiating and overriding HPCS for EP-2A, checks for proper operation DG13 (P601) and SSW C (P870).
Recognizes and reports SSW C has tripped and DG13 is running without cooling water.
CRS Directs securing DG13.
BOP Stops DG13 by depressing HPCS DSL ENG EMERG STOP pushbutton on P601 per 04-1-01-P81-1 step 6.6.2a(1).
- denotes critical task
Crew Turnover
- The plant is at 73% power during st artup at section 6.5 of IOI 03 01-2 and step 177 of the control rod movement sequence. The target control rod pattern has not been reached.
Power ascension is temporarily suspended to place EHC pump C in service and remove EHC pump A from operation. Immediately following turnover, the BOP operator is to perform the EHC pump rotation in accordance with SOI 04-1-01-N32-1 section 5.1.
There is no out of service equi pment, and EOOS is green.
A Division 1 work week is in effect.
Appendix D Scenario Outline Form ES-D-1 Scenario 2 Facility: GRAND GULF NUCLEAR STATION Scenario No.:
2 Op-Test No.:
030209 Examiners: ________________________ Operators:__________________________
________________________ _________________________
________________________ __________________________
Objectives: To evaluate the candidates' ability to operate the facility in response to the following evolutions:
- 1. Raise reactor power from 81%
to 88% using Recirc FCVs.
- 2. Recognize and respond to a low failu re of APRM B Flow Reference Signal resulting in an APRM B Upscale.
- 3. Recognize and respond to Reacto r Feed Pump B Controller failure -
increasing speed.
- 4. Respond to an SRV failing open.
- 5. Recognize and respond to failure of HPCS suction to automatically align to Suppression Pool on high Suppression Pool level.
- 6. Respond to bus 12HE lockout.
- 7. Respond to trip of Service Transformer 11.
Initial Conditions:
Reactor Power is at 81 %.
INOPERABLE Equipment None Turnover: The plant is at 81% power following a tem porary downpower for a control rod pattern adjustment. Power ascension is to continue to 88% where it will be held due to fuel preconditioning limitations. The current envel ope is at 90% power. There is no out of service equipment. EOOS is green.
A Division 1 work week is in effect.
REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 1 of 23
Appendix D Scenario Outline Form ES-D-1 Scenario 2 REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 2 of 23 Event No. Malf. No.
Event Type* Event Description 1 R(ACRO) Raise reactor power from 81% to 88% using Recirc FCVs (03-1-01-2) 2 aprmbus C(ACRO) APRM B Flow Reference Signal Failure Low - APRM Upscale (ARI 04-1-021H13-P680-5A-B10) 3 fw121b C(ACRO) Reactor Feed Pump B Controller failure - increasing speed (05-1-02-V-7) 4 di_1b21606d
C(BOP) Respond to an SRV B21-F041D failing open (EP-3) 5 Att 4 C(BOP) Respond to failure of HPCS suction to automatically align to Suppression Pool on high Su ppression Pool level (ARI 1H13-P601-16A-C5) 6 r21138b C(ACRO) Respond to bus 12HE lockout (ONEP 05-1-02-I-4)
7 r21133a M (ALL) Respond to trip of Service Transformer 11 (ONEP 05-1-02-I-4, EP-2)
8 e51050 e51187a e51187b M (ALL) Respond to a RCIC steam li ne break in the RCIC room with failure/inability to isolate (EP-4)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks
- When Maximum Safe temperature is reached in RCIC Room and auxiliary building Steam Tunnel, enters the Emergency Depressurization leg of EP-2 and opens at least 7 SRVs.
- During Emergency Depressurization, ma intains reactor water level above -
192" Compensated Fuel Zone using Condensate system.
Appendix D Simulator Operation Form ES-D-2 Scenario 2 CREW TURNOVER The plant is at 81% power at the target r od pattern following a temporary downpower for a control rod pattern adjustment. Power ascensi on is in progress at 03-1-01-2 Attachment VIII step 12.9.
The current fuel preconditioned envelope is at 90% power. Reactor Engineering has requested power be raised to 88% immediately a fter turnover. Power will be held there for 30 minutes, then another ramp rate edit will be obtained.
There is no out of service equipment, and EOOS is green. A Division 1 work week is in effect.
SIMULATOR SETUP Start the process from a new simulator load. Reset to IC-123 (password protected).
Verify or perform the following:
IC: 123 OOS: none Active malfunctions:
e51187a RCIC Steam Sply E51F063 loss of power on stroke e51187b RCIC Steam Sply E51F064 loss of power on stroke
Active overrides none Active Remote Functions:
Att 4 Done Defeat HPCS high Supp P ool suction transfer Att 3 Done Defeat all RCIC isolations
Pending Rem. Functions:
ms065 Pulled SRV B21F041D division 2 fuses (TRG 13)
Pending overrides di_1b21m606d Open SRV B21F041D Failure Open (TRG 4)
P601_16a_c_5 HPCS Supp Pool Level High (TRG 5)
Pending malfunctions: fw121b @ 70, r90 RFP B controller failure - increasing (TRG 3) r21138b Bus 12HE Lockout (TRG 6) r21133a Service Transformer 11 Lockout (TRG 7) e51050 RCIC steam leak upstream of F045 (TRG 8) tte31n031a_d @ 220, r300 Steam tunnel temper ature (TRG 17) tte31n031b_d @ 220, r300 Steam tunnel temper ature (TRG 17) tte31n031c_d @ 220, r300 Steam tunnel temper ature (TRG 17) tte31n031d_d @ 220, r300 Steam tunnel temper ature (TRG 17)
Trigger files:
rcicsplvlhi RCIC Supp Pool level high alarm on (TRG 5) BAT/CAEP files:
aprmbus APRM B Flow Reference Failure (TRG 2)
REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 3 of 23
Appendix D Simulator Operation Form ES-D-2 Scenario 2 SIMULATOR SETUP (Continued)
Startup all PDS / SPDS scr eens. Clear any graphs and trends off of SPDS.
Setup cyclops display and verify it is functional.
Ensure the correct control rod movement sequence is available at the P680.
Mark IOI for startup to 81% power 03-1-01-02 Temporary Do wnpower Attachment VIII through Step 12.8 completed, as appropriate.
Place/position turnover guide.
Erase all temporary markings from control room panels, posted operator aids, switch covers, and indicators.
Erase all prior markings from procedures and hard cards expected to be referenced by the crew during this scenario.
Advance all chart recorders and ensure all pens are inking properly.
(APRM chart recorders must be turned on and settings for scales on pens 0 - 125 scale)
REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 4 of 23
Appendix D Simulator Operation Form ES-D-2 Scenario 2 SIMULATOR OPERATION Once simulator is reinitialized and setup complete take the simulator out of Freeze.
Once the Crew has taken control, note the simulator time.
Raise power from 81% to 88% using Recirc flow The ACRO will open Recirc FCVs in slow detent to raise power to 88%. The BOP operator will raise turbine load demand as power is raised.
When the lead evaluator is ready, activate TRIGGER 2, (APRM B Upscale)
APRM B Flow Reference Signal Failure Low - APRM Upscale
The ACRO should recognize and report APRM Upscale and Control Rod Withdrawal Block alarms and diagnose the condition is attributable to APRM B. Flux indication for APRM B will be unchanged, so the operator should diagnose the condition is related to a change in the upscale setpoint. The operat or may check the flow biased alarm setting by depressing the PUSH TO REC button for APRM B recor der on P680 per ARI P680-5A-B10 step 3.6. The crew will determine the condition is not valid and will bypass APRM B per ARI step 3.8 using SOI 04-1-01-C51-1 section 5.1. TS will still be satisfied since seven APRMs will remain operable, but the CRS will discuss initiating a Potentia l LCO for APRM B with respect to TS 3.3.
1.1 and TR 3.3.2.1.
Cue: As I&C, state that a problem must exist in th e APRM B electronics and a work request will be required for troubleshooting.
When the lead evaluator is ready, activate TRIGGER 3, (Reactor Feed Pump B Controller Failure)
Reactor Feed Pump B Controller Failure (Increasing)
The ACRO should note the perturbation in FW controller outputs on P680 and diagnose RFP B controller is malfunctioning. The AC RO should place RFP B speed controller in manual per Feedwater System Malfunctions ONEP 05-1-02-V-7 step 2.1 and stabilize the feedwater pumps. The operator may lower output on RFP B to match feed pump flows.
The CRS may elect not to reduce RFP B speed, allowing time for conservative decision making, since the transient will have terminated when controller output was stabilized. Power ascension will be suspended with the controller in manual. I&C will be contacted to investigate.
Cue: As I&C, state that a work request will be required for troubleshooting.
REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 5 of 23
Appendix D Simulator Operation Form ES-D-2 Scenario 2 SIMULATOR OPERATION (Continued)
When the lead evaluator is ready, activate TRIGGER 4, (SVR B21F041D Fails Open)
SRV B21-F041D Fails Open (EP-3))
The BOP operator should respond to ala rm 1H13-P601-19A-A5 SRV/ADS VLV OPEN/
DISCH LINE PRESS HI and recognize B21F041D is open from the r ed light on its P601 handswitch. The ACRO should observe a perturbation in FW controller output and a step decrease in generator output. The BOP operator should diagnose the Division 2 solenoid for B21F041D is energized by observing the red solenoid light on the P601 vertical section above the SRV handswitches. The CRS should direct attempting to close the SRV by placing its handswitches on P601 and P631 to O FF. When this is unsuccessful, the CRS should direct maintenance to pull Division 2 fuses for B21F041D. The CRS should direct Suppression Pool temperature monitoring as a critical parameter and establish scram criteria at 110°F Suppression Pool temperature. The CRS may direct Suppression Pool Cooling be placed into operation. The SRV discharge will cause Suppression Pool level to rise above the EP-3 entry condition limit of 18.81 ft. The CRS will enter EP-3, then
simulation of fuses being pulled will close t he SRV. The CRS shoul d enter TS 3.6.2.2 Condition A and direct action to lower Suppre ssion Pool level to less than 18.81 ft. within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> using P11, HPCS, or RCI C per EP-3, although the crew is not expected to progress to performing that action within the timeframe of the scenario. By the time the SRV is closed, Suppression Pool Temperature will be near the EP-3 entry condition. If Suppression Pool Cooling is placed into operati on, entry into TS 3.5.1 Condition A (for one loop) or Condition C (if two loops are placed into operation). Pulling of the Division 2 fuses for B21F041D will require entry into TS 3.3.
5.1 Conditions
F and G fo r ADS trip system B.
Cue: When requested to pull fuses for B21F041D, wait until average Suppression Pool water level exceeds 18.81 feet, then activate Trigger 5 to simulate pulling Division 2 fuses, and report Divi sion 2 fuses have been pulled.
REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 6 of 23
Appendix D Simulator Operation Form ES-D-2 Scenario 2 Failure of HPCS suction to automatically align to Suppression Pool on high Suppression Pool level (ARI 1H13-P601-16A-C5)
As Suppression Pool level is rising while SRV B21F041D is open, high Suppression Pool
level signals will be received by HPCS and RCIC systems. RCIC sucti on will automatically align to Suppression Pool as designed, however, HPCS sucti on will not. The BOP operator will recognize and report the fa ilure of HPCS PMP SUCT FM SUPP POOL E22F015 to open and HPCS PMP SUCT FM CST E22F001 to close. The CRS should enter TS 3.3.5.1 Condition D and direct HPCS suction be manually align ed to the Suppression Pool within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Cue: If requested, report Suppression Pool L evel trip units E22-LIS-N655C and G are tripped and indicate high Suppression Pool level.
When TS have been addressed and the lead evaluator is ready to proceed, initiate TRIGGER 6, (Bus 12HE Lockout)
Bus 12HE Lockout (ONEP 05-1-02-I-4)
The BOP operator will respond to alarms on P807 indicating the incoming feeder breaker from BOP transformer 11B to 6.9KV bus 12HE has tripped and undervoltage conditions exist on associated 480V busses. The BO P operator will attempt to close the supply breaker from BOP transformer 12B, but being unsuccessful, will report bus 12HE is locked out. The CRS will enter Loss of AC Power ONEP 05-1-02-I-4, but it will provide no additional actions. Though no direct alarms relating to core flow will be received, the ACRO should recognize a large drop in power and diagnose and report it is due to the core flow reduction resulting from loss of power to Recirc pump B. The ACRO should close B33F067B and plot the point of operation on the Power/Flow Map in the Restricted Region. The CRS will enter Reduction in Recirc Flow Rate ONEP 05-1-02-III-3 and direct the ACRO to monitor for thermal hydraulic instability without concurrent duties. The CRS should immediately begin preparing for action to exit the Restricted Region using CRAM rod insertion. The ACRO should report loss of Circ Water Pump B due to the bus loss. The CRS should direct the BOP operator to monitor condenser vacuum, which will stabilize above the operating limit of 23.5"Hg. Afte r CRAM rods are inserted and the Restricted Region is exited, the CRS should direct FCTR and thermal limit setpoints be installed for single Recirc Loop operation per TS 3.4.1. The CRS should direct Circ Water system
alignment for single pump/doubl e train operation per 03-1-01-2 and begin working through that IOI to ensure system alignments are proper for reduced pow er conditions. Some other plant auxiliaries, such as pl ant chilled water, will have been lost due to the bus 12HE trip, but nothing that will require an immediate plant shutdown. The CRS should notify the Duty Mgr and direct maintenance to assess the c ondition of bus 12HE and provide a repair estimate.
Cues: As Electrical Maintenance, report there is no apparent damage to the exterior of bus 12HE, but a tagout for bus 12HE is needed for internal inspection.
REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 7 of 23
Appendix D Simulator Operation Form ES-D-2 Scenario 2 SIMULATOR OPERATION (Continued)
When the lead evaluator is ready to proceed, initiate TRIGGER 7 (Service Transformer 11 Lockout)
Service Transformer 11 Lockout The BOP operator will report loss of Service Transformer 11 and resulting loss of power to busses 13AD and 15AA. The BOP operator will verify DG11 re-energizes bus 15AA. He will manually re-energize bus 13AD via BOP Transformer 12A from P807 and direct the building operator to reset bus 13AD undervoltage lockout relays. The ACRO will observe loss of both Reactor Feed Pumps due to loss of power to their AC oil pumps and will place the Reactor Mode Switch to Shutdown due to the imminent Level 3. The CRS will enter Loss of AC Power ONEP 05-1-02-I-4, Feedwat er Systems Malfunct ions ONEP 05-1-02-V-7, and Reactor Scram ONEP 05-1-02-I-1.
When the BOP operat or is made aware Feedwater has tripped, he should ensure RCIC and HP CS are initiated, as required. After bus 13AD has been re-energized, the ACRO should restart the 'A' AC oil pump for either Reactor Feed Pump and align Condensate/Feedwater on Startup Level Control. The crew should coordinate securing HPCS to transition to Condensate/Feedwater for level control. The CRS should direct restoring Plant Service Water to the auxiliary building and instrument air to containment per Automatic Isolations ONEP 05-1-02-III-5.
Approximately five (5) minutes after the scram, initiate TRIGGER 8 (RCIC Steam Line Break)
RCIC Steam Line Break with Inability to Isolate
The BOP operator will respond to and report EP-4 Alarm RCIC EQUIP AREA TEMP HI (1H13-P601-21A-G3) and RCIC turbine trip. He will verify the signal is valid by observing independent RCIC room temperature alarms (1H13-P601-21A-H2 and H3), the PDS EP-4 Operator Guide, and/or Division 2 Leak Dete ction temperature swit ches on backpanel P642 and recognize steam supply isolation valves E51F063 and E51F064 did not automatically close, as required. The BOP operator will attempt to manually close E51F063 and E51F064 from P601, but the valves will lose power in the open position. The CRS will enter EP-4 and assign the BOP operator to monitor EP-4 parameters as a critical parameter. The CRS should dispat ch a repair team to restore power to at least one of the RCIC isolation valves. The BOP operator will observe and report RCIC room temperature above its Maximum Safe limit. The CRS may el ect to lower pressure to a band of 450-600 psig to reduce the driving head of the leak per Operation Philosophy step 6.4.3. The BOP operator will observe auxiliary building steam tunnel temperature rising toward its Maximum
Safe limit. The CRS should anticipate Emergency Depressurization being required because RCIC room communicates with the st eam tunnel and should fully open main bypass valves to the condenser per EP-2 step P-
- 1. Once auxiliary building steam tunnel temperature reaches its Maximum Safe limit, indicated on the LDS common temperature meter on P642 by the BOP operator selecting "read" for temperat ure switch E31-TS-N604B or F, the CRS will enter the Emergency Depressurization leg of EP-2 as required by REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 8 of 23
Appendix D Simulator Operation Form ES-D-2 Scenario 2 REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 9 of 23 EP-4 step 10. The BOP operat or will open 8 ADS/SRVs from P601. The ACRO will ensure Condensate is aligned with Startup Level Control in autom atic to maintain reactor water level during the depressurization. This includes ensuring RFP discharge valve N21F014A and/or B are reopened if they had closed due r eaching Level 9 from the swell following HPCS injection.
EP Attachments that may be requested Time to install Att 12 - Defeat RHR Shutdown Cooling interlocks 6 minutes Att 1 - Defeat RCIC High Supp P ool Level Suction Transfer 8 minutes
TERMINATION Once Control Rods are being inserted and as directed by the Lead Evaluator, terminate the scenario by placing the simulator in freeze and turning the "horns" off.
Critical Tasks
- When Maximum Safe temperature is reac hed in RCIC Room and Auxiliary Building Steam Tunnel, enters the Emergency Depressurization leg of EP-2 and opens at least 7 SRVs.
- During Emergency Depressurization, main tains reactor water level above -192" Compensated Fuel Zone using Condensate system.
Emergency Classification Site Area Emergency per EAL FS2 Loss of 2 Fission Product Barriers, (RC3 and PC3)
Appendix D Operator Actions Form ES-D-2 Scenario 2 Op-Test No.: __
030209___ Scenario No.: __
2___ Event No.: ___
1__ Event
Description:
Raise reactor power from 81% to 88% using Recirc FCVs (03-1-01-2)
Time Position Applicant's Actions or Behavior CRS Conducts reactivity briefing and directs power increase to 88%
ACRO Raises power by simultaneously opening Recirc flow control valves in slow detent on P680. Monitors APRMs, recirc drive flows, total core flow, reactor water level on P680 during power increase.
BOP Raises load turbine demand using LOAD DEMAND RAISE pushbutton on P680 to maintain the load demand limited value within 65 MW above generator actual load during the power ascension Op-Test No.: __
030209___ Scenario No.: __
2___ Event No.: ___
2__ Event
Description:
APRM B Flow Reference Signal Failure Low - APRM Upscale (ARI 04-1-021H13-P680-5A-B10)
Time Position Applicant's Actions or Behavior ACRO Recognizes and reports APRM Upscale and Control Rod Withdrawal Block alarms attributable to APRM B.
ACRO Observes APRM recorders and notes all APRM readings are unchanged. Checks the flow biased alarm setting by depressing the PUSH TO REC button for APRM B recorder on P680 per ARI P680-5A-B10.
CRS Determines the condition is not valid and directs bypassing APRM B per ARI P680-5A-B10 step 3.8.
ACRO Bypasses APRM B using the Division 2 APRM Bypass Joystick on P680 per SOI 04-1-01-C51-1 section 5.1.
BOP Verifies the bypassed light is illuminated on the drawer for APRM B on P671 in the control room backpanel area per the SOI.
CRS Enters a Potential LCO for TS 3.3.1.1 and TR 3.3.2.1 for one APRM inoperable REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 10 of 23
Appendix D Operator Actions Form ES-D-2 Scenario 2 Op-Test No.: __
030209___ Scenario No.: __
2___ Event No.: ___
3__ Event
Description:
Reactor Feed Pump B Controller failure - increasing speed (05-1-02-V-7)
Time Position Applicant's Actions or Behavior ACRO ACRO should note the perturbat ion in FW controller outputs on P680 and diagnose RFP B contro ller is malfunctioning. The ACRO should place RFP B speed controller 1C34-FK-
R613 on P680 vertical section or RFP B controls on P680 apron section in manual per F eedwater System Malfunctions ONEP 05-1-02-V-7 step 2.1 and stabilize the feedwater
pumps. The operator may lower output on RFP B to match
feed pump flows by depressing the LOWER pushbutton on
the associated controller..
CRS Enters Feedwater Systems Ma lfunction ONEP 05-1-02-V-7 and directs manual control of RF P B. The CRS may elect not
to immediately reduce RFP B speed. Suspends power ascension and formulates contingencies for the controller in
manual. CRS Notifies Duty Mgr and I&C of the controller failure.
BOP If RFP B reaches the point at which a high vibration alarm is
received, directs operator to c heck vibration monitoring panel in the control building and to check RFP B operation locally.
CRS If a high vibration condition exis ts for RFP B, directs reducing RFP B speed to reduce vibration levels in accordance with
the intent of ARI 1H 13-P680-2A-E12 step 4.1.
ACRO Slowly lowers RFP B speed controller output as directed REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 11 of 23
Appendix D Operator Actions Form ES-D-2 Scenario 2 Op-Test No.: __
030209___ Scenario No.: __
2___ Event No.: ___
4__ Event
Description:
SRV B21F041D Fails Open (ARI P601-19A-A5, EP-3) Time Position Applicant's Actions or Behavior BOP Responds to alarm SRV/ADS VLV OPEN/ DISCH LINE PRESS HI and recognize B21F 041D is open from the red light on its P601 handswitch. Recognizes the Division 2
solenoid for B21F041D is energized by observing the red solenoid light on the P601 vertical section ACRO Confirms SRV open based on a step decrease in generator
output. BOP Attempts to close SRV by plac ing its P601 handswitch to OFF per ARI P601-19A-A5 step 3.4.
CRS Directs placing Division 2 handswitch for B21F041D to OFF
on P631. BOP Places Division 2 handswitch fo r B21F041D to OFF on P631, as directed.
CRS Directs monitoring Suppressi on Pool Temperature as a critical parameter and assigns scram criteria of 110°F average Suppression P ool temperature.
BOP Frequently reports Suppression Pool temperature, as directed.
CRS Directs I&C to pull Division 2 fuses for B21F041D.
CRS May direct placing Suppression Pool Cooling in operation for pool circulation and cooling bef ore reaching the EP-3 entry condition of 95°F.
BOP Reports Suppression Pool level high from alarms and indications on P870 and P601.
CRS Enters EP-3 and TS 3.6.2.2 Condition A on Suppression Pool level above 18.81 ft. Directs action to reduce Suppression Pool level to the normal band using P11, HPCS, or RCIC within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per TS.
REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 12 of 23
Appendix D Operator Actions Form ES-D-2 Scenario 2 Time Position Applicant's Actions or Behavior CRS If Suppression Pool Cooling is placed into operation, enters TS 3.5.1 Condition A (for one loop) or Condition C (if two
loops are placed into operation). Note: Since below the EP-3 entry condition of 95°F Suppression Pool temperature, only one loop of Suppression Pool Cooling should be placed into
operation to minimize plant risk.
CRS Enters TS 3.3.5.1 Conditions F and G for ADS trip system B
due to pulling of the Division 2 fuses for B21F041D REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 13 of 23
Appendix D Operator Actions Form ES-D-2 Scenario 2 Time Position Applicant's Actions or Behavior BOP If directed to place Suppression Pool Cooling into operation, Starts SSW A(B) at P870 to support Suppression Pool Cooling using 04-1-01-P41-1 Att. VIII as follows
- Presses both SSW Div 1(2) MAN INIT pushbuttons.
OR Performs the following: Checks open P41-F006A(B), SSW PMP A(B) RECIRC VLV Starts SSW pump A(B). Opens the following valves:
P41-F001A(B), SSW PMP A(B) DISCH VLV P41-F014A(B), SSW INL TO RHR HX A(B) P41-F068A(B), SSW OUTL FM RHR HX A(B) Opens P41-F005A(B), SSW LOOP A(B) RTN TO CLG TWR A(B). Closes P41-F006A(B), SSW PMP A(B) RECIRC VLV. Starts Cooling Tower Fans P41-C003A&B (C&D).
Starts RHR A(B) at P601 in Suppression Pool Cooling using 04-1-01-E12-1 Att. VI as follows:
Verifies open E12-F003A(B), RHR HX A(B) OUTL VLV. Starts RHR PMP A(B). Opens E12-F024A(B), RHR A(B) TEST RTN TO SUPP POOL. Closes E12-F048A(B), RHR HX A(B) BYP VLV. Verifies E12-F064A(B), RHR A(B) MIN FLO TO SUPP POOL, Closes when flow exceeds 1000 gpm. Refers to appropriate sections of 04-1-01-P41-1 and 04-1-01-E12-1 when time permits REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 14 of 23
Appendix D Operator Actions Form ES-D-2 Scenario 2 Op-Test No.: __
030209___ Scenario No.: __
2___ Event No.: ___
5__ Event
Description:
Failure of HPCS Suction to Automatically Align to Suppression Pool on High Suppressi on Pool Level (ARI 1H13-P601-16A-C5)
Time Position Applicant's Actions or Behavior BOP Responds to SUPP POOL LV L HI alarm P601-16A-C5.
Recognizes and reports the failure of HPCS PMP SUCT FM SUPP POOL E22F015 to open and HPCS PMP SUCT FM CST E22F001 to close.
CRS Enters TS 3.3.5.1 Condition D and directs HPCS suction be manually aligned to the Suppression Pool within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
BOP Realigns HPCS suction to S uppression Pool per SOI 04 01-E22-1 steps 5.4.2b and 5.4.2d:
Opens HPCS PMP SUCT FM SUPP POOL E22F015 Ensures HPCS PMP SUCT FM CST E22F001 closes when F015 reaches fully open.
CRS Notifies Duty Mgr and I&C of the failure.
REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 15 of 23
Appendix D Operator Actions Form ES-D-2 Scenario 2 Op-Test No.: __
030209___ Scenario No.: __
2___ Event No.: ___
6__ Event
Description:
BOP Bus 12HE lockout (ONEP 05-1-02-I-4)
Time Position Applicant's Actions or Behavior BOP Recognizes and reports loss of power to bus 12HE and attempts to close the supply breaker from BOP transformer 12B, then reports bus 12HE is locked out..
CRS Enters Loss of AC Power ONEP 05-1-02-I-4. Directs building
operator and electrical maint enance to investigate 12HE lockout. ACRO Recognizes a large drop in power and diagnoses and reports
loss of power to Recirc pump B. Closes B33F067B per 05 02-I-4 step 3.2.
ACRO Plots the point of operation on the Power/Flow Map in the Restricted Region BOP Verifies ACRO's plot on the Power/Flow Map.
CRS Enters Reduction in Recirc Flow Rate ONEP 05-1-02-III-3 and direct the ACRO to monitor for thermal hydraulic
instability without c oncurrent duties.
CRS Begin preparing for action to exit the Restricted Region using
CRAM rod insertion including reviewing the Control Rod Movement Sequence notes, notifying Reactor Engineering, conduction a reactivity brief, directs CRAM rod insertion.
ACRO Inserts control rods per the Control Rod Movement Sequence BOP Verifies control rod movements CRS Directs I&C to install FCTR setpoints be installed for single
Recirc Loop operation per TS
3.4.1. Directs
Reactor Engineering to install thermal limits for LCO 3.2.1 and 3.2.2 due to single loop operation.
ACRO Reports trip of Circ Water Pump B REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 16 of 23
Appendix D Operator Actions Form ES-D-2 Scenario 2 Time Position Applicant's Actions or Behavior CRS Assigns monitoring condenser vacuum CRS Assess plant and system status. Reviews 03-1-01-2 for necessary configuration changes due to decreased power level. CRS Directs aligning Circ Water system to single pump/double
train operation per 03-1-01-2 step 8.4.2 and 04-1-01-N71 section 5.7.
REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 17 of 23
Appendix D Operator Actions Form ES-D-2 Scenario 2 Op-Test No.: __
030209___ Scenario No.: __
2___ Event No.: ___
7__ Event
Description:
Service Transformer 11 Lockout (ONEPs 05-1-02-I-4, 05-1-02-V-7, 05-1-02-I-1, and EP-2))
Time Position Applicant's Actions or Behavior BOP At P807, recognizes and reports trip of Service Transformer 11 and loss of power to bus 13AD. Re-energizes bus 13AD via BOP Transformer 12A from P807 per 05-1-02-I-4 step 2.1 and direct the building operator to reset bus 13AD
undervoltage lockout relays per step 2.2.
BOP At P601, verifies DG11 starts and re-energizes ESF bus
15AA. ACRO Recognizes and reports trip of both Reactor Feed Pumps.
Places Reactor Mode Switch in Shutdown due to water level decreasing and reports manual scram.
CRS Enters Loss of AC Power ONEP 05-1-02-I-4, Feedwater System Malfunctions ONEP 05-1-02-V-7, and Reactor Scram
ONEP 05-1-02-I-1. Directs initiation of RCIC. Directs building operator and electrical maintenance to investigate 12HE lockout.
ACRO Provides Scram Report: All control rods fully inserted Reactor power decreasing Feedwater tripped but recoverable Reactor pressure being controlled by EHC control system CRS Enters EP-2 on low reactor water level. Directs level band
+11.4" to +53.5" using Condensate/Feedwater. May initially direct level band of -30" to
+30" if HPCS and RCIC are injecting and Feedwater has not yet been recovered.
BOP If Level 2 has not already been reached, initiates RCIC by
arming and depressing RCIC MAN INIT pushbutton on P601.
REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 18 of 23
Appendix D Operator Actions Form ES-D-2 Scenario 2 Time Position Applicant's Actions or Behavior BOP Reports Level 2 received:
HPCS initiation RCIC initiation Level 2 isolations BOP At P870, verifies SSW A a ligns to support DG11 and RCIC operation BOP At P870, verifies SSW C ali gns to support HPCS operation ACRO Aligns Startup Level Control per 04-1-01-N21-1 Att. VII:
On P680, closes the following valves: N21-F009A, FW HTR 6A OUTL VLV N21-F009B, FW HTR 6B OUTL VLV.
On P870, opens the following valves: N21-F001, SU FCV OUTL ISOL VLV. N21-F010A, HP FW HTR STRNG A SU OUTL VLV. N21-F010B, HP FW HTR STRNG B SU OUTL VLV.
On P680, verifies the following valves are closed: N21-F513, X WTR LVL SU CONTR Valve (via controller 1C34-LK-R602) N21-F510, FW CU RECIRC VLV N21-F040, FW SU BYP VLV REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 19 of 23
Appendix D Operator Actions Form ES-D-2 Scenario 2 Time Position Applicant's Actions or Behavior ACRO Recovers a RFP injection per 04-1-01-N21-1 Att. VI at P680: (may be delayed if Level 9 was reached due to HPCS
injection)
Restarts the 'A' AC lube oil pump for RFPT to be restarted by depressing STOP then AUTO for the oil pump. Opens RFP A(B) DISCH VLV N21-F014A(B).
Depresses the RFPT A(B) TRIP RESET pushbutton.
Raises pump speed using the RAISE pushbutton until governor position is approx. 60%
or as required to obtain discharge pressure approx. 250 psig above reactor pressure.
Adjusts N21-F513, RX WTR LVL SU CONT valve, as necessary in MANUAL or AUTO to maintain desired Reactor level. N21-F040 and/or N21-F009A(B) may be OPEN/CLOSED as necessary to augment flow.
Ultimately places Startup Lev el Control in automatic when level is in band +11.4" to 53.5" CRS Directs restoring isolations for Plant Service Water to the auxiliary building and Instrum ent Air and Drywell Chilled Water to containment that isol ated due to power loss to bus 15 AA and Level 2 BOP At P807, restores isolations as directed using 05-1-02-III-5 Att. II for P53, P44, and P72 Primary and Secondary CTMT valves that isolated due to power loss to bus 15AA and Level 2 : REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 20 of 23
Appendix D Operator Actions Form ES-D-2 Scenario 2 Op-Test No.: __
030209___ Scenario No.: __
1___ Event No.: ___
8__ Event
Description:
RCIC Steam Line Break in the RCIC Room with Failure/Inability to Isolate (EP-4)
Time Position Applicant's Actions or Behavior BOP Recognizes and reports RCIC EQUIP AREA TEMP HI alarm (H13-P601-21A-G3) and ident ifies it as and EP-4 entry condition. Confirms signal is valid by observing independent RCIC room temperature alarms (1H13-P601-21A-H2 and H3), the PDS EP-4 Operator Guide, and/or Division 2 Leak Detection temperature switches on backpanel P642. Reports RCIC tripped.
BOP Recognizes steam supply isol ation valves E51F063 and E51F064 did not automatically cl ose, as required. The BOP operator will attempt to manually close E51F063 and E51F064 from P601, but the valves will lose power in the
open position. Reports RCIC status.
CRS Enters EP-4 and assign the BO P operator to monitor EP-4 parameters as a crit ical parameter.
BOP Obtains EP-4 data collection oper ator aid at backpanel P844 And begins collecti ng EP-4 parameters:
Area Radiation Monitors (P844) Division 2 LDS (Riley) Te mperature Switches (P642) May use EP-4 Operator Guide display on PDS for confirmation (P680)
Reports EP-4 readings to CRS. Initially specifies RCIC room temperature is above the Maximum Safe limit, 212°F.
CRS Dispatches a repair team to rest ore power to at least one of the RCIC isolation valves to is olate the leak (breakers 52-163134 and 52-153129).
REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 21 of 23
Appendix D Operator Actions Form ES-D-2 Scenario 2 REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 22 of 23 Time Position Applicant's Actions or Behavior CRS May elect to lower pressure to a band of 450-600 psig using Main Bypass valves to reduce t he driving head of the leak per Operation Philosophy step 6.4.3 BOP Recognizes and reports Auxiliary Building Steam Tunnel temperature rising based on EP-4 readings or receipt of MN STM TNL AMBIENT TEMP HI (P601-19A-E3) and reports
value CRS Depending on Steam Tunnel temper ature rate of rise, may direct fully opening Main Bypass Valves per EP-2 step P-1 due to anticipating Emergency Depressurization, which would
be required when Steam Tunnel temperature reached 250°F BOP Operates Main Bypass Valves on P680, as directed, using 04-1-01-N32-2 Att. V:
Energize Manual Bypass Valve Controller by simultaneously depressing MANUAL BYPASS CONTROL RELEASE pushbutton and MANUAL BYPASS VALVE CONTROLLER ON pushbutton until
ON pushbutton becomes illuminated.
Uses the RAISE or LOWER pushbuttons to open or close the Bypass Valves to control reactor pressure BOP Reports Steam Tunnel Temperature above its Maximum Safe
limit, 250°F. Specifies 2 area temperatures are now above Maximum safe limits.
CRS** Enters Emergency Depressuriza tion leg of EP-2 and directs opening 8 ADS/SRVs.
BOP** Opens 8 ADS/SRVs at P601 CRS Verifies Feedwater/Condensate is aligned for injection through Startup Level C ontrol in automatic ACRO** Ensures Feedwater/Condensate is aligned for proper control of RPV level and ensures level is maintained above -192".
- denotes critical task
CREW TURNOVER The plant is at 81% power at the target rod pattern following a temporary downpower for a control rod pattern adjustment. Power ascension is in progress at 03-1-01-2 Attachment VIII step 12.9.
The current fuel preconditioned envelope is at 90% power. Reactor Engineering has requested power be raised to 88% immediately after turnover. Power will be held there for 30 minutes, then, another ramp rate edit will be obtained.
There is no out of service equi pment, and EOOS is green.
A Division 1 work week is in effect.
ES-301 Transient and Event Checklist Form ES-301-5 Facility:
Grand Gulf Nuclear Station Date of Exam:
3/2/2009 Operating Test No.:
Scenarios 1 2 3 4 CREW POSITION CREW POSITION CREW POSITION CREW POSITION M I N I M U M(*)
A P P L I C A N T E V E N T T Y P E 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 T O T A L RI U RX 0 1 1 0NOR 1 1 1 1 1 I/C 2,3, 4,5, 7 4,5 7 4 4 2 MAJ 6 7,8 3 2 2 1 RO SRO-I SRO-U TS 3,4 2 0 2 2 RX 0 1 1 0NOR 0 1 1 1 I/C 2,3, 4 2,3, 4,5, 6 8 4 4 2 MAJ 6 7,8 3 2 2 1 RO SRO-I SRO-U TS 4,5 2 0 2 2 RX 1 1 1 1 0NOR 1 1 1 1 1 I/C 5,7 2,3 6 5 4 4 2 MAJ 6 7,8 3 2 2 1 RO SRO-I SRO-U TS 0 0 2 2 RX 1 1 0NOR 1 1 1 I/C 4 4 2 MAJ 2 2 1 RO SRO-I SRO-U TS 0 2 2Instructions:
- 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 do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in 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.
Revision 0 11/16/2006 ES-301 Competencies Checklist Form ES-301-6 Facility: Grand Gulf Nuclear Station Date of Examination: 03/02/2009 Operating Test No.:
APPLICANTS RO SRO-I SRO-U RO SRO-I SRO-U RO SRO-I SRO-U RO SRO-I SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 1 2 1 2 1 2 3 4 SRO BOP ATC SRO BOP ATC Interpret/Diagnose Events and Conditions 2,3,4 6,7 4,5,6 7,8 2,3, 4,6 2,3,4, 5,6,7, 8 3,5, 6,7 2,3, 6,7 Comply With and Use Procedures
(1) ALL 1,4,5 6,7,8 2,3, 4,6 ALL 1,3, 5,6, 7 1,2, 3,6, 7 Operate Control Boards (2)
N/A 1,4,5 6,7,8 2,3, 4,5, 6 N/A 1,3, 5,6, 7 1,2, 3,6, 7 Communicate and Interact ALL 1,4,5 6,7,8 2,3, 4,6 ALL 1,3, 5,6, 7 1,2, 3,6, 7 Demonstrate Supervisory Ability
(3) 1,2,3 4,5,6 ,7 N/A N/A ALL N/A N/A Comply With and Use Tech Specs (3) 3,4 N/A N/A 4,5 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 applicants' license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
Revision 0 1/14/2009