ML14010A038
ML14010A038 | |
Person / Time | |
---|---|
Site: | Millstone |
Issue date: | 10/03/2013 |
From: | Peter Presby Operations Branch I |
To: | Royce R Dominion Nuclear Connecticut |
Jackson D | |
Shared Package | |
ML13164A263 | List: |
References | |
TAC U01874 | |
Download: ML14010A038 (367) | |
Text
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Determine reactivity change for rod withdrawal JPM Number: 2K13 NRC ROA.1.1 Revision: 0 Initiated:
9/19/13 Developer Date Reviewed:
~ Paul Scott Technical Reviewer Date
~orner Approved:
Supervisor, Nuclear Training 1
SUMMARY
OF CHANGES A/1 & DATE DESCRIPTION REV/CHANGE 2
JPM WORKSHEET Facility: __;_;,;M"-P...:;.3_ _ __ Examinee:
JPM Number: 2K13 NRC RO A.1.1 Revision:
Task
Title:
Determine reactivity change for rod withdrawal System: NA Time Critical Task: ( ) YES (X) NO Validated Time (minutes): 15 min.
Task Number(s): 009-01-004 Applicable To: SRO RO X PEO KIA Number: 2.1.37 KIA Rating: _ _ _4_.3_/4_._6_ _
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: X Simulator: In-Plant: _ __
Task Standards: Using RE Curve and Data Book and OP 3304C, calculate the amount of boric acid needed to perform a rod withdrawal.
Required Materials: OP 3304C, Primary Makeup and Chemical Addition (procedures, equipment, etc.)
RE Curve and Data Book, Cycle 16 Calculator General
References:
3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC ROA.1.1 Revision: 0 Initial Conditions: In order to mitigate intake problems, the crew reduced reactor power to 88% using 'Load Limit'. After the downpower, MB4C 3-9 "Rod Control Bank Limit Lo" annunciator became lit requiring use of OP 3304C to restore rod position to greater than alarm setpoint.
The current plant conditions are:
- Reactor power is at 88%
- Control Bank Dis at 140 steps withdrawn
- Xenon is expected to build in over the next hour (i.e Xenon concentrations will rise). This will be effect core reactivity by 40 pcm in the next hour.
- Tavg is presently 584 F
- Pressurizer pressure is 2250 psia
- Pressurizer level is 60%
- The PPC is not functional
- Core burn-up is 150 MWD/MTU (BOL)
- Equilibrium Xenon curves should be used for the calculation 4
Initiating Cues: In order to clear MB4C 3-9, the US desires to withdraw Control Bank D to 160 steps withdrawn while maintaining RCS temperature and Reactor Power stable.
The US directs you to determine the quantity of boric acid OR primary grade water needed to achieve this 20 step withdrawal of Control Bank D.
Specifically, OP 3304C, step 4.7.1 for boration (or step 4.9.1 for dilution) requires:
DETERMINE the quantity AND flow rate of boric acid (dilution water) using one of the following:
- Attachment 2, "Determining Boration or Dilution Volume and Rate" The calculation should include:
- Amount of boric acid OR primary grade water over the next hour
- Expected fuel depletion should not be accounted for
- A value of 1 may be used for K (Correction Factor) in OP 3304C, Attachment 2 When done with the calculation, record value below AND circle boric acid or primary grade water:
_ _ _ _ _ gallons (in next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) of boric acid I primary grade water Simulator Requirements: NA
- NOTES TO TASK PERFORMANCE EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: 2K13 NRC RO A.1.1 Revision: 0 Task
Title:
Determine reactivity change for rod withdrawal STARTTThJE: ~~~-
PERFORMANCE STANDARD STEP Calculate the total reactivity change in pcm. Adds reactivity change from (1) rod Critical: Grade
- 1 withdrawal and (2) xenon y [ ] s[]
N [X] u[ ]
(1) Rod withdrawal of 20 steps:
Integral Rod Worth= 63 pcm (allowable band of 60 to 66 pcm)
Options on how value was derived:
- 62.5 pcm: Derives integral rod worth of 62.5 pcm from graph on page 1 of RE-D-02 "Integral Rod Worth vs Steps Withdrawn ... Cycle 16, BOL-HFP, Equilibrium Xenon"
- 65 pcm: Uses above RE-D-02 page 2 to calculate value of 65 pcm
- 66 pcm: Uses above RE-D-02 page 3 to interpolate value of 66 pcm on table
.. 60 pcm: Uses Cycle 16 thumbrules for pcm per step above and below 200 steps to derive a value of 60 pcm (2) Xenon:
- 40 pcm (given in initial conditions)
TOTAL REACTIVITY CHANGE= 23 pcm positive reactivity (63 + -40 pcm = 23 pcm)
(allowable band of 20 - 26 pcm) 6
STEP Determine a boron worth value. Boron worth = -6.1 pcm I ppm Critical: Grade I
- 2 (allowable band of -6.0 to -6.1) y [ ] s []
N[x] u[ ] I Options on how value was derived:
- Derives from RE-F-02 "Differential Boron Worth vs Core Average I Burnup ... Cycle 16" (--6.1 pcmlppm)
- Uses above RE-F-02 page 2 to I interpolate value of -6.1 pcm I ppm on table I
- Uses Cycle 16 thumbrules to use a value of -6.0 pcm I ppm I Comments: I I
Cue: I STEP Calculates reactivity worth of boron change. Calculates reactivity worth by dividing total Critical: Grade '
1
- 3 reactivity derived in Step #1 by boron worth y [ ] s[]
derirved in Step #2. N[x] u[ ]
Total reactivity (pcm) I Boron worth (pcm I ppm) 23 pcm I 6.1 pcm I ppm = 3.8 ppm (allowable band of 3.2-4.4 pppm)
Comments:
I Cue:
I 7
STEP Calculates the amount of boric acid needed for
- Determines a boration is required to Critical: Grade
- 4 RCS addition. offset the positive net positive y [ ] s[]
reactivity calculated in step #3. N[x] u[ ]
- Uses step 4. 7.1 of OP 3304C to go to Attachment 2 of OP 3304C.
- Calculates amount of boric acid using equation in Attachment 2 (M)[
8.33 In COOO-C)]
7000 - c; K Substituting values:
M= 507,127 (Att 2 of OP 3304C)
Ci= 1500 ppm Cf= 1503.8 ppm (1500 ppm+ 3.8 ppm (derived in step 3)
K- 1 (approx. based on near full power level)
Calculation equals:
42 gallons of boric acid needed Comments:
Cue:
STEP When done with calculation, record value Records 42 gallons and circles boric acid Critical: Grade
- 5 below AND circle boric acid or primary grade (allowable band is 35.4 gallons to 48.7 y [X) s[]
water: gallons) N[ ] u[ ]
Comments:
Cue:
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ _ __
8
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC RO A.1.1 Revision: 0 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 15 min.
Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
9
STUDENT HANDOUT (Page 1 of 2)
JPM Number: 2K13 NRC ROA.1.1 Revision: 0 Initial Conditions: In order to mitigate intake problems, the crew reduced reactor power to 88% using 'Load Limit'. After the down power, MB4C 3-9 "Rod Control Bank Limit Lo" annunciator became lit requiring use of OP 3304C to restore rod position to greater than alarm setpoint.
The current plant conditions are:
- Reactor power is at 88%
- Control Bank Dis at 140 steps withdrawn
- Xenon is expected to build in over the next hour (i.e Xenon concentrations will rise). This will be effect core reactivity by 40 pcm in the next hour.
- T avg is presently 584 F
- Pressurizer pressure is 2250 psia
- Pressurizer level is 60%
- The PPC is not functional
- Core burn-up is 150 MWD/MTU (BOL)
- Equilibrium Xenon curves should be used for the calculation 10
STUDENT HANDOUT (Page 2 of 2)
JPM Number: 2K13 NRC RO A.1.1 Revision: 0 Initiating Cues: In order to clear MB4C 3-9, the US desires to withdraw Control Bank D to 160 steps withdrawn while maintaining RCS temperature and Reactor Power stable.
The US directs you to determine the quantity of boric acid OR primary grade water needed to achieve this 20 step withdrawal of Control Bank D.
Specifically, OP 3304C, step 4.7.1 for boration (or step 4.9.1 for dilution) requires:
DETERMINE the quantity AND flow rate of boric acid (dilution water) using one of the following:
- Attachment 2, "Determining Boration or Dilution Volume and Rate" The calculation should include:
- Amount of boric acid OR primary grade water over the next hour
- Expected fuel depletion should not be accounted for
- A value of 1 may be used for K (Correction Factor) in OP 3304C, Attachment 2 When done with the calculation, record value below AND circle boric acid or primary grade water:
_ _ _ _ _ gallons (in next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) of boric acid I primary grade water 11
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Review and Approve Reactivity Calculation JPM Number: 2K13 NRC SRO A.1.1 Revision: 0 Initiated:
tf!:::. - ~ tlr William M. Forrestt 9/23/13 Developer Date Reviewed:
Technical Reviewer Date
~
Approved:
Trad Horner Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES All & DATE DESCRIPTION REV/CHANGE 2
JPM WORKSHEET Facility: _M_P_3_ _ __ Examinee:
JPM Number: 2K13NRCSROA.1.1 Revision:
Task
Title:
Review and Approve Reactivity Calculation System: NA Time Critical Task: ( ) YES (X) NO Validated Time (minutes): 22 minutes Task Number(s): 009-01-004 Applicable To: SRO X RO _ __ PEO _ __
KIA Number: 2.1.37 KIA Rating: ___4_._3_/_4_.6_ __
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: X Simulator: In-Plant:
Task Standards: Using RE Curve and Data Book and OP 3304C, calculate the amount of boric acid needed to perform a rod withdrawal.
Required Materials: 1. Attachment 2 of OP 3304C Rev 23-06, Primary Makeup and
{procedures, equipment, etc.) Chemical Addition (handout)
- 2. RE Curve and Data Book, Cycle 16 (handout put on reference cart)
- 3. Calculator General
References:
3
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC SRO A.1.1 Revision: 0 Initial Conditions: In order to mitigate intake problems, the crew reduced reactor power to 88% using 'Load Limit'. After the downpower, MB4C 3-9 "Rod Control Bank Limit Lo" annunciator became lit requiring use of OP 3304C to restore rod position to greater than alarm setpoint.
The current plant conditions are:
- Reactor power is at 88%
- Control Bank D is at 140 steps withdrawn
- Xenon is expected to build in over the next hour (i.e Xenon concentrations will rise). This will be effect core reactivity by 40 pcm in the next hour.
- T avg is presently 584 F
- Pressurizer pressure is 2250 psia
- Pressurizer level is 60%
- The PPC is not functional
- Core burn-up is 150 MWD/MTU (BOL)
- Equilibrium Xenon curves should be used for the calculation 4
Initiating Cues: In order to clear MB4C 3-9, the plan is to withdraw Control Bank D to 160 steps withdrawn while maintaining RCS temperature and Reactor Power stable.
You have directed the RO to determine the quantity of boric acid OR primary grade water needed to achieve this 20 step withdrawal of Control Bank D.
Specifically, OP 3304C, step 4.7.1 for boration (or step 4.9.1 for dilution) requires:
DETERMINE the quantity AND flow rate of boric acid (dilution water) using one of the following:
- Attachment 2, "Determining Boration or Dilution Volume and Rate"
- Computer Program The calculation from the RO should include:
- Amount of boric acid OR primary grade water over the next hour
- Expected fuel depletion should not be accounted for
- A value of 1 may be used for K (Correction Factor) in OP 3304C, Attachment 2 The RO has just completed the calculation, and he determined that 18.8 gallons of boric acid should be added.
You are to review and approve the attached calculation.
Simulator Requirements: NA 5
- NOTES TO TASK PERFORMANCE EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
6
PERFORMANCE INFORMATION JPM Number: 2K13 NRC SRO A.1.1 Revision: 0 Task
Title:
Review and Approve Reactivity Calculation STARTTThJE: _______
PERFORMANCE STANDARD STEP Reviews attached reactivity calculation Determines there are two errors: Critical: Grade
- 1 (Student Handout page 3 of 3) 1. In total reactivity calc (part 2), the RO Y[X] s[]
incorrectly credited Xenon as positive N[ ] u[ ]
reactivity. The initial conditions stated Xenon was building in. This would be causing negative reactivity and should have been subtracted from the rod worth: i 62.5 pcm (Rods)- 40 pcm (Xenon)= 22.5 pcm
- 2. In the calculation on Att. 2 of OP 3304C
( -,.,-
M ) [ ln s..,3 COOO 1ooo -- cfC.) ] K 1
The RO mistakenly adds an additional '0' to the natural log value. This lowers the calculated value from 188.5 gallons to 18.8 gallons.
Comments: The SRO must perform two critical actions to PASS this JPM. First they must recognize there is a mistake with the calculation. Secondly, they must perform the calculation correctly. The correct answer of 35.4 to 48.7 gallons of Boric Acid is proven in the attached steps.
Cue: After the SRO identifies a problem (identification of one of the two problems is ACCEPTABLE) with the calculation, ask them to perform the calculation.
7
STEP Calculate the total reactivity change in pcm. Adds reactivity change from ( 1) rod Critical: Grade
- 2 withdrawal and (2) xenon y[ ] s[]
N [X] u[ ]
(1) Rod withdrawal of 20 steps:
Integral Rod Worth= 63 pcm {allowable band of 60 to 66 pcm)
Options on how value was derived:
- 62.5 pcm: Derives integral rod worth of 62.5 pcm from graph on page 1 of RE-D-02 "Integral Rod Worth vs Steps Withdrawn ... Cycle 16, BOL-HFP, Equilibrium Xenon"
- 65 pcm: Uses above RE-D-02 page 2 to calculate value of 65 pcm
- 66 pcm: Uses above RE-D-02 page 3 to interpolate value of 66 pcm on table
- 60 pcm: Uses Cycle 16 thumbrules for pcm per step above and below 200 steps to derive a value of 60 pcm (2) Xenon:
- 40 pcm (given in initial conditions)
TOTAL REACTIVITY CHANGE= 23 pcm positive reactivity (63 + -40 pcm = 23 pcm)
{allowable band of 20 - 26 pcm) 8
STEP Determine a boron worth value. =
Boron worth -6.1 pcm I ppm Critical: Grade
- 3 (allowable band of -6.0 to -6.1) y [ ] s[]
N[x] u[ ]
Options on how value was derived:
- Derives from RE-F-02 "Differential Boron Worth vs Core Average Burnup ... Cycle 16" (--6.1 pcmlppm)
- Uses above RE-F-02 page 2 to interpolate value of -6.1 pcm I ppm on table
- Uses Cycle 16 thumbrules to use a value of -6.0 pcm /ppm Comments:
Cue:
STEP Calculates reactivity worth of boron change. Calculates reactivity worth by dividing total Critical: Grade
- 4 reactivity derived in Step #2 by boron worth y [ ] s[]
derived in Step #3. N[x] u[ ]
Total reactivity (pcm) I Boron worth (pcm I ppm) 23 pcm I 6.1 pcm I ppm =3.8 ppm (allowable band of 3.2 - 4.4 ppm)
Comments:
Cue:
9
STEP Calculates the amount of boric acid needed for
- Determines a boration is required to Critical: Grade i
- 5 RCS addition. offset the net positive reactivity y [ ] s[]
calculated in step #2. N[x] u[ ]
- Uses step 4. 7.1 of OP 3304C to go to Attachment 2 of OP 3304C.
- Calculates amount of boric acid using equation in Attachment 2 (M)[
8.33 1n cOOO-C)]
7000 - c: K Substituting values:
M= 507,127 (Att 2 of OP 3304C)
Ci= 1500 ppm Cf= 1503.8 ppm (1500 ppm+ 3.8 ppm (derived in step 4)
K-1 (approx. based on near full power level)
Calculation equals:
42 gallons of boric acid needed Comments:
Cue:
STEP When done with calculation, records value and Records 42 gallons and circles boric acid Critical: Grade
- 6 reports to Examiner. (allowable band is 35.4 gallons to 48.7 Y[X] s[]
gallons) N[ ] u[ ]
Comments:
Cue: -- ---
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ _ __
10
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC SRO A.1.1 Revision: 0 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 22 minutes Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
11
STUDENT HANDOUT (Page 1 of 3)
JPM Number: 2K13 NRC SRO A.1.1 Revision: 0 Initial Conditions: In order to mitigate intake problems, the crew reduced reactor power to 88% using 'Load Limit'. After the downpower, MB4C 3-9 "Rod Control Bank Limit Lo" annunciator became lit requiring use of OP 3304C to restore rod position to greater than alarm setpoint.
The current plant conditions are:
- Reactor power is at 88%
- Control Bank Dis at 140 steps withdrawn
- Xenon is expected to build in over the next hour (i.e Xenon concentrations will rise). This will be effect core reactivity by 40 pcm in the next hour.
- Tavg is presently 584 F
- Pressurizer pressure is 2250 psia
- Pressurizer level is 60%
- The PPC is not functional
- Core burn-up is 150 MWD/MTU (BOL)
- Equilibrium Xenon curves should be used for the calculation 12
STUDENT HANDOUT (Page 2 of 3)
JPM Number: 2K13 NRC SRO A.1.1 Revision: 0 Initiating Cues: In order to clear MB4C 3-9, the plan is to withdraw Control Bank D to 160 steps withdrawn while maintaining RCS temperature and Reactor Power stable.
You have directed the RO to determine the quantity of boric acid OR primary grade water needed to achieve this 20 step withdrawal of Control Bank D.
Specifically, OP 3304C, step 4.7.1 for boration (or step 4.9.1 for dilution) requires:
DETERMINE the quantity AND flow rate of boric acid (dilution water) using one of the following:
- Attachment 2, "Determining Boration or Dilution Volume and Rate"
- Computer Program The calculation from the RO should include:
- Amount of boric acid OR primary grade water over the next hour
- Expected fuel depletion should not be accounted for
- A value of 1 may be used forK (Correction Factor) in OP 3304C, Attachment 2 The RO has just completed the calculation, and he determined that 18.8 gallons of boric acid should be added.
You are to review and approve the attached calculation.
13
STUDENT HANDOUT (Page 3 of 3)
Reactor Operator's Calculation
- 1. Rod worth = 62.5 pcm
- 2. Total reactivity= 62.5 pcm (Rods)+ 40 pcm (Xenon)= 102.5 pcm
- 3. Reactivity Worth of Boron Change =
102.5 pcm /6.0 pcm I ppm= 17 ppm {or Final Boron Concentration of 1517 ppm)
- 6.0 pcm from attached thumbrules
- 4. Calculates the amount of boric acid needed for RCS addition (per OP 3304C Att.2)
(-M - )[ln (7000-C*)] K 8.33. 7ooo - cf 1
Substituting values:
M= 507,127 (Att 2 of OP 3304C)
Ci= 1500 ppm Cf= 1517 ppm K= 1 Amount of Boric Acid Needed= 18.8 gallons 14
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Determine Reactor Vessel Venting Time JPM Number: 2K13 NRC RO A.1.2 (A100-1) Revision: 0 chg 2 Initiated:
William M. Forrestt 9/19/13 Developer Date Reviewed:
Technical Reviewer Date Approved:
Trad Horner Supervisor, Nuclear Training Date
SUMMARY
OF CHANGES Nl & DATE DESCRIPTION REV/CHANGE 9-28-09 New revision of old JPM 100 in new format with new 0 numbering system for an admin JPM.
05/06/11 Updated procedure references, Corrected tyops, reformatted 0/1
-CTRyan 9/19/13 Updated format. Modified initial conditions resulting in a 0/2 changed, calculated vent time. - WMF 2
JPM WORKSHEET Facility: _M_P_3_ _ __ Examinee:
JPM Number: 2K13 NRC ROA.1.2 Revision: 0 chg 2 Task
Title:
Determine Reactor Vessel Venting Time System: NA Time Critical Task: ) YES (X) NO Validated Time (minutes): _ ____;?~--
Task Number(s): 000-05-035 Applicable To: SRO X RO X PEO _ __
KIA Number: GEN 2.1.25 KIA Rating: _ _ _3_.9_/_4_.2 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: X Simulator: In-Plant:
Task Standards: Satisfactorily complete the calculation of reactor vessel venting time iaw Attachment A of EOP 35 FR-1.3.
Required Materials: 1 .) Calculator (procedures, equipment, etc.)
2.) Blank copy of Attachment A of EOP 35 FR-1.3 General
References:
EOP 35 FR-1.3 Rev. 013 3
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC ROA.1.1 Revision: 0 chg 2 Initial Conditions: The unit has experienced an event which resulted in an inadequate core cooling condition and a hydrogen void in the reactor vessel head. The control room team is carrying out the actions of EOP 35 FR-1.3., Response to Voids in Reactor Vessel, and has completed the first 16 steps. The containment hydrogen concentration has been verified as less than 3%. The following plant conditions exist:
- Sl Terminated
- All RCPs are OFF
- Containment hydrogen concentration = 1.3%
- RCS pressure stable at 615 psia
- Pressurizer level stable at 50%
- Containment temperature is 100°F
- RCS subcooling is 1OOoF
- Containment pressure is 13.9 psia Initiating Cues: The US has directed you to determine the maximum allowable reactor vessel venting time using Attachment A in EOP 35 FR-1.3.
Simulator Requirements: None 4
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: 2K13 NRC RO A.1.2 Revision: 0 chg 2 Task
Title:
STARTTThJE: ~~~-
PERFORMANCE STANDARD STEP Determine Calculated Containment Critical: Grade
- 1 Pressure (Peale) Based on initial conditions of 13.9 psia for y [ ] s []
- a. Current Containment Pressure = containment pressure, enters 13.9 psia N[x] u[ ]
psi a for P calc.
- b. IF Current Containment Pressure is
_14.7 psia then Peale= 14.7 psia
- c. IF Current Containment Pressure is
_14. 7 psia then Peale = Current Containment Pressure.
- d. Peale= psia (NOTE:
Must be 14.7 psia)
Comments:
Cue:
6
STEP Determine Calculated Containment Critical: Grade
- 2 Temperature (Teale} Based on initial conditions of 100 F for y [ ] s[]
- a. Current Containment Temperature (T) = containment temperature, calculates Teale to N [X] u[ ]
OF be 560 oR.
- b. Convert Containment Temperature to (100 F + 460 =560 °R)
Rankine as follows:
(T) °F+460 =
Teale) OR
- c. Teale= OR Comments:
Cue:
STEP Determine the containment volume at Critical: Grade
- 3 STP: (A} Using the formula in step 3 of attachment y [ ] s[]
A, enters 13.9 psia for containment N [X] u[ ]
~ A = (2.26x 106 cuftl Peale 492"R X
- 14. 7psia X
Teale pressure and 560°R for containment temperature to obtain containment 492°R volume of 1.878 x 106 cu. ft.
A= (2.26 x 1()6 cu ft) X 14.7 psia X
A=l cu n 1 Comments:
Cue:
7
STEP Determine the maximum hydrogen Using the formula in step 4 of attachment Critical: Grade
- 4 volume that can be vented: (B) A, enters 1.3% for the current y [ 1 s[1 containment hydrogen concentration and N [X 1 u[ 1
~ (JJJ% - Ctmt hydrogen concentration) x A B= the value obtained in JPM step 1 for the J()()!J};
containment volume to obtain the (3.0%- )x maximum hydrogen volume of 3.19 x 104 B= cu. ft.
100%
B=l cu ft I Comments:
Cue:
STEP Determine hydrogen flow rate as a Using the formula in step 5 of Attachment Critical: Grade
- a. Enter RCS pressure : psi a.
N[x1 u[ 1 psi a
- b. Use the attached graph of Hydrogen Flow Rate vs RCS Pressure to Uses the attached graph of Hydrogen determine the maximum allowable flow. Flow Rate vs. RCS Pressure to determine
Comments:
Cue:
STEP Calculate maximum venting time in Using the formula in step 6 of Attachment Critical: Grade
- 6 minutes(MVT) A, enters the values obtained in JPM y [ 1 s [1 steps 4 and 5 and calculates an MVT of N[x1 u[ 1 Formula I JYlaximum t*eming time = -
B 1.77 minutes.
c MVT=
Comments:
Cue:
8
STEP Enter venting time (step 17.b.) 1.68 min~ Vent Time~ 1.88 min Critical: Grade
- 7 minutes y [X] s[]
N[ l U[J Comments: The allowable value was derived to allow up to for an interpolation band of 18,000 scfm hydrogen flow plus I minus 1,000 scfm.
Cue:
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ _ __
9
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC RO A.1.2 Revision: 0 chg 2 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 7 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
10
STUDENT HANDOUT JPM Number: 2K13 NRC RO A.1.2 Revision: 0 chg 2 Initial Conditions: The unit has experienced an event which resulted in an inadequate core cooling condition and a hydrogen void in the reactor vessel head. The control room team is carrying out the actions of EOP 35 FR-1.3., Response to Voids in Reactor Vessel, and has completed the first 16 steps. The containment hydrogen concentration has been verified as less than 3%. The following plant conditions exist:
- Sl Terminated
- All RCPs are OFF
- Containment hydrogen concentration =1.3%
- RCS pressure stable at 615 psia
- Pressurizer level stable at 50%
-Containment temperature is 100°F
- RCS subcooling is 100°F
- Containment pressure is 13.9 psia Initiating Cues: The US has directed you to determine the maximum allowable reactor vessel venting time using Attachment A in EOP 35 FR-1.3.
11
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Respond to Degrading Intake Conditions.
JPM Number: NRC SRO A.1.2 Revision: 0 chg 2 Initiated:
IL- ~~
William M. Forrestt 9/23/13 Developer Date Reviewed:
Technical Reviewer Date
~
Approved:
Trad Horner Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES A/1 & DATE DESCRIPTION REV/CHANGE 8/20/09 Modified the cue to add that actions for the yellow condition 0 /1 are already in progress. Modified the cue to separate the direction given to the candidate into two discrete steps to avoid confusion. Removed the JPM steps associated with carrying out actions associated with section 4.6 of OP 3215-the applicant need only identify that these actions apply to an environmental factor condition of "RED." These changes a result of NRC comments during prep week.
9/23/13 Modified initial conditions to include a change to plant factors 0/2 (decreasing trash rack dp will cause plant factors to go from 6 to 3). Also, changed initiating cue to read "specify any changes to required actions" from "specified any new required actions". Both changes made to add complexity and make JPM less "leading". The downstream changes (factor totals) were changed in the JPM body. Additionally, instructions on setup (along with a surveillance copy, back of JPM) was added to aid in administration. WMF 2
JPM WORKSHEET Facility: _;M:. .:. ;.:_P-=.3_ _ __ Examinee:
JPM Number: NRC SRO A.1.2 Revision: 0 chg 2 Task
Title:
Respond to Degrading Intake Conditions.
System: N/A Time Critical Task: ) YES (X ) NO Validated Time (minutes):- - - 15 Task Number(s): 341-01-107, Response to degrading intake conditions.
Applicable To: SRO X RO - - - PEO - - -
KIA KIA Rating:
Number: 2.1.20 4.6 I 4.6 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: X Simulator: In-Plant:
Task Standards: Respond to degrading intake conditions.
Review and disposition surveillance for Intake Structure Condition Determination.
Required Materials: 1. Completed OPS form SP 3665.2-001 Rev 9-03, Intake Structure (procedures, equipment, etc.) Condition Determination with Vacuum in Condenser (handout)
- 2. SP 3665.2 Rev 8-03, Intake Structure Condition Determination (handout)
- 3. OP 3215 Rev 8-05, Response to Intake Structure Degraded Conditions (reference cart)
General
References:
N/A 3
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: NRC SRO A.1.2 Revision: 0 chg 2 Initial Conditions: You are the Shift Manager. It is October 15th and the unit is experiencing degrading conditions at the intake structure.
The Shift Technical Advisor (STA) is keeping SP 3665.2, Intake Structure Condition Determination current. The last surveillance was done at 0800 and indicated a plant factor condition of YELLOW, and an environmental factor condition of YELLOW. Plant actions for the yellow condition are already in progress (OP 3215 sections 4.4 and 4.5).
Initiating Cues: At 0900 the following conditions changed:
- PEO's have finished raking trash racks
- Trash rack dp's are now stable at 6.5", 6.0", 2.0", 2.5",
2.0", and 1.5".
- Traveling screen dp's are now stable at 5.0", 5.0",
4.0", 3.5", 2.0", 2.0".
- Wind speed, from 33' Met. Tower data, has increased to a steady 27 mph and from a new direction of 250°,
which is verified by the marine forecast.
You directed the STA to conduct a new Intake Structure Condition Determination which he just completed.
- 1. Review and disposition the completed SP 3665.2-001 surveillance.
- 2. Specify any changes to required actions associated with the new plant and environmental conditions.
Simulator Requirements: NONE
- NOTES TO TASK PERFORMANCE EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: NRC SRO A.1.2 Revision: 0 chg 2 Task
Title:
Respond to Degrading Intake Conditions STARTTThJE: _______
PERFORMANCE STANDARD Comments: I (1) Preparation of 3665.2-001 by Examiner. Use the attached, marked up copy for guidance. In addition to highlighting (or circling) individual values the examiner will need to add factor totals. See below:
Page 3 "Plant Factors Section Total"= 6 Page 3 "Wind Correction" = 5 Page 4 "E9 Wave Height I Seas Factor"= 2 Page 4 "Environmental Factors Section Total= 21 Page 5 (top to bottom, "Sustained" I "Plant" I "Enviro" I "Intake Total")= NA I 6 I 21 I 27 After a copy of 3665.2-001 is marked up with embedded errors (wind correction should be 10 vice 5 and trash rack dp is 3 points vice 6 points), hand applicant the surveillance form.
(2) The applicant may request a copy of SP 3665.2, Intake Structure Condition Determination. If so, provide.
STEP REQUEST SM review SP 3665.2-001. Applicant reviews the correct portion of the Critical: Grade
- 1 surveillance form which is the 'Per SM/US y [ ] s[]
SP 3665.2 Review and assess conditions for current column' for the denoted plant conditions for N [ X] u[ ]
Step Plant Factors. each of the plant factors.
4.3.5 5
3665.2- Reviews Plant Factors portion of Applicant reviews the plant factor values for Critical: Grade 001 p g 2 -3 surveillance. Circulating water Pumps and Screens (P1 ), y [ ] s[]
Screen Wash Pumps (P2), Trash Racks (P3), N [X ] u[ ]
Trash Rakes (P4), Traveling Screens (P5) and Debris Conveyor (P6). Determines that P3 "Trash Racks" should be 3 points vice 6 points (based on only 2 racks equal I above 6 in.
Comments: This change (from 6 to 3 points) will still result in a yellow condition. The applicant missing this step will have no adverse effect. Therefore is not a critical step.
Cue:
Applicant reviews the Plant Factors Section Critical: Grade Total value and determines that a total value y [ ] s[]
of '6' was erroneously entered, instead of N[X] u[ ]
the correct value of '3'.
Comments: This change (from 6 to 3 points) will still result in a yellow condition. The applicant missing this step will have no adverse effect. Therefore is not a critical step.
Cue: I STEP Review and assess conditions for current Applicant reviews the correct portion of the Critical: Grade 1
- 2 Environmental Plant Factors. surveillance form which is the 'Per SM/US y [ ] s[]
3665.2-001 column' for the denoted environmental N[X] u[ ]
p g 3 - 4 conditions for each of the environmental factors.
Comments:
Cue:
Applicant reviews the environmental factor Critical: Grade values for Predicted Height of Next High Tide y [ ] s []
(E1) and Height of Tide in Last 48 Hours N[X] u[ ]
(E2), and determines that correct environmental factor values were denoted.
Comments:
Cue:
6
Applicant reviews the environmental factor Critical: Grade value for Wind Direction (E3) and Y[X] s[]
determines that a value of '1' was N[ ] u[ ]
erroneously circled, instead of the correct value of '2'.
Comments: The new wind direction, as given in the cue, is from 250°. SP 3665.2-001 specifies a Wind Speed factor value of '2' for directions from 120° to 270°.
Cue:
Applicant reviews the environmental factor Critical: Grade values for Wind Speed (E4) and Historical y [ ] s[]
Wind Speed (E5) and determines that correct N[X] u[ ]
environmental factor values were denoted.
Comments:
Cue: I Applicant reviews the environmental factor Critical: Grade value for Wind Correction (E6) and Y[X] s[]
determines that a value of '5' was N[ ] u[ ]
erroneously entered, instead of the correct value of '10'.
Comments: Wind Correction (E6) is equal to Wind Speed (E4) plus Historical Wind Speed (E5) times Wind Direction (E3).
E6 = E3 x (E4 + E5). Wind Direction (E3) should actually be a factor of '2' as opposed to '1'.
Cue:
Applicant reviews the environmental factor Critical: Grade values for Predicted Wave Height (E7), y [ ] s[]
Historical Wave Height (EB), Wave Height I N[X] u[ ]
Seas Factor (E9), Barometric Pressure (E10),
Season (E11 ), Historical Environmental Factor (E12) and Seaweed Loading (E13) and determines that correct environmental factor values were denoted.
Comments:
Cue:
7
3665.2- Applicant reviews the Environmental Critical: Grade 001 pg 5 Factors Section Total value and determines Y[X] s[]
that a total value of '21' was erroneously N[ ] u[ ]
entered, instead of the correct value of
'26'.
Comments:
Cue:
3665.2- Applicant recognizes that the Plant Factors Critical: Grade 001 pg 5 Section Total value is 2:::3, and therefore Plant y [ ] s []
Factor Condition remains "YELLOW". N[X] u[ ]
Comments:
Cue:
3665.2- Applicant recognizes that the Environmental Critical: Grade 001 pg 5 Factors Section Total value is > 23 Y[X] s[]
(specifically 26), and therefore is an N[ ] u[ ]
Environmental Factor Condition of "RED" not "YELLOW".
Comments: This is an Environmental Factor Condition change from "YELLOW" to "RED'.
Cue:
3665.2- Applicant recognizes that the Intake Critical: Grade 001 pg 5 Condition Total is NOT> 29 (specifically y [ ] s[]
29). N [X] u[ ]
Comments:
Cue:
STEP Determine Required Actions Applicant recognizes that if any action level is Critical: Grade
- 3 exceeded, OP 3215 must be referred to. (SP y [ ] s []
3665.2-001 Note 2) N[X] u[ ]
Comments:
Cue:
8
(SP 3665.2-001 Note 3) Applicant recognizes that if 'RED' action level Critical: Grade is exceeded (environmental total or Intake y [ ] s[]
total), a risk review must be performed. N[X] u[ ]
Comments:
Cue: The STA will refer to NF-M-PRA-370, and PERFORM a risk review.
STEP Obtain proper procedure. Applicant obtains a copy of OP 3215 and Critical: Grade
- 4 reviews the procedure steps to determine y [ ] s[]
which are applicable with the plant factor N[X] u[ ]
condition "RED", OR the environmental factor condition "RED".
Comments:
Cue:
STEP OP 3215, Steps 4.4 and 4.5. Applicant should recognize these steps are
- 5 already in progress per initial condition.
OP 3215 Step 4.4 step 4.5 Comments: OP 3215 step 4.4 and 4.5 are already in progress based on the 0800 surveillance results which indicated both a plant factor condition and an environmental factor condition of "YELLOW", as given in the initial conditions. If questioned by the applicant, provide the following cue:
Cue: The actions associated with OP 3215, steps 4.4 and 4.5 are already in progress.
STEP !E environmental factor OR unplanned plant Applicant recognizes that step 4.6 is Critical: Grade
- 6 factor condition is "RED," applicable for the new environmental Y[X] s[]
OP 3215 Step 4.6 conditions. N[ ] u[ ]
PERFORM the following as appropriate:
Comments: It is not necessary for the applicant to discuss the specific actions associated with section 4.6 of OP 3215- but only identify or otherwise recognize that these actions apply to an environmental factor condition of "RED." Additional actions in SP 3665.2 or OP 3215 may be identified by the applicant. However, these are actions are not critical.
Cue:
Termination Cue: The Evaluation For This JPM is Complete. STOP TIME: _ _ __
9
VERIFICATION OF JPM COMPLETION JPM Number: NRC SRO A.1.2 Revision: 0 chg 2 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 15 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
10
STUDENT HANDOUT JPM Number: NRC SRO A.1.2 Revision: 0 chg 2 Initial Conditions: You are the Shift Manager and the unit is experiencing degrading conditions at the intake structure. The Shift Technical Advisor (STA) is keeping SP 3665.2, Intake Structure Condition Determination current. The last surveillance was done at 0800 and indicated a plant factor condition of YELLOW, and an environmental factor condition of YELLOW. Plant actions for the yellow condition are already in progress (OP 3215 sections 4.4 and 4.5).
Initiating cues: At 0900 the following conditions changed:
- PEO's have finished raking trash racks
- Trash rack dp's are now stable at 6.5", 6", 2", 2.5", 2.0", and 1.5".
- Traveling screen dp's are now stable at 5.0", 5.0", 4.0", 3.5",
2.0", 2.0".
- Wind speed, from 33' Met. Tower data, has increased to a steady 27 mph and from a new direction of 250°, which is verified by the marine forecast.
You directed the STA to conduct a new Intake Structure Condition Determination which he just completed.
- 1. Review and disposition the completed SP 3665.2-001 surveillance.
- 2. Specify any changes to required actions associated with the new plant and environmental conditions.
11
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Recommend a clearance boundary for 3CCI*P1 A JPM Number: NRC RO A.2 Revision: 3 Initiated:
1?:- ifl /1 Wilham M. Forrestt 8/19/13 Developer Date Reviewed:
il;vvv-PauiScott Technical Reviewer Date Approved:
Trad Horner Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES All & DATE DESCRIPTION REV/CHANGE 6/15/09 Updated JPM to use OP-AA-200, Equipment Clearance as 1/0 the governing reference. WC 2 was superceded by OP-AA-200. Modified JPM to conform to the new fleet JPM format.
Changed 'red' tags to danger tags, and 'yellow' tags to caution tags.
7/16/09 Modified the JPM to tagout a different component at the 2/0 NRC's request. Specifically, from 3GWS-P1 B, to 3LWS-P6A, "A" Waste Test Tank Pump.
8/21/09 Added '(red)' and '(yellow)' after danger and caution tags 2/1 respectively to remove any ambiguity involving the correct nomenclature of tag type. This change a result of NRC comments during prep week.
8/19/13 Changed equipment tagout to 'A' CCI pump. 3/0 2
JPM WORKSHEET Facility: _M:..:..:..;_P~3_ _ __ Examinee:
JPM Number: NRC RO A.2 Revision: - -
Task
Title:
Recommend a clearance boundary for 3CCI*P1 A System: Tagging and Clearance Time Critical Task: ( ) YES (X) NO Validated Time (minutes): 15 min.
Task Number(s): 341-01-079 Applicable To: SRO - - - RO X PEO KIA Number: GEN 2.2.13 KIA Rating: 4.1/4.3 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: X Simulator: In-Plant:
Task Standards: Develop and review a tag clearance.
Required Materials: 1) Team Lead Tag-Out Request (Attachment 5 to OP-AA-(procedures, equipment, etc.) 200) (See beginning of JPM, this needs to be filled in PRIOR TO START)
- 2) P&IDs, EM-1138, EM-114A
- 3) EE One-Line diagrams
- 4) ESK Power Supply Book
- 5) OP 3330E, Safety Injection Pump Cooling System
- 6) OP 3308-006, Electrical Checklist for High Pressure Safety Injection General
References:
- 1) OP-AA-200 Rev. 18, Equipment Clearance
- 2) OP 3250 Rev. 14-05, Removing Equipment from Service for Maintenance 3
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: NRC RO A.2 Revision: 3 Initial Conditions: The mechanical seal on 3CCI*P1A, "SI PP A Cooling Pp",
has to be replaced. Repair efforts are planned and the maintenance first line supervisor has made a work package tag-out request for the repair.
Initiating Cues: Your task is to develop a clearance boundary for this repair activity. Using page 2 of this handout, RECORD the components to be tagged, the required tagged position(s), and the tag color. Tag is sequence is not required.
Simulator Requirements: None
- NOTES TO TASK PERFORMANCE EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: NRC RO A.2 Revision: 3 Task
Title:
Recommend a clearance boundary for 3CCI*P1A STARTTThJE: _______
PERFORMANCE STANDARD Examiner Prior to start, mark-up OP-AA-200 Att. 5 "Tag-Out Request" with the following information:
Actions Issued to: Unit 3 OPS, x6200 Before Unit: 3 Start Reason: Corrective Maintenance & write in AWO number: 53102476838 Equip Affected: 3CCI*P1A Work to be Done: pump seal replacement on 3CCI*P1 A Assist in Defining Work Scope ... : Full Tagout Tagout Request Submitted By: John Franklin Tagout Request Verified By: Jeff Moore Attachment 5 is on page 3 of the STUDENT HANDOUT. Once marked up with the above information, it may be passed out. At this point, the JPM may begin.
STEP Identifies correct piping isolation boundary Candidate uses P&ID EM-114A and other Critical: Grade
- 1 for 3CCI*P1A, "SI PP A Cooling Pp". appropriate references (listed in required Y[X] s[]
materials) and identifies the correct N[ ] u[ ]
isolation boundary:
- Pump Discharge (3CCI*V2) CLOSED and danger (red) tagged
- Pump Suction (3CCI*V7) CLOSED and danger (red) ta~med !
Comments:
Cue:
5
STEP Identifies correct vent configuration for Candidate uses P&ID EM-114A and Critical: Grade
- 2 3CCI*P1A, "SI PP A Cooling Pp". identifies at least ONE of the following Y[X] s []
vent valves:
N[ ] u[ ]
- Vent valve (3CCI*V992) OPEN and danger (red) tagged
- Pump Suction Test Valve (3CCI*V29)
OPEN and danger (red) tagged
- Pump Suction Test Valve (3CCI*V30)
OPEN and danQer (red) taQQed Comments:
Cue:
STEP Identifies correct drain configuration for Candidate uses P&ID EM-114A and Critical: Grade
- 3 3CCI*P1A, "SI PP A Cooling Pp". identifies the following drain valve:
Y[X] s []
N[ ] u[ ]
- Pump Casing Drain (3CCI*V32)
OPEN and danQer (red) taQQed Comments:
Cue:
STEP Identifies correct electrical isolation Candidate uses EE-1AH or other Critical: Grade
- 4 boundary for 3CCI*P1A, "SI PP A Cooling appropriate references and identifies the Y[X] s[]
Pp". correct electrical isolation point:
N[ ] u[ ]
- At MCC 32-4T (F2F), OFF and danger (red) tagged Comments:
Cue:
Identifies correct electrical isolation Candidate uses EE-1AH or other Critical: Grade boundary for 3CCI*P1A, "SI PP A Cooling appropriate references and identifies the y [ ] s[]
Pp". correct electrical isolation point:
N[X] u[ ]
- 3CCI*P1A Control Switch OFF (or blank) and danger (red) or caution (yellow) tagged -(at MB2)
Comments: TaQQinQ the pump control switch is not required to meet the critical nature of this step.
Cue:
6
STEP Identifies correct electrical isolation Candidate uses OP 3308-006 or other Critical: Grade
- 5 boundary for 3SIH*P1A, "SI PP A Cooling appropriate references and identifies the Y[X] s[]
Pp". correct electrical isolation point:
N[ ] u[ ]
- 3SIH*P1A Control Switch in PTL and danger (red) tagged (at MB2)
Comments: 1.) Isolating cooling water (3CCI*P1A) to the 'A' Safety Injection Pump (3SIH*P1A) lube oil system will inop 3SIH*P1A. In order to prevent damage to this pump (should it auto start), the control switch for 3SIH*P1A should be placed in Pull to Lock (PTL).
2.) OP 3250, Removing Equipment from Service for Maintenance, step 1.6.3 discusses use of pull to lock for non-electrical isolation. If the candidate chooses to rack down the breaker for 3SIH*P1A, it would also be considered acceptable. The associated breaker for 3SIH*P1 A is 34C8-2. The associated pump control switch is not critical.
Cue:
STEP Candidate submits completed Page 2 of Critical: Grade
- 5 the STUDENT HANDOUT to the y [ ] s []
examiner. (Tagout should include all N[X] u[ ]
critical components previously identified.)
Comments:
Cue:
TERMINATION CUE: Acknowledge the Candidate's tagout submittal. The evaluation for this JPM is complete.
STOP TIME: _ _ __
7
HrJ SAI-1::_1 Y INJECTION PUMP 3SIH*P1A tAO)
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?(A-)
< EM-1138 --~( \
25913 SH 2 \
(H-S\i I
lc\
~;sz 2R2
\~~v I
~I I
~
SAFETY I'I /2,I
~
I I TN TECTICJN PUMP 3SIH*P1A y-- I I
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A\ , ~~II I lx7Aj
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(;}.,A*\;*
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- V2(A- I
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~
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- V2'3(A-) 2'JA)_
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( TE '; /'\!\
__ ' \ *Vl(A- i 37
- V7\A- J NOTE 3-CCI-150-1l-J(A- J j ~
SAFETY INJECTION PUM::>
COOLING PLMP D M 3CCI *P1A (AC)
~
Boundary for 3CCI*P1A. Provided for examiner review.
8
VERIFICATION OF JPM COMPLETION JPM Number: NRC RO A.2 Revision: 3 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 15 min.
Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
9
STUDENT HANDOUT (page 1 of 3)
JPM Number: NRC RO A.2 Revision: - - - 3 --
Initial Conditions: The mechanical seal on 3CCI*P1A, "SI PP A Cooling Pp", has to be replaced. Repair efforts are planned and the maintenance first line supervisor has made a work package tag-out request for the repair.
Initiating Cues: Your task is to develop a clearance boundary for this repair activity.
Using page 2 of this handout, RECORD the components to be tagged, the required tagged position(s), and the tag color. Tag is sequence is not required.
10
STUDENT HANDOUT (page 2 of 3)
Component Tagged Position Tag Color 11
STUDENT HANDOUT {page 3 of 3)
Tag-Out Request OP-AA-200- Attachment 5 Pa 1 of 1 Issued To (Name) Extension Department Tag-Out Requested On Un~: 01 02 03 0 Common Reason For Tag-Out Initiating Document 0 Corrective Maintenance Work Order Number D Preventive Maintenance Design Change Package Number 0 Trouble Shooting Other 0 Testing 0 Engineering Work Package D Other Equipment AHected Work To Be Done Assist in Defining Work Scope and establishing safe work boundaries, review the following and check all that apply:
0 "NO ROTATION" Tags (Equipment de-energized and prevented from D Heat Trace (consider if removing insulation) turning; Non-intrusive maintenance.)
D Purge Path Required (Describe Below) 0 "NO FLOW" Tags (System isolated to allow equipment to be D System in-service for Freon removal manipulated without affecting the plant. Non-intrusive maintenance.)
0 "FULL TAOOUT" Tags (Equipment isolated from all energy sources 0 Steam removed from air handler and depressurized. Intrusive maintenance.) O Hazardous Chemicals involved 0 "ELECTRICAL ONLY" (Equipment electrically isolated, the craft will O Control Power fuses removal required use LOCKOUT, if required, for all other energy sources.)
0 Controlling Procedure, which defines energy sources (OP, 0 Grounds required MOP, PT, ICP, MCM, etc. List in remarks.} 0 Motor Healer fuses D Personnel entering a piping system or plant equipment (List in remarks.) 0 MOV motor/grease heater fuse
{Operations will assist in determining applicable OPS procedures.)
D Auxiliary Components associated with equipment: 0 MOV internal power supplies on LS/Rotor Contacts D Seal Water 0 PMT requires Danger Tags {MOV testing, Flow Scan)
D Oil sub-system 0 Cooling Water (i.e., BC, SW, CO, CC)
Tag-Out Request Submmed By (Name) Date Time Tag-Out Request Verified By {Name) Date Time Recommended Isolations or Remarks (If possible, include tag type and posaion.)
F"orm No. 72171~f.Aug 2011) 12
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Response to Door lnoperability JPM Number: 2K13 NRC SRO A.2 Revision: 0 chg 3 Initiated:
William M. Forrestt 9/23/13 Developer Date Reviewed:
{Vvvv---
PauiScott Technical Reviewer Date Approved:
Trad Horner Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES All & DATE DESCRIPTION REV/CHANGE 5/6/11 Corrected tyops, reformatted. -CTRyan 0/1 8/16/12 Updated JPM number to A207. Verified JPM updated through 012 Rev 009-02 to OP 3261. Modified JPM step 10 (OP 3261, step 1.4.5) to be a critical step since it is appropriate to enter TIS 3.6.6.2 with the door blocked open. Minor editorial corrections. DLM 9/23/13 Minor editorial changes to cues. Modified to five column 0/3 JPM format. - WMF 2
JPM WORKSHEET Facility: _M___;_;_P.. :. .3_ _ __ Examinee:
JPM Number: 2K13 NRC SRO A.2 Revision: 0 chg 3 Task
Title:
Response to Door lnoperability System: NA Time Critical Task: ) YES (X) NO Validated Time (minutes): ___2_0_ _
Task Number(s): 341-01-014 Applicable To: SRO X RO _ __ PEO - - -
KIA Number: GEN 2.2.21 KIA Rating: ___2_._9-'-/_4_.1_ __
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: X Simulator: In-Plant:
Task Standards: Correctly determine the required actions for an INOPERABLE MP3 door.
Required Materials: 1. OP 3261 Rev. 009-04, Response to Door lnoperability
{procedures, equipment, etc.) (handout)
- 2. Unit 3 Technical Specifications (reference cart)
- 3. Unit 3 Technical Requirements Manual (reference cart)
General
References:
NA 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC SRO A.2 Revision: 0 chg 3 Initial Conditions: The plant is at 100% power and you are the Work Control SRO on shift. An emergent repair is required on the "A" RPCCW Heat Exchanger. Maintenance requires door A 4 be blocked open and have its center post removed, to move in equipment and scaffolding. Door work will be performed under W.O. 53102111111. It is estimated that the door will need to be blocked open for approximately four (4) hours.
Initiating Cues: You are asked to determine any compensatory actions necessary before blocking open door A-24-4. All Service Building and Auxiliary Building fire detectors are operable.
Sliding tornado door A-24-4A will remain undisturbed.
Maintain a rough log with all actions needed to authorize this work (such as applicable Tech Spec actions, TRM actions and necessary compensatory actions).
Simulator Requirements: NA
- NOTES TO TASK PERFORMANCE EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: 2K13 NRC SRO A.2 Revision: 0 chg 3 Task
Title:
Response to Door lnoperability START TIME: ----
PERFORMANCE STANDARD STEP Obtains copy of OP 3261 "Response to Obtains proper procedure. Critical: Grade
- 1 Door lnoperability". y [ ] s[]
N [X] u[ ]
Comments:
Cue:
STEP Obtain the following information for each Reviews initial conditions for required Critical: Grade
- 2 affected door: information.
y [ ] s[]
OP 3261 N [X] u[ ]
Step 1.1
- Door ID number and location
- Nature of inoperability (blocked open, doesn't latch, etc.)
- If door is being blocked open, AWO/clearance number/activity.
- If known, expected duration of inoperability.
Comments:
Cue:
5
STEP Refer To Attachment 2, "Unit 3 Door Examinee refers to Attachment 2 and Critical: Grade
- 3 Attributes," and DETERMINE applicable determines and logs that for door A-24-4, Y [X 1 s [1 OP 3261 attributes to door in question. the following attributes apply:
N[ 1 u[ 1 Step 1.2
- TRM Fire Door
- Locked TRM Fire Door
- SLCRS Door
- Radiation Door
- Security Door Comments:
Cue:
STEP IF door is a Dual---Train (D) door, Examinee recognizes that door A-24-4 is Critical: Grade
- 4 PERFORM the following: NOT a Dual Train Protection Door, and y [ 1 s [1 OP 3261 Step 1.3 proceeds to next step. N[x1 u[ 1 Comments:
Cue:
STEP IF one of the following types of doors is
- Examinee recognizes that door A-24-4 Critical: Grade
- 5 not capable of performing itsintended is a security door, refers to Attachment Y [X 1 s [1 function, PERFORM the specified 1 and determines that the security N[ 1 u[ 1 OP 3261 Step 1.4 actions: door number is 306.
IF door is a security door, PERFORM the
- Examinee annotates rough log with following: Security notification for door 306 being
- Refer To Attachment 1 for list of blocked open .
security door number cross references.
- NOTIFY Security Department of problems with doors or expected maintenance.
Comments:
Cue:
6
STEP
- 6 IF door is a "TRM Related Fire Door,"
- Examinee recognizes that door A Critical:
y (X]
Grade s[]
PERFORM the following: 4 is a TRM Related Fire Door and
Systems, Fire Rated Assemblies," "Fire Protection Systems, Fire Rated and PERFORM applicable actions. Assemblies,"
- NOTIFY Site Fire Marshal.
- Recognizes that TRM 3.7.13 applies and logs into LCO 3.7.13, ACTION a.
(1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> allowed outage time to establish fire rove)
- Examinee notifies Site Fire Marshall that door A-24-4 will be blocked open (via rough log entry).
Comments:
Cue:
STEP IF door is a "Locked TRM Related Fire Examinee recognizes door A-24-4 is a Critical: Grade
- 7 Door," PERFORM the Locked TRM Related Fire Door, and that y (X] s []
following: the door will NOT be just unlocked to N[ ] u[ ]
- a. Refer To TRM 3.7.13, "Plant Systems, provide temporary access.
Fire Rated Assemblies," and PERFORM applicable Also recognizes that the other actions actions. specified are redundant to the previous
- b. IF the only action performed is to unlock step.
door to provide i
temporary access, Refer To SP 3670.3, "Control of Temporary Logs," and INITIATE approved temporary log requiring verification that door is closed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. NOTIFY Site Fire Marshal.
Comments:
Cue:
7
STEP IF door is a non---TRM fire door AND IF Examinee recognizes that door A-24-4 is Critical: Grade
- 8 door will not berestored before shift not a non-TRM Fire Door and proceeds y [ ] s[]
turnover, PERFORM the following: to next step. N [X] u[ ]
Comments:
Cue:
STEP
- 9 IF door is a SLCRS door, PERFORM the
- Recognizes not a latch only problem . Critical:
y (X]
Grade s[]
following:
- Door - does close in the SLCRS air
- a. IF the only problem with the door is that flow direction, however, the door is to N [ ] u[ ]
it does not latch, Refer To Attachment 2 be BLOCKED open. (See Note 15 of and DETERMINE if door closes in Attachment 2) This step should be the SLCRS air flow direction (Reference marked NIA.
Note 15).
- Examinee recognizes that door A b. IF door closes in the SLCRS air flow 4 is a SLCRS Door and obtains and direction, Go To step 1.4.6. refers to TIS 3.6.6.2, "Containment
- c. Refer To TIS 3.6.6.2, "Containment Systems Secondary Containment."
Systems Secondary Containment," and PERFORM applicable actions.
- Recognizes that TIS 3.6.6.2 applies and logs into LCO 3.6.6.2 ACTION.
- d. IF SLCRS door A---24---6 is inoperable (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowed outage time)
AND crediting stairwell boundaries is desired, Refer To Attachment 3 and
- Alternate barriers are not applicable for this door.
PERFORM listed actions to credit alternate barriers.
- e. IF alternate barriers are successfully credited, Refer To TIS 3.6.6.2, "Containment Systems Secondary Containment," for continued applicability and actions.
Comments: If the examinee does not mark step b NIA, he or she may proceed to step 1.4.6 without logging into TIS 3.6.6.2. The examinee needs to realize that the door will be blocked open and the TIS needs to be entered.
Cue:
8
STEP IF door is a Control Room Habitability Examinee recognizes that door A-24-4 is Critical: Grade
- 10 Leakage door, PERFORM the following: not a Control Room habitability leakage y [ ] s[]
door and proceeds to next step. N[x] u[ ]
Cue:
Comments:
STEP IF door is a C02 boundary door, Examinee recognizes that door A-24-4 is Critical: Grade
- 11 PERFORM the following: not a C02 boundary door and proceeds y [ ] s[]
to next step. N[x] u[ ]
Comments:
Cue:
STEP IF door is a Technical Support Center Examinee recognizes that door A-24-4 is Critical: Grade
- 13 Habitability (A) door, NOTIFY Onsite not a Technical Support Center y [ ] s[]
Emergency Planning group. Habitability (A) door and proceeds to next N[x] u[ ]
step.
Comments:
Cue:
STEP IF door is a Fuel Building Integrity Examinee recognizes that door A-24-4 is Critical: Grade
- 14 Boundary (B) door, PERFORM the not a Fuel Building Integrity Boundary y [ ] s[]
following: door and proceeds to next step. N[x] u[ ]
I Comments: I I
Cue: !
STEP IF door is a Cold Weather (CW) door AND Examinee recognizes that door A-24-4 is Critical: Grade *
- 15 air temperatures are OR are expected to be not cold weather door and proceeds to y [ ] s[]
below 40°F, PERFORMthe following: next step. N[x] u[ ]
Comments:
Cue:
9
STEP IF door is a Flooding (F) door, PERFORM Examinee recognizes that door A-24-4 is Critical: Grade
- 16 the following: not a Flooding (F) door and proceeds to y [ ] s[]
next step. N[x] u[ ]
Comments:
Cue:
STEP IF door is a High Energy Line Break (H) Examinee recognizes that door A-24-4 is Critical: Grade
PERFORM the following: to next step. N [X] u[ ]
Comments:
Cue:
STEP IF door is a PRA HELB (HPRA) door AND Examinee recognizes that door A-24-4 is Critical: Grade
following: proceeds to next step. N [X] u[ ]
Comments:
Cue:
STEP IF door is a HELB Blowout (HBO) door, Examinee recognizes that door A-24-4 is Critical: Grade
- 19 PERFORM the following: not a HELB Blowout (HBO) door and y [ ] s []
proceeds to next step. N[x] u[ ]
Comments:
Cue: i STEP IF door is a Radiation (R) door, NOTIFY Examinee recognizes that door A-24-4 is Critical: Grade
- 20 Health Physics. a radiation boundary door and notifies y (X] s []
(via rough log entry) Health Physics N[ ] u[ ]
Department that door A-24-4 will be blocked open.
Comments:
Cue: I STEP IF door is a Tornado (T) door, INITIATE Examinee recognizes that door A-24-4 is Critical: Grade
- 21 actions to restore door to service in an not a tornado door and proceeds to next y [ ] s []
expeditious manner. step. N[x] u[ ]
Comments:
Cue:
10
STEP IF door is a Halon door, PERFORM the Examinee recognizes that door A-24-4 is Critical: Grade
- 22 following: not a Halon Door. y[ ] s[]
N[x] UlJ Comments: The candidate is not required to document any additional requirements (signage, wedge use, and shift turnover log).
Cue:
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ _ __
11
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC SRO A.2 Revision: 0 chg 3 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 20 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT KEY NOTE: Critical steps are denoted in bold.
Security door Refers to Attachment 1 that the security door number is 306.
Notifies Security Department.
TRM Fire Door TRM LCO 3.7.13, ACTION a. applies ("Fire Protection Systems, Fire Rated Assemblies.")
Notifies Site Fire Marshall Locked TRM Fire Door Effectively same actions as for a TRM Fire Door SLCRS Door TIS LCO 3.6.6.2 ACTION applies ("Containment Systems Secondary Containment.")
Radiation Door Notifies Health Physics Department 12
STUDENT HANDOUT JPM Number: 2K13 NRC SRO A.2 Revision: 0 chg 3 Initial Conditions: The plant is at 100 % power and you are the Work Control SRO on shift. An emergent repair is required on the "A" RPCCW Heat Exchanger. Maintenance requires door A-24-4 be blocked open and have its center post removed, to move in equipment and scaffolding. Door work will be performed under W .0.
53102111111. It is estimated that the door will need to be blocked open for approximately four (4) hours.
Initiating Cues: You are asked to determine any compensatory actions necessary before blocking open door A-24-4. All Service Building and Auxiliary Building fire detectors are operable. Sliding tornado door A-24-4A will remain undisturbed. Maintain a rough log with all actions needed to authorize this work (such as applicable Tech Spec actions, TRM actions and necessary compensatory actions).
13
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Review Radiological Work Procedure for Regenerative Heat Exchanger Room Entry JPM Number: NRC RO A.3 Revision:
Initiated:
fl_ /t !J-7 William M. Forrestt 9/25/13 Developer Date Reviewed:
Paul Scott Technical Reviewer Date Approved:
~Trad Horner Supervisor, Nuclear Training Date Page 1 of 10
SUMMARY
OF CHANGES:
All & DATE DESCRIPTION REV/CHANGE 8/21/09 Modified this JPM to review the survey map for the 'A' 0/1 RHR cubicle. This removes the ambiguity of the applicant needing to determine whether the mezzanine in 'B' RHR cubicle area was encompassed in the assigned task (higher radiation level). As a result, radiation levels, contamination levels, stay time, etc.,
changed as well. This change a result of NRC comments during prep week.
9/25/13 Changed survey map to CTMT 11 ft. MIDS area. 1/0 Changed RWP. Changed questions to include locked high radiation area questions and calculation of minimum stay time.
Page 2 of 10
Facility: MP3 Examinee:
JPM Number: ROA.3 Rev. - - -
1 --
Title:
Review Radiological Work Procedure for Regenerative Heat Exchanger Room Entry System: Radiation Control Time Critical Task: Yes No X Validated Time (minutes): -20 - min.
Task No.(s): 119-03-070, Approve entry and/or enter/exit the various radiation areas located within Millstone Station Applicable To: SRO X RO X PEO KIA No. 2.3.7 KIA Rating 3.5/3.6 Method of Testing:
Simulated Performance: Actual Performance: X Location:
Classroom: X Simulator: In-Plant:
Task Standards: At the completion of this JPM the examinee has reviewed the applicable RWP and survey map to determine the radiological requirements to perform the assigned task.
Required Materials Operations blanket RWP No. 3130205.
(procedures. equipment. etc.): Survey map for CTMT 11' MIDS Area General
References:
RPM 5.2.2 Rev16, Basic Radiation Worker Responsibilities RPM 2.5.1 0 Rev01, Health Physics Central Monitoring
- READ TO THE EXAMINEE****
I will ex lain the initial conditions, which ste s to simulate or discuss, and rovide Page 3 of 10
initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.
Initial Conditions: A refueling outage is in progress at Millstone Unit 3. Preparations are being made to vent and drain the Regenerative Heat Exchanger (3CHS*E1 ).
Initiating Cues: You have been directed to make preparations to vent and drain the Regenerative Heat Exchanger. Your task will be limited to the Regenerative Heat Exchanger room in the CTMT 11' MIDS Area.
- Your remaining available dose is 800 mR for the year
- Your technical review (i.e. flowpaths, tagging boundaries, etc) is complete
- Your expectant work will be throughout the Regenerative Heat Exchanger Room. In this room, you will NOT have to access the mezzanine.
- The examiner will act as Health Physics for any related questions.
- After reviewing BOTH:
- 1. Attached Survey Map for CTMT 11' MIDS Area
- 2. Radiation Work Permit, no. 3130205 Complete the attached PRE-JOB Brief Questionnaire Simulator Requirements: N/A
- NOTES TO EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question the student for details of simulated actions/observations (i.e.
"What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
Page 4 of 10
PERFORMANCE INFORMATION JPM Number: RO A.3 Revision: 1 Task
Title:
Review Radiological Work Procedure for Regenerative Heat Exchanger Room Entry START TIME: _ _ __
PERFORMANCE STANDARD
- 1. Questionnaire step 1. Reviews CTMT 11' MIDS Area survey Critical: Grade Which RWP task Uob step) will be used for map and determines area is a locked high Y[X] N [ ] S[]U[]
this job? radiation area. After reviewing RWP, determines appropriate job step is 2 for a locked high rad area.
Cue: * *Pfovi~~xamirWe witibperations BlanketBWP Nl>. 313d2os anti CTM),1'1y IIIJDSIAieasun/'¥ m&J).
- Comments:
- 2. Questionnaire step 2. Reviews RWP Job Step 2 and determines Critical: Grade What is the Dose Limit Alarm for this task Dose Limit Alarm is 100 mrem. Y[X] N [ ] S[]U[]
(including units of measure)?
.. ....:*:.: .*.;j*. . **s- i ;,;,:{:\ ) {3 Cue: ~ ... . 1. : ..
Comments:
- 3. Questionnaire step 3. Reviews RWP Job Step 2 and determines Critical: Grade What is the Dose Rate alarm for this task Dose Rate Alarm is 950 mrem/Hr. Y[X] N [ ] S[]U[]
(including units of measure)?
Cue: . *':~ . r* ~ .!! **
. *.* *~
- . ~) > .... {'2 '
Comments:
Page 5 of 10
- 4. Questionnaire step 4. Reviews CTMT 11' MIDS Area survey Critical: Grade I What type of radiation area Is the map and determines the area is a locked Y[X] N [ ] S[]U[]
Regenerative Heat Exchanger Room (i.e. high radiation area.
I normal, high radiation area, locked high radiation area)? I I
~-~ l#lr,
" <; ... ~! lf t *.* :* ~.\J:
Cue: .*~1kL
- I {j"f:(!,.* **f':(,i ~<.. *~. <*. (' /':r:f W6t. . ;;:k . I Comments:
- 5. Questionnaire step 5. Determines must wear all of the following: Critical: Grade List all the dosimetry requirements for this 1. ED (Electronic Dosimeter) Y[X] N [ ] S[]U[]
job 2. Teledosimetry
- 3. TLD
- it *(;*~r. ! .}( ! ***~t:*f'i . {Jfi'; ..... ..
. ~ .::: ]~~ . .* ~~':ii. .:.~*i!
- "'~*. I Cue: I .:
Comments:
- 6. Questionnaire step 6. Reviews CTMT 11' MIDS Area survey Critical: Grade Using the survey map's high general area map and determines highest dose rate is Y[X] N [ ] S[]U[]
radiation level (for the Regen Heat 900 mrem/hr and recognizes dose limit alarm is 100 mrem.
Exchanger Room), what is your expected Calculates 900 mrem per hour I 100 mrem stay time?
And determines min stay time is .11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> or 6.6 minutes ALLOWABLE BAND of +/- 10% is:
0.10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to 0.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR 6 min to 7.2 min .
/. . ., *' : ; .",*r* . .* ,,, *:: ... :..,.. ..
Cue: ... . *,;: .J... .*. .* ;
I }.' c.-
Comments:
Page 6 of 10
- 7. Questionnaire step 7. Reviews CTMT 11' MIDS Area survey Critical: Grade Is the work area contaminated? map and determines YES area is Y[X] N [ ] S[]U[]
contaminated and highest contamination If YES, what is the highest contamination level is 50,000 dpm /100 cm2.
level (using the survey map) in the work area (including units of measure)?
Cue:
Comments:
TERMINATION CUE: The evaluation for this JPM is concluded. STOP T I M E : - - - - - -
Page 7 of 10
VERIFICATION OF JPM COMPLETION JPM Number: NRC RO A.3 Revision: 1 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 20 min.
Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
Page 8 of 10
STUDENT HANDOUT (page 1 of 2)
Initial Conditions: A refueling outage is in progress at Millstone Unit 3. Preparations are being made to vent and drain the Regenerative Heat Exchanger (3CHS*E1).
Initiating Cues: You have been directed to make preparations to vent and drain the Regenerative Heat Exchanger. Your task will be limited to the Regenerative Heat Exchanger room in the CTMT 11' MIDS Area.
- Your remaining available dose is 800 mR for the year
- Your technical review (i.e. flowpaths, tagging boundaries, etc) is complete
- Your expectant work will be throughout the Regenerative Heat Exchanger Room. In this room, you will NOT have to access the mezzanine.
- The examiner will act as Health Physics for any related questions.
- After reviewing BOTH:
- 3. Attached Survey Map for CTMT 11' MIDS Area
- 4. Radiation Work Permit, no. 3130205 Complete the attached PRE-JOB Brief Questionnaire Page 9 of 10
STUDENT HANDOUT (page 2 of 2)
Pre-Job Brief Questionnaire
- 1. Which RWP task Uob step) will be used for this job?
- 2. What is the Dose Limit Alarm for this task (including units of measure)? _ _ _ _ __
- 3. What is the Dose Rate alarm for this task (including units of measure)? _ _ _ _ __
- 4. What type of radiation area Is the Regenerative Heat Exchanger Room (i.e. normal (RCA), high radiation area, locked high radiation area, etc.)? _ _ _ _ _ _ _ __
- 5. List all the dosimetry requirements for this job: _ _ _ _ _ _ _ _ _ _ _ __
- 6. Using the survey map's highest general area radiation level (for the Regen Heat Exchanger Room), what is your expected stay t i m e ? - - - - - - - - - - - -
- 7. Is the work area contaminated? _ _ _ _ _ If YES, what is the highest contamination level (using the survey map) in the work area (including units of measure)? _ _ __
Page 10 of 10
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
3DAS-RE50, "Turbine Floor Drains Radmonitor", is inoperable JPM Number: 2K13 NRC SRO A.3 Revision: 0 Initiated:
/l- /10!
William M. Forrestt 9/23/13 Developer Date Reviewed:
<\Wvv---
PauiScott Technical Reviewer Date Approved:
Trad Horner Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES All & DATE DESCRIPTION REV/CHANGE 2
JPM WORKSHEET Facility: _M~P-=-3_ _ __ Examinee:
JPM Number: 2K13 NRC SRO A.3 Revision: - -
Task
Title:
3DAS-RE50, "Turbine Floor Drains Radmonitor", is inoperable System:
Time Critical Task: ( ) YES ( x) NO Validated Time (minutes): 20 min.
Task Number(s): 119-03-208 Applicable To: SRO X RO _ __ PEO _ __
KIA Number: 2.3.14 KIA Rating: ___3_._4_/_3_.8_ __
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: X Simulator: In-Plant:
Task Standards: Review narrative log and properly determine that DAS-RESO is inoperable. As a result, log into appropriate REMODCM action.
Required Materials:
(procedures, equipment, etc.) Full cart of reference material, to include:
- 2. OP 3362, "Radiation Monitor System Display and Control System" (reference cart, have 2 additional copies w/ Examiner)
- 3. MP-22-REC-BAP01, "REMODCM" (generate 3 references and place on reference cart)
General
References:
N/A 3
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC SRO A.3 Revision: 0 Initial Conditions: You are an SRO and have been asked to relieve the on shift US who has fallen ill 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> into the shift.
Initiating Cues: Review the attached narrative log entries and identify any situation that needs to be addressed. If action(s) are required to be taken, include the action to be taken.
Record any identified problem(s) below along with proposed action.
Simulator Requirements: N/A
- NOTES TO TASK PERFORMANCE EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: 2K13 NRC SRO A_3 Revision: 0 Task
Title:
3DAS-RE50, "Turbine Floor Drains Radmonitor", is inoperable STARTTThJE: _______
PERFORMANCE STANDARD STEP Reviews narrative log. Identifies two problems. Critical: Grade
- 1 1. 3SWT-SSC1 F-CS was not returned to AUTO Y[X] s[]
following daily PEO rounds cleaning of Screen N [ ] u[ ]
Wash Spray Header Strainers (OP 3327 sec.
4.16). This is NOT CRITICAL.
- 2. Identifies 3DAS-RE50 is inoperable AND enters REMODCM Table V.C.1 Action B. This is CRITICAL. The candidate made this determination by referencing the ARP (MB2B 2-9 "RMS Trouble"). This ARP directed referencing OP 3362 "Radiation Monitor System Display and Control". Section 4.13 of OP 3362 ("Equipment Failure Alarms") directs reference to Attachment
- 6. On Attachment 6 of OP 3362, comment 8 states "If momentary aux failure alarm is received frequently (several times a day), the rad monitor should be declared inoperable until the cause of the alarm is corrected."
Comments: The component positioning problem (item 1 above) is not critical as there is no significant plant impact with leaving this control switch in manual SLOW 1 for an extended period of time.
Cue: ----
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _______
5
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC SRO A.3 Revision: 0 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 20 min.
Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
6
STUDENT HANDOUT (page 1 of 3)
JPM Number: 2K13 NRC SRO A.3 Revision: 0 Initial Conditions: You are an SRO and have been asked to relieve the on shift US who has fallen ill 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> into the shift.
Initiating Cues: Review the attached narrative log entries and identify any situation that needs to be addressed. If action(s) are required to be taken, include the action to be taken.
Record any identified problem(s) below along with proposed action.
7
STUDENT HANDOUT (page 2 of 3)
Today 06:00 Assumed the watch as Shift Manager:
- Plant is in Mode 1
- Reactor Power is 100%
- Gross Generator Output is 1268 MWe *'A' Train Protected
- Additional Protected Equipment: -NONE
- Time to Spent Fuel Pool 200 °F on loss of all cooling is greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
- Spent Fuel Pool Temperature: 93.7°F
- Active LCO Action's requiring lower Mode within 7 days: NONE
- Abnormal plant conditions I Key equipment OOS with expected resolution date (ERD) (responsible work group):
- 'A' Screen Wash Pump high vibrations. Minimize use status. CR521924 (mech mntc)
-Condenser Air Ejector flow rate is high (~21 scfm) (Chemistry)
- Degasifier to be restored to service following repair of3GWS-V013 and 3GWS-V015 (mech mntc)
Today 06:01 The reactivity plan for the shift developed by the RO estimates approximately 30 to 40 gallons of dilution water required to maintain reactor power. This is to be performed with 2 to 3, light blended make-ups to the VCT adding 11-13 extra gallons of water each. This plan has been independently reviewed by the STA and is acceptable. The Boric Acid Flow Controller, 3CHS-FK11 0, potentiometer setting is 4.21 turns and has been verified by the RO, STA & US. [RO]
Today 06:18 Commenced CPE Operations,will respond to Demineralizer Control Panel and Condensate Demineralizer Waste Treating Panel alarms. [Chemist]
Today 07:10 Received MB2B 2-9 "RMS Trouble". Alarm was due momentary aux equipment failure for 3DAS-RE50, Turbine Building Floor Drains Radmonitor. Alarm is clear and channel check is SAT for 3DAS-RE50.
Today 07:40 Placed 'F' traveling water screen, 3SWT-SSC1F-CS, in SLOW-1 to start 'A' Screen Wash Pump for strainerblowdown lAW OP3327 Section 4.16. [BOP]
Today 08:00 Performed 80 gallon total blended make up to the VCT while decreasing RCS Boron concentration, added an additional 11 gallons of dilution water lAW OP 3304C step 4.5. [RO]
Initial Conditions Reactor Power= 3648.0 MWth Tave = 587.0°F 8
STUDENT HANDOUT (page 3 of 3)
Today 08:20 Shutdown Boric Acid System lAW OP3304C section 4.18 to support scheduled work on 3CHS*MV8104 [RO]
Today 08:40 Final Conditions: [RO]
Reactor Power= 3649.9 MWth (CVQRPA); Tavg = 587.4°F.
Today 08:41 Received several more annunciators (MB2B 2-9 "RMS Trouble") for recurring aux equipment failure alarms on 3DAS-RE50. Alarm is momentarily occurring and clearing. Channel check is SAT for 3DAS-RE50.
Today 0845 3CCI*P1A and 3CCI*P1B, SAFETY INJECTION PUMP COOLING PUMPS, started, run for 2 minutes and stopped for Chemistry sampling. [RO]
Today 09:40 Reactor Coolant System Sampled From Letdown. Boron Concentration is 1454 PPM Boron. [Chemist]
Today 09:45 Adjusted 3CHS-FK11 0 Controller Pot Setting iaw OP 3304C, Primary Makeup and Chemical Addition.
9
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Emergency Plan Classification and PAR JPM Number: SRO A.4 Revision: 0 I)_- jh Or Initiated:
William M. Forrestt 9/24/13 Developer Date
~
Reviewed:
Paul Scott Technical Reviewer Date
~
Approved:
Trad Horner Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 2
JPM WORKSHEET Facility: _M_P_;_3_ _ __ Examinee:
JPM Number: SRO A.4 Revision: 0 Task
Title:
Emergency Plan Classification and PAR System: N/A Time Critical Task: (X ) YES ( ) NO Validated Time (minutes) 10 min.
classify /12 min PAR Task Number(s): 301-05-366, 301-05-449 Applicable To: SRO X RO
--- PEO KIA 2.4.41 KIA Rating: 2.9/4.6 Number: 2.4.44 2.4/4.4 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: X Simulator: In-Plant:
Task Standards: Determine the EAL and State Posture Code Determine the minimum required PAR Required Materials:
- MP-26-EPI-FAP06-003 Rev 8, MILLSTONE UNIT 3 EMERGENCY ACTION LEVELS
- MP-26-EPI-FAP06 Rev 8, CLASSIFICATION AND PARs
- MP-26-EPI-FAP06-005 Rev 4, CONTROL ROOM PROTECTIVE ACTION RECOMMENDATIONS
- Incident Report Form (MP-26-EPI-FAPO? -001 )- Rev1-03 (all required materials are on the reference cart in book labeled "CR DSEO", need two additional books)
General
References:
MP-26-EPI-FAP-01-001, CONTROL ROOM DIRECTOR OF STATION EMERGENCY OPERATION, Rev 10-1 (CR DSEO) 3
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: SRO A.4 Revision: 0 Initial The plant is at 100% power on a 107 day run. All systems functioning Conditions: normally. The 'B' Safety Injection pump has been out of service for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for maintenance and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The following events occur:
- 1. (0800) Small Break LOCA occurs coincident with a failure of the running Charging Pump.
- 2. (0804) The 'A' Safety Injection Pump trips.
- 3. (0805) The standby Charging Pump will not start.
- 4. (0806) Core Cooling Status Tree is yellow based on a loss of RCS subcooling.
- 5. (0810) Core Cooling Status Tree is orange based on low RVLMS plenum level.
- 6. (0815) Crew exits E-0 and enters FR-C.1
- 7. (0828) RE-04A/05A reading 5.2 Rlhr and increasing
- 8. (0830) Core Cooling Status Tree is red based on GET's reading 1210 F and rising.
- 9. (0835) RE-04A/05A reading 230 R/hr and increasing
- 10. (0846) GET's are 1450 F and rising.
- 11. (0847) RE-04A/05A reading 31,000 R/hr and increasing
- 12. (0900) Offsite dose rates downwind of MP3 CTMT indicate -15mR!hr
- 13. (0915) The Control Room is using the Containment Vacuum System to vent Containment to the Aux Building for fifteen minutes The current wind speed is fifteen (15) miles per hour. The current wind direction is from 140°.
4
Initiating Determine the applicable emergency action level and make any Cues: appropriate protective action recommendations.
Perform the following 2 tasks. Both of these tasks are time critical.
(1) Record your Highest Classification response (EAL Major and Minor Heading) on the space provided below. Report to the Examiner when your Classification is made (FOR PROPER TIMING).
EAL MAJOR HEADING _ _ _ _ MINOR HEADING _ _ _ __
(2) After the classification is made and the Examiner is notified: If a PAR is required, RECORD the PAR recommendation on the space provided below. As applicable, notify the Examiner when complete with the PAR determination (FOR PROPER TIMING).
ARE THERE ANY QUESTIONS? You may see the Examiner to obtain the book labeled "CR DSEO" and START the TIMING.
Simulator NONE Requirements:
- NOTES TO TASK PERFORMANCE EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: SRO A.4 Revision: 0 Task
Title:
Emergency Plan Classification and PAR START TIME: _ _ __
PERFORMANCE STANDARD For timing purposes, both of the following tasks have time limits:
- 1. 15 minutes to determine Emergency Action Level and State Posture Code.
- 2. 15 minutes after classifying event to determine minimum required PAR.
The timing for the EAL determination (item 1 above) will begin ONCE the book labeled "CR DSEO" is handed to the candidate (this will be after the STUDENT HANDOUT is read and understood)
Record the JPM start time:
STEP Obtain Proper procedure. Applicant obtains or requests copy of Critical: Grade
- 1 MP-26-EPI-FAP06-003, MP3 Y [ ] N [X] S[]U[]
Emergency Action Levels.
Comments: Provide the Candidate a blank copy of an Incident Report Form and a Control Room PAR Process Flowchart (Handout #1 ).
Applicant may also request copies of:
- MP-26-EPI-FAP-01-001, CR-DSEO Checklist
- MP-26-EPI-FAP06, Classification and PARs
- MP-26-EPI-FAP06-005, CR PARs
- MP-26-EPI-FAPO?, Notifications & Comms
- MP-26-EPI-FAP0?-001, Incident Report Form The CR DSEO Notebook contains all these procedures.
Cue:
The examiner should pass out the CR DSEO book and inform the candidate that timing has begun.
6
STEP Classify the Event Applicant recognizes a LOSS of the Critical: Grade
- 2 Fuel Clad Barrier, based on EITHER Y [ ] N [X] S[]U[]
one of following:
- FCB1 -Core Cooling RED
- FCB2- GET > 1200 F
- FCB3- > 200 Rlhr on RE04/05,
=::;;2hrs after shutdown. (FCB3 AND Table 1 values}
Comments:
Cue:
Classify the Event Applicant recognizes a LOSS of the Critical: Grade RCS Barrier based on RCB2 RCS Y [ ] N [X] S[]U[]
Subcooling < 32 F Due to RCS Leak Comments:
Cue:
Classify the Event Applicant recognizes a POTENTIAL Critical: Grade LOSS of the CTMT Barrier based on Y [ ] N [X] S[]U[]
EITHER one of the following:
- CNB2- Entry in FR-C.1 with conditions met
- CNB5- > 800 Rlhr on RE04/05,
=::;;2hrs after shutdown. (FCB3 AND Table 1 values}
Comments:
Cue:
7
Applicant reviews MP-26-EPI-FAP06- Critical: Grade 003 and determines that a NRC EAL of Y[X] N[] S[]U[]
GENERAL EMERGENCY based on EITHER one of the following:
- Barrier Table (BG1) described above (BG 1 exists. Fuel Clad Barrier (L), RCS Barrier (L) and CTMT Barrier (Potential L)).
- IN PLANT RADIATION (RG1)
Based on sustained RE04A/05A reading> 800 Rlhr Comments:
Cue:
STEP Determine State Posture Code Applicant reviews MP-26-EPI-FAP06- Critical: Grade
- 3 003 and determines that the block for y [X] N [ ] S[]U[]
BG1 or RG1 is the same color as State Posture ALPHA.
Comments: Tables are color coded to reflect the State Posture.
NOTE 1. Record the Time Classification is Completed: (must be within 15 minutes of JPM start)
- 2. CUE Candidate: "Is a PAR required?"
- 3. If the Candidate correctly answers YES, then inform them to complete a PAR and record start time STEP Determine the State Protective Applicant uses MP-26-EPI-FAP06-005, Critical: Grade
- 4 Action Recommendation Y [ ] N [X] S[]U[]
Section B, Control Room PAR Process Flowchart, to determine the PAR.
Comments:
Cue:
8
STEP Determine the State Protective Applicant reviews flowchart and Critical: Grade
- 5 Action Recommendation Y [ ] N [X] S[]U[]
diagnoses that all only 2 barriers ARE lost (No) and transitions to "Does CTMT Radiation Exceed Table 1 Values?"
Comments:
Cue:
STEP Determine the State Protective Applicant reviews Table 1 and Critical: Grade
- 6 Action Recommendation determines that 31,000 Rlhr exceeds Y [ ] N [X] S[]U[]
Table 1 Values (Yes). Transition is made to "Is There a Release in Progress".
Comments:
Cue:
STEP Determine the State Protective Applicant reviews flowchart and Critical: Grade
- 7 Action Recommendation determines that a release IS in Y [ ] N [X] S[]U[]
progress (Yes). Transitions to "Is the Release Controlled."
Comments: Although not specifically stated in initial conditions, the applicant should determine that a release is in progress based on the cue that the Containment Vacuum System is being used to vent containment.
Cue:
STEP Determine the State Protective Applicant reviews flowchart and Critical: Grade
- 8 Action Recommendation determines that the release is Y [ ] N [X] S[]U[]
controlled {Yes).
Comments: Although not specifically stated in initial conditions, the applicant should determine that the release is controlled based on MP-26-EPI-FAP06 definition for controlled release: "Short term release (less than one hour), which is a controlled evolution and the release duration can be accurately determined (such as containment venting)."
Cue:
9
STEP Determine the State Protective Applicant reviews flowchart and makes Critical: Grade
- 9 Action Recommendation Y[X] N[] S[]U[]
the determination to SHELTER ALL ZONES.
Comments: It is possible AND acceptable, that the Candidate will stop here. If so: Record the Time PAR is Completed: (this must be done within 15 minutes of completing Classification)
Cue:
STEP Communication of the State Applicant reviews flowchart and Critical: Grade
- 10 Protective Action transitions to Section A, Step 2 of MP- Y [ ] N [X] S[]U[]
Recommendation 26-EPI-FAP06-005 (Control Room PAR) for the notification.
Comments: Steps 10 and 11 are not required for successful completion. These are added notifications.
Cue:
STEP If a General Emergency ALPHA is Applicant verbalizes or otherwise notes Critical: Grade
- 11 declared with actions necessary out that the DEP dispatcher in Hartford Y [ ] N [X] S[]U[]
to 10 miles, PARs are verbally should be contacted to communicate transmitted to the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DEP the applicable evacuation and Dispatcher in Hartford. sheltering recommendations, and Kl strategy implementation.
Comments:
NOTE: Record the Time PAR is Completed: (this must be done within 15 minutes of completing Classification}
Cue: The evaluation for this JPM is complete.
STOP TIME: _ _ __
10
VERIFICATION OF JPM COMPLETION JPM Number: SRO A.4 Revision: 0 Date Performed:
Student:
Evaluator:
For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
If task is Time Critical, it MUST be completed within specified time to achieve a satisfactory grade.
Time Critical Task? Yes X No Validated Time (minutes): 10 min.
classify
/12 min PAR Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
11
STUDENT HANDOUT Initial Conditions: The plant is at 100% power on a 107 day run. All systems functioning normally. The 'B' Safety Injection pump has been out of service for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for maintenance and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The following events occur:
- 14. (0800) Small Break LOCA occurs coincident with a failure of the running Charging Pump.
- 15. (0804) The 'A' Safety Injection Pump trips.
- 16. (0805) The standby Charging Pump will not start.
- 17. (0806) Core Cooling Status Tree is yellow based on a loss of RCS subcooling.
- 18. (081 0) Core Cooling Status Tree is orange based on low RVLMS plenum level.
- 19. (0815) Crew exits E-0 and enters FR-C.1
- 20. (0828) RE-04A/05A reading 5.2 R/hr and increasing
- 21. (0830) Core Cooling Status Tree is red based on GET's reading 1210 F and rising.
- 22. (0835) RE-04A/05A reading 230 R/hr and increasing
- 23. (0846) GET's are 1450 F and rising.
- 24. (0847) RE-04A/05A reading 31,000 R/hr and increasing
- 25. (0900) Offsite dose rates downwind of MP3 CTMT indicate
-15mR/hr
- 26. (0915) The Control Room is using the Containment Vacuum System to vent Containment to the Aux Building for fifteen minutes The current wind speed is fifteen (15) miles per hour. The current wind direction is from 140°.
12
Initiating Cues: Determine the applicable emergency action level and make any appropriate protective action recommendations.
Perform the following 2 tasks. Both of these tasks are time critical.
(1) Record your Highest Classification response (EAL Major and Minor Heading) on the space provided below. Report to the Examiner when your Classification is made (FOR PROPER TIMING).
EAL MAJOR HEADING _ _ __
MINOR HEADING _ _ _ __
(2) After the classification is made and the Examiner is notified: If a PAR is required, RECORD the PAR recommendation on the space provided below. As applicable, Notify the Examiner when complete with the PAR determination (FOR PROPER TIMING).
ARE THERE ANY QUESTIONS? You may see the Examiner to obtain the book labeled "CR DSEO" and START the TIMING.
13
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
CONTROL ROD OUT OF ALIGNMENT JPM Number: 2K13 NRC S.1 (8130) Revision: 1 chg 7 Initiated:
fl__ ;< tJ)
William M. Forrestt 9/26/13 Developer Date Reviewed:
~ Paul Scott Technical Reviewer Date Approved:
dQ_
Trad Horner Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES All & DATE DESCRIPTION REV/CHANGE Change 1 Update to procedure rev 4. Barry Pinkowitz 08/04/2003 Change 2 Update to procedure rev 5 01. John Deveau 09/24/2003 Change 3 Update to procedure rev 007-00 and other minor 05/30/2006 enhancements. R.J. Acquaro Change 4 Updated to procedure rev 008-00, updated reference 5/31/2007 task, updated reference to OP-AP-300. PGM Change 5 Updated for TRex and use of schedule to set up 7/23/2009 misaligned rod Change 6 Updated to new JPM numbering (8130 vs 130) and 1/23/13 JPM format Change 7 Added sim set-up step (pg 4) to remove malfunction, RD 9/26/13 0457, prior to starting JPM. Updated to 5 column JPM format. - WMF 2
JPM WORKSHEET Facility: . . :M:. :. .:.:. . P-=.3_ _ __ Examinee:
JPM Number: 2K13 NRC S.1 Revision: 1 chg 7 Task
Title:
CONTROL ROD OUT OF ALIGNMENT System: 001 Time Critical Task: ) YES ( X) NO Validated Time (minutes):. _ _-=2:. : .0_ _
Task Number(s): 344-05-030 Applicable To: SRO X RO X PEO KIA Number: 001 A2.03
-I-KIA Rating:
- - -3.5 4.2 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In-Plant:
Task Standards: Satisfactorily recover from a misaligned control rod using AOP 3552 Attachment A Required Materials: AOP 3552, Rev. 011-001 (procedures, equipment, etc.)
General
References:
NA 3
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC 8.1 Revision: 1 chg 7 Initial Conditions: A problem in the EHC circuit caused a momentary runback of the turbine/generator. During the subsequent insertion of the reactor control rods, rod D4 in Control Bank D was observed to be misaligned. The control room team entered AOP 3552 and has decided that Attachment A will be used to recover the misaligned rod.
The lift coil fuse for rod D4 was blown, and has been replaced.
MB4C 6-5 "Tref I Auct Tave Deviation" is lit. Another Operator will perform SP 3601G.3 "Tavg monitoring" and address this ARP.
Initiating Cues: The US has directed you to complete Attachment A of AOP 3552 step 1 through step 7 .f.
Simulator Requirements: Preferred: 5 minute set-up
- 2. Insert schedule JPM130R2
- 3. Allow rod D4 to misalign by greater than 12 steps, then place Rod Bank SEL switch to MAN.
- 4. Remove malfunction RD0457 to allow recovery of the rod.
- 5. Verify Rod Disconnect Box unlocked Optional: 12 minute set-up
- 1. Reset to any 100% IC.
- 2. Enter malfunction RD0457 Control Band "D" stuck rod "D4"
- 3. Place the master silence switch in the "Master Silence" position and place the simulator in "RUN".
- 4. Reduce turbine load by about 20 MWe using the Load Limit potentiometer to cause Control Bank D to insert by greater than 12 steps, then place Rod Bank SEL switch to MAN.
4
- 5. Allow rod 04 to misalign
- 6. Allow the simulator time to stabilize prior to performing the next step.
- 7. Remove malfunction RD0457 to allow recovery of the rod.
- 8. Verify Rod Disconnect Box unlocked.
- NOTES TO TASK PERFORMANCE EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: 2K13 NRC S.1 Revision: 1 chg 7 Task
Title:
Control Rod Out Of Alignment STARTTThJE: _______
PERFORMANCE STANDARD STEP CAUTION Reads caution and note. Critical: Grade
- 1
- Improper rod alignment can cause y [ ] s[]
3552 A tt. A fuel damage either directly or in N [X] u[ ]
conjunction with plant transients.
- Resetting ROD CONTROL URGENT FAILURE (MB4C 4-8) alarm without correcting the cause may result in dropping a group of control rods.
NOTE
- A ROD CONTROL URGENT FAILURE (MB4C 4-8) alarm will inhibit both manual and automatic motion for all rods controlled from the affected power cabinet.
Comments:
Cue:
STEP Check Plant Conditions Verifies that the plant is in Mode 1 based Critical: Grade
- 2
- Verify operational mode - MODE 1 on current power level. y [ ] s[]
3552 A tt. A N [X] u[ ]
Step 1 Comments:
Cue:
6
STEP Identify misaligned rod(s) using: Checks the DRPI display and calls up Critical: Grade
- 3
- Rod Supervision on plant process menu, Rod Supervision button) and N [X] u[ ]
computer identifies rod D4 as the only affected rod.
Comments:
Cue:
STEP Check ROD CONTROL URGENT Checks Main Board annunciator MB4C 4- Critical: Grade
- 4 FAILURE (MB4C 4-8) annunciator- LIT 8 NOT LIT. Takes RNO action and y [ ] s[]
proceeds to step 1 o. N [X] u[ ]
Comments:
Cue:
STEP Using Attachment G, request I&C Verify Recognizes from Initial Conditions that Critical: Grade
- 5 affected rod lift coil fuse--- the lift coil fuse for rod D4 was blown and y [ ] s []
3552 A tt. A NOT BLOWN has been replaced by I&C.
N [X] u[ ]
Step1o Comments:
Cue: As needed, inform the examinee that the lift coil fuse for rod D4 was blown and has been replaced by I&C.
STEP Verify Reactivity Control Systems Refers TRM and verifies that the Critical: Grade
- 6 Limits shutdown rods are greater than the listed y [ ] s []
3552 A tt. A Using TRM, Appendix 8.1 ,COLR, Check all insertion limit of 220 steps. N [X] u[ ]
Step 2 shutdown rods ---
WITHDRAWN TO GREATER THAN OR EQUAL TO THE SHUTDOWN INSERTION LIMIT Comments:
Cue:
7
STEP Check rods--- Checks DRPI and/ or the PPC "Rod Critical: Grade
- 7 AT LEAST ONE ROD MISALIGNED BY Supervision" display and verifies that rod y [ ] s[]
MORE THAN +/-12 STEPS FROM ITS D4 is out of alignment by more than 12 N [X] u[ ]
GROUP STEP COUNTER steps.
Comments:
Cue:
STEP Check rods --- Checks DRPI and/or the PPC "Rod Critical: Grade
- 8 A MAXIMUM OF ONE ROD MISALIGNED Supervision" display, and verifies that y [ ] s[]
BY MORE THAN +/-12 STEPS FROM ITS ONLY rod D4 is out of alignment by more N [X] u[ ]
GROUP STEP COUNTER than 12 steps Comments:
Cue:
STEP Notify Reactor Engineering Notifies Reactor Engineering that D4 is Critical: Grade
- 9 misaligned more than 12 steps from its y [ ] s[]
group. N [X] u[ ]
Comments:
Cue:
STEP Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Using OP 3209B, "Shutdown Completed Shutdown Margin calculation Critical: Grade
- 10 Margin," Determine Shutdown Margin in shows that SDM is adequate in present y [ ] s[]
MODES 1 and 2 with an inoperable rod plant mode of operation. N [X] u[ ]
Comments:
Cue: Inform examinee that Shutdown Margin is adequate for present plant conditions.
STEP Verify Power Distribution Limits Checks the power range meters on MB4 Critical: Grade
- 11 Check reactor power--- and determines that reactor power is y [ ] s[]
3552 A tt. A GREATER THAN 50% greater than 50% N [X] u[ ]
Step 3 Comments:
Cue: - --*--****---***--
8
STEP Determine QPTR using: Plant computer--- Examinee may start to determine QPTR. Critical: Grade
Power Tilt Ratio N [X] u[ ]
Comments:
Cue: Inform the examinee that the QPTR is less than 1.02.
STEP Check QPTR --- Recognizes that QPTR < 1.09, and Critical: Grade
- 13 LESS THAN OR proceeds to next step. y [ ] s []
EQUAL TO 1.09 N [X] u[ ]
Comments:
Cue:
STEP Check QPTR --- Recognizes that QPTR provided indicates Critical: Grade
- 14 LESS THAN OR < 1.02, and proceeds to next step. y [ ] s[]
EQUAL TO 1.02 N [X] u[ ]
Comments:
Cue:
STEP Using TRM, Appendix 8.1, AFD within limits, examinee proceeds to Critical: Grade
- 15 COLR, Check AFD --- next step. y[ ] s[]
WITHIN LIMITS N [X] u[ ]
Comments:
Cue: Inform the examinee that AFD is within the limits specified in the TRM. i STEP Check If Power Should Be Examinee proceeds to 4b RNO based on Critical: Grade
- 16 Reduced rod not misaligned greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. y [ ] s[]
3552 N [X] u[ ] !
A tt. A If necessary, Request Reactor Step 4 Engineering determine time rod has been misaligned !
Check rod misaligned - GREATER THAN 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Comments:
Cue: Inform examinee that rod has been misaligned less than one hour. !
9
STEP Perform the applicable action: Examinee proceeds to NOTE prior to step Critical: Grade
- 17 5. y [ ] s[]
IF performing rod alignment within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is N [X] u[ ]
Desired (TIS 3.1.3.1 ACTION b.1. or TIS 3.1.3.5 ACTION a.), THEN Proceed to NOTE prior to step 5. and, IF the rod is NOT aligned within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, THEN Perform steps 4.c. through 4.h.
Comments:
Cue:
STEP NOTE Critical: Grade
- 18
- A ROD CONTROL URGENT y [ ] s[]
FAILURE (MB4C 4---8) alarm will N [X] u[ ]
occur during recovery unless the affected rod is in Shutdown Bank C, D, or E.
- If the affected rod is in a Control Bank, a ROD CONTROL BANKS LIMIT LO (MB4C 3---9) alarm and ROD CONTROL BANKS LIMIT LO LO (MB4C 4---9) alarm may occur during recovery and remain in alarm until the PIA converter is reset.
Therefore, response to these alarms is not appropriate during this period.
Comments:
Cue:
STEP Establish Conditions For Rod Recognizes that cause has been Critical: Grade
- 19 Alignment corrected from information provided in the y [ ] s[]
3552 A tt. A Verify cause of misaligned - CORRECTED Initial Conditions. N [X] u[ ]
Step 5 Comments:
Cue:
10
STEP Record affected group step counter Notes the position of the control bank D Critical: Grade
- 20 position group 1 step counter and records that y [X] s []
number in Step 5.b. N[ ] u[ ]
Comments:
Cue:
STEP Align control rod disconnect 1. ) Locates and opens control rod Critical: Grade
- 21 switches: disconnect switch box.
y [X] s[]
- 1) Unlock and Open control rod disconnect N[ ] u[ ]
2.) Positions all of the disconnect switch box (3RDS---HDSBOX1) using switches for the control bank D rods with CAT 60, Key #18 in CO key locker) the exception of rod D4 "up" to the ROD
- 2) Place each rod disconnect switch for the affected bank, except the misaligned rod, DISCONNECT position (Both Group 1 and 2 of Control Bank D).
to the ROD DISCONNECTED position Comments:
Cue: Inform examinee that the rod control disconnect box is unlocked.
STEP Place control rod bank SEL switch to the Places the control bank SEL switch to the Critical: Grade
- 22 affected bank position CBD position. y [X] s[]
N[ ] u[ ]
Comments:
Cue:
STEP Align Rod Checks the DRPI display and verifies that Critical: Grade
- 23 Using DRPI display, Check misaligned rod rod D4 is higher than the remaining rods y [X] s[]
3552 A tt. A ---HIGHER THAN ASSOCIATED BANK in control bank D. N[ ] u[ ]
Step 6 Comments:
Cue:
STEP Insert misaligned rod until next lower Takes the In-Hold-Out switch to the "IN" Critical: Grade
- 24 position DRPI LED just changes state position until the next lower position LED y [X] s[]
for rod D4 comes on, then releases the N[ ] u[ ]
switch.
Comments: This action will cause main board annunciator MB4C 4-8 to alarm. The examinee should acknowledge the alarm. This is not required to satisfy the critical nature of the step.
Cue: Per OP-AP-300, the examinee is expected to notify the control room team when a reactivity change is going to occur. However, this is not required to complete the critical task of this JPM.
11
STEP Reset affected group step counter to a Resets the control bank D group 1 step Critical: Grade
- 25 value of 2 steps higher than affected rod's counter to a position that corresponds to y [X] s[]
indicated DRPI position 2 steps higher than the DRPI indication N[ ] u[ ]
for rod D4.
Comments:
Cue:
STEP Proceed to step 6.g. Proceeds to step 6.g. Critical: Grade
- 26 y [ ] s[]
N [X] u[ ]
Comments:
Cue:
STEP Verify rod misaligned --- Acknowledges cue and continues to next Critical: Grade
- 27 LESS THAN 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> step. y [ ] s[]
N [Xl u[ 1 Comments: '
Cue: Inform the candidate "The rod has been misaligned for 30 minutes".
STEP Move misaligned rod until affected group Takes the In-Hold-Out switch to the "IN" Critical: Grade
- 28 step counter indicates value recorded in position until the control bank D group 1 y [X] s[]
step 5.b. step counter is at the number that was N [ ] ur l I previously recorded and then releases the switch.
Comments: Per OP-AP-300, the examinee is expected to notify the control room team when a reactivity change is going to occur. However, this is not required to complete the critical task of this JPM.
I Cue: I i
STEP Restore Rod Control System Returns all lift coil disconnect switches to Critical: Grade
- 29 Place all lift coil disconnect the "Connected" position (Both Group 1 y [X] s[]
3552 At t. A switches for affected bank to and 2 of Control Bank D). N[ ] u[ ]
Step 7 ROD CONNECTED position Comments:
Cue: J 12
STEP Check ROD CONTROL URGENT
- Observes that annunciator MB4C 4-8 IS Critical: Grade
- 30 FAILURE LIT. y [ ] s[]
(MB4C 4---8) annunciator N [X] u[ ]
---LIT Comments:
Cue:
STEP Press ROD DRIVE RESET Presses the ROD DRIVE RESET Critical: Grade
- 31 pushbutton on MB4. y [X] s []
N[ ] u[ ]
Comments: This action will cause annunciator MB4C 4-8 to clear. The examinee should reset this alarm. This is not required to complete the critical task of the step Cue:
STEP Place control rod bank SEL switch in MAN Rotates the control bank SEL switch to Critical: Grade
- 32 the MAN position. y [ ] s[]
N [X] u[ ]
Comments:
Cue:
STEP Check affected rod in a--- Examinee determines that rod D4 is in a Critical: Grade
- 33 CONTROL BANK control bank. y [ ] s[]
N [X] u[ ]
Comments:
Cue:
STEP Check affected rod in --- GROUP 1 Examinee determines that D4 is a Group Critical: Grade
- 34 1 rod. y [ ] s[]
N [X] u[ ]
Comments:
Cue: **- -- ----*- - -
TERMINATION CUE: The evaluation for this JPM is complete.
STOP TIME: _ __
13
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC S.1 Revision: 1 chg 7 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 20 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
14
STUDENT HANDOUT JPM Number: 2K13 NRC 8.1 Revision: 1 chg 7 Initial Conditions: A problem in the EHC circuit caused a momentary run back of the turbine/generator. During the subsequent insertion of the reactor control rods, rod D4 in Control Bank D was observed to be misaligned. The control room team entered AOP 3552 and has decided that Attachment A will be used to recover the misaligned rod.
The lift coil fuse for rod D4 was blown, and has been replaced.
MB4C 6-5 "Tref I Auct Tave Deviation" is lit. Another Operator will perform SP 3601 G.3 "Tavg monitoring" and address this ARP.
Initiating Cues: The US has directed you to complete Attachment A of AOP 3552 step 1 through step 7 .f.
15
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Manual CIA JPM Number: 2K13 NRC S.2 (076-1) Revision: 1 chg 6 Initiated:
fL_ ~fh William M. Forrestt 9/26/13 Developer Date Reviewed:
Technical Reviewer Date Approved:
Trad Horner Supervisor, Nuclear Training Date
SUMMARY
OF CHANGES All & DATE DESCRIPTION REV/CHANGE 10/21/02 Updated task number, knowledge per NUREG 1122 and 1 /1 minor editorial and format changes. DELETED tables in JPM and provided direction for evaluator to use copies of latest revision of E-0 Attachment "A" for CIA valves. Verified through rev 021-01 of E-0 CM 9/26/06 Update to E-0 rev 22 MJS 1/ 2 6/5/09 Fleet format and E-0 rev 25 BMP 1/ 3 8/31/09 Added new IC# and removed reference to Train A. (Att A is 1/4 no longer segregated by Train.) RJM 1/6/11 Update to E-0 Rev 26 JSY 1/ 5 9/26/13 Update to new 5 column JPM format. Revised cue to 1/ 6 perform E-0 steps 13 and 14. Added failure of 3 valves to re-position making this an alt path JPM. Changed to setup to IC-120 - WMF 2
JPM WORKSHEET Facility: _M_P_3_ _ __ Examinee:
JPM Number: 2K13 NRC S.2 Revision: 1 chg 6 Task
Title:
Manual CIA System: 013 (ESFAS)
Time Critical Task: ) YES (X) NO Validated Time (minutes): _ __;g=-----
Task Number(s): 000-05-084 Applicable To: SRO X RO X PEO - - -
KIA Number: 013 A4.01 KIA Rating: _ _ _ _ _ _ __
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In-Plant:
Task Standards: Complete a manual CIA, using EOP 35 E-0 Required Materials: E-0, Rev. 26-01 Attachment "A" (procedures, equipment, etc.)
General
References:
NA 3
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC 8.2 Revision: 1 chg 6 Initial Conditions: The plant has just experienced a Reactor Trip and Safety Injection. The crew has performed E-0, Reactor Trip or Safety Injection, and is currently at step 13, Verify CIA.
Initiating Cues: The US directs you to perform E-0 steps 13 and 14.
Simulator Requirements: Preferred:
Reset to IC-120 Optional:
- 1. Reset to any 100% power IC
- 2. Insert Malfunctions:
- a. MS01A-1 E 6
- b. RP11 K - Failure of "CIA" to actuate
- 3. Insert 1/0 overrides for manual CIA:
- a. PB1-31SC-CIA, RPDI0066 NISOLATE
- b. PB2-31SC-CIA, RPDI0067 NISOLATE
- c. CHDI0082 "3FPW*CTV48" (open/auto)
- d. CHDI0060 "3CDS-CTV39B" (open/auto)
- e. CHDI0062 "3CDS-CTV40B" (open/auto)
- 4. Take the master silence switch to the SILENCE position
- 5. Place simulator in "RUN"
- 6. A reactor trip and safety injection will occur. Allow ESF Status Panel to finish changing state (CIA) components will remain "as is")
- 7. Place the simulator in "FREEZE"
- 8. Place simulator in "RUN", after the examinee has received the initial conditions and initiating cues Approximate simulator setup time is 15 minutes.
4
- NOTES TO TASK PERFORMANCE EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: 2K13 NRC S.2 Revision: 1 chg 6 Task
Title:
Manual CIA START TIME: ----
PERFORMANCE STANDARD STEP Critical: Grade
- 1 Verify CIA Observes Status Panel indication on MB2 y [X] s[]
E-0 Step and observes not all lights are lit (Group 2, N[ ] u[ ]
13 Check ESF Group 2, columns 2 through 10 columns 2 through 10).
-LIT Proceeds to RNO.
Comments This begins alt path portion of the JPM.
I Cue:
I STEP Critical: Grade 1
- 2 Initiate CIA. Initiates CIA by depressing pushbutton on y [X] s[]
E-0 Step MB2. N[ ] u[ ]
13 RN0 IF ESF Group 2, columns 2 through 10 are I NOT lit, THEN Using Attachment A, Determines CIA did NOT actuate and obtains Reposition valves as necessary for Attachment A.
minimum safety function Comments Cue:
6
STEP Using Attachment A, Reposition valves as Obtains copy of E-0, Attachment A. Critical: Grade
- 3 necessary for minimum safety function. 1 .) For each containment penetration y [X] s[]
E-0 Step isolation valve depresses the close push N[ ] u[ ]
13 RN0 SEE ATTACHMENT 'A' ON button or rotates control switch to the "close" FOLLOWING PAGE position and observes indicating lights shift to green illuminated, red extinguished.
2.) Recognizes three valves (in comment 2 below} will not_g_o closed.
Comments: 1.) The examinee should attempt to close all valves on Attachment 'A'. However, only one valve per block is needed to meet minimum safety function. Some penetrations only have single valve isolation. In these penetrations there is only one valve in a block and it must be closed to meet minimum safety function.
2.) All valves will operate as expected with the exception of: a.) 3FPW*CTV48, Fire Water b.) 3CDS*CTV39B, Train B Return c.) 3CDS*CTV40B, Train B Return (all of these valves have failed in the OPEN position). These failures make JPM alt path.
3.) Critical nature of step is that the examinee isolates penetrations to meet minimum safety function (see comment 1 above_l__I_his will b~ssible in aii_Qenetr§tions ~xcep_!_ the f?_ulted QDS penetration.
Cue:
STEP Observes status panel indication on MB2 and Critical: Grade
- 4 Verify Proper ESF Status Panel Indication makes the following determination I report: y [X] s[]
E-0 Step
- Verify ESF Group 1 lights -OFF 1 .)All valves are closed with the exception of N[ ] u[ ]
14
- Verify ESF Group 2 lights - LIT 3FPW*CTV48, 3CDS*CTV39B, and 3CDS*CTV40B.
RNO- Align component(s) as necessary 2.) MINIMUM SAFETY FUNCTION is NOT for minimum safety function. MET as a CDS penetration is not isolated.
Comments: I (1) The critical aspect of this step is that the examinee recognizes that the CDS penetration is not isolated and does NOT meet minimum safety function. In order to make this decision, the examinee may reference a P&ID.
(2) The candidate may have to be prompted for a determination of Minimum Safety Function.
(3) For the SRO candidates ONLY:
After he I she determines that Minimum Safety Function is NOT met, ask the following:
"What actions, if any, should be performed to address the valve failures?"
Answer: An Operator and or Maintenance should be sent to investigate and manually close at least on the CDS valves (3CDS*CTV39B and 3CDS*CTV40B). This SRO follow-UJ! question is NOT critical.
Cue:
TERMINATION CUE: The evaluation for this JPM is concluded. STOP TIME:
7
Attachment A "Containment Isolation Phase A Valves" COMPONENT DESCRIPTION POSffiON 3SSP*CTV7 PASS Isolation Closed 3SSP*CTV8 PASS Isolation Closed 3SSR*CTV26 R'\':Hot Leg Closed 3SSR*CTV27 R~Hot Leg Closed 3SSR*CTV19 Rx Cold Leg Closed 3SSR*CTV30 R'\: Cold Leg Closed 3SSR*CTV20 PZR Vapor Closed 3SSR*CTV11 PZR Vapor Closed 3SSR *CV8026 PRT Gas Closed 3SSR *CV8025 PRT Gas Closed 3SSR*CTV32 SI Accumulator Closed 3SSR*CTV33 SI Accmnulator Closed 3IAS*PV15 Instnm1ent Air Closed 3IAS*MOV72 Instnuuent Air Closed 3GSN*CTV105 Nitrogen to PRT Closed 3GSN* CV8033 Nitrogen to PRT Closed 3C?v1S *CTV20 Ctmt Atmospheric Monitor Closed 3CMS*CTV21 Ctmt Atmospheric Monitor Closed 3CMS*C'f\.'23 Ctmt Atmospheric Monitor Closed 3CMS*MOV24 Ctmt Atmospheric Monitor Closed 3VRS*CTV20 Gas Vent Closed 3VRS*CTV21 Gas Vent Closed 3DGS*CTV24 Reactor Plant Drains Gaseous Closed 3DGS*CTV25 Reactor Plant Drains Gaseous Closed 3DAS*CTV24 Reactor Plant Drains Aerated Closed 3DAS*CTV25 Reactor Plant Drains Aerated C1osed 8
Main Board 1 (Vertical) (Continued)
COMPONENT DESCRIPTION POSmON 3PGS* C\18046 Primary Water Closed 3PGS*CV8028 Prilnary Water Closed 3FP\\l*CTV48 Fire \Vater Closed 3FP\\l* CTV49 Fire \Vater Closed 3CVS *CfV20A Ctmt Vacuun1 Pump Closed 3CVS*CfV21A Ctmt Vacuum Pump Closed 3CVS *CTV20B <=Jttllt ~~Cllllm JlllllliJ Closed 3CVS*CfV21B Onlt Vacuum Pump Closed Main Board 1 (Horizontal)
COMPONENT DESCRIPTION PosmoN 3CDS*CTV38A Train A Supply Closed 3CDS *CTV91A Train A Supply Closed 3CDS *CTV38B Train B Supply Closed 3CDS*CTV91B Train B SupiJly Closed 3CDS*CTV39A Train A Return Closed 3CDS*CTV40A Train A Return Closed 3CDS*CTV39B Train B Return Closed 3CDS* CTV40B Train B Return Closed 3CDS*AOV45C/46C Coil lA (Train A) Closed 3CDS* AOV45B/46B Coil 1B (Train B) Closed 3CCP* AOV10N19A Train A Supply/Rentrn Isolation Closed 3CCP* AOV197A/194A Train A Supply/Return Isolation Closed 3CCP* AOV10B/19B Train B SnpiJly/Rehlrn Isolation Closed 3CCP* AOV197B/194B Train B Supply./Rentrn Isolation Closed
-lCCP*MV'J?3 1?J5 CDS/CCP Train A cross-connect Open
' _..,. J--
~* "' . _.. . . t--
3CCP *~lJ? J tJ J4 CDS/CCP Train A cross-connect Open 3CCP *M\'226/228 CDS/CCP Train B cross- connect Open JCCP*M\'227/229 CDS/CCP Train B cross- connect Open 9
COMPONENT DESCRIPTION PO SillON 3SIH*CV8823 Cold Legs Closed 3SIH* CV8824 1/3 Hot Legs Closed 3SIH*CV8881 2/4 Hot Legs Closed 3SIH* CV8843 Chg Cold Legs Closed 3SIH* CV8888 SI Accmnulator Master Fill Closed 3SIH* C'V8964 SI Test Header C1osed 3SIH* CV8871 SI Test Header Closed 3SIL*CV8890A l/2 Cold Legs Closed 3SIL*CV8890B 3/4 Cold Legs Closed 3SIL*CV8825 2/4 Hot Legs Closed 3SIL *CV8968 Nitrogen Supply Closed 3SIL *CV8880 Nitrogen Supply C1osed Main Board 3 (Horizontal)
CO~fPONENT DESCRIPTION PO SillON 3CHS*MV8100 RCP Seal Isolation Closed 3CHS*MV8112 RCP Seal Isolation Closed 3CHS*CV8160 Letdown Hdr Isolation Closed 3CHS*CV8152 Letdown Hdr Isolation Closed 10
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC S.2 Revision: 1 chg 6 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 9 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
11
STUDENT HANDOUT JPM Number: 2K13 NRC S.2 Revision: 1 chg 6 Initial Conditions: The plant has just experienced a Reactor Trip and Safety Injection.
The crew has performed E-0, Reactor Trip or Safety Injection, and is currently at step 13, Verify CIA.
Initiating Cues: The US directs you to perform E-0 steps 13 and 14.
12
STUDENT HANDOUT JPM Number: 2K13 NRC S.2 Revision: __1.:.__::.:ch..:..;;;g!....,;6=---
Initial Conditions: The plant has just experienced a Reactor Trip and Safety Injection.
The crew has performed E-0, Reactor Trip or Safety Injection, and is currently at step 13, Verify CIA.
Initiating Cues: The US directs you to perform E-0 steps 13 and 14.
12
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Transfer To Cold Leg Recirculation JPM Number: 2K13 NRC S.3 (S022A-3) Revision: 2 chg 1 Initiated:
(L_/1 Ut William M. Forrestt 9/18/13 Developer Date Reviewed:
Technical Reviewer Date Approved:
Trad Horner to{, {13 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES All & DATE DESCRIPTION REV/CHANGE 5/5/09 ES 3.1 rev 15 and updates to fleet template. 8MP 1/1 8/31/09 Added IC# and minor changes. RJM 1/2 9/25/10 Corrected old JPM step 3, in that it was not marked 1/3 critical (it is a critical step), and corrected the status of 3RHS*P1 8 in that it has auto-stopped on lo-lo level.
Also corrected the status of all RSS pumps in that 'A' train pumps fail to auto-start, '8' train RSS pumps do auto start. Modified old JPM step 3 into 3 separate steps. Renumbered steps. Verified updated to Rev 015 of ES-1.3. Added Pass/Fail criteria for the JPM as specified in TR-AA-410. DLM 5/2/11 Verified update to Rev 015-01 of ES-1.3 1/4 Updated JPM number and format JSY 8/18/12 This is a new revision 2. The last revision, revision 1 2/0 change 4, was found in the approved directory, but with no approval signatures. In addition, no hardcopy of an approved revision 1 change 4 could be found. Verified update to Rev 015-01 of ES-1.3. Changed JPM number from 0228 to S022A-3. DLM 9/18/13 Updated to new 5 column JPM format. Added new 2/1 imbedded failure, 3SIH*MV88078. Clarified performance steps throughout. - WMF 2
JPM WORKSHEET Facility: ~M~P..:..3_ _ __ Examinee:
JPM Number: 2K13 NRC S.3 Revision: 2 chg 1 Task
Title:
Transfer To Cold Leg Recirculation System: 006 (ECCS)
Time Critical Task: (X) YES ( ) NO Validated Time (minutes): 22 min.
overall Task Number(s): 000-05-051' 600-05-015, 600-05-016 Applicable To: SRO X RO X PEO - - -
KIA Number: 006 A4.05/ KIA Rating: 3.9/3.8 EPE:011-EA1.11 4.2/4.2 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In-Plant:
Task Standards: JPM consists of two timed Operator Credited Actions (COP 200.18, Time Critical Action Validation and Verification)
(1) Stop RHR pumps within 5 minutes of receiving RWST LO LO signal (2) Successfully align RHR and Recirculation Spray System for Cold Leg Recirculation lAW EOP 35 ES - 1.3, Transfer to Cold Leg Recirculation. The time credited Operator action is 25 minutes from RWST LO LO to achieve this sump recirculation alignment.
Required Materials: EOP 35 ES-1.3 Rev. 015-01 (procedures, equipment, etc.)
General
References:
NA 3
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC S.3 Revision: 2 chg 1 Initial Conditions: A Loss of Coolant Accident has occurred which resulted in a Reactor Trip and Sl. The Control Room team has implemented the applicable EOPs through E-1 step 13. All emergency equipment operated as designed when the Reactor tripped and Safety Injection Initiated. Sl has been reset.
Initiating Cues: The "RWST LO LO LEVEL RHR PUMP OFF" annunciator has just illuminated. RWST level is- 520,000 gallons. You are to perform ES-1.3, Transfer To Cold Leg Recirculation,"
beginning at step 1.
Simulator Requirements:
Reset to IC 245 (preferred)
- 1. Reset to any 100% IC and disable annunciators
- 2. Insert the following malfunctions:
- c. SIDI0017 "3SIHMV8807B" to close
- 2. When RWST level decreases to the LO-LO setpoint, verify RHS*P1 A does not trip and RSS*P1 A & P1 C do not start.
- 3. Acknowledge and clear all alarms
- 4. FREEZE the simulator
- 5. After the examinee has read the initial conditions and initiating cues, place the simulator in "RUN" Approximate simulator setup time is 45 minutes.
4
- NOTES TO TASK PERFORMANCE EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: 2K13 NRC S.3 Revision: 2 chg 1 Task
Title:
Transfer To Cold Leg Recirculation STANDARD START TIME:
PERFORMANCE STEP CAUTION: I Reads cautions and notes. Critical: Grade
- 1
- Sl recirculation flow to RCS must be y [ ] s[]
maintained at all times. N[X] u[ ]
ES-1.3 Step 1
- After Sl reset, manual action to restart safeguards equipment may be required, if offsite power is lost.
- High radiation levels may be experienced in the Auxiliary and ESF buildings following the transfer to cold leg recirculation.
NOTE:
- Foldout page must be open.
- DO NOT implement Functional Response procedures until completion of step 5.
Comments: I This JPM will start with a 5 minute Operator credited action (stop RHR pump(s)). Therefore, it is important to ensure that the Examinee is fully ready to begin before starting the JPM. Once the candidate is ready to b~in~ark the start time_iwUI_I:>euse<!for 5 minute and a 25 minute O~erator credited action).
Cue: I If the candidate asks to perform two handed operation, report "The SM allows you to perform two handed operation".
If the candidate asks for a peer check, report "No peer check will be provided".
6
STEP RESET ESF Actuation Signals, If Locates RESET push buttons on M82 Critical: Grade
- 2 Required and depresses push buttons (two buttons Y[X] s[]
- RESET Sl per signal, 'A' and '8' train). lAW N [ ] u[ ]
RESET the following: standards, should use single hand
- CDA manipulation with RESET action.
- LOP Examinee acknowledges clearing of
- CIA alarms (as applicable) after SAT reset.
- Cl8 Comments: Pushing reset for signal that is not active (SI) is optional. Critical attribute is satisfactory reset of signals that are active (CDA, CIA & CIB)
Cue: Sl has been reset.
STEP Verify RWST Low---Low Level Observes that RHS*P1A is NOT stopped Critical: Grade
- 3 Automatic Actions by observing bkr indicating lights, and/or Y[X] s[]
Check RHR pumps - STOPPED amps, flow, pressure N[ ] u[ ]
ES-1.3 Step 2 Place RHR pump control switches in Pull-To-Lock Rotates RHS*P1A to the stop position.
Observes pump stops by bkr indicating red light OFF, green ON, and/or amps, flow etc.
Rotates RHS*P1A & P1 8 control switches to stop and places in PTL.
Observes green bkr indicating lights OFF Comments: I (1) Booth operator record time "A" RHS pump stopped and verify pump is stopped within 5 minutes of JPM start time (See Task Standard discussion of Operator credited action). (2) This begins the AL T PATH portion of JPM.
Cue:
7
STEP Check RSS pumps A and B Observes breaker indicating lights and or Critical: Grade
- 4 -RUNNING amps, flow etc and determines RSS*P1 B y [X] s[]
RNO: START pump(s). running, P1A off.
N[ ] u[ ]
Rotates RSS*P1A to the start position.
Observes pump starts by breaker indicating red light ON, green OFF, and/or amps, flow etc.
Comments:
Cue:
STEP Check RSS pumps C and D Observes breaker indicating lights and or Critical: Grade
- 5 -RUNNING amps, flow etc and determines RSS*P1 D Y[X] s[]
RNO: IF CTMT pressure is GREATER running, P1 C off.
N[ ] u[ ]
THAN 17.5 psia THEN START pumps.
Observes Ctmt pressure > 17.5 psia, Rotates RSS*P1 C to the start position.
Observes pump starts by bkr indicating red light ON, green OFF, and/or amps, flow etc.
Comments:
Cue:
8
STEP Critical: Grade I
- 6 CAUTION: Reads the Cautions and Notes. y [ ] s[]
- All ECCS pumps taking a suction N[X] u[ ] I from the RWST should be stopped if RWST level decreases to 100,000 I gal.
- Consult with the ADTS and RMT I prior to performing any local RHR and Recirculation Spray System operations.
NOTE:
- Either train of recirculation spray can supply water to the core.
Comments:
Cue:
STEP Align RHR And Recirculation Acknowledges, after cue, that this has Critical: Grade
- 7 Spray Systems For Cold Leg been completed and proceeds to next y [ ] s[]
Recirculation step. N[X] u[ ]
ES-1.3 Step 3 Verify cold leg recirculation capability (if previously performed, proceed to step 3.b.)
- 1) Recirculation spray pumps
---AVAILABLE
- 2) Using Attachment A, Verify power for cold leg recirculation valves ---
AVAILABLE Comments:
Cue: Inform examinee that "Recirculation capability has previously been verified".
9
STEP Verify recirculation spray heat exchanger Locates valves (3SWP*MV54A & Critical: Grade
- 8 SW inlet isolation valves--- OPEN 3SWP*MV54B) and verifies both valves y [ ] s[]
- 3SWP*MOV54A N[X] u[ ]
are OPEN (red light on with green light
- 3SWP*MOV54B off) .
Comments:
Cue:
STEP Verify recirculation spray header isolation Locates valves (3RSS*MOV20A & Critical: Grade
- 9 valves --- OPEN 3RSS*MOV20B) and verifies both valves y [ ] s[]
- 3RSS*MOV20A are OPEN (red light on with green light N[X] u[ ]
- 3RSS*MOV20B off).
Cue:
Comments:
STEP Verify recirculation spray Locates pumps (3RSS*P1A & Critical: Grade
- 10 pumps A AND B --- 3RSS*P1 B) and verifies both are ON y [ ] s[]
RUNNING (red light on with green light off). N[X] u[ ]
Examinee may also choose to monitor pump amps, discharge pressure, and flow using MB instruments.
Comments:
Cue:
STEP CLOSE RHR cold leg injection valves Locates valves (3SIL*MV8809A & Critical: Grade
- 11
- 3SIL *MV8809A 3SIL*MV8809B) and depresses CLOSE Y[X] s[]
- 3SIL *MV8809B P/B(s) while monitoring for closure (green N[ ] u[ ]
light on with red light off).
Comments:
Cue:
10
STEP CLOSE RWST/RHR pump suction valves Locates valves (3SIL*MV8812A & Critical: Grade I
- 12
- 3SIL*MV8812A 3SIL*MV8812B) and depresses CLOSE Y[X] s[] .
- 3SIL*MV8812B P/B(s) while monitoring for closure (green N[ ] u[ ]
light on with red light off). J I
Comments:
Cue:
STEP CLOSE RHR pump cross---over valves Locates valves (3RHS*MV8716A & Critical: Grade
- 13
- 3RHS*MV8716A 3RHS*MV8716B) and depresses CLOSE Y[X] s[]
- 3RHS*MV87168 P/B(s) while monitoring for closure (green N[ ] u[ ]
light on with red light off).
Comments:
Cue:
STEP CLOSE Sl pump recirculation valves to Locates valves (3SIH*MV8813, Critical: Grade
- 14 RWST 3SIH*MV8814 & 3SIH*MV8920) and Y[X] s[]
- 3SIH*MV8813 depresses CLOSE P/B(s) while N[ ] u[ ]
- 3SIH*MV8814 monitoring for closure (green light on with
- 3SIH*MV8920 red light off).
Comments:
Cue:
STEP CLOSE charging pump miniflow isolation Locates valves 3CHS*MV8511A, Critical: Grade
- 15 valves to RWST 3CHS*MV8511 B, 3CHS*MV8512A & Y[X] s[]
- 3CHS*MV8511A 3CHS*MV8512B) N[ ] u[ ]
- 3CHS*MV8511 B and depresses CLOSE P/B(s) while
- 3CHS*MV8512A monitoring for closure (green light on with
- 3CHS*MV85128 red light off).
Comments:
Cue:
11
STEP Verify RSS pumps have The examinee may start a timer to ensure Critical: Grade
- 16 been in operation --- AT the three minute minimum run time is Y[X] s[]
LEAST 3 MINUTES achieved. Other methods, such as a N[ ] u[ ]
check of the computer, are acceptable.
Comments:
Cue:
STEP OPEN recirculation spray RHR isolation Locates valves (3RSS*MV8837A & Critical: Grade
- 17 valves 3RSS*MV8837B) and depresses OPEN Y[X] s[]
- 3RSS*MV8837A P/B(s) while monitoring for open N[ ] u[ ]
- 3RSS*MV8837B indication (red light on with green light off).
Comments: I Cue:
STEP OPEN RHR to CHG and Sl Locates valves (3SIL *MV8804A & Critical: Grade 1
- 18 suction isolation valves 3SIL *MV8804B) and depresses OPEN Y[X] s[l I
- 3SIL *MV8804A P/B(s) while monitoring for open N[ ] u[ ]
- 3SIL*MV8804B indication (red light on with green light I off). i Comments:
Cue:
STEP OPEN SI/CHG pump cross---connect Locates valves (3SIH*MV8807A & Critical: Grade
- 19 valves 3SIH*MV8807B) and depresses OPEN Y[X] s[]
- 3SIH*MV8807A P/B(s) while monitoring for open N [ ] u[ ]
- 3SIH*MV8807B indication (red light on with green light off).
Identifies that 3SIH*MV8807B will not open. After consideration (no RNO, flowpath still exists), the examinee proceeds to next ste_p.
Comments: The imbedded failure of 3SIH*MV8807B should be handled based on EOP rules of usage and knowledge of system design. First, there is no RNO to address this. Based on this, EOP rules of usage requires moving to next step.
Additionally, this valve is in parallel with 3SIH*MV8807A which is open.
Cue:
12
STEP Verify a flow path from the Ctmt sump to Traces flow path from the RSS sumps to Critical: Grade 1
Comments: Failure to establish 2 flow_r::>aths from the sump through EGGS is a failure of the JPM Cue:
STEP Verify at least one charging Locates each pump (3CHS*P3A& BAND Critical: Grade
- 21 AND one Sl pump--- 3SIH*P1A & B) and monitors running y [ ] s[]
RUNNING indication of red light on and green light N[X] u[ ]
off. Additional indication may be used including pump amps, discharge pressure, and flow.
Comments:
Cue:
STEP NOTE: Reads note. Critical: Grade
- 22 If a Loss of Offsite Power occurs in the y [ ] s[]
Recirculation Mode, the EDG sequencer N[X] u[ ]
automatically restarts cold leg recirculation components.
Comments:
Cue:
STEP Complete Cold Leg Recirculation Examinee locates valve (3SIH*MV8806) Critical: Grade
- 23 Alignment and depresses CLOSE P/B while Y[X] s []
ES-1.3 Step 4 CLOSE RWST/SI pump suction monitoring for closure (green light on with N[ ] u[ ]
(SIH*MV8806) red light off).
Comments:
Cue:
STEP In cabinets 3RPS*RAKOTA2 Continues on once told another Operator Critical: Grade
- 24 and 3RPS*RAKOTB2, will complete this step. y[ ] s[]
Separate the gray boot N[X] u[ ]
connectors for the VCT level input to 3CHS*LCV112D and 3CHS*LCV112E Comments:
Cue: Inform the examinee that another operator has been dispatched and the task is complete.
13
STEP CLOSE RWST/CHG pump suction valves Locates valves (3CHS*LCV112D & Critical: Grade
- 25
- 3CHS*LCV112D 3CHS*LCV112E) and depresses CLOSE Y[X] s []
- 3CHS*LCV112E P/B(s} while monitoring for closure (green N [ ] u[ ]
light on with red light off).
Comments: Booth operator record time step number 25 is completed and verify time is within 25 minutes of JPM start time (See Task Standard discussion of Operator credited action).
Cue:
STEP Verify Cold Leg Recirculation Traces flow path using MB mimic. Critical: Grade
- 26 Check injection flow to RCS from charging Y[X] s[]
ES-1.3 Step 5 pumps AND Sl pumps --- ESTABLISHED N[ ] u[ ]
Comments: Failure to establish 2 flow paths from the sump through ECCS is a failure of the JPM.
Cue:
STEP Verify at least one recirculation spray pump Traces flow path using MB mimic. Critical: Grade !
- 27 in Y[X] s [l I each train--- ALIGNED FOR COLD LEG N[ ] u[ ]
RECIRC AND RUNNING Comments: Failure to establish 2 flow paths from the sump through ECCS is a failure of the JPM.
Cue:
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ _ __
14
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC S.3 Revision: 2 chg 1 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes X No Validated Time (minutes): 22 min Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
15
STUDENT HANDOUT JPM Number: 2K13 NRC 8.3 Revision: 2 chg 1 Initial Conditions: A Loss of Coolant Accident has occurred which resulted in a Reactor Trip and Sl. The Control Room team has implemented the applicable EOPs through E-1 step 13. All emergency equipment operated as designed when the Reactor tripped and Safety Injection Initiated. Sl has been reset.
Initiating Cues: The "RWST LO LO LEVEL RHR PUMP OFF" annunciator has just illuminated. RWST level is- 520,000 gallons. You are to perform ES-1.3, Transfer To Cold Leg Recirculation," beginning at step 1.
16
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC S.3 Revision: 2 chg 1 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes X No Validated Time (minutes): 22 min Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
15
STUDENT HANDOUT JPM Number: 2K13 NRC 8.3 Revision: 2 chg 1 Initial Conditions: A Loss of Coolant Accident has occurred which resulted in a Reactor Trip and Sl. The Control Room team has implemented the applicable EOPs through E-1 step 13. All emergency equipment operated as designed when the Reactor tripped and Safety Injection Initiated. Sl has been reset.
Initiating Cues: The "RWST LO LO LEVEL RHR PUMP OFF" annunciator has just illuminated. RWST level is- 520,000 gallons. You are to perform ES-1.3, Transfer To Cold Leg Recirculation," beginning at step 1.
16
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Aligning RHR for SDR Inventory Control JPM Number: 2K13 NRC 8.4 Revision: 0 chg 2 Initiated:
fL_/Lfh William M. Forrestt 9/26/13 Developer Date Reviewed:
Technical Reviewer Date Approved:
dDr-Trad Horner Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES All & DATE DESCRIPTION REV/CHANGE 8/18/09 Updated this new JPM (2K9 NRC S.4) to new fleet JPM 0 chg 1 format. Incorporated comments from NRC Prep week. dim 9/26/13 Added hanging Mode 5 tags in sim set-up to improve realism. 0 chg 2 Modified JPM step 8 for expectant condition of 3CCP*FV66A being closed. Modified JPM step 10 to have evaluator remove caution tag.
2
JPM WORKSHEET Facility:
-MP3----- Examinee:
JPM Number: 2K13 NRC S.4 Revision: 0 chg 2 Task
Title:
Aligning RHR for SDR Inventory Control System: 005 Time Critical Task: ) YES ( X) NO Validated Time (minutes): 8 Task Number(s): 005-01-002/019 Applicable To: SRO X RO X PEO KIA Number: 005 A4.01 I 4.02 KIA Rating: 3.6 I 3.4; 3.4 I 3.1 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In-Plant:
Task Standards: Satisfactorily align RHR Train A for shutdown risk inventory control.
Required Materials: 1. OP 3310A, Sec 4.21 (handout)
{procedures, equipment, etc.)
- 2. MP3 Simulator General
References:
OP331 OA Rev 17106 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC S.4 Revision: 0 chg 2 Initial Conditions: The plant is in MODE 5 post refueling, with various maintenance activities being completed prior to plant heat up.
All RCS loops are full, the B RHR pump is OPERABLE and all steam generators have adequate level.
Initiating Cues: The US has directed you to align RHR Train A for shutdown risk inventory control using OP331 OA section 4.21.
Simulator Requirements: Set for IC-235 Ensure that key no. 7 is in at least one RHR suction valve.
(MB2)
Ensure Caution tag on 3SIL*MV8812A reading:
"Maintain valve closed unless needed for inventory control."
Ensure 3CCP*FV66A is closed Hang Mode 5 tags
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: 2K13 NRC S.4 Revision: 0 chg 2 Task
Title:
Aligning RHR for SDR Inventory Control STARTTThJE: _______
PERFORMANCE STANDARD Comments: Candidate may review OP 331 OA precautions prior to starting the task. This is acceptable.
Cue:
STEP Aligning RHR Train A for Shutdown Risk Candidate reviews NOTE Critical: Grade
- 1 Inventory Control y [ ] s[]
N[X] u[ ]
3310A section Paraphrased Note: This section aligns
- 4. 2 1 Train A of RHR for injection from the NOTE RWST to satisfy the Inventory Control requirement of OU-M3-201 "Shutdown Safety Assessment Checklist". This alignment assumes RHR Train A is initially in the cooldown alignment.
Comments: RHR A is initially in cooldown alignment. If asked about COPPS, provide the following cue:
Cue: Both trains of COPPS are being credited for cold overpressure protection.
L ______
5
STEP VERIFY one of the following conditions RO will request of US whether 3.4.1.4.1 is Critical: Grade
- 2 met: satisfied. SRO will check TS and verify y [ ] s[]
- Plant in MODE 5 with at least two from the initial prompt information that N[X] u[ ]
3310A step RCS loops filled and TIS 3.4.1.4.1 3.4.1.4.1 is met.
4.21 .1 LCO satisfied without crediting RHR Train A
- Plant in MODE 6 with water level greater than or equal to 23 feet above the top of the RV flange Comments: If requested, report "RCS has been filled in accordance with applicable procedures".
Cue: To RO only: TS 3.4.1.4.1 is satisfied without crediting RHR train A.
STEP PLACE 3RHS*P1A, "RHR PP A," in 3RHS*P1A is taken to stop, green light is Critical: Grade
- 3 "STOP" and then in "PULL-TO-LOCK" observed, and then taken to P-T-L, and Y[X] s[]
3310A (MB2). all lights observed to extinguish. N[ ] u[ ]
step
- 4. 21 . 2 Comments:
Cue:
STEP CLOSE 3RHS*V20, RHR loop A CVCS Request made to US, or directly to PEO Critical: Grade
- 4 letdown isolation. to close 3RHS*V20. y [ ] s[]
3310A N[X] u[ ]
step
- 4. 2 1 . 3 Comments: Examiner: Have the candidate page the PEO.
BOOTH: When requested, Close RHS*V20 using RHR01 to CLOSE.
Cue: BOOTH: Report 3RHS*V20 is closed once the remote is entered.
6
STEP Using key lock switch, CLOSE Operates valve switch to the CLOSE Critical: Grade
- 5 3RHS*MV8701 B, "A ISOL (OUT)" (MB2): direction for 3RHS*MV8701 B observing Y[X] s []
3310A for only GREEN light lit. N[ ] u[ ]
step
- 4. 2 1 . 4 Comments: Switch to be available on MB2. At this point there is no suction source for the 'A' RHR pump. Thus
_Qerformance step 3 is critical.
Cue:
STEP PERFORM the following (MB2): MANUAL selected on controller 3RHS- Critical: Grade
- 6 FK618. Y[X] s[]
3310A PLACE 3RHS-FK618, "RHR HDR FLOW," N[ ] u[ ]
step 4.21.5.a in"MAN."
Comments:
Cue:
STEP CLOSE the following: 3RHS-FK618 taken to 100% output, Critical: Grade I
- 7 3RHS-HC606 taken to 0 output. Y[X] s[]
- 3RHS-FK618, "RHR HDR FLOW" N[ ] u[ ] I 3310A step (1 00% output) 4.21.5.b
- 3RHS-HC606, "HX A FLOW" I I
Comments:
Cue:
STEP ADJUST 3CCP-HK66A 1, "RPCCW HX Recognizes that 3CCP*FV66A is Critical: Grade 1
- 8 FLOW" (MB2) as necessary to maintain closed (no actions are necessary). y [ ] s[]
3310A RPCCW Train A flow requirements. N[X] u[ ]
step
- 4. 2 1 . 6 Comments: 3CCP*FV66A was closed as an initial condition. I Cue:
7
STEP To align 3SIL *MV8809A, "PP A COLD LEG Verifies pressure > 100 psia and that Critical: Grade
- 9 INJ," PERFORM the following: 3SIL *MV8809A is OPEN (red light lit, y [ ] s[]
green light off). Proceeds to step 4.21.8. N[X] u[ ]
3310A step IF RCS pressure is greater than 100 4.21.7.a psia, PERFORM the following:
- 1) ENSURE 3SIL *MV8809A, "PP A COLD LEG INJ," open (MB2).
- 2) Go to step 4.21.8.
Comments: Pressure is greater than 100 psi a Cue:
STEP To open 3SIL*MV8812A, "RWST/PP A Candidate requests that tag is removed. Critical: Grade
- 10 SUCT ISOL," PERFORM the following y [ ] s[]
(MB2): N[X] u[ ]
3310A step 4.21.8.a REMOVE the following Caution Tag from 3SIL*MV8812A, "RWST/PP A SUCT ISOL," control switch.
Comments:
Cue: Inform candidate authorization has been given to remove the tag AND THEN the evaluator should remove the Caution Tag on 3SIL*MV8812A.
Comments:
STEP OPEN 3SIL*MV8812A, "RWST/PP A Candidate OPENs 3SIL*MV8812A Critical: Grade
- 11 SUCT ISOL." observing for RED light lit, GREEN light Y[X] s[]
3310A out. N[ ] u[ ]
step 4.21.8.b Comments:
Cue: -~
~ -- --------*****-- - -
8
STEP PLACE 3RHS*P1A, "RHR PP A," in 3RHS*P1A is removed from P-T-L, which Critical: Grade
- 12 "AUTO" after "STOP" (MB2). places it in the AUTO after STOP Y[X] s[]
3310A position. Only green light is illuminated. N[ ] u[ ]
step
- 4. 2 1 . 9 Comments:
Cue: ~-
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ _ __
9
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC S.4 Revision: 0 chg 2 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 8 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
10
STUDENT HANDOUT JPM Number: 2K13 NRC S.4 Revision: __0=---=..:ch..:..>ig!....:2=----
Initial Conditions: The plant is in MODE 5 post refueling, with various maintenance activities being completed prior to plant heat up.
All RCS loops are full, the B RHR pump is OPERABLE and all steam generators have adequate level.
Initiating Cues: The US has directed you to align RHR Train A for shutdown risk inventory control using OP331 OA section 4.21.
11
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Natural Circulation Cooldown using GA-26 JPM Number: 2K13 NRC S.5 Revision: 0 Initiated:
9/26/13 Developer Date Reviewed:
Technical Reviewer Date Approved:
Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES A/1 & DATE DESCRIPTION REV/CHANGE 2
JPM WORKSHEET Facility: _Mc.:. :.:. . P. :;. .3_ _ __ Examinee:
JPM Number: 2K13 NRC S.5 Revision:
Task
Title:
Natural Circulation Cooldown using GA-26 System: 039 Main Steam Time Critical Task: ( ) YES (X) NO Validated Time (minutes): 20 min.
Task Number(s): 000-05-101 Applicable To: SRO X RO X PEO _ __
KIA Number: 039 A1.05 KIA Rating: _ _. . : 3. :. : .2: . . *. :. . /. :;. .3:. :. 3_ _
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In-Plant:
Task Standards: Initiate an RCS cooldown, using Atmospheric Relief Bypass Valves, iaw step 5 of ES-0.2, Natural Circulation Cooldown.
Required Materials: ES-0.2, Natural Circulation Cooldown (procedures, equipment, etc.) GA-26, Dumping Steam to Condenser or Atmosphere General
References:
NA 3
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC S.5 Revision: 0 Initial Conditions: A loss of offsite power has occurred and the reactor tripped. Its reported that offsite power will not be restored for an extended period of time. The following conditions exist:
- The control room team has completed through step 4 of ES-0.2, Natural Circulation Cooldown.
- GA - 15, Establishing Boron Concentration For Natural Circulation Cooldown, has been completed and RCS boron concentrations are satisfactory.
- GA- 1, Energizing 32-3T, has been completed and the PPC is available. This included the reset of 'LOP'.
- All four MSIV's are closed
Initiating Cues: The US has directed you to commence a natural circulation cooldown using the Atmospheric Relief Valves per ES-0.2 Step 5.
The US directs you to:
- Review step 5 of ES-0.2 and then initiate a cooldown of the RCS at approximately 30 F /hr {NOT TO EXCEED 50 F/hr)
- Maintain SG NR level at 40-60%
Report when you have established a controlled cool down of all SG's A floor instructor will be responsible for all annunciators EXCEPT for MBS 4
Simulator Reguirements: 1. Reset to IC 152 OR
- 2. Place Simulator in RUN
- 3. Insert ED01 (Loss of Offsite Power)
- 4. Insert IA02B (IAS-C1 B trip)
- 5. Reset LOP at MB2
(excluding performance of GA-26)
- 7. Restart PPC by inserting the following remotes
- EDR 18 (MCC1A3 Reset)
- EDR 44 (Battery 6 inverter 6 trouble reset)
- PCR01 (Restart Realtime) (start)
- PCR02 (Ready to start Rtime 58 sec)
- PCR03 (Rtime start delay) (final value 0)
- NOTES TO TASK PERFORMANCE EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: 2K13 NRC S.5 Revision: 0 Task
Title:
Natural Circulation Cooldown using GA-26 STARTTIME: _ _ __
PERFORMANCE STANDARD Comments:
Cue:
STEP CAUTION Reads caution and note. Critical: Grade I
reduced below 520 F until main steam line low N [ x] u[ ]
pressure Sl is blocked (P---11 ).
I NOTE If this procedure is being performed during a loss of offsite power with the wind speed I GREATER THAN 90 mph anticipated, the following conditions should be established using this procedure:
- RCS pressure of GREATER THAN 850 I psi a
- Sl accumulator isolation valves all open Comments: ;
Cue:
6
STEP Initiate RCS Cooldown To Cold Recognizes that GA-15 has been completed Critical: Grade
- 2 Shutdown from initiating cue (or cue below) and y [ ] s[]
proceeds to next step. N [X] u[ ]
ES-0.2 Verify boration as specified by GA---15 ---
Step 5 COMPLETED Comments:
Cue: As needed, report "GA-15 has been completed. Cooldown can commence with current RCS boron concentrations".
STEP Maintain cooldown rate in RCS cold legs --- Reads step and proceeds to next step. Critical: Grade
- 3 LESS THAN 50 F/hr y [ ] s[]
N [X 1 u[ ]
Comments: This limit will be met by the US direction to maintain cooldown rate at approx. 30 F/hr (initiating cue). If needed, ensure examinee understands desired cooldown rate is per US direction.
Cue:
STEP Using GA---26, Dump steam to initiate RCS Reads step and proceeds to GA-26. Critical: Grade
- 4 cool down y [ ] s[]
N[x1 u[ 1 Comments:
Cue:
STEP NOTE Reads note and proceeds to next step. Critical: Grade
- 5
- Auxiliary feed flow directly impacts RCS y [ ] s []
heatup and cooldown rates and must be N[x] u[ ]
considered along with dumping steam.
- Steam line pressure changes more rapidly if fewer than four SGs are used.
- After Low Steamline Pressure Safety Injection signal is BLOCKED, MSI will occur if the High Steam Pressure Rate setpoint is exceeded.
Comments:
Cue:
7
STEP Verify Plant Conditions At MB1, observes 31AS-C1 B is not running Critical: Grade
- 6 (Green light 'On', Red light 'Off') y [ ] s[]
GA-26 Check instrument air compressors -AT LEAST N [X] u[ ]
Step 5 ONE RUNNING Comments:
Cue:
STEP Perform the following: Observes the following annunciators not lit: Critical: Grade
- 7
- MB2B 5-5 "CDA" y [ ] s []
IF Sl or CDA present, THEN Place both trains
- MB2B 5-9 "SI" N [X] u[ ]
of steam dump interlock selector switches in OFF and Proceed to step 6. Proceeds to next step.
Comments:
I Cue:
STEP RESET LOP if required. Recognizes that 'LOP' has been reset from Critical: Grade
- 8 initiating cue (or cue below) and proceeds to y [ ] s[]
next step. N [X] u[ ]
Comments:
Cue:
As needed, report "LOP has been reset".
STEP START one instrument air At MB2, closes breaker for 31AS-C1 B and Critical: Grade
- 9 compressor. observes breaker remaining open (Green y [ ] s[]
light 'ON' and Amber light 'ON'). N [X] u[ ]
!E instrument air can NOT be restored, THEN Recognizes failure of 31AS-C1 B and Place both trains of steam dump interlock proceeds to step 6.
selector switches in OFF and Proceed to step 6.
Comments: This begins the alternate path portion of the JPM.
Cue: -
8
STEP Dump Steam to Atmosphere Using SG Places Control Lockout switches (M85R) in Critical: Grade
- 10 Atmospheric Relief Bypass Valves Normal for: y [X] s[]
- 3MSS*MOV74A N[ ] u[ ]
GA-26 Place the desired SG atmospheric relief bypass
- 3MSS*MOV748 Ste p6 valves' CONTROL LOCKOUT switches in
- 3MSS*MOV74C NORMAL (M85R)
- 3MSS*MOV74D
- 3MSS*MOV7 4A
- 3MSS*MOV7 48
- 3MSS*MOV74C
- 3MSS*MOV740 Comments:
I Cue: I
I 9
STEP Throttle the desired SG atmospheric relief Throttles open (momentarily depresses Open Critical: Grade
- 11 bypass valves to reduce or maintain pushbutton, observes dual light indication) y [X] s[]
RCS temperature or SG pressures as specified the following valves: N[ ] u[ ]
by the procedure in effect
- 3MSS*MOV74A
- 3MSS*MOV7 4A
- 3MSS*MOV748
- 3MSS*MOV7 48
- 3MSS*MOV74C
- 3MSS*MOV74C
- 3MSS*MOV740
- 3MSS*MOV740
-Monitors RCS temperatures (may use M8 indications for RCS T cold or PPC trends for RCS Tcold).
- Makes adjustments to atmospheric relief bypass valves (as necessary) to obtain approx. 30 F per hour cooldown rate.
- Monitors SG levels. Adjusts AFW throttle valves to maintain SG levels between 40 -
60%.
If P19 actuates on MB4D 4-5, the floor instructor should reset both trains of "Steam Line lsol Sl" signals on MB2.
Comments: I 1. The critical nature of step is not to exceed a 50 F/hr cooldown rate (as measured using individual loop Tcold temperatures) over a 15 minute period. If the candidate does exceed this rate over 15 minutes, he I she may still PASS if they take action to reduce the cooldown such that the 50 F/hr limit would not be exceeded. Otherwise, a JPM failure will occur.
- 2. Under these plant conditions (MSIV's closed, Natural Circulation), it will be very difficult to achieve exactly 30 F/hr cooldown per SG. The goal is establish a controlled cooldown less than 50 F/hr (head voiding concerns). The JPM does not have to continue until a cooldown of exactly 30 F/hr is established. When the examiner has observed a controlled cooldown, he or she may end the JPM. A PASS will be given for any cooldown rate, provided: 1.) 50 F/hr is not exceeded (see earlier discussion) AND 2.) All RCS temperatures are trending down. 3.) SG inventory control is maintained within an allowable band of greater than 8% NR and less than 80% NR.
Cue:
TERMINATION CUE: The evaluation for this JPM is concluded. STOP TIME: _ _ __
10
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC S.5 Revision: 0 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is ITime Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 20 min.
Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT I I Areas for Improvement I Comments:
11
STUDENT HANDOUT JPM Number: 2K13 NRC S.5 Revision: 0 Initial Conditions: A loss of offsite power has occurred and the reactor tripped. Its reported that offsite power will not be restored for an extended period of time. The following conditions exist:
- The control room team has completed through step 4 of ES-0.2, Natural Circulation Cooldown.
- GA - 15, Establishing Boron Concentration For Natural Circulation Cooldown, has been completed and RCS boron concentrations are satisfactory.
- GA- 1, Energizing 32-3T, has been completed and the PPC is available. This included the reset of 'LOP'.
- All four MSIV's are closed
Initiating Cues: The US has directed you to commence a natural circulation cooldown using the Atmospheric Relief Valves per ES-0.2 Step 5.
The US directs you to:
- Review step 5 of ES-0.2 and then initiate a cooldown of the RCS at approximately 30 F /hr (NOT TO EXCEED 50 F/hr)
- Maintain SG NR level at 40-60%
Report when you have established a controlled cool down of all SG's A floor instructor will be responsible for all annunciators EXCEPT for MBS 12
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
RESPOND TO A LOSS OF ALL AC POWER AND ENERGIZE AN AC EMERGENCY BUS JPM Number: 2K13 NRC S.6 Revision: 0 Initiated:
William M. Forrestt 9/18/13 Developer Date Reviewed:
Technical Reviewer Date UJ--
Approved:
Trad Horner Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES All & DATE DESCRIPTION REV/CHANGE 9/18/13 Modified JPM's, S-30 & S-212, to form this new JPM. Added Of 0 alt path with failure of letdown isolation valves. Also, this JPM was made to complete actions, steps 4- 6 of ECA-0.0, that were not previously covered.- WMF 2
JPM WORKSHEET Facility: _.:..;..:M~P-=-3_ _ __ Examinee:
JPM Number: 2K13 NRC S.6 (S212) Revision: - - - '0- - - -
Task
Title:
RESPOND TO A LOSS OF ALL AC POWER AND ENERGIZE AN AC EMERGENCY BUS System: 062 AC Electrical Distribution Time Critical Task: ) YES (X) NO Validated Time (minutes): _ _ _ 5_ _
Task Number(s): 000-05-097 Applicable To: SRO X RO X PEO KIA Number: 062.A2.05 KIA Rating: 2.9 I 3.3 EPE EA1.07 4.3 I 4.5 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In-Plant:
Task Standards: Respond to a Loss of All AC Power Required Materials: ECA-0.0, Loss of All AC Power, Rev. 023 (procedures, equipment, etc.)
EOP 35 General Attachment, GA-3; Energizing 4. 16 KV Bus From Offsite Power, Rev. 002 General
References:
None 3
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC 8.6 Revision: 2 chg 2 Simulator Requirements: 1. Reset to IC 198 .... OR
- 1. Reset to any 100% power IC, and Reset to IC-1 0, 100%
steady state.
- 2. Insert the following malfunctions and 1/0s:
- a. EGO?A - "A" Diesel Generator Trip.
- b. EG068 - "8" Diesel Generator fails to start.
- c. RP1 OA and RP1 08 Reactor fails to Auto trip.
- d. 1/0 1A-3ENSAC8-A-A, "OFF" (green indicating light).
- e. CVDI0012- 3CHS*AV8149C fails to close
- 4. Hang a yellow tag on "A" Diesel Generator control switch and breaker. The following annunciators should be present when the simulator is in "RUN" and the next malfunction entered:
&V' DG "A" Local Panel Trouble
&V' DG "A" Emergency Shutdown
&V' DG "A" Not Ready For Auto Start
- 4. Place the simulator in "RUN" and then insert malfunction ED01 - Loss of Offsite Power.
- 5. Leave the simulator in "RUN" until indicated total AFW flow is >525 GPM.
- 6. Place the master silence switch to silence but do not acknowledge any alarms. Place the simulator in "FREEZE".
- 7. After the examinee has received the initial conditions and initiating cues, place the simulator in "RUN".
Approximate setup time is 10 minutes.
4
Initial Conditions: The plant has experienced a Loss of Offsite Power. The 'A' EDG is tagged out for maintenance. The 'B' EDG failed to start. The crew responded using E-0 and ECA-0.0 and has completed ECA-0.0 through step 2. CONVEX has reported there was a momentary loss of offsite power; however, offsite power has been restored.
Initiating Cues: The Unit Supervisor directs you to restore power to bus 34C using the RSST. You are to begin at step 3 of ECA-0.0.
5
- NOTES TO EVALUATOR****
- 1. Critical steps for this JPM are indicated by an "X" after the step number. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue."
- 3. If necessary, question the student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
6
PERFORMANCE INFORMATION JPM Number: 2K13 NRC S.6 Revision: 0 Task
Title:
RESPOND TO A LOSS OF ALL AC POWER AND ENERGIZE AN AC EMERGENCY BUS START TIME: ----
PERFORMANCE STANDARD STEP Check If RCS Is Isolated Depresses CLOSE pushbutton for the in Critical: Grade
- 1 service letdown isolation valve and Y[X] s[]
ECA-0.0 CLOSE letdown orifice isolation valves observes no change in valve position. N[ ] u[ ]
Step 3 RNO: Performs RNO action:
CLOSE Ctmt letdown isolation valves: Depresses CLOSE pushbutton(s) for
- 3CHS*CV8152 3CHS*CV8152 & 3CHS*CV8160 and
- 3CHS*CV8160 observes valve closure (green light on I red light off).
Comments:
Cue:
STEP Verify PZR PORVs --- Locates both valves (3RCS*PCV455A & Critical: Grade
- 2 CLOSED 3RCS*PCV456) and verifies both valves y [ ] s[]
are closed (green light on with red light N[X] u[ ]
off).
Comments:
Cue:
STEP Verify excess letdown and reactor head Locates valves (3RCS-AV8153, Critical: Grade
- 3 vent isolation valves --- CLOSED 3RCS*SV8095A & B, 3RCS*SV8096A & y [ ] s[]
B) and verifies valves are closed (green N[X] u[ ]
light on with red light off).
Comments:
Cue:
7
STEP Verify. Total AFW Flow To Monitors MB5 AFW flow to all 4 S/G's Critical: Grade ;
ECA-0.0 Step 4 GREATER THAN 530 gpm 530 gpm. N[X] u[ ]
Comments:
Cue:
STEP CAUTION Reads CAUTION. Critical: Grade
- 5 If power is NOT restored to Bus 34C within y [ ] s[]
30 minutes, Inverter 6 de---energizes and N[X] u[ ]
the process computer will be unavailable.
Use GA---12 as required to determine core cooling parameters.
Comments:
Cue:
STEP Try To Restore Power To Any AC Recognizes from Initial Cue that no EDG Critical: Grade
- 6 Emergency Bus is available ('A' is RTO & 'B' failed to y [ ] s[]
ECA-0.0 start). N[X] u[ ]
Step 5 START at least one EDG (MB8) Proceeds to RNO (Step 6 of ECA-0.0)
RNO: Proceed to step 6 Comments:
Cue: If Examinee doesn't recall initial conditions, provide prompt '"A' EDG is RTO and 'B' EDG has failed to start". - *-
8
STEP CAUTION: Reads Caution I Note. Critical: Grade
- 7
- Maintain one service water pump available to y [ ] s[]
automatically load on its AC emergency bus N[X] u[ ]
to provide emergency diesel generator cooling.
- If a Sl signal is actuated during this procedure, it must be reset to permit manual loading of equipment on an AC emergency bus.
- Spurious fire alarms may occur in areas where the temperatures exceed 120_F due to a loss of ventilation. The locking out of C02 protected areas which have spurious fire alarms is recommended.
NOTE:
- When power is restored to any AC emergency bus from offsite or an emergency diesel generator, recovery actions should continue starting with step 26.
Comments:
Cue:
STEP Block Automatic Loading Of AC Monitors for plant conditions and Critical: Grade
- 8 Emergency Busses determines that only the Aux FW Y[X] s[]
ECA-0.0 LO -LO signals need to be reset. N[ ] u[ ]
Step 6 RESET the following if necessary:
- Sl On MB5 depresses:
- Aux FW Train A for La---
- Aux FW Train B for La---
La SG Level Comments: Critical nature is that Aux FW gets reset. If Examinee resets Sl and CDA, it is acceptable as there are no adverse effects. Annunciator, MB5A 5-1 "Aux FW Auto Init Reset" will light when Aux FW is reset.
Cue:
9
STEP Place the following control Locates and Places the listed component Critical: Grade
- 9 switches in control switches in PULL-TO-LOCK. Y[X1 s[ 1 PULL---TO---LOCK: N[ 1 u[ 1
- Charging pumps For each component, the Examinee
- One service water pump per train should first place the control switch in (follow pumps preferred in PTL) stop and verify the breaker opens (as
- RPCCW pumps applicable). After this, the control switch
- Quench spray pumps is placed in pull-to-lock.
- Recirculation spray pumps
- Sl pumps
- RHR pumps
- MDAFW pumps
- CAR fans
- Control Building HVAC chillers
- CRDM cooling fans
- Auxiliary Building filter exhaust fans
- SLCRS fans Comments: It's critical that the Examinee open any breakers prior to placing the component in pull-to-lock.
Cue:
STEP Place the following control switches in OFF: Locates listed fan control switches on Critical: Grade
- 10
- CHG & CCW PP area supply fans VP1: Y[X1 s[ 1
- Train A and B Control Building filter
- 3HVR-FN14A & B N[ 1 u[ 1 units
- 3HVC*FN 1A & B Comments:
Cue:
STEP Locally Attempt To Restore AC Power At MB8 verifies offsite power using any of Critical: Grade
- 11 the following: y [ 1 s[ 1 Check offsite power - N[X1 u[ 1 ECA-0.0 Step 7 AVAILABLE
- Grid frequency meter (upright)
- Grid voltage meter (upright)
- RSST "available" white lights (apron)
Comments: This information was also given in initial conditions. Candidate may choose not to verify.
Cue:
10
STEP Using GA-3, Energize emergency bus 34C Candidate locates and opens GA binder Critical: Grade
- 12 or34D to GA-3. y [ ] s[]
N[X] u[ ]
Comments:
Cue: The applicant should question the US which emergency bus is desired to be energized and from which offsite source. When questioned, respond as the US and provide the following cue:
"Restore power to Bus 34C with the RSST" STEP NOTE Reads Note and recognizes it is not Critical: Grade
G A- 3 diesel using ECA-0.0, Attachment H or I is aligned for service using Attach H or I). N[X] u[ ]
Step 1 NOT available for energizing by this procedure. Candidate Proceeds to step 2 based on previous cue.
Check Energizing Bus 34C - DESIRED Comments:
Cue: If needed, provide following cue to clarify note I circumstances of JPM: "Attachment H or I has not been used to align the SBO diesel for service".
11
STEP Energize Bus 34C. This step (for both trains) was already Critical: Grade
- 14 completed in Step 6 of ECA-0.0. y [ ] s[]
G A- 3 Place the following control switches in Examinee may walk down components N [X] u[ ]
PULL-TO-LOCK again OR review list against previous Step 2 activity.
- One Train A Service Water Pump
- RPCCW Pump A
- RPCCW Pump C (Train A)
- Quench Spray Pump A
- Recirc Spray Pump A
- Recirc Spray Pump C
- Sl Pump A
- RHR Pump A
- Control Building Chiller A
- Aux Building Filter A
- Charging Pump A
- Charging Pump C (Train A)
- MDAFW Pump A Comments:
Cue:
STEP Reset LOP (MB2) Locates LOP Reset pushbuttons on MB2, Critical: Grade
- 15 pushes the Train A and Train B LOP Y[X] s[]
Reset pushbuttons. Observes N[ ] u[ ]
annunciators MB2B 2-4, "SEQUENCER AlB TROUBLE" lit, and MB8, "DG AlB AUTO START" clear.
Comments: Resetting the 'A' Train LOP Reset pushbutton is the critical nature of this step.
Cue:
STEP Verify annunciator, "Bus 34C Observes annunciator MB8A 3-12, "Bus Critical: Grade
- 16 UNDERVOLTAGE" (MB8A 3-12)- NOT LIT 34C UNDERVOLTAGE" not lit on MB8A. y [ ] s[]
N[X] u[ ]
Comments:
Cue:
12
STEP Press "BYPASS" for 34C undervoltage Locates pushbutton on MB8R, pushes Critical: Grade
- 17 block pushbutton. (MB8R) button and observes white light go off. Y[X] s[]
N[ ] u[ ]
Comments: The 34C undervoltage block pushbutton is the pushbutton on the left.
Cue:
STEP Check undervoltage block white light - NOT Observes white light NOT LIT on Critical: Grade
- 18 LIT. pushbutton on MB8R. y[ ] s[]
N[X] u[ ]
Comments:
Cue:
STEP Check energizing Bus 34C from Bus 34A - Candidate Proceeds to step 2.f.RNO Critical: Grade
- 19 DESIRED based on previous cue. y [ ] s[]
N[X] u[ ]
Comments:
Cue: IF questioned, respond as the US and provide the following cue:
"Restore power to Bus 34C with the RSST".
STEP Energize Bus 34C from RSSA: Places or checks sync selector handle in Critical: Grade
- 20 synchronizing selector for RSSA to bus Y[X] s[]
- 1) Place RSSA sync selector switch in ON. 34C and turns to ON position. N[ ] u[ ]
Comments:
Cue:
STEP 2) CLOSE RSSA supply breaker Locates and turns RSSA*34C-2, RSSA Critical: Grade
- 21 (RSSA*34C-2). supply breaker to the close position and Y[X] s[]
N[ ] u[ ]
releases.
Observes breaker green light go OFF and red light go ON. Also, may choose to observe voltage on bus 34C at approx.
4000 v.
Comments: Lights come on in the Control Room Cue:
13
STEP 3) Place RSSA sync selector switch in Places sync selector handle in Critical: Grade
- 22 OFF. synchronizing selector for RSSA to bus y [ ] s[]
34C and turns to OFF position. N[X] u[ ]
Comments:
Cue: I TERMINATION CUE: The evaluation for this JPM is concluded. STOP TIME: _ _ __
14
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC S.6 Revision: 0 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 5 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT JPM Work Practice Evaluation*: SAT UNSAT N/A
- As per TR-AA-41 0, the Pass/Fail criteria for the JPM is that the trainee must 1) Perform the task correctly and lAW procedure use and adherence requirements, 2) Never put anyone's safety at risk, 3) Never put equipment reliability at risk, 4) Never violate radiological work practices, 5) Demonstrate effective use of event-free human performance tools. If a failure occurs, indicate why the failure occurred and which of these 5 task performance criteria contributed to the failure.
Areas for Improvement I Comments:
15
STUDENT HANDOUT JPM Number: 2K13 NRC S.6 Revision: 0 Initial Conditions: The plant has experienced a Loss of Offsite Power. The 'A' EDG is tagged out for maintenance. The 'B' EDG failed to start. The crew responded using E-0 and ECA-0.0 and has completed ECA-0.0 through step 2. CONVEX has reported there was a momentary loss of offsite power; however, offsite power has been restored.
Initiating Cues: The Unit Supervisor directs you to restore power to bus 34C using the RSST. You are to begin at step 3 of ECA-0.0.
16
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Respond To High Containment Pressure JPM Number: 2K13 NRC 8.7 (JPM-128) Revision: 2 chg 2 Initiated:
FZ--
William M. Forrestt
~~
9/18/13 Developer Date Reviewed:
Technical Reviewer Date Approved:
Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 2/17/11 Updated JPM to revision 016-02 to FR-Z.1. This involved a 2/0 substantial rewrite of this JPM. Modified JPM format to be consistent with the NRC 2K11 JPM set. DLM 6/20/11 Modified the standard associated with JPM step 27 to be a 2I 1 direct order from the RO to the PEO for specific field actions.
Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week). Corrected a typographical error in the comment associated with JPM step 30.
9/18/13 Renamed 8.7 for 2K13 NRC submittal. WMF 2/2 2
JPM WORKSHEET Facility:
-MP3----- Examinee:
JPM Number: 2K13 NRC S.? Revision: 2 chg 2 Task
Title:
Respond To High Containment Pressure System: 005-026 (CTMT Spray System)
Time Critical Task: ) YES ( X) NO Validated Time (minutes): ___1_0_ _
Task Number(s): 000-05-052 Applicable To: SRO X RO X PEO _ __
KIA EPE: E14- EA1.1 KIA Rating: 3.7 I 3.7 Number:
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In-Plant:
Task Standards: Start a containment spray pump by completing the first 5 steps of FR-Z.1.
Required Materials: 1. FR-Z.1, Response To High Containment Pressure (procedures, equipment, etc.) 2. MP3 Simulator General
References:
N/A 3
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC S.7 Revision: 2 chg 2 Simulator Requirements: 1. Reset to IC 301 .... OR
- 2. Reset to IC-18, or equivalent 100% power IC.
- 3. Insert the following malfunctions:
- CS01 B - "B" Quench Spray Pump trip.
- 4. Insert the following 1/0 overrides:
- RPDI0004 (PB1 CDA Actuate Train A)- 'NACTUATE'.
- RPDI0006 (PB3 CDA Actuate Train B)- 'NACTUATE'.
- 5. Place the "A" Quench Spray Pump in "PULL-TO-LOCK" and place a yellow caution tag on the control switch.
- 6. Place the simulator in "RUN."
- Take the MASTER SILENCE SWITCH to "SILENCE."
- Insert malfunction MS01A- S/G "A" faulted inside containment, at 100% severity.
- 7. Allow the simulator to run for 1-2 minutes. (Adverse CTMT will be met due to CTMT temperature.) During this time perform the following:
- Stop the "C" CAR fan.
- Stop the kitchen exhaust fan.
- Stop AFW flow to "A" S/G.
- Throttle AFW flow to 200 gpm to each of the other S/Gs.
- 8. When the above actions are complete and the Containment Hl-3 setpoint is reached, perform the following:
- Acknowledge/clear all alarms
- Come out of Master Silence
- Place the simulator in 'FREEZE."
4
- 9. When the examinee has received the initial conditions and initiating cues, place the simulator in "RUN."
Approximate simulator setup time is 6-8 minutes.
Initial Conditions: A steam-line break inside containment has occurred. Based on plant conditions, a manual reactor trip and safety injection were initiated. The Control Room Team is progressing through the EOPs and during the transition to E-2, Faulted Steam Generator Isolation, a CDA signal was received and an "orange" path for containment integrity. The "A" Quench Spray Pump is tagged out for maintenance.
Initiating Cues: The US has directed you to perform FR-Z.1, Response To High Containment Pressure, in an attempt to initiate containment spray.
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: 2K13 NRC S.7 Revision: 2 chg 2 Task
Title:
Respond To High Containment Pressure START TIME: ----
PERFORMANCE STEP STANDARD STEP Obtains copy of FR-Z.1. Obtains a copy of FR-Z.1, refers to Critical: Grade
- 1 Step 1, Caution.
y [ ] s[]
NlX] Ul]
Comments:
Cue:
STEP CAUTION: Applicant reviews CAUTION, and at Critical: Grade
THAN 520,000 gal, Go to ES-1.3, greater than 520,000 gallons.
FR-Z.1, Transfer to Cold Leg Recirculation, step 1 CAUTION to align the ECCS system.
Comments:
Cue:
STEP Check IF CDA Required Applicant observes CTMT pressure is Critical: Grade
- 3 greater than 23 psia by checking any of Y[] N[X] S[]U[]
FR-Z.1, Check Ctmt pressure --- the following: Meters at MB2:
step 1.a GREATER THAN 23 psia LMS*PI934, 935, 936 or 937, or recorder 3LMS*PR934.
Comments:
Cue:
6
STEP Verify annunciator "CONTAINMENT Observes that annunciator MB2B:5-5 Critical: Grade
- 4 DEPRES ACTUATION" (MB2B 5-5) IS lit. Y[]N[X] S[] U[]
FR-Z.1, ---LIT step step 1.b Comments:
Cue:
STEP Check RPCCW pumps- STOPPED Observes that RPCCW pumps Critical: Grade
- 5 3CCP*P1A & P1 B have no running Y [ ] N [X ] S[]U[]
FR-Z.1, amps indicated and the indicating lights step 1.c are green ON, red OFF.
Comments:
Cue:
STEP STOP all RCPs Rotates the 3RCS-P1A control switch Critical: Grade
- 6 to "STOP" and observes amperage Y[X] N[] S[]U[]
FR-Z.1, indication go to zero; and indicating step 1 .d lights shift to green ON, red OFF.
Rotates the 3RCS-P1 B control switch Critical: Grade to "STOP" and observes amperage Y[X] N[] S[]U[]
indication go to zero; and indicating lights shift to green ON, red OFF.
Rotates the 3RCS-P1 C control switch Critical: Grade to "STOP" and observes amperage Y[X] N[] S[]U[]
indication go to zero; and indicating lights shift to green ON, red OFF.
Rotates the 3RCS-P1 D control switch Critical: Grade to "STOP" and observes amperage Y[X] N[] S[]U[]
indication go to zero; and indicating lights shift to green ON, red OFF.
Comments: The RCPs may be stopped in any order.
Cue:
7
STEP Check CAR fans - STOPPED Observes at VP1 that the 'A', 'B' and Critical: Grade
- 7 'C' CAR fans are stopped. Y[] N[X] S[]U[]
FR-Z.1, step 1 .e Comments:
Cue:
STEP Check CRDM fans - STOPPED Observes at VP1 that the 'A' and 'B' Critical: Grade
- 8 CRDM fans are stopped, but Y[] N[X] S[]U[]
FR-Z.1, recognizes the 'C' CRDM fan is still step 1 .f running by indicating lights red ON, green OFF.
Transitions to the RNO column.
Comments:
Cue:
STEP STOP CRDM fans. Rotates the 3HVU-FN2C control switch Critical: Grade
- 9 Y[X] N[] S[]U[]
FR-Z.1, to "STOP" and observes the flag shifts step 1.f to "green;" and indicating lights shift to RNO green ON, red OFF.
Comments:
Cue:
STEP If ECA-1 .1, Loss of Emergency Applicant reviews CAUTION, Critical: Grade
- 10 Coolant Recirculation, is in progress, Y[] N[X] S[]U[]
FR-Z.1, Ctmt spray should be operated as step 2 CAUTION directed in ECA-1.1 Comments: If the applicant questions the status of procedure ECA-1 .1 due to the caution in FR-Z.1 , provide the following cue:
Cue: The Control Room Team has not yet entered ECA-1.1.
8
STEP Verify Quench Spray System Observes that annunciator MB2A 5-2 is Critical: Grade
- 11 Operation not lit (dark). Y[ 1 N[X1 S[1U[1 FR-Z.1, step 2.a Check annunciator RWST EMPTY ass PP OFF (69,331 gal) (MB2A 5-2)- NOT LIT Comments:
Cue:
STEP Verify quench spray pumps- Observes that no amperage is Critical: Grade
- 12 RUNNING. indicated and the indicating lights are Y[ 1 N[X1 S[1U[1 FR-Z.1, green ON, red OFF for the 'B' ass step 2.b pump. The pump is not running.
Applicant transitions to the RNO column.
Comments: Pump 3aSS*P3A is tagged out.
Cue:
STEP START pumps. Rotates the control switch for Critical: Grade
- 13 3aSS*P3B to "START" and observes Y[ 1 N[X1 S[1U[1 FR-Z.1, IF no ass pump is running, that no amperage is indicated and the step 2.b RNO THEN indicating lights shift to green ON, Proceed to step 4. amber ON, red OFF. The pump did not start.
Applicant proceeds to step 4.
Comments:
Cue:
STEP Verify CIA Observes that the ESF Group 2 Status Critical: Grade
- 14 Lights in columns 2 through 10 are lit. Y[ 1 N[X1 S[1U[1 FR-Z.1, Check ESF Group 2, step 4.a columns 2 though 10 - LIT Comments:
Cue:
9
STEP Verify Recirculation Spray System Observes the indicating lights for Critical: Grade
- 15 Operation 3RSS*MOV23A - D are green OFF, Y[] N[X] S[]U[]I FR-Z.1, red ON. The valves are open.
step S.a Check recirculation spray pump suction isolation valves - OPEN I
- 3RSS*MOV23A
- 3RSS*MOV23B
- 3RSS*MOV23C
- 3RSS*MOV23D Comments:
Cue:
STEP Check recirculation spray pumps - Recognizes that NO RSS pumps are Critical: Grade
- 16 ANY RUNNING running by no running amps indicated Y[] N[X] S[]U[]
FR-Z.1, and the indicating lights are green ON, step S.b red OFF.
Transitions to the RNO column.
Comments:
Cue:
STEP Perform the following: Applicant observes that RWST level is Critical: Grade
- 17 1) IF RWST level is GREATER greater than 520,000 gallons by Y[] N[X] S[]U[]
FR-Z.1, THAN 520,000 gal, THEN checking level on any of the meters at step S.b RNO Proceed to step 5.d. MB2: QSS*LI930, 931, 932 or 933.
Applicant proceeds to step 5.d.
Comments:
Cue:
10
STEP Check Ctmt WR sump level Applicant observes that CTMT Wide Critical: Grade
- 18 (3RSS*LI22A, 3RSS*LI22B) - Range sump level is LESS than 7.5 Y[] N[X] S[]U[]
FR-Z.1, GREATER THAN 7.5 feet feet by checking meters 3RSS*LI22A step 5.d and I or 3RSS*LI22B level on Meters at MB2.
Transitions to the RNO column.
Comments:
Cue:
STEP Perform the applicable action: Applicant observes that ass flow is Critical: Grade
- 19 not indicated by checking meters ass- Y[] N[X] S[]U[]
FR-Z.1,
- IF ass flow is NOT indicated, FI32A and FI32B at MB2.
step 5.d RNO THEN Proceed to NOTE prior to step 6. Applicant proceeds to Note prior to step 6.
Comments:
Cue:
STEP NOTE: Applicant reviews NOTE. Critical: Grade
- 20
- The Locked Valve Key is Y[] N[X] S[]U[]
FR-Z.1, required for performance of some step 6 NOTE of the local actions in the following step.
- The preferred priority for selecting a recirculation spray pump is as follows:
- 1. Pump CorD
- 2. Pump A orB Comments: After reading the notes, the examinee may ask about which pump to use. If asked, or if the Candidate selects the 'C' RSS pum_Q, provide the following cue:
Cue: The US directs you to align recirculation spray pump "D."
11
STEP Check If Spray Using An RSS Applicant observes that RWST level is Critical: Grade
- 21 Pump From The RWST Should Be greater than 520,000 gallons by Y[] N[X] S[]U[]
FR-Z.1, Established checking level on any of the meters at step 6.a MB2: QSS*LI930, 931, 932 or 933.
Check the following:
- RWST level - GREATER THAN 100,000 gal
- Quench Spray pumps -
NONE RUNNING
Cue:
Observes that the indicating lights are Critical: Grade green ON, red OFF for the '8' QSS Y[] N[X] S[]U[]
pump. The pump is not running. Pump 3QSS*P3A is tagged out.
Comments: When the applicant asks for a ADTS/CR DSEO recommendation, provide the following cue:
Cue: The CR DSEO recommends using one RSS pump from the RWST to spray containment.
12
STEP RESET Sl Applicant depresses the MB2 Sl Critical: Grade I
- 22 RESET pushbuttons. Y[X1 N[ 1 S[1U[1 FR-Z.1, step 6.b I Comments: This action will cause several annunciators to clear and alarm. The examinee should acknowledge and reset these annunciators as appropriate. However, this action is not required to complete the critical nature of this step.
Cue:
STEP Determine the RSS pump to be The applicant should recognize that the Critical: Grade
- 23 placed in service 'D' RSS pump will be placed in service. Y[ 1 N[X1 S[1U[1 FR-Z.1, step 6.c Comments: The "D" recirculation spra_y_pump_ will be used (cue provided in JPM ste_Q_ 20)
Cue:
STEP Place the selected recirculation Rotates the 3RSS*P 1D control switch Critical: Grade !
- 24 spray pump in PULL TO LOCK to the PULL TO LOCK position and Y[X1 N[ 1 S[1U[1 FR-Z.1, then pulls the switch handle up into step 6.d "PULL-TO-LOCK".
Comments:
Cue:
STEP For the selected RSS pump, At VP1, the applicant rotates the Critical: Grade
- 25 START the associated RECIRC 3HVQ*ACU2B control switch to Y[X1 N[ 1 S[1U[1 FR-Z.1, SPRAYACU "START" and observes indicating lights step 6.e (3HVQ*ACUS2A or 3HVQ*ACUS2B) shift to green OFF, red ON.
Comments:
Cue:
STEP OPEN RWST recirculation suction Depresses the 3QSS*AOV27 OPEN Critical: Grade
- 26 valves (MB1) pushbutton, observes the indicating Y[X1 N[ 1 S[1U[1 FR-Z.1, step 6.f
- 3QSS*AOV27 lights shift to green OFF, red ON, then
- 3QSS*AOV28 releases the pushbutton.
Comments: 3QSS*AOV27 and 3QSS*AOV28 may be operated in any order.
Cue: - --*****-~
13
Depresses the 3QSS*AOV28 OPEN Critical: Grade pushbutton, observes the indicating Y[X] N[] S[1U[1 lights shift to green OFF, red ON, then releases the pushbutton.
Comments:
Cue:
STEP Using Attachment B, locally align the Contacts a PEO and directs, "locally Critical: Grade
- 27 selected RSS pump align the 'D' recirculation spray pump Y[ 1 N[X1 S[1U[1 FR-Z.1, for CTMT spray from the RWST, in step 6.g accordance with Attachment B to FR-Z.1."
Comments: As PEO acknowledge the request.
Cue:
BOOTH: At the instructor station enter the following:
- Remote Functions: CSR05 to "OPEN" 1/0 override: CSL0004 7 (3RSS*MOV230 red light) to 'OFF'.
Comments: BOOTH: Once these remotes are active, provide the following cue:
Cue: The 'D' recirculation spray pump has been locally aligned for CTMT spray from the RWST, in accordance with Attachment B to FR-Z.1.
STEP Check the selected recirculation Observes the indicating lights for Critical: Grade
- 28 spray pump RHR isolation- 3RSS*MV8838B are green ON, red Y[ 1 N[X1 S[1U[1 FR-Z.1, CLOSED OFF. The valve is closed.
step 6.h
- For pump D-3RSS*MV8838B Comments:
Cue: ---- ---------- -- --
14
STEP Check the selected recirculation Observes the indicating lights for Critical: Grade
- 29 spray pump spray header isolation 3RSS*MOV20D are green OFF, red Y[] N[X] S[]U[]I FR-Z.1, valve- OPEN ON. The valve is open.
step 6.i
- For pump D - 3RSS*MOV20D Comments:
Cue:
STEP Check local system alignment - Verifies that the local system alignment Critical: Grade
- 30 COMPLETED is complete. Y[] N[X] S[]U[]
FR-Z.1, step 6.j Comments: The examinee was informed when lineup was completed (JPM step 27).
Cue:
STEP START the selected RSS pump Pushes down on the "D" recirculation Critical: Grade
- 31 spray pump control switch to take it out Y[X] N[] S[]U[]
FR-Z.1, of "PULL-TO-LOCK." Rotates the step 6.k control switch to "START" and observes that amperage is indicated and the indicating lights shift to green OFF, red ON.
Comments:
Cue:
The applicant should also check that Critical: Grade flow is present by observing flow Y[] N[X] S[]U[]
indication on 3RSS-FI40D.
Comments:
Cue:
STEP Notify the US that containment Applicant informs the US that Critical: Grade
- 32 spray has been initiated containment spray has been initiated Y[] N[X] S[]U[]
using the "D" recirculation spray pump.
Comments:
Cue: TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME:
15
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC S.? Revision: 2 chg 2 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 10 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
16
STUDENT HANDOUT JPM Number: 2K13 NRC S.7 Revision: 2 chg 2 Initial Conditions: A steam-line break inside containment has occurred. Based on plant conditions, a manual reactor trip and safety injection were initiated. The Control Room Team is progressing through the EOPs and during the transition to E-2, Faulted Steam Generator Isolation, a CDA signal was received and an "orange" path for containment integrity. The "A" Quench Spray Pump is tagged out for maintenance.
Initiating Cues: The US has directed you to perform FR-Z.1, Response To High Containment Pressure, in an attempt to initiate containment spray.
17
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
EOP 3502 Fuel Handling Accident JPM Number: 2K13 NRC S.8 Revision: 0 il-~ /' ;/)
Initiated:
William M. Forrestt 9/18/13 Developer Date Reviewed:
Technical Reviewer Date
~
Approved:
Trad Horner Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES All & DATE DESCRIPTION REV/CHANGE 2
JPM WORKSHEET Facility: _M_P_3_ _ __ Examinee:
Revision:
Title:
EOP 3502 Fuel Handling Accident System: 034 Fuel Handling Equipment System Time Critical Task: ( ) YES (X ) NO Validated Time (minutes): 10 min.
Task Number(s): 344-05-053 Applicable To: SRO X RO X PEO KIA Number: 034 A2.01 KIA Rating: _ _ _3_.6_/_4_.4 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In-Plant:
Task Standards: Respond to a dropped fuel element in accordance with EOP 3502, Fuel Handling Accident (Steps 1 through 6 of EOP 3502).
Required Materials: EOP 3502, Fuel Handling Accident (procedures, equipment, etc.)
General
References:
NA 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC S.8 Revision: 0 Initial Conditions: The plant is in a refueling outage and is currently in Mode 6.
A core offload is in progress. A call to the Control Room has just been made to report a dropped fuel assembly inside containment. The fuel assembly is resting on its side on top of the reactor core. The assembly appears damaged based upon reports of high radiation levels.
Initiating Cues: You are to respond to this event using EOP 3502, starting at Step 1.
Simulator Requirements: Reset to IC 203
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: 2K13 NRC S.8 Revision: 0 Task
Title:
EOP 3502 Fuel Handling Accident STARTTThJE: _______
PERFORMANCE STANDARD Comments:
Cue:
STEP Check Accident Location - Based on initial conditions, recognizes Critical: Grade
- 1 IN CONTAINMENT accident is in Containment and proceeds y[ ] s[]
3502 Step 1 to Step 2. N[X] u[ ]
I Comments:
Cue: As necessary, report "The dropped fuel assembly is in Containment".
STEP Notify Personnel Locates phone and dials 810 and makes Critical: Grade
- 2 Announce the following twice over the site the following announcement over the site Y[X] s[]
paging system: paging system: N[ ] u[ ]
3502 Step2 "Attention Millstone Station personnel, a "Attention Millstone Station personnel, a fuel handling accident has occurred in the fuel handling accident has occurred in the Unit 3 Containment, all personnel evacuate Unit 3 Containment, all personnel the Unit 3 Containment" evacuate the Unit 3 Containment" Comments:
Cue:
5
STEP Stop Containment Purge Determines only 'A' train containment Critical: Grade
- 3 STOP Ctmt purge and exhaust fans: purge is operating and performs the Y[X] s[]
3502 5t ep3 3HVR-HVU1A following: N[ ] u[ ]
3HVR-HVU1B 1. Places 3HVR-HVU 1A & 3HVR-FN4A in 3HVR-FN4A 'Stop" 3HVR-FN4B 2. Observes both fans are stopped by monitoring red light 'Off' and green light
'On' i Comments:
Cue: I STEP Unlock and Close Ctmt purge air isolation Determines only 'A' train containment Critical: Grade '
- 4 valves: purge is aligned for service and performs Y[X] s[]
3HVR*CTV32A and the following (one at a time for N[ ] u[ 1 I I
3HVR*CTV32B (Key #54) 3HVR*CTV32A & 3HVR*CTV33A):
3HVR*CTV33A and 1. Unlocks valve 3HVR*CTV33B (Key #54) 2. Places valve in close I I
- 3. Observes closure indication (Red light
'Off' and Green light 'On')
Comments:
Cue:
STEP Check Containment Air Filtration Locates fans (3HVU-FN3A & 3HVU- Critical: Grade
- 5 System Operation FN3B on VP1 and determines that they y [ ] s[]
3502 Step 4 3HVU-FN3A or are not running (Red light 'Off' and Green N[X] u[ ]
3HVU-FN3B- light 'On').
RUNNING Continues to RNO column.
Comments:
Cue:
6
STEP RNO Locates fan (chooses EITHER 3HVU- Critical: Grade '
- 6 a. START one containment air FN3A or 3HVU-FN3B) on VP1 and Y[X] s[]
filtration unit: performs the following: N[ ] u[ ]
- 3HVU-FN3A 1. Places fan to start
- 3HVU-FN3B 2. Observes for fan operation (Red light
'On' and Green light 'Off')
Comments:
Cue:
STEP Verify associated annunciator For the associated fan started in Step #6, Critical: Grade
- 7 CTMT FILTER DP HIGH verifies associated annunciator not lit y [ ] s[]
(VP1 B 2-1 or VB1 B 2-1 0)
- VP1 B 2-1 "CTMT FILTER A DP N[X] u[ ]
- NOT ACTUATED HI"
- VP1 B 2-10 "CTMT FILTER B DP HI" Comments:
Cue:
STEP Check Status Of Containment Requests status of CTMT closure. Critical: Grade
- 8 Verify Ctmt closure- BEING MAINTAINED Upon hearing cue, proceeds to RNO. y [ ] s[]
3502 Step 5 USING SP 3613F.3-001 ,"Containment N[X] u[ ]
Boundary During Core Alterations or Movement of Irradiated Fuel" Comments:
Cue: When asked about the status of containment closure, report "The OCC reports Containment exceptions exist".
STEP RNO Requests the OCC to establish Critical: Grade
- 9 Establish Ctmt closure using Containment closure using SP 3613F.3- Y[X] s[]
SP 3613F.3-001, "Containment Boundary 001. N[ ] u[ ]
During Core Alterations or Movement of Irradiated Fuel."
Comments:
Cue: - ---- -
7
STEP Verify Ctmt personnel access hatch doors - Requests status of CTMT closure. Critical: Grade
- 10 AT LEAST ONE CLOSED. Upon hearing cue, proceeds to RNO. y [ ] s[]
N[X] u[ ]
Comments:
Cue: When asked about the status of the personnel hatch, report "No, both doors are currently open".
STEP RNO-Request the designated individual, Requests the designated individual to Critical: Grade
- 11 Using OP 3312A, "Containment Personnel close one Containment personnel access Y[X] s[]
Air Lock Operation," Close one Ctmt hatch door iaw OP 3312A. N[ ] u[ ]
personnel access hatch door.
Comments:
Cue:
STEP Check Security has verified - Requests Security determines status of Critical: Grade
- 13 ALL PERSONNEL HAVE EXITED CTMT. Containment evacuation. y [ ] s[]
Upon hearing cue, proceeds to RNO. N[X] u[ ]
Comments:
Cue: When asked about the status of Containment evacuation, report "There are still 12 people in Containment".
STEP RNO-Establish personnel access hatch Requests assistance in evacuating Critical: Grade
- 14 conditions to allow evacuation of Ctmt. containment. Y[X] s[]
N[ ] u[ ]
Comments:
Cue: After request for assistance, report The OCC will establish conditions to evacuate containment".
STEP Notify Health Physics of the situation. Notifies HP of the emergency. Critical: Grade
- 15 y [ ] s[]
N[X] u[ ]
Comments:
Cue: - ------- --- ---------
8
STEP Initiate Control Building Isolation Initiates CBI from MB2 or VPI by Critical: Grade
3502 5 tep6 N[ ] u[ ]
Comments:
Cue:
STEP Check Train A Control Building filter fan Observes 3HVC*FN 1A did not start. Critical: Grade
- 17 (3HVC*FN1A) -RUNNING Proceeds to RNO column y [ ] s[]
N[X] u[ ]
Comments:
Cue:
STEP IF Train B Control Building filter fan is Monitors 3HVC*FN1 B for running Critical: Grade
- 18 running (3HVC*FN1 B running), THEN indication and identifies the fan is 'ON' y [ ] s []
proceed to step 6.c. (Red light 'On' and Green light 'Off'). N[X] u[ ]
Proceeds to step 6.c.
Comments:
Cue:
STEP Check recirc damper for the running Recognizes 3HVC*AOD119B is open Critical: Grade
- 19 Control Building filter fan (3HVC*AOD119A (Red light 'On' & Green light 'Off') Y[X] s[]
or B)- OPEN N[ ] u[ ]
Comments:
Cue:
STEP Verify ESF Group 2 CBI lights - LIT At MB2, monitors associated CBI lights Critical: Grade
- 20 and determines that associated CBI lights y [ ] s []
are lit. N[X] u[ ]
Comments:
Cue:
STEP Verify Control Building purge supply fan At VP1, monitors 3HVC-FN4 & 3HVC- Critical: Grade
- 21 and purge exhaust fan- NOT RUNNING FN5 and determines both fans are off y [ ] s[]
(Red light 'Off' & Green light 'On'). N[X] u[ ]
Comments:
Cue:
9
STEP STOP kitchen exhaust fan Places kitchen exhaust fan, 3HVC-FN6, Critical: Grade
- 22 to 'Off' (Red light 'Off' & Green light 'On') .. y [ ] s[]
N[X] u[ ]
Comments:
Cue: -
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ _ __
10
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC S.8 Revision: 0 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 10 min.
Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
11
STUDENT HANDOUT JPM Number: 2K13 NRC 8.8 Revision: 0 Initial Conditions: The plant is in a refueling outage and is currently in Mode 6. A core offload is in progress. A call to the Control Room has just been made to report a dropped fuel assembly inside containment. The fuel assembly is resting on its side on top of the reactor core. The assembly appears damaged based upon report area radiation levels.
Initiating Cues: You are to respond to this event using EOP 3502, starting at Step 1.
12
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Locally Starting An Emergency Diesel Generator (ECA-0.0)
JPM Number: 2K13 P.1 (P211-1) Revision: 0 chg 1 Initiated:
William M. Forrestt 9/23/13 Developer Date Reviewed:
Technical Reviewer Date Approved:
Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES All & DATE DESCRIPTION REV/CHANGE 08/01/13 Minor editorial enhancements--WMF 0/1 2
JPM WORKSHEET Facility: Millstone Unit 3 Examinee:
JPM Number: 2K13 P.1 Revision: _..:....0..:::..;ch..:..wg'--'1-Task
Title:
Locally Starting An Emergency Diesel Generator (ECA-0.0)
System: 064 Time Critical Task: ) YES (X) NO Validated Time (minutes)'-------'-1...:...0_ _
Task Number(s): 000-05-097 064-01-023 Applicable To: SRO X RO X PEO X KIA 064 K.105 KIA Rating: 3.4/3.9 Number: EA1.02 4.3/4.4 Method of Testing: Simulated X Actual Performance: Performance:
Location: Classroom: Simulator: In-Plant: X Task Standards: Satisfactorily start an EDG locally.
Required Materials: 1. EOP 35 ECA-0.0, Attachment E (handout)
(procedures, equipment, etc.)
General
References:
EOP 35 ECA-0.0, Rev. 023 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 P.1 Revision: 0 chg 1 Initial Conditions: The plant has experienced a Station Blackout. The Crew is implementing ECA-0.0. Neither EDG started automatically.
Initiating Cues: The US has directed you to perform EOP 35 ECA-0.0, Attachment E Locally Starting An Emergency Diesel Generator. You are to start the
'A" EDG.
You have Shift Manager's key ring #87.
Simulator NA Requirements:
- NOTES TO TASK PERFORMANCE EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: 2K13 P_1 Revision: 0 chg 1 Task
Title:
Locally §tarting An Emergency Diesel Generator (ECA-0.0)
STARTTIME: _ _ __
If the examinee asks what is seen at the EDG, there is no visible problem with the EDG. The EDG is as the examinee sees it.
If the examinee asks what is seen at the EGP, the following alarms are lit:
- Window 1-1 Diesel Not Ready for Auto Start
- Window 2-2 Fail to Start STEP Performance: Standard: Critical: Grade
- 1 NOTE Examinee reads note Y [ ] N [x] S[] U[]
A key (Shift Manager's key ring #87) is required to reposition the diesel generator LOCAL/REMOTE switch to LOCAL. There is one key for each diesel generator: Yale 128554 for the A EDG, ILCO 999NY1 E for the 8 EDG.
Cue:
Comments:
STEP Performance: Standard: Critical: Grade
- 2 Verify The Diesel Service Water 1. Locates 3SWP*AOV39A (climbs up y [ ] N [x] S[]U[]
At t. E
( E C A- Outlet Valve - OPEN platform).
0.0) 2. Uses local position indicator to STEP 1
- For EDG A, 3SWP*AOV39A verify valve is open.
Cue: Valve position indicator is pointing to "OPEN".
Comments:
5
STEP Performance: Standard: Critical: Grade :
- 3 NOTE Examinee reads note. Y [ ] N [x] S[]U[]
The actions specified in steps 2 through 6 are performed at EGPA or EGPB depending on the diesel generator being started.
Cue:
Comments:
STEP Performance: Standard: Critical: Grade
- 4 At t. E Place The UNIT PARALLEL Locates the UniUParallel Switch (EGPA) Y [ ] N [x] s[ ] u[ ]
( E C A- Switch In UNIT and determines that the switch is already 0.0) in UNIT.
STEP 2
Cue:
Switch _position is a shown.
Comments:
Switch is on left hand panel of EGPA.
STEP Performance: Standard: Critical: Grade
- 5 Place The CONTROL MODE Locates CONTROL MODE selector switch Y [ ] N [x] S[] U[]
At t. E
( E C A- Switch In LOCAL and simulates inserting key into switch and 0.0) rotating switch to LOCAL STEP 3
Cue:
- Key is inserted in lock and turned .
- Control Mode Switch is in LOCAL. Alarm window 4-8 on EGPA blinks and an audible alarm is heard .
Comments:
6
STEP Performance: Standard: Critical: Grade
- 6 Press ENGINE SHUTDOWN Locates the Engine Shutdown Reset Y [ ] N [x] S[]U[]
At t. E
( E C A- RESET Pushbutton pushbutton (EGPA) and simulates 0.0) pressing it to reset the engine shutdown.
STEP 4
Cue:
The Engine Shutdown Reset pushbutton has been pressed. Alarm window 1-1 and 2-2 on EGPA blink and an audible alarm is heard.
Comments:
Examinee should simulate silencing_ and resetting_ the alarm.
STEP Performance: Standard: Critical: Grade
- 7 START The Diesel Locates the Engine Control switch (EGPA) Y [ ] N [x] S[]U[]
At t. E
( E C A- and simulates rotating it to the Start 0.0) position.
STEP 5
Cue:
No response from the EDG Comments:
- 1. If the examinee states that they would contact the US, then respond as the US that the examinee should continue with the procedure.
- 2. This begins the alternate _portion of the JPM.
STEP Performance: Standard: Critical: Grade
- 8 Press the lever on either air start Locates either air start valve and simulates Y [x] N [ ] S[]U[]
control valve. the actions of installing the valve lever and pressing down on the lever.
Releases lever after cue is given that diesel has started.
Cue:
Engine noise is heard and builds up to a steady level.
Comments:
3EGA*ASV1A is at cylinder #14 next to the fuel injector for cylinder #14. Access is via the walkway along the EDG.
3EGA*ASV2A is at cylinder #1 next to 3EGF*FLT1A, Engine Mounted Duplex Fuel Oil Filter. Access is via walkway 7
STEP Performance: Standard: Critical: Grade
- 9 Check Remote Control- DESIRED Contacts US and asks if Remote Control is Y [ ] N [x] S[]U[]
At t. E
( E C A- desired.
0.0)
STEP 6
Cue:
US replies that "Remote Control is desired".
Comments:
STEP Performance: Standard: Critical: Grade
- 10 Place CONTROL MODE switch in Locates CONTROL MODE selector switch Y [ ] N [x] S[]U[]
REMOTE and rotates switch to REMOTE.
Cue:
Control Mode Switch is in Remote. Alarm window 4-8 on EGPA blinks and an audible alarm is heard.
Comments:
The examinee should remove the key_ from the switch after restoring_ the switch to REMOTE.
STEP Performance: Standard: Critical: Grade
- 11 Notify The Control Room Of Reports to the US that the EDG has been Y [ ] N [x] S[]U[]
At t. E
( E C A- EDG(s) Status And Provide started locally and the controls restored to 0.0) Support As Requested Remote.
STEP 7
Cue:
Comments:
TERMINATION CUE: The evaluation for this JPM is concluded. STOP TIME: _ _ __
8
VERIFICATION OF JPM COMPLETION JPM Number: 2K13P.1 Revision: o chg 1 Date Performed:
Student:
Evaluator:
For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 10 Actual Time to Complete (minutes):
JPM Work Practice Evaluation*: SAT UNSAT N/A Overall Result of JPM: SAT UNSAT
- The Pass/Fail criteria for the JPM is that the trainee must 1) Perform the task correctly and lAW procedure use and adherence requirements, 2) Never put anyone's safety at risk,
- 3) Never put equipment reliability at risk, 4) Never violate radiological work practices, 5)
Demonstrate effective use of event-free human performance tools. If a failure occurs, indicate why the failure occurred and which of these 5 task performance criteria contributed to the failure.
Areas for Improvement I Comments:
9
STUDENT HANDOUT JPM Number: 2K13P.1 Revision: 0 chg 1 Initial Conditions: The plant has experienced a Station Blackout. The Crew is implementing ECA-0.0. Neither EDG started automatically.
Initiating Cues: The US has directed you to perform EOP 35 ECA-0.0, Attachment E Locally Starting An Emergency Diesel Generator. You are to start the 'A" EDG.
You have Shift Manager's key ring #87.
10
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Locally Restore AFW Flow (Includes Opening 3MSS*MSV5)
JPM Number: 2K13 P.2 Revision: 9 ch 3 Initiated:
William M. Forrestt 9/23/13 Developer Date Reviewed:
~ Paul Scott Technical Reviewer Date Approved:
Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES All & DATE DESCRIPTION REV/CHANGE 11/04/03 Include standards for valve operation and verification per Chg. 1 WC-6 and OP3260B 9/13/04 Updated to new revision of FR-H.1. Corrected tasks and Chg.2 K/As.
12/9/05 Updated to FR-H.1, Rev 16-01 (Gov. speed setting changed) Chg.3 RJM 6/20/06 Updated to FR-H.1, Rev 17-00. (Gov. speed setting changed) Chg.4 PGM 01/28/08 Added cue to step 8 and various formatting changes. CTR Chg.5 9/28/2010 Updated to Rev 20 of FR-H.1. Updated to latest format. 9 ch 0 Included JPM Work Practice Evaluation. Deleted local checks of MSS*MOV17A, Band D positions. Previous revision allowed position check using stem height as the only indication of position which is not consistent with OP 3250.
Instead an initiating cue has been provided that MSS*MOV17A,B and D have been verified to be open using control room indications.TPG 2/18/2011 Updated to Rev 020-01 of FR-H.1. Valves previously listed as 9 ch 1 OPEN on page 2 of Attachment A were changed to LOCKED OPEN. Title of 3MSS*SV5 changed to TD AFW Pump Trip Throttle Valve. TPG 6/7/13 Updated to Rev 021 of FR-H .1. Gov. speed setting changed 9 ch 2 JSY 9/23/13 Changed to opening 3MSS*MSV5 and creating an alternate 9 ch 3 path to open 3FWA*V32. -WMF 2
JPM WORKSHEET Facility: Millstone Unit 3 Examinee:
JPM Number: 2K13 P.2 Revision: 9 ch 3 Task
Title:
Locally Restore AFW Flow (Includes Opening 3MSS*MSV5)
System: AFW Time Critical Task: ( ) YES (X) NO Validated Time (minutes) 15 min.
Task Number(s): 000-05-063 Applicable To: SRO X RO X PEO ____
KIA Number: 061 A2.04 KIA Rating: _____3._4_/_3_.8___
Method of Testing: Simulated X Actual Performance: Performance:
Location: Classroom: Simulator: In-Plant: X Task Standards: Satisfactorily complete the local checks to restore AFW flow using Attachment A of FR-H.1.
Required Materials: 1. Att. A (pages 2 -4) of EOP 35 FR-H.1, Rev 021 (handout)
(procedures, equipment, etc.)
General
References:
- 1. SOER 82-8 {TDAFW Pump Steam Isolation Indication)
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 P.2 Revision: 9 ch 3 Initial Conditions: A Loss of Secondary Heat Sink event is in progress and the control room team is carrying out the actions of EOP 35 FR-H.1. AFW flow could not be established from the control room. The Control Room has indications that the Turbine Driven AFW Pump has tripped.
Initiating Cues: The US directs you to inspect 3MSS*MSV5, TD AFW Pump Trip Throttle Valve. If 3MSS*MSV5 is found closed, locally reset and open 3MSS*MSV5 per Attachment A pages 3 and 4. Call the Control Room when done.
Simulator NA Reg uirements:
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: 2K13 P.2 Revision: 9 ch 3 Task
Title:
Locally Restore AFW Flow (Includes Opening 3MSS*MS'{§}
START TIME*
5 TEP 1 Performance: Standard: Critical: Grade
- 1 Check TD AFW Pump Trip Throttle IMPORTANT: PROVIDE FOLLOWING Y[x] N[] S[]U[]
Valve, 3MSS*MSV5, OPEN. (*SOER BRIEF TO CANDIDATE ONCE THEY HAVE 82-2 related*) LOCATED 3MSS*MSV5: Avoid bump hazards while in the area of the 3MSS*MSV5. This may be done by pointing from a distance and using the diagram on Attachment A page 4.
Locates valve 3MSS*MSV5 and asks for indication (see cue below).
Based on cues provided, determines that 3MSS*MSV5 has tripped closed.
Likely, the examinee will notify the Control Room prior to proceeding (& opening the valve). However, this is not necessary based on Initial JPM Cue.
Cue: Ask examinee what he (she) would look for. Provide response only to what is being monitored. The valve indications are:
- Latch pall disengaged from trip hook
- Limit switch pointing up with position rod down
- Terry turbine is not rotating
- Hand wheel remains fully counter-clockwise Comments:
AVOID BUMP HAZARDS. PROVIDE BRIEF TO CANDIDATE (See note under Standard above).
5
STEP Critical: Grade
- 2 Performance: Standard: Y[x] N[] S[]U[]
Open 3MSS*MSV5 IMPORTANT: Avoid bump hazards while in
- 1. Move connecting rod toward the area of the 3MSS*MSV5. This may be 3MSS*MSV5 until the trip tappet done by pointing from a distance and is fully down. using the diagram on Attachment A page 4.
- 2. Verify the trip tappet is fully Simulates:
down. 1. Moves connecting rod toward
- 3. Release connecting rod. 3MSS*MSV5 until the trip tappet is fully
- 4. Turn handwheel for down.
3MSS*MSV5 clockwise until the 2. Verifies the trip tappet is fully down.
trip hook engages with the latch- 3. Releases connecting rod.
up lever. 4. Turns handwheel for 3MSS*MSV5
- 5. Press trip hook and remove any clockwise until the trip hook engages gap between latch-up lever and with the latch-up lever.
trip hook. 5. Presses trip hook and removes any
- 6. Open 3MSS*MSV5, trip throttle gap between latch-up lever and trip valve. hook.
- 6. Opens 3MSS*MSV5, trip throttle valve, by turning handwheel in counter-clockwise direction (open direction).
Cue:
- 1. Connecting rod moves toward 3MSS*MSV5 until the trip tappet is fully down.
- 2. Trip tappet is fully down.
- 3. Connecting rod is released.
- 4. 3MSS*MSV5 handwheel turns clockwise until the trip hook engages with the latch-up lever.
- 5. No gap between latch-up lever and trip hook.
- 6. 3MSS*MSV5, trip throttle valve, handwheel rotates in counter-clockwise direction, valve stem rises, and the pump rotates.
Comments:
AVOID BUMP HAZARDS. See note under Standard above.
6
STEP Performance: Simulates calling the Control Room and Critical: Grade
- 3 Call Control Room to notify of informs them that 3MSS*MSV5 was found Y [ ] N [x] S[]U[]
completed actions. closed and has since been reset and opened.
- Cue: During the simulated phone call, report to the candidate "We have indications of proper rpm; however, there is still no AFW flow to the Steam Generators. Perform EOP 35 FR-H.1 Attachment A page 2 AND locally restore any valve that is found out of position. 3MSS*MOV17 A, B and D have been verified open by control room indication."
Comments: This begins the alternate path portion of the JPM.
STEP Performance: Standard: Critical: Grade
Isolation valve, 3MSS*AOV31A, OPEN. position indicator.
Cue:
Position indication plate is aligned to OPEN.
Comments:
STEP Performance: Standard: Critical: Grade
Isolation valve, 3MSS*AOV31 B, OPEN. position indicator.
Cue:
Position indication plate is aligned to OPEN.
Comments:
STEP Performance: Standard: Critical: Grade
Isolation valve, 3MSS*AOV31 0, OPEN. position indicator.
Cue:
Position indication plate is aligned to OPEN.
Comments:
7
STEP Performance: Standard: Critical: Grade
Return Valve 3MSS*MOV17A OPEN. position of 3MSS*MOV17 A OR Manually checks valve position by:
- 1. Engaging the manual handwheel,
- 2. Rotate the valve in the closed direction,
- 3. Reopen the valve until hard stop.
- 4. Rotate the handwheel by Y,. in the clockwise (close) direction.
Cue: (as needed) 1 . The MOV clutch is disengaged.
- 2. Valve handwheel rotates in the clockwise direction.
- 3. Valve handwheel rotates in the counterclockwise direction, eventually some resistance is met and the valve comes to a hard stop.
- 4. Valve rotates Y,. turn in clockwise direction.
8
STEP Performance: Standard: Critical: Grade
Return valve 3MSS*MOV17B OPEN. position of 3MSS*MOV17B OR Manually checks valve position by: !
1 . Engaging the manual handwheel,
- 2. Rotating the valve in the closed direction,
- 3. Reopen the valve and placing% turn off open seat.
- 4. Rotate the handwheel by% turn in the clockwise (close) direction.
Cue:
1 . The MOV clutch is disengaged.
- 2. Valve handwheel rotates in the clockwise direction.
- 3. Valve handwheel rotates in the counterclockwise direction, eventually some resistance is met and the valve comes to a hard stop.
- 4. Valve rotates% turn in clockwise direction.
9
STEP Performance: Standard: Critical: Grade
Return Valve 3MSS*MOV17D OPEN. position of 3MSS*MOV17D OR Manually checks valve position by:
1 . Engaging the manual handwheel,
- 2. Rotating the valve in the closed direction,
- 3. Reopen the valve and placing% turn off open seat.
- 4. Rotate the handwheel by% turn in the clockwise (close) direction.
Cue:
1 . The MOV clutch is disengaged.
- 2. Valve handwheel rotates in the clockwise direction.
- 3. Valve handwheel rotates in the counterclockwise direction, eventually some resistance is met and the valve comes to a hard stop.
- 4. Valve rotates %turn in clockwise direction.
Comments:
10
STEP Performance: Standard: Critical: Grade
- 10 Check TO AFW Pump DWST Supply (A) Checks locking device intact, lock hinders Y [ ] N [x] s[ ] u[ ]
Isolation valve, 3FWA*V30, LOCKED operation, and valve stem position indicates OPEN. valve is open.
(A) Cue:
The locking device is intact, it inhibits valve motion, and valve stem position is as shown. (open) ---THIS STEP IS COMPLETE---
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
OR Check TO AFW Pump DWST Supply (B)
Isolation valve, 3FWA*V30, LOCKED 1. Unlocks and removes the locking device on valve.
OPEN. 2. Rotates the handwheel in the clockwise direction and observes valve stem travel.
- 3. Rotates the handwheel in the counterclockwise direction until the valve is fully open (hard stop).
- 4. Rotates the handwheel 1/4 turn in the clockwise direction.
- 5. Installs the locking device and locks the lock.
Cue:
(B)
- 1. The lock is unlocked and the locking device is removed.
- 2. The valve handwheel rotates in the clockwise direction.
- 3. Valve handwheel rotates in the counterclockwise direction and then comes to a hard stop.
- 4. The valve handwheel has been rotated 1/4 turn in the clockwise direction.
- 5. The locking device is installed and locked.
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
11
ST EP 1 Performance: Standard: Critical: Grade
- 11 Check TO AFW Pump Discharge (A) Recognizes valve is closed based on Y[x] N[] s[ ] u[ ]
Isolation valve, 3FWA*V32, LOCKED visual observation. Continues to simulate OPEN. (B) Opening 3FWA*V32:
- 1. Rotates the handwheel in the counterclockwise direction until the valve is fully open (hard stop).
- 2. Rotates the handwheel 1/4 turn in the clockwise direction.
- 3. Installs the locking device and locks the lock.
(A) Cue:
The locking device is not intact, and the valve stem position is down in valve body. (closed)---
(B) Cue:
- 1. Valve handwheel rotates in the counterclockwise direction and then comes to a hard stop.
- 2. The valve handwheel has been rotated 1/4 turn in the clockwise direction.
- 3. The locking device is installed and locked.
Comments:
The candidate may report that he I she opened 3FWA*V32. If they do, have the candidate continue to verify the alignment.
12
STEP Performance: Standard: Critical: Grade
- 12 Check TD AFW Pump to SG D Isolation (A) Checks locking device intact, lock hinders Y [ ] N [x] S[] U[]
valve, 3FWA*V45, LOCKED OPEN. operation, and valve stem position indicates valve is open.
(A) Cue:
The locking device is intact, it inhibits valve motion, and valve stem position is as shown. (open) ---THIS STEP IS COMPLETE---
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
OR Check TD AFW Pump to SG D Isolation (B) valve, 3FWA*V45, LOCKED OPEN. 1. Unlocks and removes the locking device on valve.
- 2. Rotates the handwheel in the clockwise direction and observes valve stem travel.
- 3. Rotates the handwheel in the counterclockwise direction until the valve is fully open {hard stop).
- 4. Rotates the handwheel 1/4 turn in the clockwise direction.
- 5. Installs the locking device and locks the lock.
Cue:
(B)
- 1. The lock is unlocked and the locking device is removed.
- 2. The valve handwheel rotates in the clockwise direction.
- 3. Valve handwheel rotates in the counterclockwise direction and then comes to a hard stop.
- 4. The valve handwheel has been rotated 1/4 turn in the clockwise direction.
- 5. The locking device is installed and locked.
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
13
STEP Performance: Standard: Critical: Grade
- 13 Check AFW TO Pump Isolation to SG D (A) Checks locking device intact, lock hinders Y [ ] N [x] S[] U[]
valve, 3FWA*V839, LOCKED OPEN. operation, and valve stem position indicates valve is open.
(A) Cue:
The locking device is intact, it inhibits valve motion, and valve stem position is as shown. (open) ---THIS STEP IS COMPLETE---
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
OR Check AFW TO Pump Isolation to SG D (B) valve, 3FWA*V839, LOCKED OPEN. 1. Unlocks and removes the locking device on valve.
- 2. Rotates the handwheel in the clockwise direction and observes valve stem travel.
- 3. Rotates the handwheel in the counterclockwise direction until the valve is fully open (hard stop).
- 4. Rotates the handwheel 1/4 turn in the clockwise direction.
- 5. Installs the locking device and locks the lock.
Cue:
(B)
- 1. The lock is unlocked and the locking device is removed.
- 2. The valve handwheel rotates in the clockwise direction.
- 3. Valve handwheel rotates in the counterclockwise direction and then comes to a hard stop.
- 4. The valve handwheel has been rotated 1/4 turn in the clockwise direction.
- 5. The locking device is installed and locked.
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
14
STEP Performance: Standard: Critical: Grade
- 14 Check TO AFW Pump to SG A Isolation (A) Checks locking device intact, lock hinders Y [ ] N [x] s[ ] u[ ]
valve, 3FWA*V41, LOCKED OPEN. operation, and valve stem position indicates valve is open.
(A) Cue:
The locking device is intact, it inhibits valve motion, and valve stem position is as shown. (open) ---THIS STEP IS COMPLETE---
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
OR Check TO AFW Pump to SG A Isolation (B) valve, 3FWA*V41, LOCKED OPEN. 1. Unlocks and removes the locking device on valve.
- 2. Rotates the handwheel in the clockwise direction and observes valve stem travel.
- 3. Rotates the handwheel in the counterclockwise direction until the valve is fully open (hard stop).
- 4. Rotates the handwheel 1/4 turn in the clockwise direction.
- 5. Installs the locking device and locks the lock.
Cue:
(B)
- 1. The lock is unlocked and the locking device is removed.
- 2. The valve handwheel rotates in the clockwise direction.
- 3. Valve handwheel rotates in the counterclockwise direction and then comes to a hard stop.
- 4. The valve handwheel has been rotated 1/4 turn in the clockwise direction.
- 5. The locking device is installed and locked.
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
15
STEP Performance: Standard: Critical: Grade
- 15 Check TD AFW Pump to SG A Isolation (A) Checks locking device intact, lock hinders Y [ ] N [x] S[] U[]
valve, 3FWA*V836, LOCKED OPEN. operation, and valve stem position indicates valve is open.
(A) Cue:
The locking device is intact, it inhibits valve motion, and valve stem position is as shown. (open) ---THIS STEP IS COMPLETE---
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
OR Check TD AFW Pump to SG A Isolation (B) valve, 3FWA*V836, LOCKED OPEN. 1. Unlocks and removes the locking device on valve.
- 2. Rotates the handwheel in the clockwise direction and observes valve stem travel.
- 3. Rotates the handwheel in the counterclockwise direction until the valve is fully open (hard stop).
- 4. Rotates the handwheel 1/4 turn in the clockwise direction.
- 5. Installs the locking device and locks the lock.
Cue:
(B)
- 1. The lock is unlocked and the locking device is removed.
- 2. The valve handwheel rotates in the clockwise direction.
- 3. Valve handwheel rotates in the counterclockwise direction and then comes to a hard stop.
- 4. The valve handwheel has been rotated 1/4 turn in the clockwise direction.
- 5. The locking device is installed and locked.
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
16
STEP Performance: Standard: Critical: Grade
3FWA*V37, LOCKED OPEN. operation, and valve stem position indicates valve is OQen.
(A) Cue:
The locking device is intact, it inhibits valve motion, and valve stem position is as shown. (open) ---THIS STEP IS COMPLETE---
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
OR Check TO AFW Pump to SG B, (B) 3FWA*V37, LOCKED OPEN. 1. Unlocks and removes the locking device on valve.
- 2. Rotates the handwheel in the clockwise direction and observes valve stem travel.
- 3. Rotates the handwheel in the counterclockwise direction until the valve is fully open (hard stop).
- 4. Rotates the handwheel1/4 turn in the clockwise direction.
- 5. Installs the locking device and locks the lock.
Cue:
(B)
- 1. The lock is unlocked and the locking device is removed.
- 2. The valve handwheel rotates in the clockwise direction.
- 3. Valve handwheel rotates in the counterclockwise direction and then comes to a hard stop.
- 4. The valve handwheel has been rotated 1/4 turn in the clockwise direction.
- 5. The locking device is installed and locked.
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
17
STEP Performance: Standard: Critical: Grade
- 17 Check AFW TO Pump Isolation to SG (A) Checks locking device intact, lock hinders Y [ ] N [x] S[]U[]
B, 3FWA*V837, LOCKED OPEN. operation, and valve stem position indicates I valve is open.
(A) Cue:
The locking device is intact, it inhibits valve motion, and valve stem position is as shown. (open) ---THIS STEP IS COMPLETE---
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
OR Check AFW TO Pump Isolation to SG (B)
B, 3FWA*V837, LOCKED OPEN. 1. Unlocks and removes the locking device on valve.
- 2. Rotates the handwheel in the clockwise direction and observes valve stem travel.
- 3. Rotates the handwheel in the counterclockwise direction until the valve is fully open {hard stop).
- 4. Rotates the handwheel 1/4 turn in the clockwise direction.
- 5. Installs the locking device and locks the lock.
Cue:
(B)
- 1. The lock is unlocked and the locking device is removed.
- 2. The valve handwheel rotates in the clockwise direction.
- 3. Valve handwheel rotates in the counterclockwise direction and then comes to a hard stop.
- 4. The valve handwheel has been rotated 1/4 turn in the clockwise direction.
- 5. The locking device is installed and locked.
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
18
STEP Performance: Standard: Critical: Grade
- 18 Check TO AFW Pump to SG C Isolation (A) Checks locking device intact, lock hinders Y [ ] N [x] S[] U[]
valve, 3FWA*V33, LOCKED OPEN. operation, and valve stem position indicates valve is open.
(A) Cue:
The locking device is intact, it inhibits valve motion, and valve stem position is as shown. (open) ---THIS STEP IS COMPLETE--- .
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
OR !
Check TO AFW Pump to SG C Isolation (B) valve, 3FWA*V33, LOCKED OPEN. 1. Unlocks and removes the locking device on valve.
- 2. Rotates the handwheel in the clockwise direction and observes valve stem travel. I
- 3. Rotates the handwheel in the counterclockwise direction until the valve is fully open (hard stop).
- 4. Rotates the handwheel 1/4 turn in the clockwise direction.
I
- 5. Installs the locking device and locks the lock.
I Cue:
I (B)
- 1. The lock is unlocked and the locking device is removed.
- 2. The valve handwheel rotates in the clockwise direction. I
- 3. Valve handwheel rotates in the counterclockwise direction and then comes to a hard stop.
- 4. The valve handwheel has been rotated 1/4 turn in the clockwise direction.
- 5. The locking device is installed and locked.
I Comments:
Either Method A or Method B is acceptable. Both methods are not required. I 19
STEP Performance: Standard: Critical: Grade
- 19 Check AFW TD Pump Isolation to SG (A) Checks locking device intact, lock hinders Y [ ] N [x] s[ ] u[ ]
C, 3FWA*V838, LOCKED OPEN. operation, and valve stem position indicates valve is open.
(A) Cue:
The locking device is intact, it inhibits valve motion, and valve stem position is as shown. (open) ---THIS STEP IS COMPLETE---
Comments:
Either Method A or Method B is acceptable. Both methods are not required. I I
OR !
Check AFW TD Pump Isolation to SG (B)
C, 3FWA*V838, LOCKED OPEN. 1. Unlocks and removes the locking device on valve.
- 2. Rotates the handwheel in the clockwise direction and observes valve stem travel.
- 3. Rotates the handwheel in the counterclockwise direction until the valve is fully open (hard stop).
- 4. Rotates the handwheel 1/4 turn in the clockwise direction.
- 5. Installs the locking device and locks the lock.
Cue:
(B)
- 1. The lock is unlocked and the locking device is removed.
- 2. The valve handwheel rotates in the clockwise direction.
- 3. Valve handwheel rotates in the counterclockwise direction and then comes to a hard stop.
- 4. The valve handwheel has been rotated 1/4 turn in the clockwise direction.
- 5. The locking device is installed and locked.
Comments:
Either Method A or Method B is acceptable. Both methods are not required.
20
STEP Performance: Standard: Critical: Grade
- 20 Check the Governor Speed Droop set JPM WILL BE STOPPED HERE DUE TO Y [ ] N [x] s[ ] u[ ]
at zero. BUMP HAZARDS. SEE CUE BELOW.
Cue:
Before the candidate gains access to the governor controls, TERMINATE JPM by reporting "This JPM is complete. The remainder of the governor checks are not going to be performed due to the bump hazard."
Comments:
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ _ __
21
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 P.2 Revision: 9 ch 3 Date Performed:
Student:
Evaluator:
For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 15 min.
Actual Time to Complete (minutes):
JPM Work Practice Evaluation*: SAT UNSAT N/A Overall Result of JPM: SAT UNSAT
- As per TR-M-41 0, the Pass/Fail criteria for the JPM is that the trainee must 1) Perform the task correctly and lAW procedure use and adherence requirements, 2) Never put anyone's safety at risk, 3) Never put equipment reliability at risk, 4) Never violate radiological work practices, 5) Demonstrate effective use of event-free human performance tools. If a failure occurs, indicate why the failure occurred and which of these 5 task performance criteria contributed to the failure.
Areas for Improvement I Comments:
22
STUDENT HANDOUT JPM Number: 2K13 P.2 Revision: 9 ch 3 Initial Conditions: A Loss of Secondary Heat Sink event is in progress and the control room team is carrying out the actions of EOP 35 FR-H.1. AFW flow could not be established from the control room. The Control Room has indications that the Turbine Driven AFW Pump has tripped.
Initiating Cues: The US directs you to inspect 3MSS*MSV5, TD AFW Pump Trip Throttle Valve. If 3MSS*MSV5 is found closed, locally reset and open 3MSS*MSV5 per Attachment A pages 3 and 4. Call the Control Room when done.
23
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
ALIGN "C" RPCCW PUMP AND HEAT EXCHANGER TO THE "A" TRAIN JPM 2K13 NRC P.3 (P113) Revision: 4 chg 10 Number:
Initiated:
fL_~~(h William M. Forrestt 9/24/13 Developer Date Reviewed:
')lvvv--
PauiScott Technical Reviewer Date Approved:
Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES All & DATE DESCRIPTION REV/CHANGE 9/29/03 Updated to OP 3330A Rev. 15 1 9/14/04 2 6/20/05 Updated to OP 3330A Rev 16, revised task number, added 3 module reference 10/17/06 Updated to OP 3330A Rev 16-04, corrected valve position 4 verification steps to non-critical, RJM 08/21/2010 Updated to OP 3330A Rev 17-05, MJSiebert 5 10/09/2010 Updated to OP 3330A Rev 17-07. Updated to latest format. 6 TPG 02/09/2012 Updated to OP 3330A Rev 17-09. Revised JPM number to 7 P113 vice 113 to align with numbering system. TPG 9/7/12 Updated to OP 3330A Rev 018-00. Reversed the order of the 8 initial conditions and initiating cue to put initial conditions first.
DLM 1/18/13 Updated to OP 3330A Rev 18-02. JSY 9 9/24/13 Updated to OP 330A Rev 018-06. WMF 10 2
JPM WORKSHEET Facility: Millstone Unit 3 Examinee:
JPM 2K13 NRC P.3 Revision: 4 chg 10 Number:
Task
Title:
ALIGN "C" RPCCW PUMP AND HEAT EXCHANGER TO THE "A" TRAIN System: ccw Time Critical Task: ) YES (X) NO Validated Time (minutes),____1_5_ _
Task Number(s): 344-05-024 Applicable To: SRO X RO X PEO X KIA 008-A.201 KIA Rating: 3.3/3.6 Number:
Method of Testing: Simulated X Actual Performance: Performance:
Location: Classroom: Simulator: In-Plant: X Task Standards: Satisfactorily align the "C" RPCCW pump and heat exchanger to the "A" train of RPCCW using OP 3330A Section 4.9.
Required Materials: 1. OP 3330A, Rev. 018-06 Section 4.9 (handout)
(procedures, equipment, etc.)
General
References:
N/A 3
- READ TO THE EXAMINEE***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K13 NRC P.3 Revision : 4 chg 10 Initial Conditions: Train "A" RPCCW pump has been lost and the Control Room team is carrying out the actions in AOP 3561 for a loss of RPCCW. The CTMT headers have been cross-connected.
Initiating Cue: The US has directed you to align the "C" RPCCW pump and heat exchanger to the "A" train of RPCCW using OP 3330A Section 4.9.
Both RPCCW pump "C" control switches are in the PULL-TO-LOCK position. (Step 4.9.5)
- Another PEO will complete steps 4.9.12 through 4.9.16 in OP 3330A and will provide you with the appropriate Kirk key when he has completed his actions.
- The vents on 'C' CCP heat exchanger have been closed to allow performing section 4.9 as written. This was done to comply with long term tagging section 3C16 3SWP20-0005. This tag section requires the 'C' CCP vents be closed prior to opening 3SWP*V037 or 3SWP*V69 (due to valve leak by of 3SWP*V38).
Simulator NA Requirements:
- NOTES TO TASK PERFORMANCE EVALUATOR****
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: 2K13 NRC P.3 Revision: 4 chg 10 Task
Title:
ALIGN "C" RPCCW PUMP AND HEAT EXCHANGER TO THE "A" TRAIN STARTTIME: _ _ __
Comments:
The position indicators for several of the valves that are manipulated during this JPM cannot be observed without a ladder. For the purposes of this JPM it is not required that a ladder be obtained to check the position indications. The examiner shall provide the appropriate cues as to valve positions.
Comments:
Location for Performance Steps 1 through 4 is Aux. Bldg. 24'6", near HX and pumps.
STEP Performance: Standard: Critical: Grade
- 2. Simulates rotating the handwheel
4.9.1 Critical
Grade for 3SWP*V69 in the clockwise Y [x1 N [ 1 S[1 U[1 direction until the valve is closed (hard stop).
- 3. Uses attached position indication for verification.
Cue:
- 1. The valve handwheel rotates in the clockwise direction. Eventually some resistance is met and the valve comes to a hard stop.
- 2. The position indicator points to the "closed" position (not observable).
Comments:
-- -~
5
STEP Performance: Standard: Critical: Grade
- 2 CLOSE the following RPCCW heat 1. Locates 3SWP*V70 & 3SWP*V71. Y [x] N [ ] S[]U[]
exchanger C Train B service water 2. Simulates rotating the handwheel(s) 3330A return valves: for 3SWP*V70 and 3SWP*V71 in 1---C-r-.t-ic-al-.-1---G-ra-d-e--1 4.9.2
- 3SWP*V70, RPCCW HX C SW B the clockwise direction until the y [xJ N [ 1 s [ 1 u [ 1 valve(s) are closed (hard stop).
rtn isol
- 3. Uses attached position indication(s)
rtn stop Cue:
- 1. The valve handwheel rotates in the clockwise direction and the position indicator starts moving toward the close position. Eventually some resistance is met and the valve comes to a hard stop.
- 2. The position indicator points to the "closed" position.
Comments:
STEP Performance: Standard: Critical: Grade
- 3 OPEN the following RPCCW heat 1. Locates 3SWP*V36 & 3SWP*V37. Y [x] N [ ] s[ ] u[ ]
exchanger C Train A service water 2. Simulates rotating the handwheel(s) 3330A supply valves: for 3SWP*V36 and 3SWP*V37 in 4.9.3 the counterclockwise direction until
sply isol
- 3. Uses attached position indication(s)
sply stop 4. Rotates the handwheel(s) ~in the clockwise (close) direction.
Cue:
(If needed, remind candidate that vents on 'C' CCP heat exchanger have been closed and 3SWP*V37 may be Opened).
- 1. The valve handwheel rotates in the counterclockwise direction. Eventually some resistance Is met and the valve comes to a hard stop.
- 2. The position indicator points to the "open" position (not observable).
- 3. The handwheel has been rotated 1/4 turn in the clockwise direction.
1-------1 Comments:
6
STEP Performance: Standard: Critical: Grade
- 4 OPEN the following RPCCW heat 1. Locates 3SWP*V40 & 3SWP*V41. Y [x] N [ ] s[ ] u[ ]
3330A exchanger C Train A service water 2. Simulates rotating the handwheel(s) return valves: for 3SWP*V40 and 3SWP*V41 in 4.9.4 the counterclockwise direction until
rtn stop
- 3. Uses attached position indication(s)
rtn isol 4. Rotates the handwheel(s)% in the clockwise (close) direction.
Cue:
- 1. The valve handwheel rotates in the counterclockwise direction. Eventually some resistance Is met and the valve comes to a hard stop.
- 2. The position indicator points to the "open" position.
- 3. The handwheel has been rotated 1/4 turn in the clockwise direction.
Comments:
STEP Performance: Standard: Critical: Grade
- 5 PLACE the following in PULL-TO- No action required. Both control switches are Y [ ] N [x] S[]U[]
LOCK (MB-1 ): in PULL-TO-LOCK. This was given in the 3330A 3CCP*P1 C, "PP C" (Train A) initial conditions.
4.9.5 3CCP*P1 C, "PP C" (Train B) i Cue: I If the examinee asks the status of these switches, inform him that both switches are in the PULL-TO-LOCK position.
Comments:
7
STEP Performance: Standard: Critical: Grade
- 6 CLOSE the following Train 8 1. Locates 3CCP*V8 & 3CCP*V10. Y [x] N [ ] S[]U[]
3330A RPCCW discharge cross-connect 2. Simulates rotating the handwheel(s) valves: for 3CCP*V8 and 3CCP*V1 0 in the
4.9.6 Critical
Grade clockwise direction until the valve(s) Y [x] N [ ] S[] U[]
- 3CCP*V8, train 8 RPCCW are closed (hard stop).
secondary discharge cross connect to P1 C 3. Uses attached position indication(s) for verification.
- 3CCP*V1 0, train 8 RPCCW primary discharge cross connect to P1C Cue:
- 1. The valve handwheel rotates in the clockwise direction and the position indicator starts moving toward the close position. Eventually some resistance is met and the valve comes to a hard stop.
- 2. The position indicator points to the "closed" position.
Comments:
Location for Performance Steps 7 and 8 is Aux. Bldg. 14' platform.
STEP Performance: Standard: Critical: Grade
- 7 CLOSE the following Train 8 1. Locates 3CCP*V94 & 3CCP*V95. Y [x] N [ ] s[ ] u[ ]
3330A RPCCW suction cross-connect 2. Simulates rotating the handwheel(s) valves: for 3CCP*V94 and 3CCP*V95 in
4.9.7 Critical
Grade the clockwise direction until the Y [x] N [ ] s[ ] u[ ]
- 3CCP*V94, train 8 RPCCW valve(s) are closed (hard stop).
secondary suction cross connect to P1C 3. Uses attached position indication(s) for verification.
- 3CCP*V95, train 8 RPCCW primary suction cross connect to P1C Cue:
- 1. The valve handwheel rotates in the clockwise direction and the position indicator starts to move toward the close position. Eventually some resistance is met and the valve comes to a hard stop.
- 2. The position indicator points to the "closed' position.
Comments:
8
STEP Performance: Standard: Critical: Grade
- 8 OPEN the following Train A RPCCW 1. Locates 3CCP*V92 & 3CCP*V93. y [x] N [ ] S[]U[]
suction cross-connect valves: 2. Simulates rotating the handwheel(s) 3330A for 3CCP*V92 and 3CCP*V93 in 4.9.8
- 3CCP*V92, train A RPCCW the counterclockwise direction until primary suction cross connect to the valve(s) are open (hard stop).
P1C
- 3. Uses attached position indication(s)
- 3CCP*V93, train A RPCCW for verification.
secondary suction cross connect 4. Rotates the handwheel(s)% in the to P1C clockwise (close) direction.
Cue:
- 1. The valve handwheel rotates in the counterclockwise direction. Eventually some resistance Is met and the valve comes to a hard stop.
- 2. The position indicator points to the "open" position.
- 3. The handwheel has been rotated 1/4 turn in the clockwise direction.
Comments:
Location for Performance Step 9, 3CCP*V96 is Aux. Bldg. 14'Piatform STEP Performance: Standard: Critical: Grade
- 9 Ensure 3CCP*V96, RPCCW pump 1. Rotates the handwheel for Y [ ] N [x] S[]U[]
3330A C suction isolation, open. 3CCP*V96 in the clockwise direction and verifies stem 4.9.9 movement.
- 2. Returns valve to open position.
- 3. Rotates the handwheel % turn in the clockwise (close) direction.
Cue:
- 1. The valve handwheel rotates in the clockwise direction and valve stem movement is verified.
- 2. Valve indicator is aligned to open
- 3. Valve rotates 1/4 turn in the closed direction.
9
STEP Performance: Standard: Critical: Grade
- 10 OPEN the following Train A RPCCW 1. Locates 3CCP*V7 & 3CCP*V9. Y [x] N [ ] S[]U[]
3330A discharge cross connect valves: 2. Simulates rotating the handwheel(s) for 3CCP*V7 and 3CCP*V9 in the
- 4. 9. 1 0
- 3CCP*V7, train A RPCCW counterclockwise direction until the primary discharge cross connect valve is open (hard stop).
to P1C
- 3. Uses attached position indication(s)
- 3CCP*V9, train A RPCCW for verification.
secondary discharge cross 4. Rotates the handwheel(s)% in the connect to P1 C clockwise (close) direction.
Cue:
- 1. The valve handwheel rotates in the counterclockwise direction and the position indicator starts moving toward the open position. Eventually some resistance is met and the valve comes to a hard stop.
- 2. The position indicator points to the "open" position.
- 3. The handwheel has been rotated 1/4 turn in the clockwise direction.
Comments:
Location for Performance Step 11, 3CCP*V5 is Aux. Bldg. 24'6", near HX and pumps.
STEP Performance: Standard: Critical: Grade
- 11 Ensure 3CCP*V5, RPCCW pump C 1. Rotates the handwheel for y [ ] N [x] S[]U[]
3330A discharge isolation, open. 3CCP*V5 in the clockwise direction and verifies stem movement.
- 4. 9. 1 1
- 2. Returns valve to open position.
- 3. Rotates the handwheel % in the clockwise (close) direction.
Cue:
- 1. The valve handwheel rotates in the clockwise direction and valve stem movement is verified.
- 2. Valve indicator is aligned to open
- 3. Valve rotates 1/4 turn in the closed direction.
Comments:
CUE:
Step_!_4.9.12 Thru 4.9.16 have been completed. Simulate handing Kirk Key No.3 to the examinee.
10
STEP Performance: Standard: Critical: Grade
- 12 At 3CCP*TRS-P1C (east MCC/RCA Inserts Kirk key No. 3 into the lower block Y [x] N [ ] s[ ] u[ ]
3330A 46'), INSERT the Kirk key No. 3 and rotates the key to unlock switch 2.
(RE11339) into the lower block at
- 4. 9. 1 7 switch 2 and UNLOCK switch 2.
Cue:
The Kirk key has been inserted, rotated, and switch 2 is unlocked.
Comments:
STEP Performance: Standard: Critical: Grade
- 13 To open switch 2, PULL the lever Pulls the lever arm down Y [x] N [ ] S[] U[]
3330A arm down.
- 4. 9. 1 8 Cue:
The lever arm is in the down position Comments:
STEP Performance: Standard: Critical: Grade
- 14 LOCK switch 2 open and REMOVE Rotates the Kirk key No.2 to lock switch 2 Y [x] N [ ] S[]U[]
3330A the upper Kirk key No.2 (RE11337). and pulls the Kirk key out of the locking block.
- 4. 9. 1 9 Cue:
The upper Kirk key No. 2 has been rotated and you have the key in your hand.
Comments:
STEP Performance: Standard: Critical: Grade
- 15 INSERT Kirk key No.2 (RE11337) Inserts Kirk key No.2 into the lower block Y [x] N [ ] S[]U[]
3330A into the lower block at switch 1 and and rotates the key to unlock switch 1 .
UNLOCK switch 1.
- 4. 9. 2 0 Cue:
The Kirk key has been inserted, rotated, and switch 1 is unlocked.
Comments:
11
STEP Performance: Standard: Critical: Grade
- 16 To close switch 1, PUSH the lever Pushestheleverup. Y [x] N [ ] S[] U[]
3330A UP.
- 4. 9. 2 1 Cue:
The lever is aligned to the up position.
Comments:
STEP Performance: Standard: Critical: Grade
- 17 LOCK switch 1 closed and REMOVE Rotates the Kirk key No. 1 to lock switch 1 Y [x] N [ ] S[]U[]
3330A the upper Kirk key No. 1 (RE11336). and pulls the Kirk key out of the locking block.
- 4. 9. 2 2 Cue:
The upper Kirk key No. 1 has been rotated and you have the key in your hand.
Comments:
For the next JPM step, the cabinet should not be opened. The examinee will have to simulate opening the door, explain his actions and simulate closing the door.
Comments:
The examinee should explain during the next step that he would turn the key as far as it will go to ensure the electrical interlocks are also made up.
STEP Performance: Standard: Critical: Grade
- 18 Using Kirk key No. 1 (RE11336), Inserts Kirk key No. 1 into the locking Y [x] N [ ] S[]U[]
3330A UNLOCK the elevator mechanism at block and rotates the key to unlock the breaker 34C1 0-2 and release clutch elevator mechanism and releases clutch
- 4. 9. 2 3 lever. lever.
Cue:
- 1. The Kirk key is inserted and rotated.
- 2. For the purposes of this JPM assume that he has RACKED-UP the "C" RPCCW pump circuit breaker into cubicle 34C10-2.
Comments:
12
STEP Performance: Standard: Critical: Grade
- 19 Notify the US that the "C" RPCCW Informs the US that Section 4.9 of OP Y [ ] N [x] s[ ] u[ ]
pump and heat exchanger are 3330A has been completed and the "C" aligned to the Train A RPCCW RPCCW pump and heat exchanger are System. aligned to the Train A RPCCW System.
Cue:
Comments:
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ _ __
13
VERIFICATION OF JPM COMPLETION JPM Number: 2K13 NRC P.3 Revision: 4 chg 10 Date Performed:
Student:
Evaluator:
For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 15 Actual Time to Complete (minutes):
JPM Work Practice Evaluation*: SAT UNSAT N/A Overall Result of JPM: SAT UNSAT The Pass/Fail criteria for the JPM is that the trainee must 1) Perform the task correctly and lAW procedure use and adherence requirements, 2) Never put anyone's safety at risk, 3)
Never put equipment reliability at risk, 4) Never violate radiological work practices, 5)
Demonstrate effective use of event-free human performance tools. If a failure occurs, indicate why the failure occurred and which of these 5 task performance criteria contributed to the failure.
Areas for Improvement I Comments:
14
STUDENT HANDOUT JPM Number: 2K13NRC P.3 Revision: 4 chg 10 Initial Conditions: Train "A" RPCCW pump has been lost and the Control Room team is carrying out the actions in AOP 3561 for a loss of RPCCW. The CTMT headers have been cross-connected.
Initiating Cue: The US has directed you to align the "C" RPCCW pump and heat exchanger to the "A" train of RPCCW using OP 3330A Section 4.9.
Both RPCCW pump "C" control switches are in the PULL-TO-LOCK position. (Step 4.9.5)
- Another PEO will complete steps 4.9.12 through 4.9.16 in OP 3330A and will provide you with the appropriate Kirk key when he has completed his actions.
- The vents on 'C' CCP heat exchanger have been closed to allow performing section 4.9 as written. This was done to comply with long term tagging section 3C16 3SWP20-0005. This tag section requires the 'C' CCP vents be closed prior to opening 3SWP*V037 or 3SWP*V69 (due to valve leak by of 3SWP*V38).
15
I ~ITE: I MP3 PROGRAM: ILT PROGRAM No.
LESSON TITLE: '8' Steam Generator Tube Rupture I LESSON#: 2K13 NRC-01 Total Time 90 minutes Prepared by: William M. Forrestt t;__ /-fl-t 9/27/13 Printed Name Developer Signature Date 1eviewed by: Bob Royce Printed Name ~til:: 'l/!J/t3
/
Date Approved by: Paul Scott "]~11r~ 1j2-7fr~
Printed Name li[:::ns Supervisor Date Approved by: Trad Horner \of 4f l3 Printed Name Training Supervisor Date
Simulator Exercise Guide Job Aid Page 2 of 50 SEG# 2K13 NRC-01 Rev: 0 All & DATE DESCRIPTION REV/CHANGE
SECTION 2 SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER
- 1. Cover Page Table of Contents
- 3. Exercise/Exam Overview
- 4. Exam Guide Attachments:
Shift Turnover Report Validation Checklist Scenario Outline (ES-D-1)
Attributes Checklist
Simulator Exercise Guide Job Aid Page 4 of 50 SEG# 2K13 NRC-01 Rev: 0 SECTION 3 EXAM OVERVIEW
Title:
'B' SG Tube Rupture ID Number: 2K13 NRC-01
- 1. The crew will take the shift with Reactor power stable at 100%. The 'C' Reactor Plant Component Cooling heat exchanger is tagged out for tube leak repair. Additionally, Control Rods are in manual for repair of auto circuitry (which is not functional due to Tavg I Tref circuit card failure).
The scenario will start with a phone call informing the Unit Supervisor (US) that 'B' Emergency Diesel Generator governor sightglass is empty and there is a puddle of oil beneath the governor. The US will enter the appropriate Tech Spec and have the BOP disable the 'B' EDG.
Next, the controlling channel of pressurizer pressure fails high. The RO will take manual control of the Master Pressure Controller and the crew will carry out actions of AOP 3571, Instrument Failure Response.
Once the associated bistables are tripped, the 'A' Heater Drain Pump will trip. The associated annunciator response procedure will direct a 7% down power. The loss of the Heater Drain Pump will cause Reactor power to exceed license limits and could cause a loss of the Main Feed Pumps on low suction pressure. The crew may decide to start a third condensate pump to allow time to enter AOP 3575, Rapid Down power. Conversely, the crew may decide to use turbine controls to lower power while having the RO step Control Rods in manual. In either case, the crew will stabilize the plant at -93% power.
Next, the letdown pressure transmitter fails to an intermediate value causing the letdown pressure controller to modulate close. This will lift a letdown relief valve to the Pressurizer Relief Tank in Containment. The RO will diagnose the failure and take manual control using diverse indications of letdown and RCS parameters.
Shortly afterwards, a tube leak on 'B' SG will develop into a rupture. At first, the crew will attempt to mitigate using AOP 3576, SG Tube Leak. However, the leak will develop and exceed Charging System make-up capacity. The crew will identify this and attempt a manual Reactor Trip. All Reactor Trip switches will be defeated and the BOP will be successful using load center switches [Critical Task]. Following the successful Reactor Trip, the crew will manually initiate Safety Injection.
Simulator Exercise Guide Job Aid Page 5 of 50 SEG# 2K13 NRC-01 Rev: 0 The crew will carry out actions in E-0, Reactor Trip or Safety Injection. The crew will need to identify and re-align multiple Charging components which are out of position (Critical Task] and take actions to align Feed Water Isolation components.
The crew will transition to E-3 and mitigate the tube rupture by successfully implementing the strategies of this procedure. The crew will isolate the affected SG, establish and maintain the necessary subcooling [Critical Task], depressurize the RCS, and terminate Safety Injection. The scenario will end once the crew successfully implements E-3, step 27 "Control RCS Pressure and Charging Flow to Minimize RCS-To-Secondary Leakage.
- 2. The SRO candidate (US) should classify this event as an ALERT Charlie One based on barrier failure, BA 1.
- 3. Duration of Exam: 90 minutes
Simulator Exercise Guide Job Aid Page 6 of 50 SEG# 2K13 NRC-01 Rev: 0 SECTION 4 EXAM GUIDE
Title:
'B' SG Tube Rupture 10 Number: 2K13 NRC-01 All Control Room Conduct, Operations and Communications shall be in accordance with OP-AA-1 00, Conduct of Operations.
~eview the Simulator Operating Limits (design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded."
(NSEM 6.06)
Simulator Exercise Guide Job Aid Page 7 of 50 SEG# 2K13 NRC-01 Rev: 0 Event I Delay I Ramp I Delete Severity ID I Description J Trigger Time Time Time I Or Value MALFUNCTIONS RX09A I PZR PT455 FAIL 1 0 0 2500 psia FW16A 4TH POINT HTR DRN PP TRIP (P1A) 2 0 0 CV05 LTDN PRES TRANS FAIL PT131 3 0 30 sec 275 psig SG01B S/G B TUBE RUPTURE 4 0 22 min 200 gpm RP10A AUTO REACTOR TRIP TRAIN A FAIL 0 0 RP10B AUTO REACTOR TRIP TRAIN B FAIL 0 0 RP09A REACTOR MANUAL TRIP SWITCH MB4 FAIL 0 10 RP09B REACTOR MANUAL TRIP SWITCH MB7 FAIL 0 0 RP11L AUTO ACT FAIL: FW ISO (FWI} 0 0 R11F AUTO ACT FAIL: CVCS 0 10 MS12B MS ISO VALVE CTV27B STUCK OPEN 0 Jo REMOTE FUNCTIONS RXR 106,05, PZR PRESSURE BISTABLES AND DOOR 110 I sec o to 40 I o I Bistables to TRIP 34, 44, 40, 48, 120 I Door open/ close RPR40
Simulator Exercise Guide Job Aid Page 8 of 50 SEG# 2K13 NRC-01 Rev: 0 Event I Delay I Ramp I Delete Severity ID Description Trigger Time Time Time I Or Value MSR01 Start Aux Boiler 11 5 min 0 START FWR33 Close 3CNS-V9 & V11 12 5 min 0 CLOSE FWR62 RCR 23 thru RCP Hot I Cold Switches 1 13 IO IO I I COLD 26 OVERRIDES
Simulator Exercise Guide Job Aid Page 9 of 50 SEG# 2K13 NRC-01 Rev: 0 o COMPLETE Simulator Setup and Readiness Checklist. I NIA o SELECT appropriate IC o LOAD and RUN applicable Schedule.
o As necessary, ENTER or VERIFY the following Initial Malfunctions I IIOs I Remote Functions, OR, as specified on previous 'Input Summary' page:
o As necessary, PERFORM verification of Initial Malfunctions I IIOs I Remote Functions entered.
o When the simulator is ready, PLACE to Run and VERIFY the simulator reflects the following Initial Conditions for the scenario and is stable:
o As necessary, REMOVE the following Equipment from service and tag accordingly:
- PLACE Rod Control in Manual with YCT
- PLACE YCT on 'C' CCP pump control switches (both trains) o CONDUCT briefing with evaluators. PRE-SCENARIO: NIA o BRIEF the crew initial plant conditions and provide a shift turnover.
o lE this is the first simulator scenario of the week, REVIEW the Plant/Simulator Differences List and Simulator Training Objectives with the crew.
o As necessary, REVIEW any scenario specific differences and any planned simulator freeze ooints.
(All) Walk down control boards and conduct shift briefi
Simulator Exercise Guide Job Aid Page 10 of 50 SEG# 2K13 NRC-01 Rev: 0 Event 1:
'BJ EMERGENCY DIESEL GENERATOR INOP NOTE: Anything the booth instructor needs to perform or report as part of the scenario should be BOLD.
Call x6200 as Outside Rounds PEO and RO or BOP: Acknowledges field report and report: transmits to US.
"'B' EDG governor oil level is empty. There is a puddle of oil beneath the governor." US: Determines that the 'B' EDG is inoperable and performs I directs:
(1) BOP to place 'B' EDG Start switch in PTL.
(2) Enters TIS 3.8.1.1 Action b (table requires addressing b.1, b.2, b.3, b.4, & b Event 2 Notes on failure: RO: Recognizes channel 1 of pressurizer
( 1) Placing the Master Pressure pressure has failed high, notifies US of INSERT TRIGGER 1 (RX09A) Controller at 50% (normal output) failure, and manually raises output of CONTROLLING PZR PRESS CHANNEL will close the pressurizer spray master pressure controller to close FAILS HIGH valves and stabilize the plant. pressurizer spray valves.
(2) The failure will lower RCS pressure.
Some RCS pressure limits:
2204 psia (DNB, TIS 3.2.5) 1900 psi a (Auto Reactor Trip)
US: Enters AOP 3571 (Rev-09-07) after plant is stable and reads:
CAUTION Do not leave the rod selector switch in AUTO while diagnosing a related instrument failure unless the reason for rod movement is a turbine runback.
NOTE If a reactor trip occurs, immediately to E-0, Reactor Trio or Safetv lniection.
Simulator Exercise Guide Job Aid Page 11 of 50 SEG# 2K13 NRC-01 Rev: 0 LINE BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS The RO should have already placed the RO:
Master Pressure Controller in Manual. Determine The Initiating Parameter And Place The Affected Controller In MANUAL RO:
Stabilize The Plant Parameters US: Reads Note to crew:
NOTE It is desired that I&C personnel trip the bistables specified in this procedure. If, during off-hours, I&C personnel are not able to trip the necessary bistables within the time limitations required by the Technical Specifications, Operations Department personnel may trip the bistables using the guidance provided within this procedure.
US:
Perform Corrective Actions Using Appropriate
Attachment:
Pressurizer Pressure Channel Failu RO should select Channel 3/4. RO:
Defeat the failed channel input. Pressurizer Press Select - Control 3RCS-PS455F RO should select a channel other than Ch 1 RO:
(likely channel 3). Pressurizer Press Select - Record 3RCS-PS455G RO should select a channel other than Ch 1 RO:
OT/OP Delta T Record Select RCS-TS411 E RO:
Restore RCS pressure to normal, then Place PZR pressure control in automatic.
Simulator Exercise Guide Job Aid Page 12 of 50 SEG# 2K13 NRC-01 Rev: 0 RO & BOP:
When conditions have stabilized, Observe MB annunciators and parameters.
Immediately report any unexpected or unexplained conditions to the Shift Manaaer.
US:
Trip the associated Reactor Protection System bistable(s): Place a check mark in the box above the appropriate channel that requires tripping on pages 5 or 6 of this Attachment.
Logs into 3.3.1 Action 6 (FU #7,9 &1 0) and US:
3.3.2 Actions 20 and 21 (FU #1.d & 9.a). Refer to Technical Specification 3.3.1, 3.3.2, and 3.3.3.5.
Logs into TRM 3.3.2.1, Action 27 .. A. US:
Refer to Technical Requirement 3.3.2.1.
RO:
Check the existing bistable status to ensure a reactor trip will not occur when the failed channel is tri US: Reads to crew:
CAUTION If the General Warning lamp is lit on 3RPS*RAKLOGB, placing train A SSPS "Multiplexer Test" switch in "A+B" will cause the reactor to trip.
NOTE The following step will distinguish whether the failure is within SSPS or the Protection channel.
US determines this step is not applicable as US:
the instrument channel has failed. If bistable status light(s) (MB2D or MB4F) indicate that a single bistable input has tripped and channel indications are normal, PERFORM the followina ....
Simulator Exercise Guide Job Aid Page 13 of 50 SEG# 2K13 NRC-01 Rev: 0 STUDENTS After I&C brief, INSERT TRIGGER 10 to When requested, report to the Control US:
trip bistables Room as I&C. Request the I&C Department trip the appropriate bistables using Attachment B and Attachment S.
RO:
Verify the appropriate bistable status light(s) are lit.
Enters 14 day TRM Action Statement, 7.4.1 US:
Action a.2. If indicator 3RCS*PI 4558 is failed, Refer to TRM Table 7.4.1, Fire Related Safe Shutdown Components, Reactor Coolant m."
Request I&C Department perform corrective maintenance on failed instrument.
Simulator Exercise Guide Job Aid Page 14 of 50 SEG# 2K13 NRC-01 Rev: 0 Event 3: Notes on failure:
(1) The loss of a heater drain pump will INSERT TRIGGER 2 (FW16A) initially cause Reactor Power to exceed 4TH POINT HTR DRN PP TRIP (P1A) license thermal limit of 3650 MWth (due to colder Condensate water. Op 3204, At Power Operation, step 4.3.1 directs Immediately reducing reactor power to less than or equal to 3,650 MWth if CVQRPA (4 min calorimetric average) exceeds 102% (3723 MWth).
(2) The next impact is Main Feed Pump suction pressure and a concern for pump trip (250 psig after 30 seconds).
This can be addressed by a.) Starting a third condensate pump (not in Heater Drain Pump ARP BUT guidance is in TDFW PP A or B Suction Press Lo ARP) OR b.) Immediately starting a downpower (3) The result of the above concerns may cause the US to provide immediate direction to the crew and later back-up with procedures (allowed by site guidance). The crew may decide to start a third condensate pump to allow time to enter AOP 3575, Rapid Downpower. Conversely, the crew may decide to use turbine controls to lower power while having the RO step Control Rods in manual. In either case, the crew will stabilize the plant at -93%
power (per ARP guidance).
Simulator Exercise Guide Job Aid Page 15 of 50 SEG# 2K13 NRC-01 Rev: 0 BOP determines the 'A' Heater Drain Pump US:
(HOP) has tripped. Enters ARP OP3353.MB6A (5-7) (Rev06-12)
Check heater drain pump current and re to determine affected The crew may elect to start a third BOP:
condensate pump. This ARP guidance is ADJUST feedwater flow to match steam contained in 'TDFW PP A or B SUCTION flow.
PRESS LO" ARP. Additionally, if MB6A 2-7, "COND DEMIN DP HIGH", becomes lit then the crew will bypass the condensate demins bv throttlina open, 3CNM-MOV78.
As stated above, the US may either direct: RO & BOP:
a.) Having BOP use load limit dial to reduce If reactor power is greater than 93.4%
power -7%. If this occurs, the crew (3411 MWth}, REDUCE reactor power to must recognize that control rods are in less than 93.4% (3411 MWth}.
manual and the RO will need to insert rods (OP 3204 Tavg band is+ I- 5 F).
b.) Entering AOP 3575, Rapid Downpower, to lower reactor power -7%.
N/A BOP:
IF directed by SM/US, STOP affected heater drain pump.
Follow ARP action. Do not allow RO:
completion of this activity to stop transition IF reactor power was reduced, Refer To to next Event. "Reactor Engineering Curve and Data Book," reactivity plan RE---H---01 for guidance on positioning control rods for AFD control.
N/A BOP:
IF heater drain pump trip is due to feedwater heater low level, PERFORM the following:
Simulator Exercise Guide Job Aid Page 16 of 50 SEG# 2K13 NRC-01 Rev: 0 Follow ARP action. Do not allow BOP:
completion of this activity to stop transition IF heater drain pump trip is not due to to next Event. feedwater heater low level, Refer to OP 3320, "Feedwater Heater Drains and Vents," and REMOVE affected heater drain from service.
Follow ARP action. Do not allow BOP:
completion of this activity to stop transition IF feedwater heater string is isolated, Go To to next Event. AOP 3567, "Operation With One Feedwater Heater Strina Isolated."
Follow ARP action. Do not allow BOP:
completion of this activity to stop transition Using "Feedwater Heater Level" display, to next Event. MONITOR affected string feedwater heater levels (Foxboro DCS) for operation of normal and emergency drain valves.
Event 4 RO responds by (1) announcing An nun MB3A"Letdown Relief Vv Temp Hi", (2)
INSERT TRIGGER 3 (CV05) notes that letdown flow is reduced, and (3)
LETDOWN PRESSURE TRANSMITTER identifies letdown pressure control valve FAILS TO 275 PSIG throttling closed. The RO may take manual control of 3CHS-PK131 at this time.
US:
Enters ARP OP3353.MB3A (Rev. 02-13)
RO:
CHECK 3RCS*TI 125, letdown relief valve temoerature (M83). to confirm alarm.
US: Reads note to crew:
NOTE 3CHS*RV8117, letdown relief valve, lifts at 600 psig
Simulator Exercise Guide Job Aid Page 17 of 50 SEG# 2K13 NRC-01 Rev: 0 RO will see process input (green arrow) on RO:
3CHS-PK131 drifting towards its failed state Check 3 CHS*PI 131, letdown pressure 300 of 275 psig (30 sec ramp). The RO will to 350 psig.
need to recognize that the valve is modulating closed correctly and there is a failure of the orocess inout.
Based on failure to pressure instrument, RO RO:
will need to use diverse indication to !E directed by SM/US, PLACE maintain letdown pressure (letdown flow, 3CHS*PK131, letdown pressure controller, normal controller output of approx 50%, in "MANUAL", and MAINTAIN letdown inventory balance). ressure 300 to 350 This letdown relief tailpiece temperature is RO:
modeled and will drift down SLOWLY after CHECK 3RCS*TI 125, letdown reJief valve the relief valve is re-seated. temperature (MB3), to check 3CHS*RV8117, letdown relief valve, seated.
Event 5 Notes on failure: US:
This malfunction is ramped such that it Enters AOP 3576 (Rev-04-03)
INSERT TRIGGER 4 (SG01 B) begins as a small tube leak on 'B' SG. At 200 GPM 'B' SG TUBE RUPTURE first, the crew will attempt to mitigate using (ramps in over 22 minutes) AOP 3576, SG Tube Leak. However, the leak will develop and exceed Charging System make-up capacity. This will cause the crew to return to Step 1 (per note instruction) and eventuallv trio the reactor.
This is significant as it becomes the reason US: Reads Note to crew:
for later transition to E-0 per the definition of NOTE Foldout Page must be open. Step 1 a continuous step in the User's guide. is a continuous action step and should be performed at any time additional charging flow is required to maintain pressurizer level.
RO:
Verify PZR Level Check PZR Level-DECREASING
Simulator Exercise Guide Job Aid Page 18 of 50 SEG# 2K13 NRC-01 Rev: 0
~-~~~~E-ti&lli::!*'
BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS RO:
Full RO:
Check letdown orifice isolation valves ---
ONLY ONE OPEN At this point, PZR level should be RO:
increasing. The US will transition to RNO. Check PZR level --DECREASING RNO: Proceed to step 1.g.
RO:
Adjust charging flow control valve to maintain PZR level on level setpoint RO:
If desired, place charging line flow controller in AUTO ROorBOP:
Notify Chemistry Request Chemistry perform SP 3861, "Primary to Secondary Leak Rate Determination," to:
- 1) Determine the presence of primary to secondary leakage
- 2) Determine the leak rate
- 3) Identify the leaking SG US: Reads Note to crew:
NOTE SG tube leakage can be interpreted as "verified" when any two of the bulleted substeps of step 3 are satisfied.
Simulator Exercise Guide Job Aid Page 19 of 50 SEG# 2K13 NRC-01 Rev: 0 The crew will satisfy this step by meeting ROorBOP:
multiple bullets (likely all satisfied except Verify Primary To Secondary Leakage Chemistry grab sample is not completed
- Check trend history and alarm status of yet). condenser air ejector radiation monitor---
NOT NORMAL
- Check trend history and alarm status of steam generator blowdown radiation monitor--- NOT NORMAL
- Check trend history and alarm status of main steam line radiation monitors --- NOT NORMAL
- Check Chemistry grab sample
---INDICATES PRESENCE OF PRIMARY TO SECONDARY LEAKAGE
- Check trend history and alarm status of N16 monitors ---NOT NORMAL RO or BOP:
Perform Monitoring Of N16 Monitor Trends
-Initiate monitoring of N16 monitor trends
Simulator Exercise Guide Job Aid Page 20 of 50 SEG# 2K13 NRC-01 Rev: 0 Slowdown will need to be isolated (and I RO:
likely has already auto isolated).
Verify SG Slowdown Status Check if blowdown should be isolated
- Condenser air ejector radiation monitor ---
IN ALARM OR
- Steam generator blowdown radiation monitor--- IN ALARM OR
- Chemistry grab sample indicates primary to secondary leakage--- GREATER THAN OR EQUAL TO 75 gpd OR
- Annunciator N---16 HIGH (MB2B 3---6A) --
-IN ALARM The blowdown isolation valves have likely RO:
automatically closed (depends on speed of Check SG blowdown isolation valves ---
crew thru AOP & progression of leak). CLOSED
- 3BDG---CTV22A
- 3BDG---CTV22B
- 3BDG---CTV22C
- 3BDG---CTV22D Proceed to step 6.
Simulator Exercise Guide Job Aid Page 21 of 50 SEG# 2K13 NRC-01 Rev: 0 As required by NRC Chief, MODIFY The remaining steps in AOP 3576 are not BOP:
TRIGGER 4 (SG01 B) to a severity of 200 critical. Based upon the NRC Chief's input, Limit Effects Of Secondary gpm the scenario may unfold in two possible Contamination ways: Check auxiliary steam ---SUPPLIED FROM (1) The SGTR leak size can be increased MAIN STEAM at this point (will require going back to Step 1) -OR-(2) Alternatively, the leak will continue to ramp in and will likely result in re-performance of Step 1 shortly. The following steps in AOP 3576 are given, in case. this alternative is used.
INSERT TRIGGER 11 when requested. BOP dispatches PEO to:
START OF AUX BOILER Using OP 3331A, "Auxiliary Boiler, Steam and Condensate" Perform the following:
- 1) Startup of auxiliary boiler A (B)
- 2) Shift auxiliary steam from main steam to auxiliarv boiler "'\/darn INSERT TRIGGER 12 when requested. BOP dispatches PEO to:
LOCALLY CLOSE 3CNS-V9 & V11. Locally Close condensate recirculation to condensate surge tank isolation valves (3CNS---V9 and 3CNS---V11)
BOP:
Request HP determine if personnel should be evacuated from affected areas
- Turbine Bldg (north end)
- Secondary sample sink
- MS Valve B Based upon above HP request, the US US:
would make necessary evacuations. Evacuate personnel from affected areas if However, the HP surveys will not be necessary completed yet.
Simulator Exercise Guide Job Aid Page 22 of 50 SEG# 2K13 NRC-01 Rev: 0 FLOOR INSTRUCTOR STUDENTS For this event, the amount of guidance in US:
the C-OP is limited. Reference to the C-OP Refer to C OP 200.11, "Operation of a is still required though. Cross Contaminated System," and Perform uired actions If not already performed, MODIFY The down power is not a required for this ROorBOP:
TRIGGER 4 (SG01 B) to a severity of 200 scenario. The SGTR should be modified to Check If Unit Shutdown Should gpm force a Reactor trip. Be Initiated Check any of the following:
Condenser air ejector radiation monitor ---
IN ALARM OR Chemistry grab sample indicates primary to secondary leakage in any SG ---GREATER THAN OR EQUAL TO 75 gpd OR Condenser air ejector radiation monitor correlation to leak rate (gpd) indicates primary to secondary leakage ---
GREATER THAN OR EQUAL TO 75 gpd OR Annunciator N---16 HIGH (MB2B 3---6A) ---
IN ALARM These steps are a re-performance of Step 1 RO:
"Verify PZR Level" and are required when Verify PZR Level additional charging flow is required to Check PZR Level-DECREASING maintain pressurizer level.
RO:
Full line flow control valve
Simulator Exercise Guide Job Aid Page 23 of 50 SEG# 2K13 NRC-01 Rev: 0 Check letdown orifice isolation valves ---
ONLY ONE OPEN Pressurizer level will be decreasing. 1 RO:
Check PZR level --DECREASING RO:
START second charging pump.
The RNO will be met and the crew will Trip RO:
the Reactor. Verify PZR level - STABLE OR INCREASING RNO:
1.) Trip Reactor 2.) Initiate Sl 3.) Go to E-0
Simulator Exercise Guide Job Aid Page 24 of 50 SEG# 2K13 NRC-01 Rev: 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS Event 6 US:
Notes on failures:
NO TRIGGER NECESSARY Enters E-0 (Rev-27)
(RP1 OAIB; RP9AIB) (1) Event 6: All Reactor Trip switches will be defeated and the BOP will be Event 7 successful using load center switches NO TRIGGER NECESSARY (RP11 F) [Critical Task]. Following the MULTIPLE CHG COMPONENTS FAIL TO successful Reactor Trip, the crew will RE-ALIGN manually initiate Safety Injection.
(2) Event 7: RO may identify multiple Event 8 Charging components failed to re-align NO TRIGGER NECESSARY (RP11 L) early after E-0 immediate actions. RO FEED WATER ISOLATION (FWI) will eventually work to re-align COMPONENTS FAIL TO RE-ALIGN components to achieve minimum safety function. It is a [Critical Task] tore-align CHS pump suctions without cavitating the CHS pumps.
(3) Event 8: BOP will identify FWI components out of position and will re-alian accordi RO is unsuccessful with MB4 Reactor Trip RO:
switch. Verify Reactor Trip Check reactor trip and bypass breakers ---
OPEN Check rod bottom lights ---LIT Check neutron flux ---DECREASING BOP is successful with Reactor trip by BOP:
opening 32B and 32N breakers. TRIP the reactor.
!E reactor will NOT trip, THEN RO will manual actuate Sl after successful Reactor trip. *TRIP Bus 32B AND 32N.
Simulator Exercise Guide Job Aid Page 25 of 50 SEG# 2K13 NRC-01 Rev: 0 BOP:
Verify Turbine Trip Check all turbine stoo valves --- CLOSED BOP:
Verify Power To AC Emergency Busses Check AC emergency busses 34C and 34D
-BOTH ENERGIZED The crew should have manually activated Sl / RO:
per AOP 3576. Check If 51 Is Actuated Verify SAFETY INJECTION ACTUATION annunciator (MB4D 1--6 or MB2B 5--9)---
LIT By observation of ESF Group 2 Status Panel lights, verify both trains of Sl -
ACTUATED Check reactor trip and bypass breakers --- OPEN RO:
Verify Service Water Pumps--- AT LEAST ONE PER TRAIN RUNNING RO:
Verify RPCCW Pumps --- ONE PER TRAIN RUNNING RO should red flag these components 1 RO:
Verify ECCS Pumps Running
- Check Sl pumps ---RUNNING
- Check RHR pumps ---RUNNING
- Check two charaina oumos ---RUNNING
Simulator Exercise Guide Job Aid Page 26 of 50 SEG# 2K13 NRC-01 Rev: 0 BOP should red flag the A & B MDAFW pumps. Verify AFW Pumps Running
- Check MD pumps--- RUNNING
- Check turbine---driven pump --RUNNING, IF NECESSARY BOP: BOP:
The FW isolation trip valves (3FWS*CTV 41 Verify FW Isolation A,B,C & D) did not close (Event 8) and will *Check SG feed regulating valves ---
need to be manually closed. The BOP may CLOSED have already performed this action (allowed by EOP User's Guide). *Check SG feed regulating bypass valves --
CLOSED
- Check FW isolation trip valves --CLOSED
- Check TD FW pumps ---TRIPPED
- Check SG blowdown isolation valves ---
CLOSED
- Check SG blowdown sample isolation valves --- CLOSED
- Check SG chemical feed isolation valves -
--CLOSED
Simulator Exercise Guide Job Aid Page 27 of 50 SEG# 2K13 NRC-01 Rev : 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS MSI is not required. RO:
Check If Main Steam Lines Should Be Isolated Check Ctmt pressure --- GREATER THAN 18 psia OR Any SG pressure ---LESS THAN 660 psig OR Annunciator "MAIN STEAMLINE ISOLATION" (MB2B 5---7)--- LIT Proceed to step 11 .
CDA is not required. RO:
Check If CDA Required Check Ctmt pressure--- GREATER THAN 23 psia OR Annunciator "CONTAINMENT DEPRES ACTUATION" (MB2B S---5)--- LIT Proceed to steo 12.
BOP will have to stop "C" CAR fan. BOP:
Verify CAR Fans Operating In Emergency Mode Check CAR fan status:
- CAR fans A and B ---RUNNING
- CAR fan C --- STOPPED RO:
Verify RPCCW Ctmt supply and return header isolations --- OPEN
Simulator Exercise Guide Job Aid Page 28 of 50 SEG# 2K13 NRC-01 Rev: 0 Verify Train A and B RPCCW supply and return to chill water valves --- OPEN RO: RO:
Event 7 caused several CHS system Verify CIA components to not re-align (simulated Check ESF Group 2, columns 2 through 10 failure of a slave relay). The RO must use ---LIT the ESF status panel to re-align RNO--Initiate CIA.
components accordingly. The RO must lE ESF Group 2, columns 2 complete the realignment and provide, as a through 10 are NOT lit, THEN:
minimum, single valve isolation. Based *Using Attachment A, Reposition valves as upon the lack of safety significance of the necessary for minimum safety function.
penetrations, the only [Critical Task] is to re-align the CHS pump suction valves without cavitating the CHS pumps. The failure criteria will be if a single VCT outlet isolation valve (3CHS*LCV112B OR 3CHS*LCV112C) is fully closed without at least one RWST supply valve (3CHS*LCV112D OR 3CHS*LCV112E) stroking open (dual light indication).
There is no interlock during manual operation to prevent this from occurring.
The expected action would be to fully open at least one RWST supply valve before closina the VCT outlet isolation valves.
RO:
Verify Proper ESF Status Panel Indication
- Verify ESF Group 1 lights ---OFF
- Verify ESF Group 2 lights ---LIT RNO-Aiign component(s) as necessary for minimum safety function.
Simulator Exercise Guide Job Aid Page 29 of 50 SEG# 2K13 NRC-01 Rev: 0 BOOTH INSTRUCTOR STUDENTS Containment will not be adverse. RO:
Determine If ADVERSE CTMT Conditions Exist
- Ctmt temperature ---GREATER THAN 180°F OR
- Ctmt radiation ---GREATER THAN 1 X 10E5 Rlhr RO:
Verify ECCS Flow Check PZR pressure--- GREATER THAN 1900 RO:
Check PORV block valves ---OPEN Proceed to steo 17.
BOP: Notes on 'B' SG level: BOP:
(1) The EOP User's Guide requires the Verify Adequate Heat Sink BOP to ask for US permission to isolate Check NR level in at least one SG ---
feed flow to a ruptured SG. Feed flow GREATER THAN 8% (42% ADVERSE may be isolated once SG level reaches CTMT) 8% NR or 67% WR.
(2) Based on plant conditions (MSIV's open and 'B' SG still supplying steam to the TDAFW Pp ), the 'B' SG will "steam down" level once AFW flow is isolated.
If 'B' SG level goes below 8% NR or 67% WR, the BOP will have to inform the US and re-establish level (this maintains reauired thermal BOP:
Verify Total AFW Flow---
GREATER THAN 530 apm BOP:
Verify AFW Valve Alignment ---PROPER EMERGENCY ALIGNMENT
Simulator Exercise Guide Job Aid Page 30 of 50 SEG# 2K13 NRC-01 Rev: 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS Proper ECCS valve alignment will require RO:
the RO to re-align the failed CHS system Verify ECCS Valve Alignment ---PROPER comoonents. EMERGENCY ALIGNMENT CBI will be actuated based on manual Sl RO: Check If CBI Required actuation. Check annunciator "CONTROL BUILDING ISOLATION" (MB4D 3---6)
--- LIT BOP:
Check Train A Control Building filter fan HVC*FN1A) ---RUNNING 3HVC*AOD119A will be open. BOP:
Check recirc damper for the running Control Building filter fan (3HVC*AOD119A or B)
---OPEN RO:
---LIT Report all SLCRS doors closed. Security is called on the phone.
PEO needs to be dispatched.
Perform the following:
- CLOSE and DOG the following Control Building pressure boundary doors
-CB west 47'6" (C---47---1A)
-CB east 64'6" (C---64---1 B)
- Verify the following Control Building pressure boundary doors---CLOSED
-CB west 47'6" (C-47-1)
-CB north 64'6" chiller room door (C-64-4)
-CB north 64'6" chiller room door (C-64-5)
-CB east 49'6"(C-49-1
Simulator Exercise Guide Job Aid Page 31 of 50 SEG# 2K13 NRC-01 Rev: 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS RCS temperature is currently being BOP:
maintained by the steam dump system. Check RCS Temperature Using GA--26, Dump steam as necessary to control RCS cold leg WR temperature ---
BETWEEN 550°F AND 560°F BOP:
Verify RCS cold leg WR temperature ---
GREATER THAN 550°F Proceed to steo 22.
Bus 34A will be supplying SBO auxiliaries. BOP:
Check Power To SBO Diesel Auxiliaries Verify any SBO bus tie breaker--- CLOSED TO AN ENERGIZED BUS
- Bus 34A: 34A 1---2
- Bus 34B: 34B1---2 Bus 24E: A505 (Unit RO:
Verify PORVs --- CLOSED RO:
normal PZR valves --CLOSED Verify PORV block valves---AT LEAST ONE ENERGIZED VALVE OPEN RO:
valves ---CLOSED RO:
Verify RCS pressure ---LESS THAN 1500 psia (1800 psia ADVERSE CTMT)
Proceed to step 25.
Simulator Exercise Guide Job Aid Page 32 of 50 SEG# 2K13 NRC-01 Rev: 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS All SG secondary boundaries are intact. BOP:
Check If SG Secondary Boundaries Are Intact Check pressure in all SGs ---
- NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
- NO SG COMPLETELY DEPRESSURIZED The Crew will transition to E-3 here based BOP:
upon 'B' SG tube rupture. Check If SG Tubes Are Intact Check steam generator levels --- NO SG LEVEL INCREASING IN AN UNCONTROLLED MANNER Initiate monitoring of CSF Status Trees and Go to E---3, Steam Generator Tube US:
Transitions to E-3 Rev. 24 and reads:
CAUTION To prevent seal damage, seal injection flow should be maintained to all RCPs.
NOTE
- Foldout page must be open.
- The RCP trip criteria is only applicable until a controlled cooldown is initiated in step 6.
RO:
Check If RCPs Should Be Stopped Check RCPs ---ANY RUNNING RO:
Verify RCS pressure ---LESS THAN 1500 psia (1800 psia ADVERSE CTMT}
Proceed to step 2.
Simulator Exercise Guide Job Aid Page 33 of 50 SEG# 2K13 NRC-01 Rev: 0
'B' SG is ruptured. BOP:
Identify Ruptured SGs Unexpected increase in any SG level OR High radiation from any SG steam line as indicated by the trend history or alarm status OR h radiation from US:
Reads Caution to Crew:
CAUTION
- If the TO AFW pump is the only available source of feed flow, a steam supply to the TO AFW pump must be maintained from at least one SG.
BOP:
Isolate Flow From Each Ruptured SG Verify each ruptured SG atmospheric relief valve controller ---IN AUTO AT 1125 BOP:
Check each ruptured SG atmospheric relief valve ---CLOSED BOP:
Check each ruptured SG atmospheric relief bypass valve--- CLOSED
-3MSS*MOV 748
Simulator Exercise Guide Job Aid Page 34 of 50 SEG# 2K13 NRC-01 Rev: 0
,10 .TIME. . LINE**
BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS BOP:
CLOSE each ruptured SG steam supply isolation valve to TD AFW pump
-3MSS*MOV17B BOP:
Verify each ruptured SG blowdown isolation valve ---CLOSED RO:
CLOSE each ruptured SG blowdown samole isolation valve RO:
Verify each ruptured SG chemical feed isolation valve --- CLOSED BOP:
Using table, CLOSE the main steam line drains upstream of MSIVs and TD AFW pump for the ruptured SG(s)
SG B 3DTM*AOV29B 3DTM*AOV61 B 3DTM*AOV63B 3DTM*AOV64B
'B' MSIV will not close. US must implement BOP:
RNO column. CLOSE each ruptured SG MSIV and MSIV bypass valve BOP:
RNO--Perform the following:
CLOSE all remaining SG MSIVs and MSIV bvoass valves.
Switches are labeled: BOP:
- INTLK-TRA RNO--Piace both condenser steam dump
- INTLK-TRB interlock selectors--- OFF
Simulator Exercise Guide Job Aid Page 35 of 50 SEG# 2K13 NRC-01 Rev: 0 RNO--Ciose all valves listed on Attachment A.
BOP will have to use the Atmospheric RNO--Use the intact SG atmospheric relief Relief Valves for upcoming cooldown steps. valves to dump steam, for RCS temperature control or cool down.
The transition to ECA-3.1 will not be BOP:
necessary. RNO--lE any ruptured SG can NOT be isolated from at least one intact SG, THEN Go to ECA---3.1, SGTR with Loss of Reactor Coolant --- Subcooled Recovery Desired.
US:
Reads Caution to Crew:
CAUTION If any ruptured SG is faulted, feed flow to that SG should remain isolated during subsequent recovery actions unless the SG is needed for RCS cooldown.
BOP:
Check Ruptured SG Level Verify one of the following is satisfied:
- Ruptured SG NR level--- GREATER THAN 8% (42% ADVERSE BOP should complete two valve isolation of BOP:
the 'B' SG by closing: Stop feed flow to ruptured SG(s)
- 3FWA*MOV35B
- 3FWA*HIC36B1 (Note: both FWA*HIC31B1 &
3FWA*HIC32B2 were closed earlier.
Simulator Exercise Guide Job Aid Page 36 of 50 SEG# 2K13 NRC-01 Rev: 0 FLOOR INSTRUCTOR STUDENTS US:
Reads Caution to Crew:
CAUTION: Major steam flow paths from the ruptured SG(s) must be isolated prior to RCS cooldown. Major flow paths include the main steam line, TD AFW pump steam supply, and SG atmospheric relief and lines.
Check Ruptured SGs Pressure ---
GREATER THAN 530 During the upcoming RCS depressurization US: Reads Note to Crew:
the crew must remember the 2nd bulleted NOTE note and block the "Low Steam Line *If RCPs are NOT running, the following Pressure Sl" signal when RCS is < 2000 steps may cause a false entry into the psi a. INTEGRITY Status Tree for the affected loop. Disregard the affected loop Tc indication until after performance of step 27.
- Ensure Low Steam Line Pressure Sl is blocked when PZR pressure is LESS THAN 2000 RO:
Initiate RCS Cooldown Check RCPs ---ANY RUNNING INSERT TRIGGER 13 when requested PEO will need to be dispatched. RO:
(RCR 23, 24, 25, 26) Locally, Place the eight RCP overcurrent RCP HOT/COLD SWITCHES trip switches (43PP and 43PB) in the COLD CO Kev Locker Kev #7 Ensure US selects temperature that correlates with lowest pressure (no Determine required core exit temperature without interpolating (use lower pressure)
The A, C, and D Atmospheric Relief Valves BOP:
or Atmospheric Relief Bypass Valves will be Using GA---26, Dump steam from intact used. Also, the BOP should max feed SGs at maximum rate these SGs.
Simulator Exercise Guide Job Aid Page 37 of 50 SEG# 2K13 NRC-01 Rev: 0 Verify core exit TCs --- LESS THAN REQUIRED TEMPERATURE BOP: BOP:
It is a [Critical Task] that subcooling is Using GA---26, Perform the following:
maintained less than the required 1) Stop RCS cooldown temperature. 2) Maintain core exit TCs ---LESS THAN REQUIRED TEMPERATURE US:
Reads Note to Crew:
NOTE To aid in identifying previously undetected steam generator tube failures, the wide range SG level indication should be used if the narrow ranae level is off scale.
BOP:
Check Intact SG Levels
- Verify NR level ---GREATER THAN 8%
(42% ADVERSE CTMT)
- Control feed flow to maintain NR level---
BETWEEN 30% and 50% (42% and 50%
ADVERSE CTM US:
Reads Caution to Crew:
CAUTION: If any PZR PORV opens because of high PZR pressure, step B.a.
should be repeated after pressure decreases to LESS THAN 2350 RO:
Check PZR PORVs And Block Valves Verifv PORVs ---CLOSED RO:
Verify block valves--- AT LEAST ONE OPEN
Simulator Exercise Guide Job Aid Page 38 of 50 SEG# 2K13 NRC-01 Rev: 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS US:
Reads Caution to Crew:
CAUTION: After Sl reset, manual operator action is required to:
- Open the charging pump cold leg injection valves when RCS pressure decreases to LESS THAN 1900 psia.
- Restart safeguards equipment if offsite power is lost.
Sl and CIA will need to be reset. RO:
Reset ESF Actuation Signals If Required RESET Sl RESET the following:
- CDA
- LOP
- CIA
- CIB The 'A' lAS compressor will be running. RO:
However, the instrument air containment isolation valves will need to be opened. Establish Instrument Air To Ctmt
- Check instrument air compressors ---
AT LEAST ONE RUNNING
- OPEN instrument air Ctmt isolation valves RO or BOP:
Restore MCC 32---3T Check emergency bus 34C --- ENERGIZED INSERT TRIGGER 14 when requested to I RO or BOP dispatch PEO. Using GA---1, Energize MCC 32---3T re-energize 32-3T
Simulator Exercise Guide Job Aid Page 39 of 50 SEG# 2K13 NRC-01 Rev: 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS US:
Reads Caution to Crew:
CAUTION: To provide adequate ECCS flow, RCS pressure should be monitored to ensure the RHR pumps are manually restarted if pressure decreases in an uncontrolled manner to LESS THAN 300 ia ADVERSE CT RO:
Check If RHR Pumps Should Be Stopped
- Check RHR pumps--- ANY RUNNING IN Sl MODE
- STOP RHR oumos and Place in AUTO BOP: BOP:
It is a [Critical Task] that subcooling is Check If Cooldown Should Be maintained less than the required Stopped temperature. *Check RCS Cooldown ---IN PROGRESS
- Check core exit TCs ---LESS THAN NOTE: This is a HOLD step in the REQUIRED TEMPERATURE procedure. *Using GA---26, Perform the following:
- 1) Stop RCS cooldown
relatively stable-the RNO will not be met. Check Ruptured SG(s) Pressure ---
STABLE OR INCREASING RO:
Check RCS Subcooling Based On Core Exit TCs ---GREATER THAN 52°F 35°F ADVERSE
Simulator Exercise Guide Job Aid Page 40 of 50 SEG# 2K13 NRC-01 Rev: 0 STUDENTS The RO will open 3RCS*PK455B & Depressurize RCS To Minimize Break 3RCS*PK455C. The crew will need to Flow And Refill PZR block 'La pressurizer pressure Sl' below *Check normal PZR spray --AVAILABLE 2,000 psia (per previous note).
- Spray PZR with maximum available spray RO:
Check any of the following depressurization termination conditions satisfied:
- RCS pressure --- LESS THAN ruptured SGs pressure AND PZR level is GREATER THAN 16% (50% ADVERSE CTMT) OR
- PZR level---GREATER THAN 73%
- RCS subcooling based on core exit TCs ---
LESS THAN 32°F (115°F ADVERSE
Simulator Exercise Guide Job Aid Page 41 of 50 SEG# 2K13 NRC-01 Rev: 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS All critical tasks have been completed. The RO:
NRC Chief Examiner may end the scenario Check depressurizing using ---NORMAL now or continue to run. PZR SPRAY
- Close normal PZR spray valve(s)
- Proceed to CAUTION prior to step 19.
US:
Reads Caution to Crew:
CAUTION: Sl MUST be terminated when the criteria are satisfied to prevent overfilling of the ruptured SG(s). Voiding in the upper head region should NOT preclude Sl termination.
RO:
Check If ECCS Flow Should Be Terminated Verify RCS subcooling based on core exit TCs ---GREATER THAN 32°F (115°F ADVERSE CTMT)
BOP:
Verify secondary heat sink:
- Narrow range level in at least one intact SG ---GREATER THAN 8% (42%
ADVERSE CT RO:
Verify RCS pressure --- STABLE OR INCREASING RO:
Verify PZR level---GREATER THAN 16%
%ADVERSE
Simulator Exercise Guide Job Aid Page 42 of 50 SEG# 2K13 NRC-01 Rev: 0 RO:
Stop ECCS Pumps
- STOP Sl pumps and place in AUTO
- STOP all but one charging pump and place in AUTO RO:
Establish Normal Charging Flow Path Fullv Ooen charaina line flow control valve RO:
Verify charging loop isolation valves (3CHS*AV8146 or 3CHS*AV8147) ---ONE OPEN RO:
OPEN charging isolation valves
- 3CHS*MV81 06
- 3CHS*MV8105 RO:
CLOSE the charging pump miniflow isolations to the RWST
- 3CHS*MV8511A
- 3CHS*MV8511 B RO:
CLOSE both charging pump cold leg injection valves
- 3SIH*MV8801A
- 3SIH*MV8801 B RO:
OPEN the charging pump recirculation isolation valves
- 3CHS*MV8111 A
- 3CHS*MV8111 B
- 3CHS*MV8111 C
- 3CHS*MV811 0
Simulator Exercise Guide Job Aid Page 43 of 50 SEG# 2K13 NRC-01 Rev: 0 BOOTH INSTRUCTOR RO:
Control Charging Flow To Maintain PZR Level RO:
Verify Adequate RCS Depressurization
- Check normal PZR spray -AVAILABLE
- Depressurize RCS using maximum normal PZR RO:
Check any of the following depressurization termination conditions satisfied:
- PZR level- GREATER THAN 73%
RO:
urization RO:
Verify ECCS Flow Not Required
- Check PZR level- GREATER THAN 16%
RO:
Check If Letdown Can Be Established Verify PZR level---GREATER THAN 25%
ADVERSE RO:
Perform the following:
- Verify Train A RPCCW pump ---RUNNING
- Using GA---13, Establish normal letdown Proceed to step 26.
Simulator Exercise Guide Job Aid Page 44 of 50 SEG# 2K13 NRC-01 Rev: 0 RO:
Check RCS Makeup System
- Adjust boric acid flow controller to pot setting 8.3
- Check RCS makeup ---ALIGNED FOR AUTO RO:
Align Charging Pump Suction To VCT OPEN VCT to charging isolation valves
- 3CHS*LCV112B
- 3CHS*LCV112C RO:
CLOSE RWST to charging isolation valves
- 3CHS*LCV112D
- 3CHS*LCV112E RO:
Check If Sl Accumulators Should Be Isolated Check RCS pressure --- LESS THAN 850 psi a---
Proceed to CAUTION prior to step 29. and, WHEN RCS pressure is LESS THAN 850 psia, THEN Perform steps 28.b. and 28.c US:
Reads Caution to Crew:
CAUTION: RCS and ruptured SG(s) pressures must be maintained LESS THAN the ruptured SG(s) atmospheric relief valve setpoint
Simulator Exercise Guide Job Aid Page 45 of 50 SEG# 2K13 NRC-01 Rev: 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS See table at the bottom of the page. I RO:
- 29. Control RCS Pressure And Charging Flow To Minimize RCS---To---Secondary Leakage Perform appropriate actions from table The scenario may be ended. *Depressurize using normal PZR spray as determined in step 29.a.
- IF normal letdown is in service, THEN Using GA---28, depressurize using auxiliary spray.
lE auxiliary spray is NOT available, THEN one PORV.
Simulator Exercise Guide Job Aid Pa e 46 of 50 SEG# 2K13 NRC-01 Rev : 0 SECTION 4 EXAM GUIDE
SUMMARY
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 II. Critical Tasks TASK DESCRIPTION TASK# KIA>/= 3.0 BASIS SELECTION Manually trip the reactor E-0 --A 012 A4.07 Failure to manually trip the from the control room (3.9* I 3.9*) reactor causes a challenge with either Main board to the subcriticality CSF trip switch or by opening beyond that irreparably 328 and 32N supply introduced by the postulated breakers before conditions.
completing Step 1 of E-O.
Following a postulated 103 A3.01 Failure to properly re-align slave relay failure, (3.9 I 4.2) CHS pump suctions under properly re-align CHS the postulated conditions, pump suction to the would damage both RWST without cavitating Charging pumps. This I damaging the constitutes a reduction in operating CHS pumps. safety margin.
Properly select and E-3--B EPE 038 Failure to achieve RCS maintain the target EA1.36 subcooling transitions the temperature for crew to contingency (4.3 I 4.5) cooldown based on the procedure ECA-3.1, thereby chart in E-3. delaying the RCS depressurization and Sl termination. Such a delay may lead to SG overfill.
Simulator Exercise Guide Job Aid Page 47 of 50 SEG# 2K13 NRC-01 Rev : 0 1 Rx Power: 100%
Thermal: 3645 MWTH PZR Pressure: 2250 psia Electric: 1280 MWe RCS T-AVE: lll~degF RCS Leakage: Identified: 0.078 gpm Core Burnup: 150 MWDIMTU Unidentified: 0.108 gpm Protected Train/Facility:
Intake:
Time in LCO Action Requirement Time Left OD Compensatory Actions I Temp Logs Watch Open Date Class Reason Reason Position PLANT SYSTEMS APC System Notes Auto Rod Rods are in Manual with yet to "ONLY OPERATE IN MANUAL" as I&C is repairing tavg I tref Control circuit. Rods remain operable in this configuration as they operate in Manual and are Trippable.
'C' CCP 'C' CCP HX is tagged out I drained to repair a tube leak. Both trains of 'C' CCP pump control switches are tagged out of service.
CROSS UNIT SYSTEM STATUS U3 Power to 24E 1 34A aligned to 24E SURVEILLANCES I EVOLUTIONS IN PROGRESS 1 Steady State Operation REACTIVITY BRIEFING (SEE REACTIVITY THUMBRULES I SPREAD SHEET FOR ADDITIONAL INFO)
Current Rod Height CBD@ 216 steps Xenon Trend stable Current Boron 1376 ppm Boron Pot Setting I Blend Ratio 3.93 I 15.7 gpm
Simulator Exercise Guide Job Aid Page 48 of 50
<:;EG# 2K13 NRC-01 Rev: 0 ATTACHMENT 2 VALIDATION CHECKLIST
Title:
'B' SG Tube Rupture ID Number: 2K13 NRC-01 Revision: Q Verified By:
(Initials)
Initial Conditions:
The initial condition(s) contained in the guide are certified or have WMF been developed from certified ICs.
Test Run:
The scenario contained in the guide has been test run in part or WMF
'hole on the simulator. The simulator response is reasonable and as expected. If a simulator guide revision does not affect original Test Run, then enter N/A.
Simulator Operating Limits:
The simulator guide has been evaluated for operating limits and/or WMF anomalous response by reviewing the Simulator Modeling and Anomalous Response List.
For Examination Scenario:
The Scenario Attributes Checklist is complete and attached. This is WMF not required for Progress Review Exams.
William M. Forrestt 9/6/13 Actions Complete (Signature) Date
Simulator Exercise Guide Job Aid Page 49 of 50 SEG# 2K13 NRC-01 Rev: 0 REVISION 1 Facility: Millstone 3 Scenario No.: 2K13 NRC-01 (Rev Ol Op-Test No.: 2K13 Examiners: Operators:
Initial Conditions: IC-13, 100% Power, Beginning of Life, Eguilibrium Xenon Turnover:
The Plant is stable at 100% Power. 'C' CCP heat exchanger is tagged out for tube leak regair. Control Rods are in manual for regair of auto circuit[Y (which is not functional due to Tavg I Tref circuit card failure).
Event Malf. Event Event No. No Type* Description 1 - us TIS 'B' EDG INOP based on field report of an empty governor sightglass 2 RX09A RO I Controlling channel of pressurizer pressure fails high us TIS (AOP 3571).
3 FW16A RO R 'A' Heater Drain Pump trips requiring a 7% downpower.
BOP c us R 4 CV05 RO c Letdown pressure transmitter, PT-131, fails to intermediate value below setpoint 5 SG01B RO M 'B' SG has a tube leak that develops into a 200 gpm MS12B BOP M tube rupture. Crew trips Reactor and ultimately mitigates using E-3, SG Tube Rupture. 'B' MSIV fails us M to close complicating E-3 recovery.
6 RP10A/B BOP c Automatic and manual Reactor trip switches fail. BOP RP9A/B is successful using load center switches.
7 RP11F RO c Multiple Charging components fail to re-align.
8 RP11L BOP c Feed Water Isolation (FWI) components fail to re-align.
- (N)ormal, ( R)eactivity, (l)nstrument, (C)om ponent, (M)ajor
Simulator Exercise Guide Job Aid Page 50 of 50
">EG# 2K13 NRC-01 Rev: 0 QUALITATIVE ATTRIBUTES
_Y_1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.
- y-2. The scenario consists mostly of related events.
_Y_3. Each event description consists of:
the point in the scenario when it is to be initiated the malfunctions(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)
_Y_4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
_Y_5. The events are valid with regard to physics and thermodynamics.
_Y_6. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.
_N/A_7. If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.
_Y_8. The simulator modeling is not altered.
_Y_9. The scenario has been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure functional fidelity is maintained while running the planned scenario.
_Y_10. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered lAW Section D.5 of ES-301.
_Y_11. All individual operator competencies can be evaluated, as verified using form ES-301-6.
_Y_12. Each operator will be significantly involved in the minimum number of transients and events specified on Form ES-301-5.
_Y_13. Level of difficulty is appropriate to support licensing decisions for each crew position
'ITE: l MP3 I PROGRAM: ILT PROGRAM No.
LESSON TITLE: LOCA Outside Containment I LESSON #: 2K13 NRC-02 Total Time 90 minutes Prepared by: William M. Forrestt fL- /'- (2:J 9/27/13 Printed Name Developer Signature Date Reviewed by: Bob Royce Printed Name
/AI~
Validati 1gnature
? /LJ!IJ Date Approved by: Paul Scott ~ I 1
q z::r*/t~
Printed Name ~upervisor Date Approved by: Trad Horner lc*/13 Printed Name Training Supervisor bate
Simulator Exercise Guide Job Aid Page 2 of 51 SEG# 2K13 NRC-02 Rev ; 0 All & DATE DESCRIPTION REV/CHANGE
SECTION 2 SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER
- 1. Cover Page
- 2. Table of Contents
- 3. Exercise/Exam Overview
- 4. Exam Guide Attachments:
Shift Turnover Report Validation Checklist Scenario Outline (ES-D-1)
Attributes Checklist
Simulator Exercise Guide Job Aid Page 4 of 51 SEG# 2K13 NRC-02 Rev; 0 SECTION 3 EXAM OVERVIEW
Title:
LOCA Outside Containment ID Number: 2K13 NRC-02
- 1. The crew will take the shift with reactor power at 74%. The plant is being returned to service following a refueling outage. The crew is to stabilize reactor power at 74% while Reactor Engineering performs EN 31015 "Power Ascension Testing of Millstone Unit 3". Additionally, the 'A' SIH pump was taken out of service one hour ago to repair a newly discovered oil leak.
The scenario will start with a power range nuclear instrument, N41, failing high. This will cause control rods to insert in auto. The RO will place rod control in manual and the crew will carry out action of AOP 3571, Instrument Failure Response.
Once the associated bistables are tripped, the controlling 'B' SG Feed flow instrument will fail high. This will require manual control of the 'B' Feed Reg Valve and re-entry into AOP 3571.
Next, CONVEX calls and requests an emergency load reduction. The crew will carry out actions using AOP 575, Rapid Downpower.
During the downpower, the 'A' RCP develops an oil leak as evidenced by MB alarms and computer point bearing temperatures rising at a moderate rate. The crew enters AOP 3575, Rapid Downpower, and lowers Reactor Power below P-8 (50%) at 5% per minute to allow for pump removal. Once below P-8, the crew stops
'A' RCP in accordance with AOP 3554, RCP Trip or Stopping a RCP at Power.
Shortly after 'A' RCP is stopped, a spurious 'A' train Safety Injection (SI) is caused from a tin whisker on a MSI card (MP3 OE 20450). The tin whisker causes only 'A' train Sl to actuate and a partial MSI actuation. Due to automatic reactor trip circuitry being defeated, the crew must manually trip the reactor [Critical Task] and manually actuate Sl and MSI. The spurious, auto start of ECCS equipment will generate an intersystem LOCA into the 'A' RHR system and out a break into the ESF building.
The crew will carry out actions in E-0, Reactor Trip or Safety Injection. The crew will need to identify and correct Component Cooling Water valves out of position and manually start the 'A' EDG.
After transition to ECA-1.2, LOCA Outside Containment, the crew will need to correctly diagnose that closure of 3SIL *MV8809A has successfully isolated the leak [Critical Task]. After making this diagnosis, the crew will transition to E-1, Loss of Reactor or Secondary Coolant. The scenario may end at this point.
- 2. The SRO candidate (US) should classify this event as an Site Area Emergency based on the loss of Containment and RCS barriers.
- 3. Duration of Exam: 90 minutes
Simulator Exercise Guide Job Aid Page 5 of 51 SEG# 2K13 NRC-02 Rev; 0 SECTION 4 EXAM GUIDE
Title:
LOCA Outside Containment ID Number: 2K13 NRC-02 All Control Room Conduct, Operations and Communications shall be in accordance with OP-AA-100, Conduct of Operations.
"Review the Simulator Operating Limits (design limits of plant) and the Simulator Modeling
'.imitations and Anomalous Response List prior to performing this exam scenario on the
.:iimulator. The evaluators should be aware if any of these limitations may be exceeded."
(NSEM 6.06)
Simulator Exercise Guide SEG# 2K13 NRC-02 Rev; 0 Event I Delay I Ramp I Delete I Severity ID I Description 1Trigger Time Time Time Or Value MALFUNCTIONS NI09A PR N41 B LO DET FAIL 1 0 0 5MAMP RX13C SG FD FLOW FT520 FAIL 2 0 20 sec 5E6 LBM I HR RC12A RCPA OIL LEAK UPR RSVR 3 0 0 100 RP05A SAFETY INJECTION TRAIN A ACTUATION 4 0 0 RP10A AUTOMATIC REACTOR TRIP TRAIN A FAIL 0 0 RP10B AUTOMATIC REACTOR TRIP TRAIN B FAIL 0 0 MB4E-E05 STEAM LINE PRESSURE LO ISOL Sl 4 0 0 ON MB4E-F05 MANUAL SAFETY INJECTION 4 0 0 ON MB2B-E07 MAIN STEAM LINE ISOLATION 4 0 0 ON RP11H AUTO ACT FAIL: RPCCW 30 0 0 I I SI06C RCS TO Sl LOCA (ISOLABLE) UPSTRM MV8809A 30 0 0 I 1300 GPM EG13A EDG A AUTO START FAILURE 4 0 0 I I FW01 I LOWERING CONDENSER VACUUM 11 5 min 0 I !200 cfm REMOTE FUNCTIONS
Simulator Exercise Guide Job Aid Page 7 of 51 SEG# 2K13 NRC-02 Rev; 0 Event I Delay I Ramp I Delete Severity ID Description Trigger Time Time Time Or Value OVERRIDES MSDI0023 3MSS*CTV27A SG 1 MSIV 4 0 0 CLOSE MSDI0024 3MSS*CTV27B SG 2 MSIV 4 0 0 CLOSE MSDI0025 3MSS*CTV27C SG 3 MSIV 4 0 0 CLOSE MSDI0026 3MSS*CTV27D SG 4 MSIV 4 0 0 CLOSE RXR106, N41 BISTABLES AND DOOR 10 0-40 0 Bistables to TRIP RXR05, sec Door open/ close RXR34
Simulator Exercise Guide Job Aid Page 8 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS o COMPLETE Simulator Setup and Readiness Checklist. I NIA o SELECT appropriate IC o LOAD and RUN applicable Schedule.
o As necessary, ENTER or VERIFY the following Initial Malfunctions I IIOs I Remote Functions, OR, as specified on previous 'Input Summary' page:
o As necessary, PERFORM verification of Initial Malfunctions I IIOs I Remote Functions entered.
o When the simulator is ready, PLACE to Run and VERIFY the simulator reflects the following Initial Conditions for the scenario and is stable:
o As necessary, REMOVE the following Equipment from service and tag accordingly:
- PLACE 'A' SIH Pp in PTL and YCT control switch o CONDUCT briefing with evaluators. PRE-SCENARIO: NIA o BRIEF the crew initial plant conditions and provide a shift turnover.
o lE this is the first simulator scenario of the week, REVIEW the Plant/Simulator Differences List and Simulator Training Objectives with the crew.
o As necessary, REVIEW any scenario specific differences and any planned simulator freeze points.
(All) Walk down control boards and conduct shift briefing.
Simulator Exercise Guide Job Aid Page 9 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS Event 1 INSERT TRIGGER 1 (N1 09A)
POWER RANGE INSTU, N41, FAILS HIGH i
Notes on failure: RO: *
(1) This failure will cause rods to insert. Recognizes PR CH.1 Nl failing high, control (2) The expected Operator response is to rods auto inserting, and PLACES ROD place rods in manual after verifying no CONTROL in MANUAL after verifying no runback in progress (checks MWe runback (MWe stable).
meter on MB4 stable).
US:
Enters AOP 3571 (Rev 09-07) after plant is stable and reads:
CAUTION: Do not leave the rod selector switch in AUTO while diagnosing a related instrument failure unless the reason for rod movement is a turbine runback.
NOTE If a reactor trip occurs immediately go to E-0, Reactor Trip or Safety Injection.
Rod Control is the only affected controller. RO:
Determine The Initiating Parameter And Place The Affected Controller In MANUAL RO:
Stabilize The Plant Parameters US: Reads Note to crew:
NOTE It is desired that I&C personnel trip the bistables specified in this procedure. If, during off-hours, I&C personnel are not able to trip the necessary bistables within the time limitations required by the Technical Specifications, Operations Department personnel may trip the bistables using the guidance provided within this procedure.
Simulator Exercise Guide Job Aid Page 10 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS US:
Perform Corrective Actions Using Appropriate Attachment Power Range Nuclear Instrument Channel Failure-Attachment D US: Reads Caution to crew:
CAUTION:
- Failure of two or more channels of PR instrumentation may prevent P-1 0 from resetting when power is reduced below 10%. If P-10 fails to reset, the following automatic reactor trip signals are lost:
- 1) SR HIGH FLUX TRIP (10 5 CPS)
- 2) IR HIGH FLUX TRIP (25%)
- 3) PR HIGH FLUX LOW STPT TRIP (25%)
- The reactor operator must remain alert to any power increases which would necessitate a manual reactor trip.
- The Gamma Metrics Nuclear Instrumentation System shall be used during the reactor shutdown in lieu of the source range channels.
The crew should discuss expected plant RO:
response. The following alarms are Defeat the failed channel input.
expected to clear when N41 is selected on At the detector current comparator drawer, the switches below: Turn the following switches to Rod Stop Bypass- MB4C 5-7 the failed channel:
Upper Section- No alarms clear Rod Stop Bypass Lower Section- MB4C 6-3 Upper Section Power Mismatch Bypass- No alarms clear Lower Section Power Mismatch Bypass
Simulator Exercise Guide Job Aid Page 11 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS The crew should discuss expected plant RO:
response. The following alarm will clear At the comparator and rate drawer, Turn when N41 is selected: MB4C 3-3. the following switch to the failed channel:
Comparator Channel Defeat US: Reads Note to crew:
NOTE Defeating the failed channel will remove it from the rod control_circuit and may create an artificial primary to secondary power rate of change signal to rod control. Placing rod control in automatic, prior to the signal dissipating, may result in rod motion.
RO:
Restore TAVE - TREF error to within 1oF and Place rod control in automatic.
US: Reads Note to crew:
NOTE If the plant calorimetric source is Nl's, the failure of one Nl channel will disable the calorimetric program.
RO & BOP:
When conditions have stabilized, Observe MB board annunciators and parameters and immediately report any unexpected or unexplained conditions to the Shift Manager.
US should check the box for Channel 'N41' US:
Trip the associated Reactor Protection System bistable(s):
Place a check mark in the box above the appropriate channel that requires tripping on page 6 or 7 of this Attachment.
US enters LCO 3.3.1 (FU2). This is a 6 US:
hour action statement to trip bistables. Refer to Technical Specification 3.3.1.
Simulator Exercise Guide Job Aid Page 12 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS RO:
Check the existing bistable status to ensure a reactor trip will not occur when the failed channel is tripped.
US: Reads Caution I Note to crew:
CAUTION: If the General Warning lamp is lit on 3RPS*RAKLOGB, placing the train A SSPS "Multiplexer Test" switch in "A+B" will cause the reactor to trip.
NOTE: The following step will distinguish whether the failure is within SSPS or the Protection channel.
US determines this step is not applicable as US:
the instrument channel has failed. If bistable status light{s) (MB4F or MB4G) indicate that a single bistable input has tripped and channel indication is normal, perform the following:
After I&C brief, INSERT TRIGGER 10 to When requested, report to the Control US:
trip bistables Room as I&C. Request the I&C Department trip the appropriate bistables using Attachment D and Attachment S.
RO:
Verify the appropriate bistable status light(s) are lit.
All are determined to be in required state US:
(P-7, P-8, & P-9 are off and P-10 is lit). No Within one hour, Determine by observation TIS entry is necessary. of the associated permissive annunciator window(s) that the following interlocks are in their required state for the existing plant condition {Tech. Spec. 3.3.1, Action 8):
- RX OR TURBINE NOT AT POWER P-7 (MB4D 5-3) ..... continued next page ...
Simulator Exercise Guide Job Aid Page 13 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS
- THREE LOOP PERMISSIVE P-8 (MB4D 3-3)
- NIS POWER RANGE P-9 PERMISSIVE (MB4D 6-1)
- REACTOR AT POWER P-10 (MB4D 4-3)
US: Reads Note to crew:
NOTE
- The following step for removing the failed PR channel from Program 3R5 restores OPERABILITY to the AFD Monitor Alarm and must be completed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or SURVEILLANCE REQUIREMENT 4.2.1.1.1.b. must be performed.
- The following step for removing the failed PR channel from Program 3R5 does NOT restore OPERABILITY to the QPTR Alarm Monitor; therefore, TABLE 3.3-1, ACTION 2.c., and SURVEILLANCE REQUIREMENTS 4.2.4.1.b, and 4.2.4.2 are in effect.
RO:
Perform the following to remove the affected power range input to the AFD and QPTR monitor alarm (Program 3R5) :
- a. Using PPC display "TILT_CHANNEL,"
Press the button that corresponds to the channel to be removed.
- b. Press "Apply" button to remove channel input.
US:
Refer to the following Technical Specifications and Perform any required actions:
- Surveillance Requirement 4.2.1.1.1.b.
- TABLE 3.3-1, ACTION 2.c.
- Surveillance Requirement 4.2.4.1.b.
- Surveillance Requirement 4.2.4.2 I
Simulator Exercise Guide Job Aid Page 14 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS ROorBOP:
Request I&C Department perform corrective maintenance on failed instrument.
Event 2 Notes on failure: BOP:
INSERT TRIGGER 2 (RX13C) (1) The only affected controller is the 'B' SG Recognizes 'B' SG feed flow instrument CONTROLLING 'B' SG FEED FLOW Feed Reg Valve. This valve will failed high, takes manual control of 'B' feed CHANNEL FAILS HIGH modulate closed by the failure. reg valve, and maintains 'B' SG level.
US: Enters AOP 3571 (Rev 09-07) after plant is stable and reads:
CAUTION: Do not leave the rod selector switch in AUTO while diagnosing a related instrument failure unless the reason for rod movement is a turbine runback.
NOTE If a reactor trip occurs immediately go to E-0, Reactor Trip or Safety Injection.
'B' Feed Reg Valve should be in manual. BOP:
Determine The Initiating Parameter And Place The Affected Controller In MANUAL BOP:
Stabilize The Plant Parameters US: Reads Note to crew:
NOTE It is desired that I&C personnel trip the bistables specified in this procedure. If, during off-hours, I&C personnel are not able to trip the necessary bistables within the time limitations required by the Technical Specifications, Operations Department personnel may trip the bistables using the guidance provided within this procedure.
US:
Perform Corrective Actions Using Appropriate Attachment Feed Flow Channel Failure Attachment L
Simulator Exercise Guide Job Aid Page 15 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS
'B' Feed Reg Valve should already be in BOP:
manual. If the failed feed flow channel is selected as the input to SG level control, Perform the following:
Verify the affected SG feed regulating valve controller is in MANUAL.
Normal level setpoint is 50% Narrow BOP:
Range. Restore SG level to normal.
Crew should discuss expected response (to BOP:
include: MB5 recorder coming on scale & Defeat the failed channel input by selecting annunciator MB5B 5-3 will clear. the alternate channel on the feed flow selector.
BOP:
When SG level is restored to normal and feed/steam flow are matched, Place the affected steam generator feed regulating valve controller in AUTO.
US: Reads Note to crew:
NOTE
- There are no Technical Specifications or bistables to be tripped associated with the feed flow instruments.
- When the plant calorimetric is based on feed flow, the program will automatically shift to an Nl based output if any feed flow channel is X-tagged by the process computer.
RO & BOP:
When conditions have stabilized, Observe MB annunciators and parameters.
Immediately report any unexpected or unexplained conditions to the Shift IYI~n_ager.
Simulator Exercise Guide Job Aid Page 16 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS I I
RO or BOP:
Request I&C Department perform corrective maintenance on failed instrument.
Event 3 When the eventual alarm comes in for US:
CONVEX REQUESTED DOWNPOWER Event 4 (RCP oil leak), expected operator Briefs crew on CONVEX requested TO 460 MWE (-45% Rx Power) action may be found under Event 4 (later in downpower and enters AOP 3575 (Rev 18) guide). and Reads the following Note:
Call as CONVEX and report "You are required to perform an NOTE emergency load reduction to 460 If at any time either of the following MWelectric". annunciators is received, Immediately perform step 7.:
INSERT TRIGGER 3* (RC12A) *ROD CONTROL BANKS LIMIT LO (MB4C RCP A OIL LEAK UPR RSVR 3---9)
- Once Trigger 3 is inserted (for Event 4 ), it *ROD CONTROL BANKS LIMIT LO---LO will take 12 minutes to cause MB alarm. (MB4C 4---9)
Inputting Trigger 3 now will avoid future delay for Event 4.
RO:
Check Rod Control --- IN AUTO Load set is normally desired (as it doesn't BOP:
require BOP to manually lower turbine Align EHC Panel load). a. Check load reduction using load set ---
DESIRED
- b. Using Attachment E align EHC panel for LOAD SET operation US recognizes need to perform a 5%/min US: Reads Note to crew:
down power. NOTE ISO---NE requested load reductions should be performed at 5%/min and completed within 25 minutes of notification.
Simulator Exercise Guide Job Aid Page 17 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS US selects 5%. US:
Determine Power Reduction Rate
(%I min)
- a. Check desired power reduction rate---
3%/min OR 5%/MIN US: Reads Caution to crew:
CAUTION: If Sl actuation occurs during this procedure, go to E---0, Reactor Trip or Safety Injection and restore from rapid boration lineup.
I RO:
I Initiate Rapid Boration Verify RCS makeup system in --- AUTO RO:
START one boric acid transfer pump RO:
OPEN emergency boration valve (3CHS*MV8104) and Verify direct boric acid flow (3CHS---FI 183A) --- INDICATED RO:
OPEN charging line flow control valve, to match indicated boric acid flow (3CHS---FI 183A)
RO; Record time boration started Time RO:
Check Rod Control---AVAILABLE FOR ROD INSERTION
Simulator Exercise Guide Job Aid Page 18 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS US will use RNO. RE has built rapid RO:
reactivity plans (Rapid Downpower Check use of "Rapid Down power Summary Summary Sheets); however, they all begin Sheet" (RE---H---17) in the RE Curve and at 100% power. Data Book--- DESIRED RNO Proceed To step 4.k.
RO:
Use 18 gal BN% Power to determine boration time in step 4.1.
Numbers may vary slightly .... RO:
Using formula, Determine boration time (If 29 (power change) x 18 (gal per % pwr) gravity berating, use net charging flow (chg
+seal inj---seal return total flow) for BA flow 80 (expectant flow rate) rate:
Total Power Change (.6%) X EQUALS 6.5 minutes (gaiBN%Power)/BA Flow Rate=- -min/Boration Time Proceed to step 6.
US: Reads Note to crew:
NOTE If at any time the power reduction rate or final desired power level must be changed, Return to step 1.
RO:
Initiate Load Reduction Check Rapid or gravity boration --- IN PROGRESS BOP:
Check turbine OPERATING MODE---
MANUAL US:
Check load reduction using load set ---
DESIRED Expect US to have chosen 5%. BOP:
Select LOAD RATE LIMIT% /MIN to the desired value (1 %, 3%, or 5%)
Simulator Exercise Guide Job Aid Page 19 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS BOP:
Using Attachment H and the DECREASE LOAD pushbutton, Adjust LOAD SET to desired final MWe As a plant turnover item, the pressurizer RO:
sprays are already induced. No actions Energize all PZR heaters necessary.
As a plant turnover item, the pressurizer RO:
sprays are already induced. No actions Adjust Pzr Spray Valves to 50% setpoint necessary. (RCS---PK 4558 and RCS---PK 455C)
RO:
Adjust boration time and/or flow rate as necessary to maintain:
- Rods above the Rod Insertion Limit (RIL)
- Tavg within +/-S_F of Tref
- AFD within COLR limits RO:
Check rapid OR gravity boration performed for the time determined in steps 4.i.or 4.1.
RNO Proceed to step 6.k. and, WHEN Boration has been performed for the desired time, THEN Using Attachment G,stop boration.
US:
Check power reduction ---CONVEX REQUESTED RNO Inform CONVEX of load reduction rate (MWe/min) and final MWe level.
Simulator Exercise Guide Job Aid Page 20 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS RO:
Verify Rod Position Above RIL
- a. Check ROD CONTROL BANKS LIMIT LO---LO (MB4C 4---9) annunciator ---LIT RNO Proceed to step ?.g. and, !Eat any time, the annunciator is received, THEN Perform steps ?.c., ?.d. and ?.e.
RO:
Check ROD CONTROL BANKS LIMIT LO (MB4C 3---9) annunciator ---LIT RNO Proceed to step 8. and, !E the annunciator is received, THEN Perform step ?.h. and ?.i.
RO & BOP:
Using Attachment C, "Rapid Downpower Parameters" MONITOR parameters INSERT TRIGGER 11 (FW01) and adjust BOP:
as necessary Degrade Condenser Backpressure DEGRADE CONDENSER a. Verify Final Desired Turbine Load (MWe)
BACKPRESSURE ---LESS THAN 70% (907 MWe)
- b. Using OP 3329, "Condenser Air Removal", Degrade condenser backpressure to between 2.0 in. HgA and 4.0 in. HqA.
US has BOP remove a feed pump from US:
service per Attachment A or B (for either Align One Feedwater Pump For the 'A' or 'B' TO FW Pump). Removal from Service
- a. Verify Final Desired Turbine Load (MWe)
---LESS THAN 50% (648 MWe)
RNO Proceed to step 11.
Simulator Exercise Guide Job Aid Page 21 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS RO:
Verify Power Related Interlock Status
- a. Check reactor power --- LESS THAN THE P---9 SETPOINT RNO Proceed to step 12. and, WHEN Power LESS THAN P---9, THEN Return to step 11.
US:
Align Plant Systems for less than 30% Power Operation
- a. Verify Final Desired Power Level --LESS THAN 30%
RNO Proceed to step 13.
US:
Check Plant Status
- a. Verify--- AT FINAL DESIRED POWER LEVEL RO:
Borate or Dilute as necessary to maintain AFD as close to the target value as possible while maintaining rods above the Rod Insertion Limit RO:
Using GA---9, Align for auto makeup BOP:
If desired, Using OP 3323A, "Main Turbine" PLACE turbine in "Load Limit" operation
Simulator Exercise Guide Job Aid Page 22 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS BOP:
Verify TURB LOAD REJECTION ARM C---
7 (MB4D 6---6) annunciator ---NOT LIT US:
Report Unit Status And Power Reduction
- a. Notify CONVEX and ISO New England.
- b. Notify the OMOC to make DEMI notifications RO:
Check If RCS Sample Required
- a. Verify change in reactor power ---
GREATER THAN OR EQUAL TO 15% IN ONE HOUR
- b. Request Chemistry perform SP 3855, "Reactor Coolant Analysis for Dose Equivalent 1---131" (between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the power change)
- c. Request Chemistry perform SP 3875, "SLCRS Normal Vent ESF Building Gaseous Effluent Analysis," (between 24 and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the power change) for the following process monitors:
- 3HVR---RE 108
- 3HVR---RE 198 US:
Check If Plant Should Be Shutdown
- a. Verify plant shutdown--- DESIRED
- b. Check reactor power --- LESS THAN OR EQUAL TO 25%
RNO
- Go To OP 3204, "At Power Operations."
Simulator Exercise Guide Job Aid Page 23 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS Event4 Notes on failure: RO:
TRIGGER 3* (RC12A) (1) The malfunction (RC12A) will cause a Acknowledges annunciator M848 4-28 RCP A OIL LEAK UPR RSVR slow computer point alarm for low oil "RCP A UPR OIL RSVR LVL LO" and
- SHOULD HAVE BEEN INSERTED level (level is not trendable) and will reports on status of 'A' RCP EARLIER cause a SLOW rise in 'A' RCP oil US: Acknowledges RO report and enters temperatures. ARP (OP 3353.M848 4-28 (Rev04-12):
(2) This malfunction would cause exceedance of oil temp limits (195 F) in over an hour's time.
(3) The ARP will either have crew trip reactor (if temp limit is exceeded, not the case) or use AOP 3554 to remove the RCP (this will be expected flow path).
Computer point will show low oil level. RO:
CHECK RCS---L475A, RCP A upper oil reservoir level computer point, to confirm alarm.
'A' RCP temperatures will have risen -5 RO:
deg F and will continue to slowly rise. MONITOR the following RCP A computer points:
- RCS---T 4 79A, RCP A upper thrust bearing temperature
- RCS---T4798, RCP A lower thrust bearing temperature
- RCS---T483A, RCP A upper radial bearing temperature
Simulator Exercise Guide Job Aid Page 24 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS US should recognize need to remove 'A' US: Reads conditional step to crew:
RCP from service. In order to do this, IF at any time any RCP A thrust bearing or power level will need to be reduced below radial bearing temperature computer 50% (P-8 3 loop permissive). point is greater than 195° F, PERFORM the following:
AOP 3554 will direct the downpower for (1) IF reactor power is greater than P---8 these conditions. However, this AOP is (50%), PERFORM the following:
non-specific on rate of down power. If the (2) TRIP reactor.
US consults the OMOC, direct a 5% I min (3) STOP RCP A down power. (4) Go To E---0, "Reactor Trip or Safety Injection."
OR Refer To AOP 3554, "RCP Trip or Stopping an RCP at Power," and REMOVE RCP A from service.
The US will likely go to AOP 3554 at this US: Reads note to crew:
time and not perform the rest of the ARP at Note:
this time. However, the three remaining ALARA- The following step requires ARP actions are noted here in case the US containment entry.
references them.
If US consults OMOC on a containment entry, report "The containment entry will be made after the 'A' RCP is removed from service".
RO:
IF directed by SMIUS, CHECK for RCP A lube oil leak in piping or oil pot.
TIS will not apply until the RCP is taken out US:
of service. Refer To Technical Specifications, and DETERMINE Limiting Condition for Operation.
US: Enters AOP 3554 {Rev 08-01)
RO:
Check RCP Status - ALL PUMPS RUNNING
Simulator Exercise Guide Job Aid Page 25 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS Based on timing, the US may have to wait RO:
until the downpower is complete before Check Reactor Power continuing on in AOP 3554. Verify THREE LOOP PERMISSIVE P-8 annunciator (MB4D 3-3) - LIT RNO: Using one of the following reduce power as required:
- OP 3204 "At Power Operation" Notes on event 4: US: reads Note prior to step 3:
(1) The US will have to co-ordinate timely, NOTE execution of this procedure so the If stopping the RCP due to No. 1 seal Reactor doesn't trip on a SG level failure, steps 3. through 5. should be transient. completed as quickly as possible in order to (2) The AOP will have the BOP overfeed isolate the affected pump No.1 seal within the affected SG prior to RCP removal. the recommended 5 minutes. While This will ensure the subsequent SG removing the RCP from service, it is shrink doesn't cause a SG LO LO (18%) desirable to maintain feedwater flow to the Reactor Trip. affected steam generator, to ensure that the reactor does not trip on low-low steam generator level from the shrink that will occur. Approximately 0.5 MPPH excess flow is sufficient. Feedwater flow to the affected steam generator should be stopped once shrink has stopped.
BOP:
Feed Affected Loop SG NR Level To Between 65% And 70%
ESTABLISH approximately 0.5 MPPH excess feed flow to raise affected steam generator level.
Simulator Exercise Guide Job Aid Page 26 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS RO takes Loop delta T and Tavg switche(s) RO:
to Loop 1 and pulls out. Recorder selected Defeat Affected Loops Temperature I I
to loops 2,3, or 4. Input
- Place loop temperature cutout.
switch for ~T to the affected loop and Pull out
- Place loop temperature cutout switch for Tavg to the affected loop and Pull out
- Place OT/OP ~T recorder select switch to an unaffected loop RO:
Remove Affected RCP From Service Check RCP status- ALL PUMPS RUNNING BOP:
Check the following conditions:
- Affected SG NR level- GREATER THAN 65%
- THREE LOOP PERMISSIVE P-8 annunciator (MB4D 3-3)- LIT
'A' RCP stops. RO:
STOP affected RCP BOP should continue to flow until SG BOP:
"shrink" subsides and SG level starts to rise. Verify affected S/G level-STABLE At this point, the BOP should go nearly full Stop feeding the affected S/G close on the 'A' FRV.
'A' Loop pressurizer spray valve should be RO:
closed. Check RCP 1 and 2 -BOTH RUNNING RNO: Place affected PZR Spray Controller in manual and Close spray valve.
Simulator Exercise Guide Job Aid Page 27 of 51 SEG# 2K13 NRC-02 Rev ; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS US proceeds to step 7 as the RCP was RO:
NOT stopped due to a seal failure. Check If RCP Seal Leakoff Should Be Isolated Verify RCP - STOPPED AS A RESULT OF SEAL FAILURE REQUIRING IMMEDIATE SHUTDOWN Proceed to step. 7.
BOP:
Shift Affected SG To Main Feed Bypass Flow Close affected SG feed regulating valve BOP:
CLOSE affected SG FW control isolation valve 3FWS-MOV35A BOP:
Using the SG feed regulating bypass valve, Maintain the affected SG level between 45% and 55%
US:
Perform Follow-Up Actions Using AOP 3571, Instrument Failure Response, Attachment A, step 6, Trip the associated temperature bistables for the affected loop US:
Trip the associated Reactor Protection System bistable(s):
Place a check mark in the box above the appropriate channel that requires tripping on page 6 of this Attachment.
US enters LCO 3.3.1 (FU7 & FU8). This is US:
a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> action statement to trip bistables. Refer to Technical Specification 3.3.1 and Once US completes T/S entry, the next 3.3.2.
event may be started. The remaining steps in AOP 3571 are given below for reference. - L. -- ------- -
Simulator Exercise Guide Job Aid Page 28 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS RO:
Check the existing bistable status to ensure a reactor trip will not occur when the failed channel is tripped.
US: Reads Caution I Note to crew:
CAUTION: If the General Warning lamp is lit on 3RPS*RAKLOGB, Placing train A SSPS "Multiplexer Test" switch in "A+B" will cause the reactor to trip.
NOTE The following step will distinguish whether the failure is within SSPS or the Protection channel.
NA US:
If bistable status light(s) (MB2D or MB4F) indicate that a single bistable input has tripped and channel indications are normal, PERFORM the following:
US:
Request the I&C Department trip the appropriate bistables using the last page of Attachment A and Attachment S.
RO:
Verify the appropriate bistable status light(s) are lit.
US: Reads Note to crew:
NOTE Following corrective action by the I&C Department, the channel may be declared OPERABLE if it complies with the guidelines provided in the Table found on page 5 of this Attachment.
Simulator Exercise Guide Job Aid Page 29 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS RO:
Verify MB annunciators and parameters- AS EXPECTED US:
Perform the following to be in c.
HOT STANDBY (MODE 3) within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
- 1) Check reactor power- GREATER THAN 25%
- 2) Continue plant shutdown using OP 3204, At Power Operation Event 5 Notes on failures: US:
INSERT TRIGGER 4 (1) Event 5: A spurious 'A' train Safety Enters E-0 (Rev 27)
SPURIOIUS 'A' TRN Sl WITH MSI Injection (SI) is caused from a tin ON RX TRIP, INTERSYSTEM LOCA whisker on a MSI card (MP3 OE 20450). The tin whisker causes only 'A' Event 6 train Sl to actuate and a partial MSI NO TRIGGER NECESSARY actuation (Event 7).
'B' TRN Sl DID NOT ACTUATE & MUST (2) Due to automatic reactor trip circuitry BE MANUALLY ACTUATED being defeated, the RO must manually trip the reactor [Critical Task] and manually actuate Sl (Event 6).
Event 7 (3) The spurious, auto start of ECCS OCCURS ON TRIGGER 4 equipment will generate an intersystem PARTIAL MSI, MANUAL MSI NEEDED LOCA into the 'A' RHR system and out a break into the ESF building.
RO: Recognizes Reactor Trip first out (SI) RO:
and manually trips the reactor [Critical Verify Reactor Trip Task]. *Check reactor trip and bypass breakers ---
OPEN
- Check rod bottom lights--- LIT
- Check neutron flux--- DECREASING
Simulator Exercise Guide Job Aid Page 30 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS BOP:
Verify Turbine Trip Check all turbine stop valves -- CLOSED BOP:
Verify Power To AC Emergency Busses Check AC emergency busses 34C and 34D
---BOTH ENERGIZED RO Event 6: Recognizes 'B' Train Sl did RO:
not actuate and manually actuates Sl. Check If Sl Is Actuated
- a. Verify SAFETY INJECTION ACTUATION annunciator (MB4D 1---6 or MB2B 5---9)--- LIT
- b. By observation of ESF Group 2 Status Panel lights, Verify both trains of Sl ---
ACTUATED
- c. Check reactor trip and bypass breakers --
-OPEN RO:
Verify Service Water Pumps ---AT LEAST ONE PER TRAIN RUNNING I RO:
Verify RPCCW Pumps --- ONE PER TRAIN RUNNING RO should red flag ECCS Pumps. RO:
Verify ECCS Pumps Running
- Check Sl pumps ---RUNNING
- Check RHR pumps ---RUNNING
Verify AFW Pumps Running
- a. Check MD pumps--- RUNNING
- b. Check turbine---driven pump ---
RUNNING, IF NECESSARY
~- -------- - - -~ ---
Simulator Exercise Guide Job Aid Page 31 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS BOP:
Verify FW Isolation
- Check SG feed regulating valves ---
CLOSED
- Check SG feed regulating bypass valves --
-CLOSED
- Check FW isolation trip valves --- CLOSED
- Check TO FW pumps ---TRIPPED
- Check SG blowdown isolation valves ---
CLOSED
- Check SG blowdown sample isolation valves --- CLOSED
- Check SG chemical feed isolation valves -
CLOSED Event 7 RO:
RO or BOP should notice that a MSI signal Check If Main Steam Lines was generated (MB2B 5-7 "Main Steam Should Be Isolated Isolation" is LIT} and only a partial MSI a. Check Ctmt pressure--- GREATER occurred. The MB2 or MB5 should be used THAN 18 psia to re-initiate MSI and re-align components OR accordingly.
Any SG pressure --- LESS THAN 660 psig OR Annunciator "MAIN STEAMLINE ISOLATION"(MB2B 5---7) --- LIT BOP:
Verify MSIVs and MSIV bypass valves ---
CLOSED
Simulator Exercise Guide Job Aid Page 32 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS If MSI components were not aligned above, RO:
the RNO will re-align components. Check ESF Group 3 lights--- LIT RNO: Align steam line drains for minimum safety function.
CDA will not be actuated or required. RO:
Check If CDA Required
- a. Check Ctmt pressure--- GREATER THAN 23 psia OR Annunciator "CONTAINMENT DEPRES ACTUATION" (MB2B 5---5)--- LIT
'C' CAR fan will have to be stopped. BOP:
Verify CAR Fans Operating In Emergency Mode Check CAR fan status:
- CAR fans A and B ---RUNNING
- CAR fan C --- STOPPED RNO: START/STOP CAR fans as necessary.
RO:
Verify RPCCW Ctmt supply and return header isolations --- OPEN RO:
Verify Train A and B RPCCW supply and return to chill water valves --- OPEN Notes on failures: RO:
(1) Two failures of components to re-align Verify CIA occurred on the reactor trip. See below: a. Check ESF Group 2, columns 2 through (2) Event 8: Reactor Plant Component 10 ---LIT Cooling water valves failed to re-align.
If the RO hasn't corrected this by now, Initiate CIA. !E ESF Group 2, columns 2 this step's (&next step) RNO will through 10 are NOT lit, THEN Using provide re-alignment direction [Critical Attachment A, Reposition valves as Task]. ... continued next page ... necessary for minimum safety function.
Simulator Exercise Guide Job Aid Page 33 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS (3) Event 9: The 'A' EDG failed to auto start on the original Sl. The BOP may have noticed and started the EDG by now. If not, the next step ("Verify Proper ESF Status Panel Indication")
will identify the failure. While not needed for this scenario, the 'A' EDG should be started because it's an automatic action that should have happened but did not occur (reference EOP User's Guide).
(4) While re-aligning components, the 3SIH*MV8801A& B should NOT be opened unless< P-19 (1900 psia).
RO re-align components described on RO:
previous step. Verify Proper ESF Status Panel Indication
- Verify ESF Group 1 lights ---OFF
- Verify ESF Group 2 lights ---LIT Containment will not be adverse. RO:
Determine If ADVERSE CTMT Conditions Exist
- Ctmt temperature --- GREATER THAN 180°F OR
- Ctmt radiation--- GREATER THAN 1 X 10E5 R/hr DO NOT use ADVERSE CTMT parameters.
RO:
Verify ECCS Flow
- a. Check PZR pressure--- GREATER THAN 1900 psia LProceed to ste~ 16.d. --
Simulator Exercise Guide Job Aid Page 34 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS RO:
Check charging pumps --- FLOW INDICATED RO:
Check RCS pressure --- LESS THAN 1650 psia (1950 psia ADVERSE CTMT)
Proceed to step 17.
BOP:
Verify Adequate Heat Sink
- a. Check NR level in at least one SG ---
GREATER THAN 8% (42% ADVERSE CTMT)
Proceed to step 17.d.
BOP:
Verify Total AFW Flow--- GREATER THAN 530 gpm BOP:
Verify AFW Valve Alignment ---PROPER EMERGENCY ALIGNMENT RO:
Verify ECCS Valve Alignment ---
PROPER EMERGENCY ALIGNMENT Based on previous manual Sl, CBI will have RO:
actuated. Check If CBI Required Check annunciator "CONTROL BUILDING ISOLATION" (MB4D 3---6)
---LIT BOP:
Check Train A Control Building filter fan (3HVC*FN1A) ---RUNNING 3HVC*AOD119A will be OPEN. BOP:
Check recirc damper for the running Control Building filter fan (3HVC*AOD119A or B)---
OPEN
Simulator Exercise Guide Job Aid Page 35 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS RO:
Verify ESF Group 2 CBI lights--- LIT BOP:
Verify Control Building purge supply fan and purge exhaust fan--- NOT RUNNING BOP:
Place kitchen exhaust fan in OFF Report "All Unit 3 SLCRS doors are RO:
closed." Verify SLCRS doors --- CLOSED Dispatches PEO to close and dog doors. RO:
Perform the following:
- CLOSE and DOG the following Control Building pressure boundary doors
- CB west 47'6"(C---47---1A)
- CB east 64'6"(C---64---1 B)
- Verify the following Control Building pressure boundary doors---CLOSED
- CB west 47'6"(C---47---1)
- CB north 64'6" chiller room door (C---64---4)
- CB north 64'6" chiller room door (C---64---5)
- CB east 49'6"(C---49---1)
BOP:
Check RCS Temperature
BETWEEN 550°F AND 560°F BOP:
Verify RCS cold leg WR temperature ---
GREATER THAN 550°F Proceed to step 22.
- --~-~
L_____
Simulator Exercise Guide Job Aid Page 36 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS 34A 1-2 will be closed to an energized BUS BOP:
34A. Check Power To SBO Diesel Auxiliaries
- a. Verify any SBO bus tie breaker---
CLOSED TO AN ENERGIZED BUS
- Bus 34A: 34A 1---2
- Bus 34B: 34B 1---2
- Bus 24E: A505 (Unit 2)
RO:
Check PZR Valves Verify PORVs --- CLOSED RO:
Verify normal PZR spray valves ---
CLOSED RO:
Verify PORV block valves---AT LEAST ONE ENERGIZED VALVE OPEN RO:
Verify PZR safety valves ---CLOSED RO:
Check If RCPs Should Be Stopped Verify RCPs ---ANY RUNNING RO:
Verify RCS pressure --- LESS THAN 1500 psia (1800 psia ADVERSE CTMT)
Proceed to step 25.
All SG secondary boundaries will be intact. RO:
Check If SG Secondary Boundaries Are Intact
- a. Check pressure in all SGs ---
- NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
- NO SG COMPLETELY DEPRESSURIZED
Simulator Exercise Guide Job Aid Page 37 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS All SG tubes are intact. BOP:
Check If SG Tubes Are Intact Check steam generator levels --- NO SG LEVEL INCREASING IN AN UNCONTROLLED MANNER BOP:
Verify trend history and alarm status of radiation monitors
- Main steam line --- NORMAL
- Condenser air ejector--- NORMAL
- SG blowdown --- NORMAL All CTMT conditions will be normal. RO:
Check If RCS Is Intact
- Verify Ctmt radiation using 3CMS*RE22 (pre---trip) ---NORMAL
- Verify Ctmt radiation using radiation monitoring group histogram (CTMT) ---
NORMAL
- Verify Ctmt pressure --- NORMAL
- Verify Ctmt recirculation sump level ---
NORMAL US: Reads Caution to crew:
CAUTION: Consult with ADTS and RMT prior to performing any local inspections in the Auxiliary Building or ESF Building.
RO:
Check For RCS Leakage Outside Containment
- a. Check Auxiliary Building and ESF Building radiation (radiation monitoring group histograms)
- Verify Auxiliary Building (AUX) ---
NORMAL
Simulator Exercise Guide Job Aid Page 38 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS Based on "ESF RHR CUB" MB1 Sump RO:
Level Hi lights lit, the crew will transition to Check for Auxiliary Building or ESF Building ECA-1.2. flooding
- 1) Verify SUMP LEVEL HI lights (MB1)
---NOT LIT
- AUX BLDG PIPE TNL
- ECCS PIPE CUB
- ESF RHR CUB
- ESF RSS CUB
- 2) Verify annunciator "SAFEGUARDS AREA FLOODING" (MB1C 2---8) ---NOT LIT
!E the cause is a loss of RCS inventory outside containment, THEN Initiate monitoring of CSF Status Trees and Go to ECA---1.2, LOCA Outside Containment.
US: Transitions to ECA-1.2 (RevOB) and Reads:
NOTE
- For some breaks, ECCS flow may cause an RCS pressure increase without break isolation, or a pressure increase may not be indicated, for example, if the RCS is cycling on the PORVs or if a cooldown is in progress. . .. continued next page ...
- Other means of verifying break isolation should be checked such as pressurizer level increase, reports from the field, decrease in area radiation, or an increase in PORV cycling frequency.
Aux Building conditions will be normal. RO:
Verify Loss Of Coolant Location
- a. Check loss of RCS inventory determined to be- IN THE AUXILIARY BUILDING L__ - ----------------
_ Proceed to CAUTION prior to?tep 3.
Simulator Exercise Guide Job Aid Page 39 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS US: Reads Caution to crew:
CAUTION: Consult with the ADTS and RMT prior to performing any local RHR System operations.
Valve alignments are proper. RO:
Verify Proper Valve Alignment In ESF Building
- a. Verify RHR suction isolation valves-CLOSED
- 3RHS*MV870 1A
- 3RHS*MV8701 B
- 3RHS*MV8701 C
- 3RHS*MV8702A
- 3RHS*MV8702B
- 3RHS*MV8702C Valve alignment is proper. RO:
Verify RHR hot leg injection valve (3SIL *MV8840)- CLOSED Valve alignments are proper. RO:
Verify Sl pump hot leg injection valves -
CLOSED
- 3SIH*MV8802A
- 3SI H*MV8802B RO:
Try To Identify And Isolate Break
- a. Turn the power lockout switch to ON for the following valves (MB2R):
- RHR pump A (3SIL *MV8809A)
- RHR pump B (3SIL*MV8809B)
- SI injection (3SIH*MV8835)
Simulator Exercise Guide Job Aid Page 40 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS The US will be given a choice of three RO:
valves to cycle in this step (3SIL*MV8809A, CLOSE one of the following:
3SIL*MV88098, or 3SIH*MV8835). Based *RHR pump A cold leg injection valve on 'A' RHR sump level hi, it is either (3S IL*MV8809A) 3SIL *MV8809A or 3SIH*MV8835. This guide is written such the crew chooses 3SIL *MV8809A first. It's possible and acceptable, that they choose an alternate valve first.
Once 3SIL*MV8809A is closed, the RCS RO:
leak will be isolated and RCS pressure will Check RCS pressure -INCREASING rise. It's possible that P-19 caused the CHG Cold Leg Injection Valves to OPEN and RCS pressure was already rising. If this is the case, computer trends will still show a definite increase in the rate of RCS pressure rise. In either event, the crew will be able to determine the RCS leak is isolated once 3SIL *MV8809A is closed and the US will make the proper transition to E-1 (below) [Critical Task].
RO:
Turn the power lockout switch to OFF for the following valves (MB2R):
- RHR pump A (3SIL *MV8809A)
- RHR pump 8(3SIL*MV88098)
- SI injection(3SIH*MV8835)
RO:
Check If Break Is Isolated Check RCS pressure -INCREASING
Simulator Exercise Guide Job Aid Page 41 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS At the discretion of the Chief Examiner, US:
the scenario may be ended at this point Go to E-1, Loss of Reactor or Secondary
{all required events have been Coolant completed). The remaining steps are to proceed in E-1 and kick-out to ES-1.1 and complete Sl termination.
US: Enters E-1 and Reads CAUTION: To prevent seal damage, sel injection flow should be maintained to all RCPs.
NOTE: Foldout page must be open.
RO:
Check If RCPs Should Be Stopped Verify RCPs ---ANY RUNNING RO: Verify RCS pressure --- LESS THAN 1500 psia (1800 psia ADVERSE CTMT}
RNO--Proceed to step 2.
BOP:
Check If SG Secondary Boundaries Are Intact Check pressures in all SGs ---
- NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
- NO SG COMPLETELY DEPRESSURIZED BOP:
Check Intact SG Levels
- a. Verify NR level--- GREATER THAN 8%
(42% ADVERSE CTMT}
- b. Control feed flow to maintain NR level --
BETWEEN 8% and 50% (42% and 50%
ADVERSE CTMT}
Simulator Exercise Guide Job Aid Page 42 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS RO:
Check Secondary Radiation
- a. Sample all SGs for activity
- 1. RESET SG blowdown sample isolation
- 2. OPEN SG blowdown sample isolation valves
- 3. Request Chemistry obtain activity samples using HP coverage RO:
Verify trend history and alarm status of radiation monitors
- Main steam line --- NORMAL
- Condenser air ejector--- NORMAL
- SG blowdown --- NORMAL US: Reads Caution to crew:
C AUT I 0 N: If any PZR PORVopens because of high PZR pressure, step 5.a.
should be repeated after pressure decreases to less than 2350 psia.
RO:
Check PZR PORVs and Block Valves Verify PORVs --- CLOSED RO:
Verify block valves--- AT LEAST ONE OPEN RO:
Check If ECCS Flow Should Be Reduced Verify RCS subcooling based on core exit TCs ---GREATER THAN 32°F (115°F ADVERSE CTMT)
Simulator Exercise Guide Job Aid Page 43 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS I BOP:
Verify secondary heat sink I
- Total feed flow to intact SGs ---
GREATER THAN 530 gpm I
- Narrow range level in at least one I intact SG --- GREATER THAN 8% I (42% ADVERSE CTMT) i RO: I Verify RCS pressure --- STABLE OR INCREASING I I
RO:
Verify PZR level--- GREATER THAN 16%
(50% ADVERSE CTMT) I US:
Go to ES---1.1, Sl Termination I US: Enters ES-1.1 (Rev016-02) and reads:
CAUTION: After Sl reset, manual operator action is required to: I
- Open the charging pump cold leg injection valves when RCS pressure I decrease to LESS THAN 1900 psia.
- Restart safeguards equipment if I offsite power is lost.
NOTE: Foldout page must be open. I RO:
I Reset ESF Actuation Signals If Required
- a. RESET Sl I
- b. RESET the following:
- CDA i
- CIA
- CIS I
Simulator Exercise Guide Job Aid Page 44 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS BOP:
Restore MCC 32---3T
- a. Check emergency bus 34C-ENERGIZED
- b. Using GA---1, Energize MCC 32---3T RO:
STOP All But One Charging Pump And Place In AUTO RO:
Check RCS Pressure--- STABLE OR INCREASING RO:
Establish Instrument Air To Ctmt Check instrument air compressors ---
AT LEAST ONE RUNNING RO:
OPEN instrument air Ctmt isolation valves RO:
Establish Normal Charging Flow Path Fully Open charging line flow control valve RO:
Verify charging loop isolation valves (3CHS*AV8146 or 3CHS*AV8147) ---
ONE OPEN RNO-- Re---position valves to establish only one open.
RO:
OPEN charging isolation valves
- 3CHS*MV81 06
- 3CHS*MV8105 L _ _ __
Simulator Exercise Guide Job Aid Page 45 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS RO:
CLOSE the charging pump miniflow isolations to the RWST
- 3CHS*MV8511A
- 3CHS*MV8511 B RO:
CLOSE both charging pump cold leg injection valves
- 3SIH*MV8801A
- 3SIH*MV8801 B RO:
OPEN the charging pump recirculation isolation valves
- 3CHS*MV8111A
- 3CHS*MV8111 B
- 3CHS*MV8111 C
- 3CHS*MV8110 RO:
Verify PZR Level Check pressure in all SGs --- NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER RO:
Check PZR level --- STABLE OR INCREASING RO:
Control char-g_in_gflow to maintain PZR level RO:
Check If Sl Pumps Should Be Stopped Check pressure in all SGs --- NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
Simulator Exercise Guide Job Aid Page 46 of 51 SEG# 2K13 NRC-02 Rev; 0 BOOTH INSTRUCTOR FLOOR INSTRUCTOR STUDENTS RO:
Check RCS pressure:
- Pressure --- STABLE OR INCREASING
- Pressure--- GREATER THAN 1650 psia (1950 psia ADVERSE CTMT)
RO:
STOP Sl pumps and Place in AUTO RO:
STOP RHR Pumps And Place In AUTO RESTORE simulator to "training ready" SCENARIO END: Place simulator in conditions .. FREEZE.
Simulator Exercise Guide Job Aid Pa e 47 of 51 E.G# 2K13 NRC-02 Rev; 0 SECTION 4 EXAM GUIDE
SUMMARY
Title:
LOCA Outside Containment ID Number: 2K13 NRC-02 Revision: Q II. Critical Tasks TASK DESCRIPTION TASK# KIA>/= 3.0 BASIS SELECTION Manually trip the reactor E-0 --A 012 A4.07 Failure to manually trip the from the control room (3.9* I 3.9*) reactor causes a challenge with either Main board to the subcriticality CSF trip switch or by opening beyond that irreparably 328 and 32N supply introduced by the postulated breakers before conditions.
completing E-0 Step 1.
Isolate the LOCA ECA-1.2-A Westinghouse Failure to isolate a LOCA outside containment EPE LOCA outside containment (that before transition out of Outside CTMT can be isolated) degrades ECA-1.2. EA2.1 containment integrity (3.4 I 4.3) beyond the level of degradation irreparably introduced by the postulated conditions.
Simulator Exercise Guide Job Aid Page 48 of 51 SEG# 2K13 NRC-02 Rev; 0 Rx Power: 74%
Thermal: 2726 MWTH PZR Pressure: 2250 psia Electric: 863 MWe RCS T-AVE: 5:ZI7:degF RCS Leakage: Identified: 0.078gpm Core Burnup: 150 MWD/MTU Unidentified: 0.1 08gpm Protected Train:
Intake:
Action Requirement Time Left 3.5.2 a Today Return to service within time (71 hours8.217593e-4 days <br />0.0197 hours <br />1.173942e-4 weeks <br />2.70155e-5 months <br /> left) hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 71 or Hot within next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Watch Reason Reason Position 3SIH*P1A is out of service (red tagged) to repair an oil leak. In T/S LCO with 71 hours8.217593e-4 days <br />0.0197 hours <br />1.173942e-4 weeks <br />2.70155e-5 months <br /> remain Plant is being returned to service following a refueling outage. HOLD POWER at 75% to support while Reactor Engineering performs EN 31015 "Power Ascension Testing of Millstone Unit 3". Pull rods in MANUAL (at no more than 1 or 2 steps per minute) to maintain re + I - 1 F of Tref Xenon builds in .
REACTIVITY BRIEFING (SEE REACTIVITY THUMBRULES I SPREAD SHEET FOR ADDITIONAL IN 5.25/21 gpm
Simulator Exercise Guide Job Aid Page 49 of 51
<:;EG# 2K13 NRC-02 Rev; 0 ATTACHMENT 2 VALIDATION CHECKLIST
Title:
LOCA Outside Containment ID Number: 2K13 NRC-02 Revision: Q Verified By:
(Initials)
Initial Conditions:
The initial condition(s) contained in the guide are certified or have WMF been developed from certified ICs.
Test Run:
The scenario contained in the guide has been test run in part or WMF whole on the simulator. The simulator response is reasonable and as expected. If a simulator guide revision does not affect original Test Run, then enter N/A.
- imulator Operating Limits:
The simulator guide has been evaluated for operating limits and/or WMF anomalous response by reviewing the Simulator Modeling and Anomalous Response List.
For Examination Scenario:
The Scenario Attributes Checklist is complete and attached. This is WMF not required for Progress Review Exams.
William M. Forrestt 9/6/13 Actions Complete (Signature) Date
Simulator Exercise Guide Job Aid Page 50 of 51 SEG# 2K13 NRC-02 Rev; 0 REVISION 1 Facility: Millstone 3 Scenario No.: 2K13 NRC-02 (Rev Ol Op-Test No.: 2K13 Examiners: Operators:
Initial Conditions: IC-12, 74% .QOWer, Beg oflife, Xenon building in@, 90 .QCrn I hr.
Turnover:
The 12lant is being returned to service following a refueling outage. The crew is to stabilize reactor 12ower at 74% while Reactor Engineering 12erforms EN 31015 "Power Ascension Testing of Millstone Unit 3". Additionally, the 'A' SIH 12um12 was taken out of service one hour ago to re12air a newly discovered oil leak.
Event Malf. Event Event No. No Type* Description 1 NI09A RO I Power range nuclear instrument, N41, fails high us TIS causing control rods to auto insert (AOP 3571 ).
2 RX13C BOP I The controlling 'B' SG Feed flow instrument fails high (AOP 3571).
3 RC12A RO R Convex requested emergency downpower.
BOP N us R 4 - RO c 'A' RCP develops an oil leak and requires shutdown.
BOP c 'A' RCP is removed from service iaw AOP 3554.
us TIS 5 RP05A RO M A spurious 'A' train Safety Injection is caused from a tin SI06C BOP M whisker on MSI card. The reactor fails to auto trip. An RP10A us M isolable, inter-system LOCA develops in the RHR RP10B system and out a break in the ESF building (outside containment).
6 - RO c 'B' train of Sl did not actuate and must be actuated.
7 MSDI23 BOP c Partial MSI generated caused only the MSIV's to close.
Thru The remainder of the MSI components need to be MSDI26 manually re-aligned.
8 RP11H RO c Component Cooling Water valves fail to reposition and must be manually re-aligned.
9 EG13A BOP c 'A' EDG fails to auto start and is manually started.
- (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor
Simulator Exercise Guide Job Aid Page 51 of 51 SEG# 2K13 NRC-02 Rev; 0 QUALITATIVE ATTRIBUTES y 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.
y 2. The scenario consists mostly of related events.
- y-3. Each event description consists of:
the point in the scenario when it is to be initiated the malfunctions(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)
- y-4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
y 5. The events are valid with regard to physics and thermodynamics.
y 6. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.
N/A 7. If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.
- y-8. The simulator modeling is not altered.
- y-9. The scenario has been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure functional fidelity is maintained while running the planned scenario.
y 10. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered lAW Section 0.5 of ES-301.
- y-11. All individual operator competencies can be evaluated, as verified using form ES-301-6.
- y-12. Each operator will be significantly involved in the minimum number of transients and events specified on Form ES-301-5.
y 13. Level of difficulty is appropriate to support licensing decisions for each crew position