ML022410232
| ML022410232 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/02/2002 |
| From: | Santiago M Entergy Nuclear Generation Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-293/02301 | |
| Download: ML022410232 (30) | |
Text
ES-301 -1 Facility: PNPS Date of Examination: 07/29/02 Examination Level: RO Operating Test Number: 1 Administrative Describe method of evaluation:
Topic/Subject Description 1. ONE Administrative JPM, OR
- 2. TWO Administrative Questions Plant Parameter JPM - Perform a Short Form Heat Balance A. 1 Verification Reactor Plant Question #1 - Determine Reactor period.
Startup Requirements Question #2 - Requirements for Placing the Mode Switch in Run.
A.2 Tagging and Question #1 Clearances Recommended sequence for tagging out a centrifugal pump Question # 2 Describe the tagout verification requirements for removal/
installation of fuses.
Ability to Perform Question #1 - Requirements for entry into very high radiation A.3 Procedures to areas.
Reduce Excessive Levels of Radiation and Question #2 - Actions for refuel floor hi radiation levels.
Guard Against Personnel Exposure Lines of Authority Question #1 - Emergency dose limits.
A.4 During an Emergency Question #2 - Actions in the event of a bomb threat.
1
Job Performance Measure Worksheet Facility: Pilgrim Task No: 356-01-07-004 Task
Title:
Perform a Short Form Heat Balance JPM No: Admin 1 K/A
Reference:
292008 K1.21 2.9/3.0 Position: ROISRO Examinee: NRC Examiner:_
Date:
Method of testing:
Simulated Performance Actual Performance:_ _ _ _
Classroom Simulator a Plant Read to the Examinee:
"I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied."
Initial Conditions: Plant conditions are as follows:
- The plant is at 100% power.
- Plant conditions are stable.
- The plant process computer is out of service.
Task Standard: Attachment 4 of PNPS 2.1.10 is completed with no errors. The system procedure shall be followed without failure of critical tasks. Critical steps must be performed in order. Other steps may be performed out of sequence.
Note: PNPS 9.3 Attachment 3 is an alternate method for performing a short form heat balance and provides the same results.
Required Materials: Steam Tables General
References:
PNPS 2.1.10, Rev. 22 Initiating Cue: "[Operator's name], perform a Short Form Heat Balance per PNPS 2.1.10".
Time Critical Task: NO Validation Time: 5 minutes I
PERFORMANCE INFORMATION (Critical steps denoted with a check mark)
Performance Step 1: Operator reviews the applicable sections of the procedure.
Standard: Operator reviews the applicable sections of the procedure.
Comment: IF Operator: Restore to 100% power IC (IC-14).
Performance Step 2: Operator fills out date/time and performed by on Attachment 4.
Standard: Date/time and performed by recorded on Attachment 4.
Comment:
Performance Step 3: Find and record reading for Feedwater Flow A from FI-640-24A on Panel C905.
Standard: FI-640-24A reading recorded.
Comment: Approximately 4 Mlb/hr.
Performance Step 4: Find and record reading for Feedwater Flow B from FI-640-24B on Panel C905.
Standard: FI-640-24B reading recorded.
Comment: Approximately 4 Mlb/hr.
2
PERFORMANCE INFORMATION (Critical steps denoted with a check mark)
Performance Step 5: Find and record reading for Feedwater Temperature A from TR-3496A on Panel C1.
Standard: TR-3496A reading recorded (red pen).
Comment: Approximately 3650F.
Performance Step 6: Find and record reading for Feedwater Temperature B from TR-3496B on Panel C1.
Standard: TR-3496B reading recorded (blue pen).
Comment: Approximately 365 0F.
Performance Step 7: Calculate Total Feedwater flow by adding the A and B Feedwater Flows.
Standard: Total Feedwater flow calculated.
Comment: Approximately 8 Mlb/hr.
3
PERFORMANCE INFORMATION (Critical steps denoted with a check mark)
Performance Step 8: Average the A and B Feedwater Temperatures loops together.
Standard: Average Feedwater temperature calculated.
Comment: Approximately 365 0F.
Performance Step 9: Using steam tables, determine Feedwater enthalpy.
Standard: Feedwater enthalpy is recorded.
Comment: hf 365 0F = 337.6 BTU/lb V
/ Performance Step 10: Determine Core Thermal Power by subtracting Feedwater enthalpy from 1189.6 and dividing by 3.413, multiply by Total feedwater flow and add 9.02.
Standard: Core Thermal Power is calculated [2006 MWth (+/- 50 mw)].
Comment:
Terminating Cue: When the candidate has completed the core thermal power calculation, the examiner shall inform him/her that the task is complete.
4
RO Question A.1-1 During a reactor startup, the following data is taken immediately after criticality:
To: SRM count rate is 2.OE+4 and indicated reactor period is 120 seconds.
T+1.5 minutes: SRM count rate is 4.OE+4 and indicated reactor period is 120 seconds.
No rods or SRMs have been moved during this time.
Calculate the current reactor period.
ANSWER:
90 seconds, doubling time X 1.445 = 130.05 seconds.
REFERENCE:
PNPS 2.1.4, Rev. 15, Page 10 of 11 K/A: 2.1.20 4.3/4.2 2
RO Question A.1-2 What requirements must be met in order to place the Mode Switch in Run and the basis for each?
ANSWER:
APRM downscale alarm must be clear - prevent rod block after going to Run APRM downscale indications must be clear - prevent rod block after going to Run.
Low Main Steam Line Pressure Alarm must be clear - prevent a Group I isolation after going to Run.
REFERENCE:
PNPS 2.1.1, Rev. 119, Page 44 of 131 K/A: 2.1.2 3.0 /4.0 4
RO Question A.2-1 With the reactor at rated pressure, you have been given a tagout for the 'A' Core Spray Pump. The first item to be repositioned is closing the pump minimum flow valve, 1400-13A.
What would be the adverse affects of closing the minimum flow valve without first repositioning any other components?
ANSWER:
If the pump auto started without minimum flow protection, the pump would be operating at shutoff head.
This would cause increasing pump and fluid temperature and could cause overheating of the pump.
REFERENCE:
O-RO-O1-04-04, Page 21 of 40 K/A: 2.2.13 3.6/ 3.8 6
RO Question A.2-2 You are given a tagout for opening a breaker and pulling a fuse in the Cable Spreading Room. Both tags require verification.
How do the methods used to verify the tags on the fuses differ from the method used for verifying the breaker tags?
ANSWER:
The fuse would be dependently verified prior to pulling the fuse. The breaker would be independently verified after the breaker was open and tag was hung.
REFERENCE:
1.4.5, Rev. 56, page8of 113 1.3.34, Rev. 73, page 48 of 117 K/A: 2.2.13 3.6/3.8 8
RO Question A.3-1 You have been assigned to enter a Very High Radiation Area with an RP Technician. What four (4) conditions must be met in order for the RP Technician to remain outside the area?
ANSWER:
- 1) Dose rate has been verified within frequency specified on the RWP.
- 2) Radiological conditions have not changed.
- 3) Second person must directly observe the person entering.
- 4) Second person must be dressed in the required protective set.
REFERENCE:
PNPS 1.3.114, Rev. 13, page 11 of 31 K/A: 2.3.10 2.9 /3.3 10
RO Question A.3-2 Given that the New Fuel Storage Vault ARM High Alarm has come on, what area should be evacuated and where should the personnel go?
What additional information is needed in order to determine if the scope of the evacuation needs to be expanded?
ANSWER:
- 1) Evacuate the Refuel Floor to the 91' changeout area.
- 2) Whether any other Rx Building ARM's are alarming.
REFERENCE:
PNPS 5.4.3, Rev. 16, page 3 and 4 of 5 K/A: 2.3.10 2.9 / 3.3 12
RO Question A.4-1 Life saving activities are needed during an emergency. Assuming you do not volunteer for increased dose, what is your limit for whole body and skin dose to conduct these activities?
ANSWER:
25 Whole Body and 250 Rem Skin Dose
REFERENCE:
EP-IP-440, Rev. 6, page 5 of 21 K/A: 2.4.39 3.3/3.1 14
RO Question A.4-2 You are on watch when a bomb threat is called in. Shortly thereafter, a bomb explodes behind the Medical Building which destroys the fence in that area. No plant systems have been affected.
How would the plant be maneuvered under these conditions?
ANSWER:
- 1) Scram the reactor
- 2) Maintain main condenser as a heat sink using bypass valves
- 3) Place HPCI in full flow test
- 4) Place RHR in torus cooling
REFERENCE:
PNPS 5.3.14, Rev. 13, Security Incidents K/A: 2.4.39 3.3 1 3.1 16
Facility: PNPS Date of Examination: 07/29/02 Examination Level: SRO Operating Test Number: 1 Administrative Describe method of evaluation:
Topic/Subject Description 1. ONE Administrative JPM, OR
- 2. TWO Administrative Questions Plant Parameter JPM - Perform a Short Form Heat Balance A. 1 Verification Reactor Plant Question #1 - Determine Reactor period.
Startup Requirements Question #2 - Requirements for Placing the Mode Switch in Run.
Surveillance JPM - Determine SSW Pump Operability using Flowrate A.2 Testing Surveillance Test Data l.3 Ability to Perform Question #1 - Supervisor responsibilities for work performed A.3 Procedures to under RWP.
Reduce Excessive Levels of Radiation and Question #2 - Actions for refuel floor hi radiation levels.
Guard Against Personnel Exposure Emergency JPM - Off-site Notification for Contaminated, Injured Person.
A.4 Communications l I
Job Performance Measure Worksheet Facility: Pilgrim Task No: 356-01-07-004 Task
Title:
Perform a Short Form Heat Balance JPM No: Admin 1 K/A
Reference:
293007 K1.13 2.3/2.9 Position: RO/SRO Examinee: NRC Examiner:_
Date:
Method of testing:
Simulated Performance Actual Performance: vI Classroom Simulator / Plant Read to the Examinee:
"I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied".
Initial Conditions: Plant conditions are as follows:
- The plant is at 100% power.
- Plant conditions are stable.
- The plant process computer is out of service.
Task Standard: Attachment 4 of PNPS 2.1.10 is completed with no errors. The system procedure shall be followed without failure of critical tasks. Critical steps must be performed in order. Other steps may be performed out of sequence.
Note: PNPS 9.3 Attachment 3 is an alternate method for performing a short form heat balance and provides the same results.
Required Materials: Steam Tables General
References:
PNPS 2.1.10, Rev. 22 Initiating Cue: "[Operator's name], perform a Short Form Heat Balance per PNPS 2.1.10".
Time Critical Task: NO Validation Time: 5 minutes 1
PERFORMANCE INFORMATION (Critical steps denoted with a check mark)
Performance Step 1: Operator reviews the applicable sections of the procedure.
Standard: Operator reviews the applicable sections of the procedure.
Comment: IF Operator: Restore to 100% power IC (IC-14).
Performance Step 2: Operator fills out date/time and performed by on Attachment 4.
Standard: Date/time and performed by recorded on Attachment 4.
Comment:
Performance Step 3: Find and record reading for Feedwater Flow A from Fl-640-24A on Panel C905.
Standard: FI-640-24A reading recorded.
Comment: Approximately 4 Mlb/hr.
Performance Step 4: Find and record reading for Feedwater Flow B from FI-640-24B on Panel C905.
Standard: FI-640-24B reading recorded.
Comment: Approximately 4 Mlb/hr.
2
PERFORMANCE INFORMATION (Critical steps denoted with a check mark)
Performance Step 5: Find and record reading for Feedwater Temperature A from TR-3496A on Panel C1.
Standard: TR-3496A reading recorded (red pen).
Comment: Approximately 365 0F.
Performance Step 6: Find and record reading for Feedwater Temperature B from TR-3496B on Panel C1.
Standard: TR-3496B reading recorded (blue pen).
Comment: Approximately 365 0F.
Performance Step 7: Calculate Total Feedwater flow by adding the A and B Feedwater Flows.
Standard: Total Feedwater flow calculated.
Comment: Approximately 8 Mlb/hr.
3
PERFORMANCE INFORMATION (Critical steps denoted with a check mark)
Performance Step 8: Average the A and B Feedwater Temperatures loops together.
Standard: Average Feedwater temperature calculated.
Comment: Approximately 3650F.
Performance Step 9: Using steam tables, determine Feedwater enthalpy.
Standard: Feedwater enthalpy is recorded.
Comment: hf 3650 F t 337.6 BTU/lb
- Performance Step 10: Determine Core Thermal Power by subtracting Feedwater enthalpy from 1189.6 and dividing by 3.413, multiply by Total feedwater flow and add 9.02.
Standard: Core Thermal Power is calculated [2006 MWth (+/- 50 mw)].
Comment:
Terminating Cue: When the candidate has completed the core thermal power calculation, the examiner shall inform him/her that the task is complete.
4
SRO Question A.1-1 During a reactor startup, the following data is taken immediately after criticality:
To: SRM count rate is 2.OE+4 and indicated reactor period is 120 seconds.
T+,
15 minutes: SRM count rate is 4.OE+4 and indicated reactor period is 120 seconds.
No rods or SRMs have been moved during this time.
Calculate the current reactor period.
ANSWER:
90 seconds, doubling time X 1.445 = 130.05 seconds.
REFERENCE:
PNPS 2.1.4, Rev. 15, Page 10 of 11 K/A: 2.1.20 4.3/4.2 2
SRO Question A.1-2 What requirements must be met in order to place the Mode Switch in Run and the basis for each?
ANSWER:
APRM downscale alarm must be clear - prevent rod block after going to Run APRM downscale indications must be clear - prevent rod block after going to Run.
Low Main Steam Line Pressure Alarm must be clear - prevent a Group I isolation after going to Run.
REFERENCE:
PNPS 2.1.1, Rev. 119, Page 44 of 131 K/A: 2.1.2 3.0 /4.0 4
Job Performance Measure Worksheet Facility: Pilgrim Task No: 341-03-02-021 Task
Title:
Determine SSW Loop 'A' Operability JPM No: Admin 2 Using Flow Rate Surveillance Test Data K/A
Reference:
2.2.12 3.0/3.4 Position: RO/SRO Examinee: NRC Examiner:
Date:
Method of testing:
Simulated Performance Actual Performance: /
Classroom Simulator 1 Plant_
Read to the Examinee:
"I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied".
Initial Conditions: Plant conditions are as follows:
- Data has been taken on the pump and is recorded in the working copy of the procedure.
Task Standard: Using data taken during a surveillance for the test on 'A' SSW loop, determine that the 'A' SSW loop is outside the acceptance criteria. The system procedure shall be followed without failure of critical tasks. Critical steps must be performed in order. Other steps may be performed out of sequence.
Required Materials: Calculator General
References:
PNPS 8.5.3.14, Rev. 14 Initiating Cue: "[Operator's name], evaluate the test data taken on the 'A' SSW loop".
Time Critical Task: No Validation Time: 10 minutes 1
PERFORMANCE INFORMATION (Critical steps denoted with a check mark)
Performance Step 1: Operator reviews the applicable sections of the procedure.
Standard: Operator reviews the applicable sections of the procedure.
Comment:
Performance Step 2: Complete the SSW Loop 'A' Operability Test Data (Attachment 1) as follows:
- Calculate and record the fluke flow for the 'A' SSW loop.
Standard: Using data already recorded calculates Fluke Flow = 790.5 (mA-l OmA) -50 GPM and records it in Attachment 1. Value should be 4627 GPM.
Comment:
1/ Performance Step 3: Calculate and record RBCCW Hx 'A' D/P.
Standard: Using data already recorded, calculate D/P = (Pin-Pout) - 1.86 psi. Value should be 34.14 psid.
Comment:
V/ Performance Step 4: Plots 4627 GPM and 34.14 psid on Attachment 2 and determines the
'A' SSW loop does not meet acceptance criteria.
Standard: 'A' SSW loop acceptance criteria not met.
Comment:
2
Terminating Cue: When the candidate has determined that the acceptance criteria for the 'A' SSW loop is not met, the examiner shall inform him/her that the task is complete.
3
SRO Question A.3-1 Two contractors, one male and one declared pregnant female, have been assigned to PNPS for a high dose job which you are supervising. Neither have any exposure in the last year. Both have been trained as Radiation Workers and are badged. How does the level at which they will need a TEDE dose control limit upgrade vary between these individuals, and how do the approved levels for the DCL upgrade vary?
ANSWER:
The male would have an individual DCL of 1.5 Rem, the declared pregnant female would have an individual DCL of 350 mRem. The male DCL upgrade would be approved by ALARA Team Manager, RP Manager and VP of Operations. The female would be approved by ALARA Team Manager, RP Manager, VP of Operations, and Medical.
REFERENCE:
6.1-003, Rev. 7, page 15 of 15 6.1-002, Rev. 13, page 22 of 36 K/A: 2.3.2 2.5 / 2.9
SRO Question A.3-2 Given that the New Fuel Storage Vault ARM High Alarm has come on, what area should be evacuated and where should the personnel go?
What additional information is needed in order to determine if the scope of the evacuation needs to be expanded?
ANSWER:
- 1) Evacuate the Refuel Floor to the 91' changeout area.
- 2) Whether any other Rx Building ARM's are alarming.
REFERENCE:
PNPS 5.4.3, Rev. 16, page 3 and 4 of 5 K/A: 2.3.10 2.9/3.3
Job Performance Measure Worksheet Facility: Pilgrim Task No: 015-05-02-013 Task
Title:
Emergency Plan Implementation - JPM No: Admin 4 Unusual Event K/A
Reference:
2.4.40 / 2.3 /4.0 Position: SRO Examinee: NRC Examiner:
Date:
Method of testing:
Simulated Performance Actual Performance: I/
Classroom Simulator V/ Plant Read to the Examinee:
"I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied."
Initial Conditions: Plant conditions are as follows:
- The plant is in an outage.
- An individual fell in the drywell.
- He tore his protective clothing in the process and is contaminated.
- He has just left the site in the ambulance headed for Jordan Hospital.
Task Standard: An Unusual Event shall be declared due to EAL 5.3.1.1 (Transportation of a Contaminated, Injured Person to an Offsite Medical Facility). The Initial Notification Form shall be completed and given to the Operations Assistant within 15 minutes. The Emergency Plan shall be completed up to and including Step 5.3.1 of EP-IP-100. The EPIPs shall be followed without failure of critical steps.
Required Materials: Initial Notification Form General
References:
EP-IP-100, Rev. 18 Initiating Cue: "[Operator's name], you are the SM on-shift. Implement the Emergency Plan as appropriate. Inform me when you have notified the Emergency Response Organization".
Time Critical Task: YES Validation Time: 10 minutes
PERFORMANCE INFORMATION (Critical steps denoted with a check mark)
Performance Step 1: Operator reviews the applicable sections of the procedure.
Standard: Operator reviews the applicable sections of the procedure.
Comment:
- This task is covered in EP-IP-100, Section 5.0
- Attachment 1 of this JPM contains a statement of plant conditions
- All critical steps must be performed in order unless otherwise noted Note: Simulator operator should set wind direction to 900 and speed at 10 miles per hour.
Performance Step 2: When any indication of abnormal conditions are received, personnel will verify the symptoms/indications, and then compare them with EALs (Attachment 5).
Standard: Operator verifies indications.
Comment: Operator may refer to Attachment 1 of this JPM for conditions.
Performance Step 3: Compare the symptoms or indications of the abnormal conditions with those listed in Attachment 5, "Emergency Action Levels".
Standard: Operator compares plant indications against Attachment 5 EALs.
Comment: Operator may refer to the "EAL Flowchart" vice Attachment 5.
PERFORMANCE INFORMATION (Critical steps denoted with a check mark)
Performance Step 4: Identify the highest emergency classification level.
Standard: Operator determines that an EAL has been met or exceeded.
Comment: Determines that EAL 5.3.1.1 is met aV Performance Step 5: Declare the highest emergency classification (if multiple EALs are exceeded) for which an EAL has been met or exceeded.
Standard: Operator declares an Unusual Event per 5.3.1.1, Transportation of a Contaminated Injured Person to an Offsite Medical Facility.
Comment: If operator does not verbalize this step, satisfactory completion may be verified by the subsequent announcements.
Critical Start Time:
Performance Step 6: For initial classification from the Control Room, announce the emergency classification to the Control Room operating staff and state that the SM has assumed the role of Emergency Director.
Standard: Operator announces to the control room that an Unusual Event has been declared and that the SM is the Emergency Director.
Comment:
PERFORMANCE INFORMATION (Critical steps denoted with a check mark)
Performance Step 7: Enter and execute concurrently with this procedure the following which corresponds to the appropriate declared event.
- EP-IP-100, Attachment 1, Unusual Event
- EP-IP-100, Attachment 2, Alert
- EP-IP-100, Attachment 3, Site Area Emergency
- EP-IP-1 00, Attachment 4, General Emergency Standard: Operator enters EP-IP-100, Attachment 1, Unusual Event.
Comment:
Performance Step 8: Sound/have the Control Room sound the Operator Recall Alarm and make the following announcement over the public address system, TWICE:
"Attention all personnel; attention all personnel: An Unusual Event has been declared due to (brief description of initiating event). All on-call members of the Emergency Response Organization standby for further instructions. All other personnel continue with your present duties until additional instruction is given".
Standard: Operator sounds/has sounded the Plant Emergency Alarm, and makes the announcement over the public address system twice.
Comment: Controls to activate alarm are on the right hand side of the CRS desk.
Performance Step 9: Notify the Emergency Response Organization per procedure EP-IP-100, Attachment 10, "Activation of the Emergency Response Organization".
Standard: Operator proceeds to notify the Emergency Response Organization of the event or directs the OA to make the notification.
Comment:
PERFORMANCE INFORMATION (Critical steps denoted with a check mark)
Performance Step 10: Direct the completion of or complete an Initial Notification Form.
Standard: Operator completes Initial Notification Form.
Comment: Initial Notification Form is completed.
Performance Step 11: Verify the accuracy of, and then sign the Initial Notification Form (authorizing release of information to offsite agencies).
Standard: Operator signs form.
Comment: Block 12 on page 2 is signed.
Performance Step 12: Within 15 minutes of the event classification, use the Initial Notification Form to notify the commonwealth and local authorities.
Standard: Operator directs the OA to transmit the Initial Notification Form over the DNN.
Comment:
Critical Stop Time:
Performance Step 13: As soon as possible, but no later than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after event classification, notify the NRC via the ENS phone or commercial phone. Refer to the PNPS Emergency Telephone Directory for commercial phone(s).
Standard: Operator uses the ENS phone to notify the NRC.
Comment:
Terminating Cue: