ML111460133
| ML111460133 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/16/2010 |
| From: | Palagi B NRC/RGN-III/DRS/OLB |
| To: | |
| Shared Package | |
| ML102070539 | List: |
| References | |
| Download: ML111460133 (94) | |
Text
2010 PALISADES NUCLEAR PLANT INITIAL EXAMINATION PROPOSED EXAM FILES PROPOSED ADMINISTRATIVE JPMs
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:
ROADMIN l a TITLE:
DETERMINE QUADRANT POWER TILT PER PO-3 CAN D I DATE:
EXAM1 NER:
JPM RO ADMIN l a JOB PERFORMANCE MEASURE Task: Determine Quadrant Power Tilt per PO-3 Alternate Path: NIA Facility JPM #: PL-OPS-ENG-014J WA: G2.1.7 Importance: RO: 4.4 SRO: 4.7 WA Statement: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
Task Standard: Four Quadrant Power Tilts added together total equals zero & 0.01 per PO-3 Preferred Evaluation Location: Simulator -X-In Plant Preferred Evaluation Method:
Perform X
Simulate
References:
PO-3, Alternate lncore and Excore Applications Validation Time:
12 minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
mi nu tes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 9 AUGUST 2010
Tools/Equ ipmenVProcedu res Needed:
PO-3, Alternate lncore and Excore Applications, Attachment 2 Also see Simulator Operator Instructions (last page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
IN ITlAL CONDITIONS:
Plant was at full power.
lncores #9 and #35 are inoperable.
CRD #I 1 has dropped into the core.
INITIATING CUES:
During performance of PO-3, Alternate lncore and Excore Applications, the Control Room Supervisor directs you to calculate Excore Quadrant Power Tilt utilizing Power Range NI Channels on Panel C-06.
PALISADES NUCLEAR PLANT I Page 3 of 9 AUGUST 2010
JPM RO ADMIN l a STANDARD TASK ELEMENT 1 Proc.
Step Grade nla Comment:
Evaluator cue: Provide candidate with a Working Copy of PO-3, attachment 2.
s u PO-3, Attachment 2, Excore Quadrant Power Tilt, located.
Correct Procedure located STANDARD Grade TASK ELEMENT 2 Proc.
Step Lower and upper excore readings from the Upper and Lower NI Detector meters on within +I % of the answer key.
s u Obtain lower and upper excore SOL and SAU, SBU, SCU, SOU).
5.2'1 as required*
'6L*
'CL, EC-06 are entered on PO-3, Attachment 2, Comment:
TASK ELEMENT 3 STANDARD Grade Proc.
Step Lower + Upper excore readings (SA, SB, SC, SO) summed and entered on PO-3, I Attachment #2, within +I
% of the answer Calculate the sum from the Lower +
Upper excore readings (SA, SB, SC, SD) 5.2.1 I I I
Comment:
PALISADES NUCLEAR PLANT Page 4 of 9 AUGUST 201 0
JPM RO ADMIN l a TASK ELEMENT 4 STANDARD Grade Proc.
Step Sum of all excores reading divided by 4
Calculate the sum Of all calculated and entered on PO-3,, within f 1% (0.01) of the s u readings divided by 4:
5.2.1 (S = C all detectod4).
answer key.
Comment:
TASK ELEMENT 5 STANDARD Grade Proc.
Step 5.2.1 Calculate the Quadrant Tilt.
Using the formula T E ~
= [(Sx - S)/S],
calculate the tilt for each Quadrant, within
- I%
(0.01) of the answer key.
s u Comment:
EVALUATOR NOTE:
Acceptance criteria is all four Quadrant Tilts should add up to approximately zero (0) +, 0.01.
Have calculations verified.
I I
I I
I Comment:
EVALUATOR CUE:State that someone else will veriflv the calculation.
PALISADES NUCLEAR PLANT Page 5 of 9 AUGUST 2010
JPM RO ADMIN l a TASK ELEMENT 7 STANDARD Proc.
Step Grade n/a END OF TASK Operator notifies CRS of completion of PO-3, Attachment 2, Excore Quadrant Notify the CRS that Excore Quadrant PO-3, Attachment 2.
Power Tilt has been completed per Power Tilt s u PALISADES NUCLEAR PLANT Page 6 of 9 AUGUST 2010
JPM RO ADMIN l a SIMULATOR OPERATOR INSTRUCTIONS SIMULATOR SET UP:
Simulator Setup Instructions:
0 Full power IC 0
Drop CRD #I 1 fully into the core with RD-11 (Final Value = 2) on PIDRD02 0
When plant has stabilized, freeze the Simulator and SNAP 0
Use PO-3, Attachment 2 and recordkalculate from the Upper and Lower NI Detector meters on EC-06 and use as answer key.
PALISADES NUCLEAR PLANT Page 7 of 9 AUGUST 2010
S A L =
51 8(CH D)
Upper Reading(%)
SAUt SBU, SCU, SDU S D L =
52 SAU =
50 SBU =
40 scu =
50 SDU =
49 I
Lower + Upper S = (E All Detectors)/4
= (SA + Se + sc + SD)/4 SA, SB, SC, SD I
+ SAU 101 sc = S C L + scu 101 SD = SDL
+ SDU 101 96 Excore Quadrant Tilt TEA, TEB, TEC, TED QUAD 1
~
~~
QUAD 4 NOTE:
The four QPTs should sum to approximately zero.
Comments:
Performed By: -Pat Person Date:
Today Time:
Now Calculations Verified By:
Date:
After calculations are verified, forward to Reactor Engineering Supervisor or designee for final review.
Reactor Engineering Supervisor or designee:
ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY Date:
ANSWER KEY Page 8 of 9 AUGUST 2010 PALISADES NUCLEAR PLANT
JPM RO ADMIN l a (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
0 Plant was at full power.
0 lncores #9 and #35 are inoperable.
CRD #I 1 has dropped into the core INITIATING CUES:
During performance of PO-3, Alternate ncore and Excore Applications, the Control Room-Supervisor directs you to calculate Excore Quadrant Power Tilt utilizing Power Range NI Channels on Panel C-06.
PALISADES NUCLEAR PLANT Page 9 of 9 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:
RO ADMIN l b TITLE:
RESET UFM CORRECTION FACTORS CAN DI DATE:
EXAM1 NER:
JPM RO ADMlN I b JOBPERFORMANCEMEASURE DATA PAGE Task:
Reset UFM Correction Factors Alternate Path:
PL-OPS-PPC-00 1 J WA:
2.1.19 Importance:
SRO: 3.0 RO:
3.0 WA Statement:
Ability to use plant computer to obtain and evaluate parametric information on system or component status.
UFM correction factors set to 1.OOO and UFM is not enabled on PPC Page 521.
Task Standard:
Preferred Evaluation Location:
Simulator
-X-In Plant Preferred Evaluation Method:
Perform J-Simulate
References:
DWO-1, Operators DailyNVeekly Items MODES 1, 2, 3, and 4 Validation Time:
-1 0-minutes Time Critical: NO Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
Signature PALISADES NUCLEAR PLANT Page 2 of 11 Date:
AUGUST 2010
JPM RO ADMIN I b Tools/Equipment/Procedures Needed:
DWO-1, "Operator's DailyANeekly Items MODES 1, 2, 3, and 4" GOP-8, "Power Reduction and Plant Shutdown to MODE 2 or MODE 3 2 525°F" Tech Data Book Also see Simulator Operator Instructions (later page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The Plant is at 86% power.
INITIATING CUES:
Following a power reduction from full power per GOP-8, the Control Room Supervisor directs you to reset the UFM Correction Factors to 1.OOO in accordance with DWO-1, steps 5.2.3.a through 5.2.3.f.
1 PALISADES NUCLEAR PLANT Page 3 of 11 AUGUST 2010
Grade Proe.Step TASK ELEMENT 1 STANDARD Page 521 of PPC is displayed s u OBTAIN PPC Page 521 UFM PLANT CALORIMETRIC 1 DWO-1 I Locates correct procedure.
Proc.Step TASK ELEMENT 3 Operator locates DWO-1 and refers to step I 5.2.3.a STANDARD Grade I
Comment:
I Evaluator Cue: Provide candidate with a working copy of DWO-I section 5.2.3.
5.2.3.b ProcStep TASK ELEMENT 2 STANDARD Grade I
if UFM CAL ENABLED On PPC Page 521 UFM CAL ENABLED noted to be YES.
PPC Page 521 is correct. Refer to Technical Data Book Figure 14.1.
5.2.3.c I
Comment:
I IF UFM CAL ENABLED will be changed from NOT ENABLED to ENABLED, THEN PERFORM the following:
Determines step is N/A.
s u Proc.Step TASK ELEMENT 4 STANDARD Grade I
PALISADES NUCLEAR PLANT Page 4 of 11 AUGUST 2010
JPM RO ADMIN l b Pr0c.Step TASK ELEMENT 5 STANDARD Grade 5.2.3.d.1 IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN PERFORM the following:
- 1. UPDATE Technical Data Book Figure 14.1 indicating UFM CAL ENABLED status.
Updates Tech Data Book Figure 14.1 for UFM status to Not Enabled.
I I Comment:
5.2.3.d.2 TASK ELEMENT 6 STANDARD Grade I
I IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN PERFORM the following:
to the 100% thermal power limit allowed by Refers to Attachment 12 and determines
- 2. ENSURE HB-PWR-STEADY is lowered power is < 2530 MWt. 2, "1 00% Thermal Power Limit."
s u Comment:
Evaluator Cue: Provide candidate with a working copy of DWO-I Attachment 12.
Proc.Step TASK ELEMENT 7 STANDARD Grade I
I I IF UFM CAL ENABLED will be changed I
from ENABLED to NOT ENABLED, THEN PERFORM the following:
I UFM CAL ENABLED field is selected.
I I 3. SELECT UFM CAL ENABLED.
I s u
~~
Comment:
PALISADES NUCLEAR PLANT Page 5 of 11 AUGUST 2010
JPM RO ADMIN I b IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN
- 4. ENTER N for no.
PERFORM the following:
Proc.Step TASK ELEMENT 8 STANDARD Grade N is entered.
s u 5.2.3 5.23-d.5
.d.4 IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN
- 5. PRESS UPDATE hardkey.
PERFORM the following:
UPDATE hardkey is pressed.
s u Proc.Step TASK ELEMENT I O STANDARD Grade Proc.Step TASK ELEMENT 9 STANDARD Grade I
5.2.3.d.5 IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN PERFORM the following:
- 6. ENSURE UFM Correction Factors set to 1.OOOO. Refer to Step 5.2.3f.
Operator goes to 5.2.3.f.
s u PALISADES NUCLEAR PLANT Page 6 of 11 AUGUST 2010
JPM RO ADMIN I b 5.2.3.f.1 Proc.Step TASK ELEMENT I 1 STANDARD Grade I
ENSURE Technical Data Book Figure 14.1 Enters 1.OOOO for UFM correction factors in is updated.
. Tech Data Book Figure 14.1.
5.2.3.f.3 P roc. S t e p TASK ELEMENT 12 STANDARD Grade I
s u On PPC page 521, data is selected for first UFM Correction Factor.
Select data.
I Comment:
I ProcStep TASK ELEMENT 13 STANDARD Grade I
1 Comment:
I ProcStep TASK ELEMENT 14 STANDARD Grade I
4 Enter new value.
1.OOOO is entered.
s u Comment:
PALISADES NUCLEAR PLANT Page 7 of 11 AUGUST 2010
ProcStep TASK ELEMENT 16 STANDARD Grade Proc.Step TASK ELEMENT 15 STANDARD.
Grade 5.2.3.f.3 Press UPDATE hardkey.
UPDATE hardkey is pressed.
Comment:
On PPC page 521, data is selected for second UFM Correction Factor.
Select data.
Proc.Step TASK ELEMENT 19 STANDARD Grade I
I Comment:
5.2.3.d.7 5.2-3-f-6 ProcStep TASK ELEMENT 17 STANDARD Grade Wait approximately 30 minutes for Heat Balance power to adjust to the change in the UFM Correction Factors.
Operator waits approximately 30 minutes for Heat Balance power to adjust to the change in the UFM Correction Factors.
S U 1.OOOO is entered.
Comment:
Press UPDATE hardkey.
UPDATE hardkey is pressed.
s u Comment:
PALISADES NUCLEAR PLANT Page 8 of 11 AUGUST 2010
JPM RO ADMIN 1 b ProcStep TASK ELEMENT 20 STANDARD Grade I
5.2-3.d.8 5.2.3.f.7 s u Perform a heat balance as soon as plant conditions allow.
Informs CRS that a heat balance is to be performed as soon as plant conditions allow.
Proc.Step END OF TASK TASK ELEMENT 21 STANDARD Grade I
PALISADES NUCLEAR PLANT Page 9 of 11 Operator informs the CRS that the UFM Correction Factors are reset to 1.OOOO per s u Inform CRS that the UFM Correction Factors are reset to 1.OOOO per DWO-1.
DWO-I.
AUGUST 2010
JPM RO ADMIN 1 b SIMULATOR OPERATOR INSTRUCTIONS IC-16,86% power.
Ensure UFM Correction Factors are 0.9890 and 0.9690 on PPC page 521 and Tech Data Book figure 14.1 is updated.
PALISADES NUCLEAR PLANT Page 10 of 11 AUGUST 2010
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
I INITIAL CONDITIONS:
The Plant is at 86% power.
INITIATING CUES:
Following a power reduction from full power per GOP-8, the Control Room Supervisor directs you to reset the UFM Correction Factor to 1.OOO in accordance with DWO-1, steps 5.2.3.a through 5.2.3.f.
PALISADES NUCLEAR PLANT Page 11 of 11 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO ADMIN 2 TITLE: PERFORM DWO4 ACOUSTIC MONITOR 7=DAY CHECK CANDl DATE:
EXAMINER:
JPM RO ADMIN 2 JOBPERFORMANCEMEASURE DATA PAGE Task:
Perform Operators Daily/Weekly/Bi-Weekly items in all MODES Alternate Path: N/A Facility JPM #: NEW WA: 2.2.12 Importance:
RO: 3.7 SRO: 4.1 K/A Statement: Knowledge of surveillance procedures Task Standard: Identification of one out-of-spec reading during the performance of DWO-1 for Acoustic Monitors.
Preferred Evaluation Location: Simulator X In Plant Preferred Evaluation Method:
Perform
-X-Simulate
References:
Validation Time:
15 minutes Time Critical:
NO DWO-1, Operators DailyNeekly Items Modes I
, 2, 3, and 4 Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 7 AUGUST 2010
Tools/Equipment/Procedures Needed:
0 DWO-1, Operators DailyNVeekly Items Modes 1, 2, 3, and 4, Section 6.1 and, DailyNVeekly Surveillance Data Sheet Redinkpen Also see Simulator Operator Instructions (last page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All c trol room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
0 The Plant is at full power.
0 It is Wednesday, 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />.
INITIATING CUES:
You have been directed to take the readings of DWO-1, Item 6.1. ALL remaining readings have already been taken by another NCO.
PALISADES NUCLEAR PLANT Page 3 of 7 AUGUST 2010
JPM RO ADMIN 2 Proc. Step TASK ELEMENT 1 STANDARD Grade nla I Locates correct procedure LOCATES copy of partially completed DWO-1 s u Comment:
EVALUATOR CUE: Provide candidate with a partially completed copy of DWO-I.
Proc. Step TASK ELEMENT 3 STANDARD I
6.1.1 Grade TASK ELEMENT 2 6'1'2 PUSH "read preamp bias" button (should read between 52.5 and 67.5) AND ENTER reading on Attachment 1, "DailyAVeekly Surveillance Data Sheet."
PUSH "high alarm test" pushbutton - high alarm on C-13 should annunciate.
STANDARD
. Pushes "read preamp bias" button for one of
. CHECKS reading between 52.5 and 67.5
. RECORDS reading in "Wednesday Reading" 9 Repeats above three steps for each monitor
. DETERMINES FI-l043B reading is less than 9 CIRCLES in RED FI-10438 reading*
. NOTIFY CRS of the out of spec reading
- the five (5) monitors column for applicable monitor 52.5 s u Comment:
EVALUATOR CUE: If notified as the CRS of the out of spec reading: Acknowledge. If asked if the surveillance should continue: RESPOND to continue with the surveillance.
- NOTE: Not part of the critical step Pushes "high alarm test" pushbutton for one of CHECKS that high alarm on C-I 3 annunciates
- Repeats above two steps for each monitor the five (5) monitors s u Comment:
PALISADES NUCLEAR PLANT Page 4 of 7 AUGUST 2010
JPM RO ADMIN 2 Return completed DWO-1 to CRS
. Inform CRS of out of spec readings (if nla not already done)
Proc. Step TASK ELEMENT 4 STANDARD Grade
= Completed DWO-1 RETURNED to the CRS 9 CRS INFORMED of the out of spec readings (if not already done)
TURN Channel 1 gain switch to highest point - some noise should be present after switch is at highest point.
Turns Channel 1 gain switch clockwise Until I s u 6.1.3 noise is heard.
Comment:
NOTE: Channel 1 gain switch is switch on LEFT side of panel.
Proc. Step TASK ELEMENT 5 STANDARD Grade I
I 6.1.4 I RETURN switch to zero.
9 Turns Channel 1 gain switch counterclockwise I to zero position Comment:
I Proc. Step TASK ELEMENT 6 STANDARD Grade I
9 INITIALS RECRD BY in Wednesday column for 6.,
RECORDS a note at bottom of page that preamp bias for FI-l043B indicated zero 9 Informs CRS that Work Request initiation is reauired for Preamr, bias issue on FI-01438.
IF the pre-amp bias for any of the acoustic monitors is found out of tolerance, THEN INITIATE a work request. The instrument is operable provided the other two checks (alarm operates, audible noise) passed satisfactorily.
s u 6'1m5 EVALUATOR CUE: If notified as the CRS of the out of spec reading and need for a Work Request: Acknowledge.
Proc. Step TASK ELEMENT 7 STANDARD Grade I
Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 5 of 7 AUGUST 201 0
JPM RO ADMIN 2 SIMULATOR OPERATOR INSTRUCTIONS 0
Reset to any full power IC.
Insert the following or use CAE file 0
Ensure copies of DWO-1, Section 6.1 and Attachment 1, page 3 of 4 are available 0
Ensure Simulator clipboard copy of SHO-1, Attachment 1 is the current revision Ensure Channel #I is selected on Audio Channels Switch (Panel C-I 1A rear, top right-hand corner of Acoustic Panel.)
o Override for FI-I 043B Controller Output to 0.01 1597 PALISADES NUCLEAR PLANT Page 6 of 7 AUGUST 2010
~
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Plant is at full power.
It is Wednesday, 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />.
IN IT1 AT1 NG CUES:
You have been directed to take the readings of DWO-1, Item 6.1. All remaining readings have already been taken by another NCO.
PALISADES NUCLEAR PLANT Page 7 of 7 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:
RO ADMIN 3 TITLE:
DETERMINE EXPECTED DOSE FOR EQUIPMENT INSPECTION CANDIDATE:
EXAMINER:
JPM RO ADMIN 3 JOB PERFORMANCE MEASURE DATA PAGE Task:
Determine Expected Dose for Equipment Inspection Alternate Path:
PL-OPS-ADM-002J KIA:
2.3.4 Importance
SRO:
3.7 RO:
3.2 K/A Statement:
Knowledge of radiation exposure limits under normal or emergency conditions.
Task Standard:
Expected dose is calculated to be 4.5 mR (allow 4 to 5 mR).
Preferred Evaluation Location: ANY
-x-Preferred Evaluation Method:
Perform
-X-Simulate
References:
Health Physics Procedure 2.14, "Radiological Surveys" Validation Time:
minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 8 AUGUST 2010
JPM RO ADMIN 3 Tools/Equipment/Procedures Needed:
Current "Radiological Area Status Sheet" for East Safeguards READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The Plant is in a refueling outage. Work is in progress on P-67A Low Pressure Safety Injection Pump. A report has been received in the Control Room that scaffold erecting activities may have damaged the seal cooler and seal injection lines for P-67A.
INITIATING CUES:
You have been assigned the task of inspecting P-67A seal cooler and seal injection lines for damage. This will require close inspection (within 2 feet of pump skid area next to the seal cooler), but you are NOT to cross any contamination boundary. The inspection is expected to require 15 minutes to complete.
Determine the maximum expected radiation dose you will receive for this task.
PALISADES NUCLEAR PLANT Page 3 of 8 AUGUST 2010
JPM RO ADMIN 3 ProcStep Proc.Step TASK ELEMENT I STANDARD Grade I
TASK ELEMENT 3 STANDARD Grade Obtains "Radiological Area Status Sheet" for East Engineering Safeguards.
Obtains correct survey map for P-67A.
Comment:
EVALUATOR CUE: Provide candidate with attached Radiological Area Status Sheet and picture of P-67A skid.
I Grade ProcStep TASK ELEMENT 2 STANDARD
--- I Determine dose rate near the component.
I Dose rate determined to be 18 mRem/hr.
s u Comment:
EVALUATOR NOTE: Candidate should select 78 mWhr dose rate reading from Status Sheet since this is the general area where seal cooler is located.
--- I Calculates expected dose.
Expected dose calculated to be 4.5 mRem.
s u Comment:
EVALUATOR NOTE: 18 mRem/hr X 0.25 hr = 4.5 mR (allow 4-5 mR)
PALISADES NUCLEAR PLANT END OF TASK Page 4 of 8 AUGUST 201 0
JPM RO ADMIN 3 SIMULATOR OPERATOR INSTRUCTIONS Simulator NOT required for this JPM.
PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010
JPM RO ADMIN 3 Radiological Survey Sheet Room ID RWP#
Item Description DatelTime 4
2010 010 Aux Bldg 570' East Engineered Safeguards 8/16/10 2330 I
Meter TypdSerial No.
Meter TypelSerial No.
Meter TypelSerial No.
3 Smear 7
Reviewed by Date Gamma status Shee"RWP Updated Yes XYZ1/1234~A NIA NIA 0 Beta Sup,eyed/&corde. by 1
Frisk 0 Neutron J Technician J Supervisor 8/16/10 Note: All Dose Rates in mRemlhr unless otherwise noted Comments:
5 P-66A 3 1 Smears I dpmllOOcn?
Masslinn Wipe I dpmlMasslinn Alpha Smear PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010
JPM RO ADMIN 3 PALISADES NUCLEAR PLANT Page 7 of 8 AUGUST 2010
JPM RO ADMIN 3 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Plant is in a refueling outage. Work is in progress on P-67A Low Pressure Safety Injection Pump. A report has been received in the Control Room that scaffold erecting activities may have damaged the seal cooler and seal injection lines for P-67A.
INITIATING CUES:
You have been assigned the task of inspecting P-67A seal cooler and seal injection lines for damage. This will require close inspection (within 2 feet of pump skid area next to the seal cooler), but you are NOT to cross any contamination boundary. The inspection is expected to require 15 minutes to complete.
Determine the maximum expected radiation dose you will receive for this task.
PALISADES NUCLEAR PLANT Page 8 of 8 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:
SROADMIN l a TITLE: DETERMINE COMPENSATION FOR A WITHDRAWN, INOPERABLE CONTROL ROD CAN D I DATE :
EXAM I NER:
JPM SRO ADMIN l a JOBPERFORMANCEMEASURE Task: Determine Compensation for a Withdrawn, Inoperable Control Rod Alternate Path:
PL-OPS-ENG-01 I J
WA:
2.1.25 Importance: RO:
3.9 SRO: 4.2 WA Statement:
Ability to interpret reference materials, such as graphs, curves, tables, etc.
EM-04-08, Attachment I properly completed per key.
Task Standard:
Preferred Evaluation Location:
ANY -X-Preferred Evaluation Method:
Perform
-X-Simulate
References:
EM-04-08, Shutdown Margin Requirements Validation Time:
minutes Time Critical: NO Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
PALISADES NUCLEAR PLANT Signature Page 2 of 16 Date:
AUGUST 2010
JPM SRO ADMIN l a Tools/Equipment/Procedures Needed:
EM-04-08, "Shutdown Margin Requirements" Technical Data Book Calculator READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
I N IT1 AL CON D IT1 ON S :
0 Rod #6 is inoperable and fully withdrawn.
0 It is believed that the rod is untrippable.
0 Burnup is 7,000 MWD/MTU.
0 Rx power is loo%, PCS Boron is 865 ppm. All rods out, equilibrium Xenon.
INITIATING CUES:
The Control Room Supervisor directs you to determine the compensation for shutdown margin required for control rod #6 utilizing EM-04-08.
[Provide a calculator to the examinee for this JPM.]
PALISADES NUCLEAR PLANT Page 3 of 16 AUGUST 2010
JPM SRO ADMlN l a TASK ELEMENT I
- proc, Step STANDARD Grade Locate correct procedure.
TASK ELEMENT 2 STANDARD Grade PrOC.
Step EM-04-08 and Tech Data Book located.
Determine EM-04-08, Attachment #1 is the correct attachment.
S U Record inoperable control rod identification.
TASK ELEMENT 4 STANDARD Grade Proc.
Step r
I A, 6 and untrippable recorded.
3 Comment:
~
~
Record source of inoperable control rod worth data.
Tech Data Book entered.
s u Comment:
EVALUATOR CUE: Reactor Engineering is not available.
Comment:
PALISADES NUCLEAR PLANT Page 4 of 16 AUGUST 2010
JPM SRO ADMIN l a TASK ELEMENT 5 Roc.
SMP Grade STANDARD Record current cycle burnup.
Record current cycle burnup = 7000.
s u Comment:
TASK ELEMENT 6 STANDARD Grade PCOC.
Step k
4 TASK ELEMENT 7 Proc.
Step Record current power level.
'1 00' entered.
s u
.I Comment:
STANDARD Grade TASK ELEMENT 8 Roc.
Step Control rod worth inserted into core.
'0' and 'Gp 4 @ 131/132" entered.
Comment:
STANDARD Grade Record PCS Boron concentration.
'865' entered.
s u Comment:
PALISADES NUCLEAR PLANT Page 5 of 16 AUGUST 2010
JPM SRO ADMlN l a TASK ELEMENT 10 Proc.
Step
'7.05 (7.04 to 7.06)' entered.
STANDARD Grade Comment:
TASK ELEMENT 11 STANDARD Proc.
step Grade Determine and record max worth of to 8), entered.
I S
F I stuck rod at current power.
I 5.G Determine and record PCS boron concentration at 100% at 7000 MWDIMTU.
TASK ELEMENT 12 Proc.
Step
'865 (860 to 870)' entered.
STANDARD Grade 14 Comment:
Determine and record power defect for
.53.51 to.55)9 entered.
100% power.
I 5.H I I s u PALISADES NUCLEAR PLANT Page 6 of 16 AUGUST 2010
TASK ELEMENT 13 STANDARD Grade PrOC.
Step I
5 s u Determine and record power defect at
.53 to.55), entered.
current power level.
TASK ELEMENT 14 Proc.
Step STANDARD Grade Comment:
5.5 Determine and record required SDM.
2.0 already entered.
s u r
TASK ELEMENT 15 Proc.
Step I 1.82 (1.80 to 1.84) entered.
Calculate Net amount of shutdown STANDARD Grade Comment:
TASK ELEMENT 16 STANDARD
- Proc, Step Grade Enter worth of untrippable rod.
1.17 (1.16 to 1.18)entered.
s u Comment:
PALISADES NUCLEAR PLANT Page 7 of 16 AUGUST 201 0
JPM SRO ADMIN l a TASK ELEMENT 17 STANDARD Grade Proc.
step s
6M Determine excess shutdown margin with the inoperable rod.
0.65 (0.645 to 0.655) entered. Determines Step 7 substeps are N/A.
TASK ELEMENT 18 STANDARD Grade 7N-Q Determines Step 7 substeps are NIA.
s u IF Shutdown margin is negative, THEN...
TASK ELEMENT 19 STANDARD Grade Proc.
step TASK ELEMENT 20 Proc.
Step s u 8.R at lol,,
to entered.
Determine and record PPC PDlL for current power level.
Grade STANDARD Comment:
8.S Determine and record control rod shutdown margin.
position corresponding to excess Group 4 at 20 (1 8 to 22) entered.
s u Comment:
PALISADES NUCLEAR PLANT Page 8 of 16 AUGUST 2010
JPM SRO ADMIN l a TASK ELEMENT 21 STANDARD Proc.
step Grade I s u l Group 4 at 101 (100 to 105) entered.
I Determine and record PDlL for inoperable control rod condition.
I 8-T I TASK ELEMENT 23 STANDARD ProC.
Step Comment:
Grade TASK ELEMENT 22 STANDARD Grade Pro%
step TASK ELEMENT 24 STANDARD Grade Proc.
Step Comment:
NA CRS notified.
s u Report results to Control Room Supervisor.
Sign and date Step 9.
Operator signs and dates.
s u Comment:
EVALUATOR CUE: End JPM I Note: Attach completed EM-04-08, Attachment 1 to this JPM.
PALISADES NUCLEAR PLANT Page 9 of 16 AUGUST 2010
PALISADES NUCLEAR PLANT
~
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. Page 10 of 16 AUGUST 2010
JPM SRO ADMIN l a SIMULATOR OPERATOR INSTRUCTIONS NONE PALISADES NUCLEAR PLANT Page 11 of 16 AUGUST 2010
~
~
Proc No EM-04-08 Revision 30 Page 1 of 4 UNTRIPPABLE OR DROPPED CONTROL ROD SHUTDOWN MARGIN CALCULATION
- 1.
UNTRIPPABLE OR DROPPED CONTROL ROD IDENTIFICATION:
GROUP A
NUMBER 6
CONDITION untrippable (Untrippable or Dropped)
- 2.
WORTH OF UNTRIPPABLE OR DROPPED 1.17 CONTROL ROD (TDB Figure 1.I or Reactor Engineering)
- 3.
SOURCE OF UNTRIPPABLE OR DROPPED CONTROL ROD WORTH DATA:
- 4.
REFERENCE DATA A.
CURRENT CYCLE BURNUP (TDB Fig 1.10)
- 6. CURRENT REACTOR POWER LEVEL (Percent of Rated Power)
C. CONTROL ROD WORTH INSERTED INTO CORE (TDB Fig 1.3)
GROUP 4 INCHES 132 (or 131 }
This Control Rod worth does not include the worth of a dropped Control Rod.
D.
PCS BORON CONCENTRATION (Chemistry Log or Reactor Logbook)
PALISADES NUCLEAR PLANT Page 12 of 16 7000 MWd/MTU I00 0
%Ap 865 PPm AUGUST 2010
Proc No EM-04-08 Revision 30 Page 2 of 4 UNTRIPPABLE OR DROPPED CONTROL ROD SHUTDOWN MARGIN CALCULATION
- 5.
GENERAL DATA E.
WORTH OF ALL CONTROL RODS AT A (TDB Fig 1.I)
F.
MAXIMUM WORTH OF STUCK CONTROL ROD AT A (TDB Fig 1,I)
G. PCS BORON AT 100% POWER AT A (TDB Fig 6.1, Reactor Log)
H.
POWER DEFECT AT 100% POWER (TDB Fig 3.2 and G )
7.05
%Ap 1.I7
%Ap 865 PPm 1.53
%Ap I.
POWER DEFECT AT POWER B 1.53
%Ap H x B - (1.53) x (100) 100 100 J.
REQUIRED SHUTDOWN MARGIN (4 PCPs Operating)
- 6.
CALCULATION K.
NET AMOUNT OF SHUTDOWN MARGIN (E - C - F) 1.I
- I - J
[(7.05) - (0) - 1.171 1.1
- (1.53) - (2.0) =
PALISADES NUCLEAR PLANT Page 13 of 16 2.0
%Ap 1.82
%Ap AUGUST 2010
- 7.
Proc No EM-04-08 Revision 30 Page 3 of 4 UNTRIPPABLE OR DROPPED CONTROL ROD SHUTDOWN MARGIN CALCULATION L.
WORTH OF UNTRIPPABLE OR DROPPED CONTROL ROD Step 2 M.
EXCESS SHUTDOWN MARGIN WITH ONE UNTRIPPABLE OR DROPPED CONTROL ROD 1.17
%Ap 0.65
%Ap K - L = (1.82) - (1.17)
=
IF excess Shutdown Margin (M) is NEGATIVE, THEN borate the PCS to reduce reactor power until M is POSITIVE performing Steps N through Q to calculate the maximum reduced reactor power level.
N.
POWER DEFECT AT REDUCED POWER I + M = (
) + (
)
=
N/A
%Ap
- 0.
MAXIMUM REDUCED POWER LEVEL P.
Caution Tag the Control Rod joy-stick on panel C-02 that the new PDlL is Control Rod position at C.
N /A Q. -
IF power reduction is required, THEN after power reduction re-perform Attachment 1 to verify Shutdown Margin requirements are satisfied.
N/A PALISADES NUCLEAR PLANT Page 14 of 16 AUGUST 2010
Proc No EM-04-08 Revision 30 Page 4 of 4 UNTRIPPABLE OR DROPPED CONTROL ROD SHUTDOWN MARGIN CALCULATION
- 8.
IF M is POSITIVE, THEN sufficient Shutdown Margin is available and no power reduction is necessary to ensure required Shutdown Margin. Perform Steps R though U to determine maximum allowable Control Rod insertion limit corresponding to excess Shutdown Margin available (M).
R.
PPC PDlL FOR CURRENT POWER LEVEL (TDB Fig 1.9)
Group 4
Inches 101 S.
CONTROL ROD POSITION CORRESPONDING Group 4
TO EXCESS SHUTDOWN MARGIN IN M (TDB Fig 1.3 or 5.1 and M)
Inches 20 T.
PDlL FOR UNTRIPPABLE OR DROPPED CONTROL ROD CONDITION (R or S, whichever is farthest withdrawn)
Group 4
Inches 101 U.
the Control Rod position in S is farther withdrawn than the Control Rod position in R, THEN Caution Tag the Control Rod joy-stick on panel C-02, identifying that the new PPC PDlL as the Control Rod position in S.
- 9.
REVIEWS (Operators Name)
I (Today)
Performed By Date I
Reviewed By Date Forward Completed Form to Reactor Engineering Supervisor I
Reactor Engineering Supervisor Date PALISADES NUCLEAR PLANT Page 15 of 16 AUGUST 2010
JPM SRO ADMIN l a (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Rod #6 is inoperable and fully withdrawn.
It is believed that the rod is untrippable.
0 Burnup is 7,000 MWD/MTU.
0 Rx power is loo%, PCS Boron is 865 ppm. All rods out, equilibrium Xenon.
INITIATING CUES:
The Control Room Supervisor directs you to determine the compensation for shutdown margin required for control rod #6 utilizing EM-04-08.
[Provide a calculator to the examinee for this JPM.]
PALISADES NUCLEAR PLANT Page 16 of 16 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:
SRO ADMIN l b TITLE:
CALCULATE BLEND RATIO FOR MAKEUP TO SIRWT CAN D I DATE :
EXAMINER:
JPM SRO ADMIN I b JOB PERFORMANCE MEASURE DATA PAGE Task:
Perform Safety Injection Refueling Water Tank Operations Alternate Path: NIA Facility JPM #: PL-OPS-ENG-O19J KIA:
2.1.34 Importance:
RO:
2.3 SRO:
2.9 K/A Statement: Ability to maintain primary and secondary plant chemistry within allowable limits.
Task Standard: Correct volume of Boric Acid and Primary Makeup Water Calculated for addition to SIRWT Preferred Evaluation Location:
Any
-x_
Preferred Evaluation Method:
Perform -X-Simulate
References:
SOP-2A, Chemical and Volume Control System Technical Data Book, figure 8.2 Validation Time: minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 8 AUGUST 2010
JPM SRO ADMIN I b Tools/Equ ipment/Procedu res Needed:
SOP-2A, "Chemical and Volume Control System" Calculator Pencil and paper READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performec. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Safety Injection Refueling Water Storage Tank boron concentration = 2149ppm Safety Injection Refueling Water Storage Tank level = 96%
Boric Acid Storage Tank T-53A boron concentration = 12,524ppm INITIATING CUES:
The Control Room Supervisor directs you to perform SOP-2A section 7.6.1.a to calculate the volumes of Boric Acid and Primary Makeup water needed to raise SIRWT level by 3000 gallons while maintaining current SlRWT boron concentration.
PALISADES NUCLEAR PLANT Page 3 of 8 AUGUST 2010
JPM SRO ADMIN I b Proc. Step TASK ELEMENT 1 STANDARD Grade Operator locates correct procedure SOP-2A section 7.6.1 located s u Comment:
EVALUATOR CUE: Provide candidate a working copy of SOP-2A Section 7.6.7 7.6.1.a Caution Comment:
TASK ELEMENT 2 During makeup operations to the SIRWT:
- 1. Makeup to the volume control tank is not available.
- 2. Opening CV-2155, Boric Acid Blender Outlet Control Valve, will inject the blended batch intended for the SIRWT into the PCS.
- 3. Additions that exceed 2500 ppm may result in exceeding boron concentration limits of Technical Specifications LCO 3.5.4. SITS may also be affected during fill and drain operations STANDARD Operator reviews caution s u Proc. step 7.6.1.a.l Comment:
TASK ELEMENT 3 To determine the amount of boric acid and primary makeup water to be transferred to SlRW tank, REFER TO the following formulas:
SlRW Tank Volume = (% meter reading x 2797) + 18,646 Where:
SlRW Tank Volume = SlRW total gallons
% meter reading = LIA-0332A or LIA-0331.
STANDARD Operator calculates the following:
Amount of volume to add = 3000 gallons (give in initial conditions)
PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010
JPM SRO ADMIN Ib 7.6.1.a.2 Blend Ratio = (BAST ppm/SIRW ppm)
- 1 Where:
Blend Ratio = gallons of PMW per 1 gallon of concentrated Boric Acid BAST ppm = 12,524 SIRWT ppm = 2149 STANDARD Operator calculates the following:
(12,524/2149) - 1 = 4.83 (allow 4.80 -
4.85)
Comment:
EVALUATOR NOTE: Allow 4.80 to 4.86 7.6.1.a.3 TASK ELEMENT 5 Gallons of concentrated boric acid to add = Total Volume Makeup to SIRW/(Blend Ratio + 1)
Where:
Total Volume Makeup to SlRWT =
Desired SIRWT level in gallons minus current level in gallons Blend Ratio = gallons of PMW per 1 gallon of concentrated Boric Acid Comment:
EVALUATOR NOTE: Allow 511.9 - 517.2 STANDARD Operator calculates the following:
3000/(4.83 + 1) = 514.6 gal of boric acid s u PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010
JPM SRO ADMIN 1 b 7.6.1.a.4 TASK ELEMENT 6 Gallons of PMW to add = Total volume makeup to SIRWT - Gallons of Boric Acid to add Where:
Total Volume Makeup to SIRWT =
Desired SIRWT level in gallons minus current level in gallons Gallons of Boric Acid to Add = Item 3.
above Comment:
EVALUATOR NOTE: Allow 2483 - 2488 STANDARD Operator calculates the following:
3000 - 514.6 = 2485.4 gal of PMW s u TASK ELEMENT 7 STANDARD Grade Proc.
step r
nla Operator informs Control Room Supervisor of the volume of boric acid and primary makeup water to add.
CRS informed of the following volumes:
Primary Makeup Water: 2485.4 gal Concentrated Boric Acid: 514.6 nal s u Comment:
EVALUATOR NOTE: Allow 2483 - 2488 gal for Primary Makeup Water and 511.9 -
517.2 gal for Boric Acid EVALUA TOR CUE: Role play as CRS END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010
JPM SRO ADMIN Ib SIMULATOR OPERATOR INSTRUCTIONS PALISADES NUCLEAR PLANT Page 7 of 8 AUGUST 2010
JPM SRO ADMIN I b (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Safety Injection Refueling Water Storage Tank boron concentration = 2149ppm Safety Injection Refueling Water Storage Tank level = 96%
Boric Acid Storage Tank T-53A boron concentration = 12,524ppm INITIATING CUES:
The Control Room Supervisor directs you to perform SOP-2A section 7.6.1.a to calculate the volumes of Boric Acid and Primary Makeup water needed to raise SlRWT level by 3000 gallons while maintaining current SIRWT boron concentration.
PALISADES NUCLEAR PLANT Page 8 of 8 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE
JPM SRO ADMlN 2 JOB PERFORMANCE MEASURE DATA PAGE Task:
Approve a heavy load movement Alternate Path: N/A Facility JPM #: PL-OPS-ADM-001 J K/A: 2.2.14 Importance: SRO: 4.3 WA Statement: Knowledge of the process for controlling equipment configuration or status Task Standard: Approve a heavy load movement, ensuring all prerequisites and operational requirements are met.
Preferred Evaluation Location: ANY x -
Preferred Evaluation Method:
Perform
-X-Simulate
References:
FHS-M-23, Movement Of Heavy Loads In The Spent Fuel Pool Area Administrative Procedure AP 4.02, Control Of Equipment Validation Time:
20 minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 16 AUGUST 2010
JPM SRO ADMlN 2 ToolslEquipmentlProcedures Needed:
FHS-M-23, Movement Of Heavy Loads In The Spent Fuel Pool Area, Attachment I, Rev. 29, Heavy Load Data Sheet, with applicable sections completed by Heavy Load Person In Charge (HL PIC)
Also see Simulator Operator Instructions (last page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
e e
e e
e e
e e
e e
e e
e The Plant is in Mode 1 A refueling outage was completed 95 days ago, with all spent fuel from the core stored in the south end of the Spent Fuel Pool You are an on-shift SRO It is Tuesday, Night shift, 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br /> V-IO, Radwaste Area Supply Fan; V-14A and V-146 Radwaste Area Exhaust Fan are in service Both Control Room HVAC trains for filtration and cooling are operable, with the left train in service, normal operation VF-66, Fuel Pool Area Refueling Charcoal Filter, is bypassed (not in service)
V-7, Fuel Handling Area Supply Fan; V-8A and V-8B, Radwaste Area Exhaust Fans are in service Mechanical Maintenance has requested to move the MSB Shielding Lid from the Cask Washdown Pit onto the loaded fuel cask, in the Spent Fuel Pool This evolution is expected to begin immediately after authorization and to be completed by 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> No other load movements are planned or in progress No fuel movement in the SFP is planned or in progress All spent fuel in the north tilt pit and has decayed for greater than one year INITIATING CUES:
The Shift Manager directs you to approve the requested load movement, ensuring all Operational prerequisites and requirements are met prior to the approval.
PALISADES NUCLEAR PLANT Page 3 of 16 AUGUST 2010
JPM SRO ADMIN 2 n'a Proc. Step TASK ELEMENT 1 STANDARD Grade I
I FHS-M-23, Att. 1, Heavy Load Data Sheet located, with applicable sections completed by HL PIC Operator obtains FHS-M-23, Att. 1 r
Proc. Step TASK ELEMENT 3 STANDARD Grade I
t I
s u Att. 6 Comment:
EVALUATOR CUE Provide candidate the HL PIC completed FHS-M-23, Aft. I Working COPY.
NO -
of DFS components between cask wash-down pit and cask loading floor area, Att.3 Is the load movement within Load Path 3 only?
Heavy Load path #4 determined for movement s u Proc. Step TASK ELEMENT 2 STANDARD Grade I
SRO determines:
YES, Object is a heavy load (MSB Shield Lid weighs 6457 Ibs from Att. 2) s u I Comment:
I EVALUATOR CUE:Provide candidate with a working copy of FHS-M-23.
PALISADES NUCLEAR PLANT Page 4 of 16 AUGUST 201 0
JPM SRO ADMIN 2 Proc. step TASK ELEMENT 4 STANDARD Grade I
TASK ELEMENT 5 STANDARD Grade I
I Will loads be moved over Load Path I? I Att. 6 Aft. 6 I s u Will loads be moved over Load Path 4 (Main Fuel Pool)?
YES Comment:
EVALUATOR CUE:lf asked by SRO what load move will be taking place, Reply: the MSB Shielding Lid is being moved from the Cask Wash-down area to the loaded fuel cask in the Spent Fuel Pool.
Proc. Step TASK ELEMENT 6 STANDARD Grade I
Att. 6 s u Has fuel decayed 2 30 days?
YES (given in the initial conditions) s u Comment:
PALISADES NUCLEAR PLANT Page 5 of 16 AUGUST 2010
JPM SRO ADMIN 2 Att. 6 Proc. Step TASK ELEMENT 7 STANDARD Grade Has fuel decayed 190 days?
YES (given in the initial conditions) s u Proc. step TASK ELEMENT 8 STANDARD Grade Both CRHVAC filtration trains verified operable S U I
Both CRHVAC filtration operable (refer to TS 3.7.10 if one train inoperable)
Att. 6 Comment:
EVALUATOR CUE: If asked by SRO if both CRHVAC Filtration trains are operable, RESPOND: they are not on the LCO or LCO Annex sheet for being inoperable or degraded.
Proc. Step TASK ELEMENT 9 STANDARD Grade I
I I
Both CRHVAC cooling operable (refer to TS 3.7.1 1 if one train inoperable)
Att. 6 Both CRHVAC cooling trains verified operable S U Comment:
EVALUATOR CUE: If asked by SRO if both CRHVAC cooling trains are operable, RESPOND: they are not on the LCO or LCO Annex sheet, for being inoperable or degraded.
I Proc. Step TASK ELEMENT 10 STANDARD Grade I
PALISADES NUCLEAR PLANT Page 6 of 16 AUGUST 2010
Proc. Step TASK ELEMENT I 1 STANDARD Grade I
VF-66 maybe bypassed OR out of service At least one V-8 shall be inservice One V-8 fan verified inservice s u Proc. step Comment:
TASK ELEMENT 12 STANDARD Grade I
Att. 6 Will loads be moved over Load Path 2? -
NO s u Comment:
Evaluator Note: Candidate may answer YES and review Section 4.2.7 Proc. Step TASK ELEMENT 13 STANDARD Grade I
Att. 6 Comment:
Will loads be moved over Load Path 3? -
NO s u Proc. Step I
Grade TASK ELEMENT 14 STANDARD PALISADES NUCLEAR PLANT Att. 6 Page 7 of 16 Will non-heavy loads be moved under this procedure?
_I NO (given in initial conditions) s u AUGUST 2010
Proc. Step TASK ELEMENT 15 STANDARD Grade Att. 6 Proc. Step TASK ELEMENT 16 STANDARD Grade I
s u Will load be moved in an alternate path?
NO (Path 4 is the only path for this evolution) 5.11a Comment:
I On-Shift, Duty SRO m:
Review and understand Sections 1.O through 4.0 of procedure.
SRO references Section 1.O through 4.0, and ensures:
No fuel movements in SFP Area (given in initial conditions) s u Prw. Step TASK ELEMENT 17 STANDARD Grade I
5.1.lb On-Shift, Duty SRO m:
SRO verifies plant systems and conditions are ensuring Att. 6 complete) met.
ENSURE plant systems and conditions are met (has effectively completed this step by s u
~
Comment:
On-Shift, Duty SRO shall:
Complete Attachment 1 to document permission to commence heavy load movement for approved Load Paths during specified time period.
5*1*1c I
Grade Proc. Step TASK ELEMENT 18 STANDARD SRO enters on FHS-M-23, Att. 1 :
Sinns. Dates and Times, in box (8)
TOdav1930 for Start in box (9)
Todav/2300 OR 0700 tomorrow/ Sinned for Stop in box(9) s u I Comment:
Evaluator Note: one-week duration limit found in Section 3.1.3d PALISADES NUCLEAR PLANT Page 8 of 16 AUGUST 2010
Grade Proc. Step TASK ELEMENT I 9 STANDARD f
On-Shift, Duty SRO m:
DOCUMENT authorization of heavy loads SRO makes entry.
movements in the Operations log.
s u Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 9 of 16 AUGUST 2010
JPM SRO ADMIN 2 SIMULATOR OPERATOR INSTRUCTIONS 0
N/A PALISADES NUCLEAR PLANT Page 10 of 16 AUGUST 2010
(1) Date: TODAY (4) Procedure used in conjunction w/FHS-M-23: NONE (6) General Description of HL(s) Allowed (Can attach schedule to satisfy)
To Be Moved MSB Shielding Lid 2300 (OR TODAY (OR STOP:
Tomorrow) 0700)
(2) Work Order No:
51 99999 (3) Authorization Period:
(5) Special precautions to be taken:
Measure uirder temperature for sinule failure power lift x Shift c] Daily 0 Week (7) HL Path(s)
Authorized For SRO Start: (Date / Time) Stop: (Date /Time)
(8) Approved By: On-Shift, Duty (9) HL Duration Approved Use (Name / Date /Time) 4 J Onerator/ TODAY I NOW START:
TODAY 1930
{IO) CALIBRATED EQUIPMENT (If Required)
FLUKE Model 8660 0-2OO0F/ f.02"F CMS234567 06/0 1 /20 1 0 06/01/2011 (11) HL PIC Name / Date / Time (Print)
J JOHNSON/ TODAY/ NOW (12) Crane (1 3) Crane Operator (14) Signal Person (15) On-Shift, Duty SRO Inspection Name / Date / Time Name / Date / Time Contacted -- Name Complete (4)
(Print)
(Print)
(Print)
X PALISADES NUCLEAR PLANT Page 11 of 16 AUGUST 2010
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Proc No FHS-M-23 Attach men t 1 Revision 29 Page 1 of 4 HEAVY LOAD DATA SHEET Instructions for completion of Attachment 1 :
- 1.
ENTER today's date.
- 2.
ENTER Work Order number that controls movement of heavy loads.
NOTE:
Heavy Load Person-in-Charge will contact the Work Control Center or Control Room each shift to ensure that plant conditions have not changed.
- 3.
- 4.
- 5.
- 6.
- 7.
CHECK time period where authorization from an On-Shift Duty SRO will be required (Shift, Daily, or Week).
ENTER any procedure used in conjunction with FHS-M-23.
ENTER any special precautions or temperature measurements for bridge girder (See Step 3.4.1 h).
ATTACH schedule information to Attachment 1 or list general description of heavy loads to be moved.
LIST heavy load paths authorized for use.
NOTE:
This information is only required to approve the beginning of heavy load movements for an extended load move campaign. All subsequent authorizations can be handled over the phone (See Section 3.1).
- 11.
- 12.
- 13.
- 14.
- 15.
- 16.
- 17.
- 18.
- 19.
- 20.
- 8.
- 9.
I O. Enter calibrated equipment information.
On-Shift, Duty SRO PRINT name, date, and time (SRO authorization required before starting heavy load movements. SRO authorization confirms plantkystedcomponent conditions are met. SRO signature not required for Load Path No 3 or non-heavy loads covered under this procedure).
LIST START date and time. LIST STOP date and time (this can not exceed time period authorized in Step No 3).
NOTE:
Multiple Page 3 of this attachment may be used for an extended moving campaign.
Heavy Load Person-in-Charge (HL PIC) PRINT name, date, and time (HL PIC signoff confirms proper load path, weight, 8, rigging requirements are understood and will be met. Each time HL PIC changes, new information shall be entered).
Crane Inspection requires Crane Operator to ENSURE daily crane inspection is completed. PLACE a check (0) in the box next to the Crane Operator that performed the inspection.
Crane Operator PRINT name, date, and time (Crane Operator signoff confirms understanding of heavy load requirements AND that all heavy load prerequisites, precautions & limitation, and equipmentlplant safety or limits are met. Each time Crane Operator changes, new information shall be entered).
Signal Person PRINT name, date, and time (Signal Person signoff confirms understanding of heavy load requirements AND that all heavy load prerequisites, precautions & limitation, and equipment/plant safety or limits are met. Each time Signal Person changes, new information shall be entered).
Heavy Load Person-in-Charge will DOCUMENT On-Shift, Duty SRO that was contacted by printing name.
Page 3 duplicates the information recorded in Items 11 through 15.
DESCRIBE Alternate Load Path (assistance may be required from Engineering to best determine how to best fulfill Step 5.1.4i). CIRCLE YES or NO for Attachment.
IF alternate load path is required, THEN OBTAIN Reactor Engineer approval. [CMT891009645, CMT9220014771 IF alternate load path is required, THEN OBTAIN On-Shift Duty SRO approval. [CMT891009645]
PROVIDE a sketch in the space provided (when adequate space is not available, an Attachment can be attached -- See Item 17).
PALISADES NUCLEAR PLANT Page 12 of 16 AUGUST 2010
HEAVY LOAD DATA SHEET (1) Date: TODAY (4) Procedure used in conjunction wIFHS-M-23: NONE (6) General Description of HL(s) Allowed (Can attach schedule to satisfy)
To Be Moved MSB Shielding Lid Proc No FHS-M-23 Revision 29 (2) Work Order No: 51 99999 (5) Special precautions to be taken:
Measure airder temperature for sinale failure power lift (3) Authorization Period:
x Shift 0
Daily 0
Week (7) HL Path@)
Authorized For SRO Use 4
(8) Approved By: On-Shift, Duty (Name / Date / Time)
(9) HL Duration Approved Start: (Date I Time) Stop: (Date I Time)
I I
START:
/
FLUKE Model 8660 I
I I
I I
0-20O"Fl f.02"F CMS234567 06/0 1 120 1 0 06/0 1 /20 1 1 I STOP:
I
/lo) CALIBRATED EQUIPMENT (If Required)
(11) HL PIC Name / Date / Time (Print)
J JOHNSON/ TODAY/ NOW (12) Crane (13) Crane Operator (14) Signal Person (15) On-Shift, Duty SRO Inspection Name I Date I Time Name I Date I Time Contacted -- Name Complete (4)
(Print)
(Print)
(Print)
X
HEAVY LOAD DATA SHEET Proc No FHS-M-23 Revision 29 PALISADES NUCLEAR PLANT Page 14 of 16 AUGUST 2010
HEAVY LOAD DATA SHEET (18) Approved By:
I Reactor Engineer Date Proc No FHS-M-23 Revision 29 (1 9) Approved By:
I On-Shift, Duty SRO Date Page 4 of 4 (17) Alternate Load Path (if used),
Description:
PALISADES NUCLEAR PLANT Page 15 of 16 AUGUST 2010
JPM SRO ADMIN 2 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Plant is in Mode I A refueling outage was completed 95 days ago, with all spent fuel from the core stored in the south end of the Spent Fuel Pool You are an on-shift SRO It is Tuesday, 'Night' shift, 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br /> V-IO, Radwaste Area Supply Fan; V-14A and V-146 Radwaste Area Exhaust Fan are in service Both Control Room HVAC trains for filtration and cooling are operable, with the left train in service, normal operation VF-66, Fuel Pool Area Refueling Charcoal Filter, is bypassed (not in service)
V-7, Fuel Handling Area Supply Fan; V-8A and V-86, Radwaste Area Exhaust Fans are in service Mechanical Maintenance has requested to move the MSB Shielding Lid from the Cask Washdown Pit onto the loaded fuel cask, in the Spent Fuel Pool This evolution is expected to begin immediately after authorization and to be completed by 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> No other load movements are planned or in progress No fuel movement in the SFP is planned or in progress All spent fuel in the north tilt pit and has decayed for greater than one year INITIATING CUES:
The Shift Manager directs you to approve the requested load movement, ensuring all Operational prerequisites and requirements are met prior to the approval PALISADES NUCLEAR PLANT Page 16 of 16 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 3 TITLE: DETERMINE INCREASED MONITORING LEAK PROCEDURE ACTIONS PER ONP-23.2, STEAM GENERATOR TUBE CANDIDATE:
EXAM I NER:
JPM SRO ADMIN 3 JOBPERFORMANCEMEASURE DATA PAGE Task:
Respond to Steam Generator Tube leakage in accordance with ONP-23.2 Alternate Path:
NEW WA:
2.3.11 Importance:
RO:3.8 SRO:
4.3 WA Statement: Ability to control radiation releases.
Task Standard: Determines RIA-0631 count rate of 8.5E+03 cpm (allow 8.3E+03 to 8.7E+03 cpm)
Preferred Evaluation Location: Simulator -X-In Plant Preferred Evaluation Method:
Perform
-X-Simulate
References:
ONP-23.2, Steam Generator Tube Leak Validation Time:
minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Exam in er:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 8 AUGUST 201 0
JPM SRO ADMIN 3 Tools/Equipment/Procedures Needed:
ONP-23.2, Steam Generator Tube Leak Also see Simulator Operator Instructions (later page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
I N IT1 AL CON DIT1 0 NS :
The Plant is at full power.
A Steam Generator Tube Leak is in progress on the A Steam Generator.
ONP-23.2, Steam Generator Tube Leak Procedure has been entered.
Current estimated primary to secondary leakage is 0.01 gpm and stable.
PCS Gas Total Isotope = 0.5 pCi/cc Offgas flowrate = 4 cfm (taken within last 30 minutes).
INITIATING CUES:
During implementation of ONP-23.2, the Control Room Supervisor directs you to determine the new setpoint for RIA-0631, Condenser Offgas Monitor, per ONP-23.2, Step 3a.
PALISADES NUCLEAR PLANT Page 3 of 8 AUGUST 201 0
Grade Proc.Step TASK ELEMENT 1 STANDARD TASK ELEMENT 3 STANDARD Grade I ONP-23.2 I Locates correct Drocedure.
I Locates ONP-23.2 and refers to Attachment 2. I S U I Pg 2 Step 1
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Comment EVALUATOR CUE:Provide candidate a working copy of ONP-23.2.
s u Determines Off Gas flow rate = 4 cfm from initiating cue OBTAIN Condenser Off Gas flow rate (preferred) OR USE last known reading if taken within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Att 2 step 3.a Comment:
TASK ELEMENT 2 ESTIMATE the count rate indication on RIA-0631, Condenser Off Gas Monitor, which would result in a 0.02 gpm primary to secondary leakrate. Refer to Attachment 1, Estimation of Primary to Secondary Leakrate.
Refer to ONP-23.2 Attachment 1 page 2 of 3.
s u PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010
JPM SRO ADMlN 3 pg Step 2 ProcStep TASK ELEMENT 4 STANDARD Grade I
s u OBTAIN "PCS Gas Total Isotope" from Chemistry using last known analysis.
Determines PCS Gas Total Isotope =
0.5 pCi/cc from initiating cue.
pg Step 4 I
CALCULATE uncorrected leakrate using the following equation:
Uncorrected Leakrate (pCi-gal/min-kg) =
Primary to Secondary Leakrate (gahin) X PCS Gas Total Isotope (pCi/cc) X 1000 (cclkg)
Calculates uncorrected leakrate using formula:
0.02 gpm X 0.5 pCilcc X 1000 =
s u 10.0 pCi-gal/min-kg ProcStep TASK ELEMENT 5 STANDARD Grade I
Determines 0.02 gpm (from Attachment 2 Step 3a.)
I DETERMINE maximum Primary to Secondary Leakrate based on current I Step pg2 3 I Action Level.
Comment:
Proc.Step TASK ELEMENT 6 STANDARD Grade I
PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010
JPM SRO ADMlN 3 Proc.Step TASK ELEMENT 7 STANDARD I
Grade Pgs 2&3 Step 5 ESTIMATE RIA-0631 count rate using the Uncorrected Leakrate Graph on page 3.
. Determines 8.5E+03 cpm using pg 3 graph with 4 sfm Off Gas flowrate line and 2.OE+00 Uncorrected Leak Rate line.
SIGNS Completed By on Attachment 1 Informs CRS of results and that Reviewed By signature is still required.*
PS 2.*
s u Comment:
EVALUATOR NOTE: allow 8.3+03 to 8.7+03 cpm EVALUATOR CUE: If notified as the CRS of reading and need for Review signature:
Acknowledge. If asked if Attachment 2 steps should be completed:
RESPOND that another operator will complete Attachment 2 steps.
- NOTE: Not part of the critical step END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010
JPM SRO ADMlN 4 SIMULATOR OPERATOR INSTRUCTIONS No Simulator setup required.
It is preferred that this JPM be done separately from the simulator. If, by chance, candidate IS in the simulator while doing this JPM, THEN ensure the IC is an at-power IC.
PALISADES NUCLEAR PLANT Page 7 of 8 AUGUST 2010
JPM SRO ADMlN 4 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
0 The Plant is at full power.
0 A Steam Generator Tube Leak is in progress on the A Steam Generator.
0 ONP-23.2, Steam Generator Tube Leak Procedure has been entered.
0 Current estimated primary to secondary leakage is 0.01 gpm and stable.
PCS Gas Total Isotope = 0.5 pCi/cc 0
Offgas flowrate = 4 cfm (taken within last 30 minutes).
IN IT1 AT1 NG CUES:
During implementation of ONP-23.2, the Control Room Supervisor directs you to determine the new setpoint for RIA-0631, Condenser Offgas Monitor, per ONP-23.2, Step 3a.
PALISADES NUCLEAR PLANT Page 8 of 8 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 4 TITLE:
CLASSIFY EVENT AND DETERMINE PAR CAN D I DATE :
EXAMINER:
JPM SRO ADMlN 4 JOB PERFORMANCE MEASURE DATA PAGE Task:
Classify an Event and Determine PARS - Protective Action Recommendations Alternate Path:
NEW KIA:
2.4.41, 2.4.44 Importance:
RO:4.1,4.0 SRO:
4.1 4.4 WA Statement: (2.4.41) Knowledge of the emergency action level threshholds and classifications.
(2.4.44) Knowledge of emergency plan protective action recommendations.
Task Standard: Event classified as a General Emergency within 15 minutes and PAR is evacuation of Areas 1 and 3, within 15 minutes from declaration of GE.
Preferred Evaluation Location: Simulator -X-In Plant Preferred Evaluation Method:
Perform
-X-Simulate
References:
El-1, Emergency Classifications and Actions El-3, Communications and Notifications El-6.13, Protective Action Recommendations for Offsite Populations Validation Time:
minutes Time Critical:
YES - see task standard Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 10 AUGUST 201 0
JPM SRO ADMIN 4 Tools/Equipment/Procedures Needed:
ELI, Emergency Classifications and Actions, Attachment 1 El-3, Communications and Notifications El-6.13, Protective Action Recommendations for Offsite Populations, Also see Simulator Operator Instructions (later page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The Reactor tripped 10 minutes ago.
A Steam Generator Tube Rupture Event is in progress on the A Steam Generator.
Pressurizer level is off-scale LOW.
PCS pressure is 1000 psia.
CETs indicate 5OOOF.
SlRW tank level is 92% and lowering slowly.
A release IS occurring through a stuck open code safety valve on the A Steam Generator.
Reactor Vessel Level Monitoring System (RVLMS) indicates ALL red lights Failed fuel analysis is in progress with no results to report yet.
The weather is clear with no precipitation.
INITIATING CUES:
During activation of the Site Emergency Plan, you are the Shift Manager (acting as the Emergency Plant Manager). You are to classify the event given the above information and complete the Event Notification Form. No previous event declaration has been made.
This JPM is Time Critical.
PALISADES NUCLEAR PLANT Page 3 of 10 AUGUST 2010
JPM SRO ADMIN 4 El-I Proc.Step TASK ELEMENT 1 STANDARD Grade I
Locates El-1 and refers to Attachment 1, Hot Conditions (PCS > 200 degrees F).
Locates correct procedure.
Refers to lower right-hand corner of El-I, (PCS > 200 degrees F).
s u El-1 Refers to Fission Product Barriers section Attachment,
Conditions Att 1 (lower right-hand corner) c EVALUATOR: Candidate may use placard of site emergency plan classifications or use paper copy from 1 4, attachment 1.
Proc.Stt?p TASK ELEMENT 2 STANDARD Grade I
r Comment:
El-1 Att 1 TASK ELEMENT 3 Determines status of fission product barriers.
STANDARD Refers to Table F1 Determines a POTENTIAL LOSS of Fuel Cladding (based on RVLMS elevation readings (item 4)
Determines a LOSS of PCS Barrier (based on S/G leak rate causing SI actuation)
(item 3).
Determines a LOSS of Containment Barrier (based on affected S/G faulted outside Containment) (item 4).
614 ft s u Comment:
PALISADES NUCLEAR PLANT Page 4 of 10 AUGUST 2010
JPM SRO ADMIN 4 Declares a GENERAL EMERGENCY per FGl based on status of fission product barriers (loss of TWO and potential loss of THIRD).
Proc.Step TASK ELEMENT 4 STANDARD Grade I
S U El-1 Declares Emergency Classification.
I Att 1 Proc.Step TASK ELEMENT 5 STANDARD Grade I
Comment:
I El-1 Att2 I CRITICAL STEP - musP be performed within 15 minubs of start of JPM.
s u Prepares Emergency Actions/Notifications Obtains El-,, Attachment and fills out.
form*
Comment:
EVALUATOR NOTE: This Task Element may be performed at any time during the JPM.
Filling out this form is NOT required for this JPM.
EVALUATOR NOTE: It is NOT the intent of this JPM to have candidate actually make the notifications.
Obtains El-3, Attachment 1 and fills out per attached KEY.
Prepares Event Notification Form.
Comment:
EVALUATOR NOTE: When candidate asks for Meteorological Data, hand them attachment I of 1-6.7, "Plant Site Meteorological System Worksheet, " which has been previously completed (attached)
EVALUATOR NOTE: KEY is attached to this JPM.
EVALUATOR NOTE: 1-3, Attachment 2, "Palisades Event Technical Data Sheet" is NOT required during this JPM.
EVALUATOR NOTE: If JPM is conducted in the Simulator, then Candidate may use computer on Control Room island area to prepare this form.
PALISADES NUCLEAR PLANT Page 5 of 10 AUGUST 2010
JPM SRO ADMlN 4 E'-1 Proc.Step TASK ELEMNT 7 STANDARD I
Candidate refers to El-I 1 : determines there is not enough info provided in initiating cue to determine amount of core damage.
s u Candidate may determine status of Core Damage per El-I 1.
Determines Protective Action
~ t t 1
Recommendations (PARS).
Obtains 1-6.1 3 and corresponding and determines:
Evacuate Areas 1 and 3 (minimum GE recommendation on bottom of Pg 1 of )
Comment:
EVALUATOR NOTE: Provide candidate with a working copy of 1-6.13.
Proc.Step TASK ELEMENT 8 STANDARD Grade I
I EVALUATOR NOTE: If candidate attempts to perform this step, provide them with a working copy of 1-1 7, attachment 2.
Proc.Step TASK ELEMENT 9 STANDARD Grade Completes filling out Palisades Event Att 1 Notification Form.
Palisades Event Notification Form completely filled per attached KEY AND form is approved (Candidate initials, date, and time entered at bottom of form)
- Comment:
EVALUATOR NOTE: If JPM is conducfed in the Simulator, then Candidate may use compufer on back-bar of Control Room island area to complete and print this form.
- The following are the critical parts of this step:
0 General Emergency is checked in "current classification" section Date and time filled in "current classification" section FGI filled in "reason for classification" section AND Fission Product Barrier Degradation checked in "reason for classification" section "Yes" checked in Radiological Release in Progress Areas 1 and 3 checked for Evacuation of Areas END OF TASK PALISADES NUCLEAR PLANT Page 6 of 10 AUGUST 2010
~-
ANSWER KEY JPM SRO ADMIN 4 Proc No 1-3 Revision 28 Page 1 of 1 PALISADES EVENT NOTIFICATION FORM
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0 Actual Event Drill Plant Contact Information Nuclear Power Plant:
Plant Communicator:
Time of Communication: V.B.
S.O.M.
NRC Plant Message Number Calling From:
c] Control Room c]
TSC UEOF Other Call Back Telephone Number:
Current Classification Unusual Event 0 Alert Site Area Emergency General Emergency Is] Termination Time: Within 15 minutes from start of JPM This Classification was declared as of:
Date: Todav
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Reason for Classification 0 Abnormal Rad Levels / Radiological Effluent Hazards and Other Conditions Affecting 0
System Malfunctions Cold Shutdown / Refueling System Malfunction Independent Spent Fuel Storage Fission Product Barrier Degradation Plant Safety Installation Events IC Number: FGf Radiological Release in Progress Due to Event (XI Yes No Protective Action Recommendations
[7 None Evacuation of Areas(s):
MI n 2 lxl3 0 4 0 5 In-Place Shelter of Area(s) 0 1
2 [7 3
[7 4
[7 5 PAR based on:
0 Dose Calculation (Palisades Event Technical Data Sheet required)
Plant Status Security Event (7 Other Meteorological Data Wind Direction (degrees): From 305 To 125 Wind Speed (MPH): 1 Stability Class: G Precipitation: c]
Yes No Emergency Director Approval:
Date:
Time:
ANSWER KEY PALISADES NUCLEAR PLANT Page 7 of 10 AUGUST 2010
JPM SRO ADMIN 4 SIMULATOR OPERATOR INSTRUCTIONS 0
No Simulator setup required.
0 It is preferred that this JPM be done separately from the simulator. If, by chance, candidate IS in the simulator while doing this JPM, THEN ensure the IC does NOT have a release in progress.
ENSURE ALL DATA IS CLEARED FROM EP NOTIFICATION COMPUTER ON BACK-BAR OF CRS ISLAND PRIOR TO NEXT USE OF THIS JPM.
PALISADESNUCLEARPLANT Page 8 of 10 AUGUST 2010
Proc No El-6.7 Revision 8 Page 1 of 1 PLANT SITE METEOROLOGICAL SYSTEM WORKSHEET
- 1.
WS, Wind Speed = 1.0 mph
- Multiply by 0.77 (X) 10 meters
( ) 60 meters, *corrected (see Step 5.1.3 or 5.2.6)
(X) 10 meters
( ) 60 meters (see Step 5.1.3 or 5.2.6)
(see Step 5.1.4 or 5.2.7)
- 3.
Stability Class = G Date:
TODAY Time:
NOW Completed By:
JOE OPERATOR PALISADES NUCLEAR PLANT Page 9 of 10 AUGUST 2010
JPM SRO ADMlN 4 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Reactor tripped 10 minutes ago.
A Steam Generator Tube Rupture Event is in progress on the A Steam Generator.
Pressurizer level is off-scale LOW.
PCS pressure is 1000 psia.
CETs indicate 5OOOF.
SlRW tank level is 92% and lowering slowly.
A release IS occurring through a stuck open code safety valve on the A Steam Generator.
0 Reactor Vessel Level Monitoring System (RVLMS) indicates ALL red lights Failed fuel analysis is in progress with no results to report yet.
The weather is clear with no precipitation.
IN IT1 AT1 NG CUES:
During activation of the Site Emergency Plan, you are the Shift Manager (acting as the Emergency Plant Manager). You are to classify the event given the above information and complete the Event Notification Form. No previous event declaration has been made.
This JPM is Time Critical.
PALISADES NUCLEAR PLANT Page 10 of 10 AUGUST 201 0