ML111460555
| ML111460555 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/16/2010 |
| From: | Palagi B NRC/RGN-III/DRS/OLB |
| To: | |
| Shared Package | |
| ML102070508 | List: |
| References | |
| Download: ML111460555 (134) | |
Text
2010 PALISADES NUCLEAR PLANT INITIAL EXAM I NATION AS -AD M I N ISTE RE D EXAM F I L ES 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:
JOB PERFORMANCE MEASURE DATA PAGE Task: Determine Quadrant Power Tilt per PO-3 Alternate Path: N/A 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 NI Power readings recorded within f 1 % of key and Quadrant Power Tilt calculated correctly 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:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 8 AUGUST 2010
JPM RO ADMIN l a Tools/Equipment/Procedures 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.
INITIAL CONDITIONS:
0 Plant was at full power.
0 lncores #9 and #35 are inoperable.
0 Control Rod #I 1 has dropped into the core.
I N IT1 AT1 N G C U ES :
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 Page 3 of 8 AUGUST 201 0
JPM RO ADMIN l a TASK ELEMENT 1 STANDARD EVALUATOR CUE: Provide candidate with a working copy of PO-3, Attachment 2.
Grade 5.2.1 I
Lower and upper excore readings from the EGO6 are entered on PO-3, Attachment 2, within +I
% of the answer key.
Upper and Lower NI Detector meters on Obtain lower and upper excore readings as required. (SAL, SBL, ScL, SDL and SAU, s B U 3 SCU, SDU).
s u Proc.
TASK ELEMENT 3 STANDARD Step Comment:
Grade Calculate the sum from the Lower +
- 1. Calculate the sum of all excore readings divided by 4:
(S = C all detectord4).
Sum of all excores reading divided by 4 calculated and entered on PO-3, s u 5.2.1.
Comment:
PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010
JPM RO ADMIN l a TASK ELEMENT 4 Proc.
Step STANDARD Grade 5.2.1 Using the formula TEX = [(SX - S)/S],
calculate the tilt for each Quadrant.
Calculate the Quadrant Tilt.
s u TASK ELEMENT 5 Proc.
Step Comment:
EVALUATOR CUE: State that another Operator will verify the calculation.
STANDARD Grade 5.2.1 Have another qualified individual verify the Have calculations verified.
calculations.
s u PALISADES NUCLEAR PLANT TASK ELEMENT fi Proe.
Step END OF TASK STANDARD Grade Page 5 of 8 n/a AUGUST 2010 Notify the CRS that Excore Quadrant PO-3, Attachment 2.
Power Tilt.
Operator notifies CRS of completion of PO-3, Attachment 2, Excore Quadrant Power Tilt has been completed per s u
JPM RO ADMlN l a SIMULATOR OPERATOR INSTRUCTIONS SIMULATOR SET UP:
Simulator Setup Instructions:
Full power IC Drop Control Rod #I 1 fully into the core with RD-11 (Final Value = 2) on PIDRD02 When plant has stabilized, freeze the Simulator and SNAP Use PO-3, Attachment 2 and recordlcalculate from the Upper and Lower NI Detector meters on EC-06 and use as answer key.
PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010
JPM RO ADMIN l a Upper Reading (%)
SAU, SBUv SCU, SOU Excore Lower + Upper S = 4 All DetectorsY4
= (SA + Se + s c + SD)/4 SA, SB, SC, SD 5 (CH A)
SAU =
[NI-005 Upper (B)]
50 6 (CH B)
T u = [(SA-S)/S] X 100%
5.2 8 (CH D)
QUAD I Lower Reading (%)
SAL, SBL, SCL, SDL TEB = [(Ss-S)/S] x 100%
-1 5.6 SAL =
[NI-005 Lower (A)]
51 QUAD 3 SBL =
[NI-0065 Lower (A)]
41 TEC = [(Sc-S)/S] x 100%
5.2 SCL =
[NI-007 Lower (A)]
51 QUAD 4 SDL =
[NI-008 Lower (A)]
52 SOU =
[NI-008 Upper (B)]
49 SD = SDL + SOU 101 TED = [(S&)/s]
X 100%
5.2 SBU =
[NI-006 Upper (B)]
40 QUAD 2 scu =
[NI-007 Upper (B)]
50 SB = SBL + SBU k sc = SCL + scu 96 Excore Quadrant Tilt TEA, TEE, TEC, TED 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 NSSS and 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 PALISADES NUCLEAR PLANT Page 7 of 8 AUGUST 2010
JPM RO ADMIN l a INITIAL CONDITIONS:
(TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
Plant was at full power.
lncores #9 and #35 are inoperable.
Control Rod #I 1 has dropped into the core.
IN IT1 AT1 NG 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 Page 8 of 8 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:
RO ADMIN l b TITLE:
RESET UFM CORRECTION FACTORS CAN D I DATE :
EXAM1 NER:
JPM RO ADMIN 1 b JOB PERFORMANCE MEASURE DATA PAGE Task:
Reset UFM Correction Factors Alternate Path: N/A Facility JPM #: PL-OPS-PPC-001 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.
Task Standard:
UFM correction factors set to 1.OOO and UFM is not enabled on PPC Page 521.
Preferred Evaluation Location: Simulator -X-In Plant Preferred Eva1 uation Met hod :
Perfo rm-X-Simulate
References:
DWO-1, Operators DailyNVeekly Items MODES 1, 2, 3, and 4 Validation Time:-I 0-minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Exam i ner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 10 AUGUST 2010
JPM RO ADMIN I b Tools/Equipment/Procedures Needed:
DWO-1, Operators DailyNVeekly Items MODES 1, 2, 3, and 4 DWO-1 Attachment 12 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 following a power reduction from full power.
INITIATING CUES:
The Control Room Supervisor directs you to ensure UFM CAL ENABLED on PPC Page 521 is NOT ENABLED per DWO-1, Section 5.2.3.
PALISADES NUCLEAR PLANT Page 3 of 10 AUGUST 2010
JPM RO ADMIN l b Proc.Step TASK ELEMENT 2 STANDARD Evaluator Cue: Provide candidate with a working copy of DWO-I section 5.2.3.
Grade Page 521 of PPC is displayed 5.2.3.b 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.
STANDARD ProcStep TASK ELEMENT 3 Grade IF UFM CAL ENABLED will be changed PERFORM the following:
5.2.3.c from NOT ENABLED to ENABLED, THEN Determines step is N/A.
Comment:
s u STANDARD ProcStep TASK ELEMENT 4 Grade PALISADES NUCLEAR PLANT 5.2.3.d.1 Page 4 of 10 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.
AUGUST 2010
ProcStep TASK ELEMENT 5 STANDARD Grade 5-2-3-d-2 I
IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN PERFORM the following:
- 2. ENSURE HB-PWR-STEADY is lowered to the 100% thermal power limit allowed by 2, 1 00% Thermal Power Limit.
Refers to Attachment 12 and determines power is c 2530 MWt.
5-2-3-d.4 s u IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN PERFORM the following:
- 4. ENTER N for no.
I I Comment:
Proc.Step 1
TASK ELEMENT 8 STANDARD Grade Evaluator Cue: Provide candidate with a working copy of DWO-l Attachment 12.
I 5.2-3-d5 Proc.Step TASK ELEMENT 6 IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN PERFORM the following:
- 5. PRESS UPDATE hardkey.
I IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN
- 3. SELECT UFM CAL ENABLED.
5.2.3.d-3 PERFORM the following:
Comment:
STANDARD Grade UFM CAL ENABLED field is selected.
l s u l I
Grade Proc.Stgp TASK ELEMENT 7 STANDARD N is entered.
s u I
Comment:
I UPDATE hardkey is pressed.
s u
~
~~~
Comment:
PALISADES NUCLEAR PLANT Page 5 of 10 AUGUST 2010
JPM RO ADMIN 1 b 5.2.3.f.1 Proc.Step TASK ELEMENT 9 ENSURE Technical Data Book Figure 14.1 Enters 1.OOOO for UFM correction factors in Tech Data Book Figure 14.1.
is updated.
IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN
- 6. ENSURE UFM Correction Factors set to 1.OOOO. Refer to Step 5.2.3f.
5.2.3.d.5 PERFORM the following:
5-2-3.f-2 Comment:
ENSURE HB-PWR-STEADY is acceptable for the new Total UFM Correction Factor Worth in Technical Data Book Figure 14.1.
STANDARD Proc.Step Operator goes to 5.2.3.f.
TASK ELEMENT 12 STANDARD Grade s u 5.2.3.f.3 TASK ELEMENT 10 STANDARD Grade I
s u On PPC page 521, data is selected for first UFM Correction Factor.
Select data.
ProcStep Comment:
I TASK ELEMENT 13 STANDARD Grade ProcStep TASK ELEMENT 11 STANDARD Grade I
I Operator verifies HB-PWR-STEADY is lowered to a value less than the Maximum UFM Corrected Power for Resetting Correction Factors to 1.O found in Tech Data Book Figure 14.1.
s u Comment:
I I Comment:
I Enter new value.
1.OOOO is entered.
Comment:
I I
PALISADES NUCLEAR PLANT Page 6 of 10 AUGUST 2010
JPM RO ADMIN I b Proc.Step TASK ELEMENT 14 STANDARD Grade Press UPDATE hardkey.
UPDATE hardkey is pressed.
I s u Comment:
I I
Proc.Step TASK ELEMENT 15 STANDARD Grade I
I 5.2.3.f.3 I Select data.
l s u l On PPC page 521, data is selected for second I UFM Correction Factor.
I I
Comment:
I I
I Proc.Step TASK ELEMENT 16 STANDARD Grads I
Ptoc.Step TASK ELEMENT 17 STANDARD Grade I
I 5.2.3.f.5 I Press UPDATE hardkey.
I UPDATE hardkey is pressed.
I s u I I Comment:
Proc.Step TASK ELEMENT 18 STANDARD Grade I
5.2.3.d.7 Wait approximately 30 minutes for Heat Balance power to adjust to the change in 5.2-3.f-6 the UFM Correction Factors.
the UFM Correction Factors.
Comment:
EVALUATOR CUE: Another person will perform the Heat Balance.
Operator waits approximately 30 minutes for Heat Balance power to adjust to the change in S U PALISADES NUCLEAR PLANT Page 7 of 10 AUGUST 201 0
PrOcStep TASK ELEMENT I 9 STANDARD Grade 5.2.3-d-8 5.2.3.f.7 Operator informs the CRS that the UFM Correction Factors are reset to 1.OOOO per inform CRS that the UFM Correction Factors are reset to 1.OOOO per DWO-1.
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.
I Comment:
EVALUATOR CUE: Repeat back notification.
END OF TASK PALISADES NUCLEAR PLANT Page 8 of 10 AUGUST 2010
JPM RO ADMIN I b SIMULATOR OPERATOR INSTRUCTIONS 0
lC-16,86% power.
0 Ensure UFM Correction Factors are 0.9890 and 0.9690 on PPC page 521 and Tech Data Book figure 14.1 is updated.
0 Ensure UFM CAL ENABLED (= YES)
PALISADES NUCLEAR PLANT Page 9 of 10 AUGUST 201 0
JPM RO ADMIN I b (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Plant is at 86% power following a power reduction from full power.
INITIATING CUES:
The Control Room Supervisor directs you to ensure UFM CAL ENABLED on PPC Page 521 is NOT ENABLED per DWO-1, Section 5.2.3.
PALISADES NUCLEAR PLANT Page 10 of 10 AUGUST 201 0
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: ROADMIN 2 TITLE: PERFORM DWO-I ACOUSTIC MONITOR 7-DAY CHECK CANDIDATE:
EXAM1 NER:
JPM RO ADMIN 2 JOB PERFORMANCE MEASURE DATA PAGE Task:
Perform Operators DailyNVeeklylBi-Weekly items in all MODES Alternate Path: N/A Facility JPM #: NEW WA: 2.2.12 Importance:
RO: 3.7 SRO: 4.1 WA 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:
DWO-I, Operators DailyNVeekly Items Modes I, 2, 3, and 4 Validation Time:
15 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 7 AUGUST 2010
JPM RO ADMIN 2 Tools/Equipment/Procedures Needed:
DWO-1, Operators DailyANeekly Items Modes 1, 2, 3, and 4, Section 6.1 and, Daily/Weekly Surveillance Data Sheet Red ink pen 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:
0 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 />.
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 EVALUATOR CUE: Provide candidate with page 3 of D WO-7, attachment 7 and section 6,7, PUSH "read preamp bias" button (should read between 52.5 and 67.5) AND ENTER reading on Attachment 1, "DailyNVeekly Surveillance Data Sheet."
6m1'1 STANDARD
. Pushes "read preamp bias" button for one of CHECKS reading between 52.5 and 67.5
. RECORDS reading in "Wednesday Reading"
. Repeats above three steps for each monitor
. DETERMINES FI-l043B reading is less than CIRCLES in RED FI-l043B 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 Grade Proc. Step TASK ELEMENT 2 STANDARD PUSH "high alarm test" pushbutton - high alarm on C-I 3 should annunciate.
6'1'2
= Pushes "high alarm test" pushbutton for one of
. CHECKS that high alarm on C-13 annunciates the five (5) monitors s u I
I. Repeats above two steps for each monitor I
I Comment:
PALISADES NUCLEAR PLANT Page 4 of 7 AUGUST 2010
JPM RO ADMIN 2 Proc. step TASK ELEMENT 3 STANDARD I
k Grade 6.1.3 L
. Turns Channel 1 gain switch clockwise until noise is heard.
TURN Channel 1 gain switch to highest point - some noise should be present after switch is at highest point.
s u
6.1.4 Comment
NOTE: Channel 7 gain switch is switch on LEFT side of panel.
9 Turns Channel 1 gain switch counterclockwise to zero position RETURN switch to zero.
I Grade Proc. Step TASK ELEMENT 4 STANDARD 9 Inform CRS of out of spec readings (if not already done)
- CRS INFORMED of the out of spec readings (if not already done) 6.1.5 c Comment:
TASK ELEMENT 5 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.
STANDARD
. INITIALS RECRD BY in Wednesday column for Item 6.1 9 RECORDS a note at bottom of page that preamp bias for FI-I 0438 indicated zero Informs CRS that Work Request initiation is required for preamp bias issue on FI-0143B.
s u EVALUATOR CUE: If notified as the CRS of the out of spec reading and need for a Work Request: Acknowledge.
Proc. Step TASK ELEMENT 6 STANDARD Grade I
I F Comment I
- Return completed DWO-1 to CRS I - Completed DWO-1 RETURNED to the CRS I PALISADES NUCLEAR PLANT END OF TASK Page 5 of 7 AUGUST 2010
JPM RO ADMIN 2 SI M U LATOR OPERATOR INSTRUCTIONS 0
Reset to any full power IC.
0 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 0
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 201 0
JPM RO ADMIN 2 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
IN ITlAL 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 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:
EXAM I NER:
JPM RO ADMIN 3 JOB PERFORMANCE MEASURE DATA PAGE Task:
Alternate Path:
NIA Determine Expected Dose for Equipment Inspection Facility JPM #:
PL-OPS-ADM-002J WA:
2.3.4 Importance
SRO:
3.7 RO:
3.2 WA 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: -
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 8 AUGUST 201 0
JPM RO ADMIN 3 Tools/Equ ipment/Procedu res 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 1-2 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. Do not include dose received during transit time.
PALISADES NUCLEAR PLANT Page 3 of 8 AUGUST 2010
JPM RO ADMIN 3 Proc.Step TASK ELEMENT I STANDARD Grade I
Obtains "Radiological Area Status Sheet" for I East Engineering Safeguards.
I
--- I Obtains correct survey map for P-67A.
Comment:
EVALUATOR CUE: Provide candidate with attached Radiological Area Status Sheet and picture of P-67A skid.
Proc.Step TASK ELEMENT 2 STANDARD Grade I
--- I Determine dose rate near the component. I Dose rate determined to be 18 mRem/hr.
I S "
Comment:
EVALUATOR NOTE: Candidate should select 18 mWhr dose rate reading from Status Sheet since this is the general area where seal cooler is located and they were instructed not to cross any contamination areas.
Proc.Step TASK ELEMENT 3 STANDARD Grade I
1 I --- I Calculates expected dose.
I Expected dose calculated to be 4.5 mRem.
I S U I Comment:
EVALUATOR NOTE: 18 mRem/hrX 0.25 hr = 4.5 mR (allow 4-5 mR)
PALISADES NUCLEAR PLANT END OF TASK Page 4 of 8 AUGUST 2010
JPM RO ADMlN 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 0 m k 10 Neutron I J Technician J Supervisor 811 611 0 I
Smears dpdI00 cn?
Note: All Dose Rates in rnRernlhr unless otherwise noted Comments:
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 1-2 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. Do not include dose received during transit time.
PALISADES NUCLEAR PLANT Page 8 of 8 AUGUST 201 0
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 :
EXAM1 NER:
JPM SRO ADMIN l a JOBPERFORMANCEMEASURE DATA PAGE Task:
Determine Compensation for a Withdrawn, Inoperable Control Rod Alternate Path: N/A Facility JPM #: PL-OPS-ENG-01 1 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.
Task Standard: EM-04-08, Attachment 1 properly completed per key.
Preferred Evaluation Location: ANY X
Preferred Evaluation Method:
PerformX-Simulate References :
EM-04-08, "Shutdown Margin Requirements" 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 15 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.
INITIAL CONDITIONS:
Rod #6 is inoperable and fully withdrawn.
It is believed that the rod is untrippable.
Burnup is 7,000 MWD/MTU.
Rx power is 100%.
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 15 AUGUST 2010
JPM SRO ADMIN l a TASK ELEMENT I STANDARD Proc.
SWP EVALUATOR CUE: Provide candidate a working copy of EM-04-08 Attachment 7.
Grade TASK ELEMENT 4 STANDARD Grade Proc.
StsP Record inoperable control rod identification.
I A, 6 and untrippable recorded.
I s u I
Comment:
I I
I EVALUATOR CUE: Reactor Engineering is not available.
TASK ELEMENT 3 STANDARD Grade Proc.
Step Record source of inoperable control 3
rod worth data.
Tech Data Book entered.
s u Comment:
Record current cycle burn u p.
Record current cycle burnup = 7000.
s u Comment:
PALISADES NUCLEAR PLANT Page 4 of 15 AUGUST 201 0
JPM SRO ADMlN l a TASK ELEMENT 5 STANDARD Proc.
Step Grade Record current power level.
'1 00' entered.
s u Comment:
A TASK ELEMENT 6 Proc.
step Grade STANDARD I 4.C I Control rod worth inserted into core.
I '0' and 'Gp 4 @ 131/132" entered.
I s u I TASK ELEMENT 7 Ptoc.
Step
~
~~~
Comment:
STANDARD Grade TASK ELEMENT 8 Proc.
Step Record PCS Boron concentration.
'865' entered.
Grade STANDARD Comment:
Determine and record worth of control rods at current power level.
17.05 (7.04 to 7.06. entered.
I I 5.E I l s u l Comment:
EVALUATOR NOTE: This will need to be obtained by interpolation of the graph.
PALISADES NUCLEAR PLANT Page 5 of 15 AUGUST 2010
JPM SRO ADMIN l a TASK ELEMENT 9 Roc.
Step STANDARD Grade Determine and record max worth of to 8), entered.
I 5F 1 stuck rod at current power.
I ROC.
StgP TASK ELEMENT 10 STANDARD Grade 5.G Determine and record PCS boron 7000 MWD/MTU.
concentration at 100% at 865 (860 to 870) entered.
s u TASK ELEMENT 11 P W.
Step I
Comment:
I STANDARD Grade 5.H I 1 5 3 (1.51 to 1.55) entered Determine and record power defect at I
- 5. I current power level.
s u Determine and record power defect for
.53 to,-5), entered.
100% power.
Comment:
TASK ELEMENT 12 Proc.
Step PALISADES NUCLEAR PLANT Grade STANDARD Page 6 of 15 AUGUST 2010
JPM SRO ADMIN l a TASK ELEMENT 13 Proc.
step STANDARD Grade Determine and record required SDM.
TASK ELEMENT 14 STANDARD Grade Proc.
2.0 already entered.
I s u I 1.82 (1.80 to 1.84) entered.
Calculate Net amount of shutdown Comment:
TASK ELEMENT 15 STANDARD Grade Proc.
Step Enter worth of untrippable rod.
1.17 (1.16 to 1.18)entered.
s u Comment:
TASK ELEMENT 16 STANDARD Grade Proc.
Step Determine excess shutdown margin 0.65 (0.645 to 0.655) entered. Determines I 6.M I with the inoperable rod.
I Step 7 substew are N/A.
I Comment:
PALISADES NUCLEAR PLANT Page 7 of 15 AUGUST 2010
JPM SRO ADMIN l a TASK ELEMENT I 7 Roc.
step STANDARD Grade Determines Step 7 substeps are N/A.
I IF Shutdown margin is negative, THEN...
I 7.N-Q I TASK ELEMENT 18 Proc.
Step Comment:
STANDARD Grade 8.R s u Determine and record PPC PDlL for Group at lol,,
to 105)1 entered.
current power level.
Comment:
I TASK ELEMENT 19 Proc.
Step STANDARD Grade 8.S Determine and record control rod shutdown margin.
position corresponding to excess Group 4 at 2 0 (18 to 22) entered.
s u TASK ELEMENT 20 Proc.
Step STANDARD Grade PALISADES NUCLEAR PLANT 8T Page 8 of 15 Group 4 at 101 (100 to 105) entered.
s u Determine and record PDlL for inoperable control rod condition.
AUGUST 2010 8T Group 4 at 101 (100 to 105) entered.
s u Determine and record PDlL for inoperable control rod condition.
JPM SRO ADMIN l a TASK ELEMENT 21 prOC.
step STANDARD Grade
~
Comment:
TASK ELEMENT 22 Proc.
§tep STANDARD Grade Sign and date Step 9.
Operator signs and dates.
TASK ELEMENT 23 Proc.
Step Comment:
STANDARD Grade Report results to Control Room I NA I Supervisor.
I CRS notified.
EVALUATOR CUE: End JPM I Note: Attach completed EM-04-08, Attachment 1 to this JPM.
PALISADES NUCLEAR PLANT END OF TASK Page 9 of 15 AUGUST 2010
NONE PALISADES NUCLEAR PLANT JPM SRO ADMIN l a SIMULATOR OPERATOR INSTRUCTIONS Page 10 of 15 AUGUST 2010
1
- 2.
- 3.
- 4.
Proc No EM-04-08 Revision 30 Page 1 of 4 UNTRIPPABLE OR DROPPED CONTROL ROD SHUTDOWN MARGIN CALCULATION UNTRIPPABLE OR DROPPED CONTROL ROD IDENTIFICATION:
GROUP A
NUMBER 6
CONDITION untrippable (Untrippable or Dropped)
WORTH OF UNTRIPPABLE OR DROPPED CONTROL ROD (TDB Figure 1.I or Reactor Engineering) 1.17
%Ap SOURCE OF UNTRIPPABLE OR DROPPED CONTROL ROD WORTH DATA:
REFERENCEDATA A.
B.
C.
D.
CURRENT CYCLE BURNUP (TDB Fig 1.10)
CURRENT REACTOR POWER LEVEL (Percent of Rated Power)
CONTROL ROD WORTH INSERTED INTO CORE (TDB Fig 1.3)
GROUP 4 INCHES 132(or131)
This Control Rod worth does not include the worth of a dropped Control Rod.
PCS BORON CONCENTRATION (Chemistry Log or Reactor Logbook) 7000 100 0
MWd/MTU
%Ap 865 PPm PALISADES NUCLEAR PLANT Page 11 of 15 AUGUST 2010
Proc No EM-04-08 UNTRIPPABLE OR DROPPED CONTROL ROD SHUTDOWN MARGIN CALCULATION
- 5.
GENERAL DATA E.
WORTH OF ALL CONTROL RODS AT A (TDB Fig 1.l)
F.
MAXIMUM WORTH OF STUCK CONTROL ROD AT A (TDB Fig 1.1)
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 )
Revision 30 Page 2 of 4 7.05 1.17 865 1.53 I.
POWER DEFECT AT POWER B 1.53 H x B - (1.53) x (100) 100 100 J.
REQUIRED SHUTDOWN MARGIN (4 PCPs Operating)
- 6.
CALCULATION K.
NET AMOUNT OF SHUTDOWN MARGIN
- I - J (E - C - F) 1.I 2.0
%Ap
%Ap PPm
%Ap
%Ap
%Ap PALISADES NUCLEAR PLANT Page 12 of 15 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 K - L = (1.82) - (1.17)
=
0.65
%Ap 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 = (
) + (
)
=
%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.
NlA Q.
power reduction is required, THEN after power reduction re-perform Attachment 1 to verify Shutdown Margin requirements are satisfied.
NIA PALISADES NUCLEAR PLANT Page 13 of 15 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 I
.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. If. 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 14 of 15 AUGUST 2010
JPM SRO ADMIN l a (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
0 Rod #6 is inoperable and fully withdrawn.
0 It is believed that the rod is untrippable.
Burnup is 7,000 MWD/MTU.
Rx power is 100%.
0 All rods out, equilibrium Xenon.
I N IT I AT I N G CUES :
The Control Room Supervisor directs you to determine the compensation for shutdown margin required for control rod #6 utilizing EM-04-08.
PALISADES NUCLEAR PLANT Page 15 of 15 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:
SRO ADMIN l a TITLE: DETERMINE COMPENSATION FOR A WITHDRAWN, INOPERABLE CONTROL ROD CANDl DATE:
EXAM IN ER:
JPM SRO ADMlN l a JOB PERFORMANCE MEASURE DATA PAGE Task:
Alternate Path: NIA Facility JPM #: PL-OPS-ENG-01 1 J KIA:
2.1.25 Importance: RO:3.9 SRO:
4.2 WA Statement: Ability to interpret reference materials, such as graphs, curves, tables, Determine Compensation for a Withdrawn, Inoperable Control Rod etc.
Task Standard: EM-04-08, Attachment 1 properly completed per key.
Preferred Evaluation Location: ANY
-X-Preferred Evaluation Method:
Perform-X-Simulate
References:
EM-04-08, "Shutdown Margin Requirements" 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 15 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.
IN IT1 AL CON DIT1 ONS:
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 100%.
0 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 15 AUGUST 2010
JPM SRO ADMIN l a TASK ELEMENT 2 Proc.
Step EVALUATOR CUE: Provide candidate a working copy of EM-04-08 Attachment 7.
STANDARD Grade TASK ELEMENT 1 STANDARD Grade Proc.
Step TASK ELEMENT 3 STANDARD Proc.
Step Record inoperable control rod I
identification.
Grade I A, 6 and untrippable recorded.
3 Comment:
Record source of inoperable control rod worth data.
Tech Data Book entered.
s u TASK ELEMENT 4 STANDARD Grade Proc.
step I s u I Record worth of inoperable control rod.
(1.16 to l.,8), entered.
I Comment:
EVALUATOR CUE: Reactor Engineering is not available.
I I
Record current cycle burnup.
Record current cycle burnup = 7000.
s u Comment:
I I
PALISADES NUCLEAR PLANT Page 4 of 15 AUGUST 201 0
JPM SRO ADMIN l a TASK ELEMENT 5 Roc.
Step STANDARD Grade Record current power level.
'100' entered.
t TASK ELEMENT 6 STANDARD Grade Proc.
SbP Comment:
TASK ELEMENT 7 Proc.
Step STANDARD Grade 4.C Comment:
I Control rod worth inserted into core. I '0' and 'Gp 4 @ 131/132" entered.
TASK ELEMENT 8 STANDARD Grade Proc.
step Determine and record worth of control rods at current power level.
Record PCS Boron concentration.
'865' entered.
s u Comment:
s u 17,05 (7.04 to 7.06)l entered, Comment:
EVA LUA TOR NOTE: This will need to be obtained by interpolation of the graph.
PALISADES NUCLEAR PLANT Page 5 of 15 AUGUST 2010
Step Grade TASK ELEMENT 9 STANDARD 5'F s u Determine and record max worth of stuck rod at current power.
.16 to l.18)9 entered.
PrOC.
Step Comment:
TASK ELEMENT I O STANDARD Grade TASK ELEMENT I 1 STANDARD Grade Proc.
5.G Determine and record power defect for
.53 to.55), entered, 100% power.
I I 5-H I Determine and record PCS boron 7000 MWD/MTU.
concentration at 100% at
'865 (860 to 870)' entered.
s u TASK ELEMENT 12 Proc.
step STANDARD Grade PALISADES NUCLEAR PLANT Determine and record power defect at current power level.
Page 6 of 15 s u
.53 (,.51 to.55), entered.
AUGUST 201 0
TASK ELEMENT 13 STANDARD Grade Proc.
Step TASK ELEMENT 14 STANDARD Proc.
Step I
l s u l 5.5 I Determine and record required SDM. I 2.0 already entered.
Grade TASK ELEMENT 15 STANDARD Proc.
Step l s u l I 1.82 (1.80 to 1.84) entered.
Calculate Net amount of shutdown 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:
6M Determine excess shutdown margin with the inoperable rod.
0.65 (0.645 to 0.655) entered. Determines Step 7 substeps are NIA.
I I
PALISADES NUCLEAR PLANT Page 7 of 15 AUGUST 201 0
JPM SRO ADMIN l a TASK ELEMENT 17 Roc.
Step STANDARD Grade 7.N-Q Group 4 at 101 (100 to 105) entered.
Determines Step 7 substeps are NIA.
s u IF Shutdown margin is negative, THEN...
Comment:
TASK ELEMENT 19 STANDARD Proc.
step Grade 8.S I
Determine and record control rod shutdown margin.
position corresponding to excess Group 4 at 2 0 (18 to 22) entered.
s u TASK ELEMENT 20 Proc.
Step STANDARD Grade Comment:
8T PALISADES NUCLEAR PLANT Group 4 at 101 (100 to 105) entered.
s u Determine and record PDIL for inoperable control rod condition.
Page 8 of 15 AUGUST 2010
JPM SRO ADMIN l a TASK ELEMENT 22 Proc.
Step TASK ELEMENT 21 STANDARD Grade Proc.
Step Grade STANDARD Comment:
Sign and date Step 9.
Operator signs and dates.
Comment:
TASK ELEMENT 23 STANDARD Grade Proc.
Step Report results to Control Room Supervisor.
I CRS notified.
Comment:
EVALUATOR CUE: End JPM Note: Attach completed EM-04-08, Attachment 1 to this JPM.
END OF TASK PALISADES NUCLEAR PLANT Page 9 of 15 AUGUST 201 0
JPM SRO ADMIN l a SIMULATOR OPERATOR INSTRUCTIONS NONE PALISADES NUCLEAR PLANT Page 10 of 15 AUGUST 2010
Proc No EM-04-08 Revision 30 Page 1 of 4 1
UNTRIPPABLE OR DROPPED CONTROL ROD SHUTDOWN MARGIN CALCULATION UNTRIPPABLE OR DROPPED CONTROL ROD IDENTIFICATION:
GROUP A
NUMBER 6
CONDITION untriwable (Untrippable or Dropped)
- 2.
WORTH OF UNTRIPPABLE OR DROPPED 1.17
%bp 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. I O )
B.
CURRENT REACTOR POWER LEVEL (Percent of Rated Power)
C.
CONTROL ROD WORTH INSERTED INTO CORE (TDB Fig 1.3)
GROUP 4 INCHES 132(or131)
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 11 of 15 7000 MWd/MTU 100 0
%bp 865 PPm AUGUST 2010
- 5.
- 6.
Proc No EM-04-08 Revision 30 Page 2 of 4 UNTRIPPABLE OR DROPPED CONTROL ROD SHUTDOWN MARGIN CALCULATION GENERAL DATA E.
F.
G.
H.
I.
J.
WORTH OF ALL CONTROL RODS AT A (TDB Fig 1.1)
MAXIMUM WORTH OF STUCK CONTROL ROD AT A (TDB Fig 1.1)
PCS BORON AT 100% POWER AT A (TDB Fig 6.1, Reactor Log)
POWER DEFECT AT 100% POWER (TDB Fig 3.2 and G )
7.05 1.17 865 1.53 POWER DEFECT AT POWER B H x B (1.53) x (100) 1.53 100 100 REQUIRED SHUTDOWN MARGIN (4 PCPs Operating)
CALCULATION 2.0
%Ap
%Ap PPm
%Ap
%Ap
%Ap K.
NET AMOUNT OF SHUTDOWN MARGIN
- I - J (E - C - F) 1.I 1.82
%Ap
- (1.53) - (2.0) =
- [(7.05) - (0) - 1.171 1.1 PALISADES NUCLEAR PLANT Page 12 of 15 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 1.I7
%Ap DROPPED CONTROL ROD Step 2 M.
EXCESS SHUTDOWN MARGIN WITH ONE UNTRIPPABLE OR DROPPED CONTROL ROD K - L = (1.82) - (1.17)
=
0.65
%Ap 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 = (
) + (
)
=
- 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.
Q.
power reduction is required, THEN after power reduction re-perform Attachment 1 to verify Shutdown Margin requirements are satisfied.
%Ap NIA NIA NIA PALISADES NUCLEAR PLANT Page 13 of 15 AUGUST 201 0
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)
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.
Group 4
Inches 101 NIA
- 9.
REVIEWS (Operators Name)
/
(Today)
Performed By Date Reviewed By Date Forward Completed Form to Reactor Engineering Supervisor I
Reactor Engineering Supervisor Date PALISADES NUCLEAR PLANT Page 14 of 15 AUGUST 201 0
JPM SRO ADMIN l a (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
ir Rod #6 is inoperable and fully withdrawn.
It is believed that the rod is untrippable.
Burnup is 7,000 MWD/MTU.
Rx power is 100%.
All rods out, equilibrium Xenon.
TlNG CUES:
The Control Room Supervisor directs you to determine the compensation for shutdown margin required for control rod #6 utilizing EM-04-08.
PALISADES NUCLEAR PLANT Page 15 of 15 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:
SROADMIN l a TITLE: DETERMINE COMPENSATION FOR A WITHDRAWN, INOPERABLE CONTROL ROD CANDIDATE:
EXAM I NER:
Alternate Path: N/A Facility JPM #: PL-OPS-ENG-01 1 J K/A:
2.1.25 Importance: RO:3.9 SRO:
4.2 I
~
WA Statement: Ability to interpret reference materials, such as graphs, curves, tables, etc.
Task Standard: EM-04-08, Attachment 1 properly completed per key.
Preferred Evaluation Location: ANY X
Preferred Evaluation Method:
Perform-X-Simulate
References:
EM-04-08, "Shutdown Margin Requirements" 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 15 AUGUST 2010
JPM SRO ADMIN l a Tools/EquipmentlProcedures 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.
IN ITlAL CONDITIONS:
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 100%.
0 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 15 AUGUST 2010
JPM SRO ADMIN l a EVALUATOR CUE: Provide candidate a working copy of EM-04-08 Attachment 7.
TASK ELEMENT I STANDARD Grade Proc.
Step A,
6 and untrippable recorded.
s u Record inoperable control rod identification.
Comment:
I Comment:
EVALUATOR CUE: Reactor Engineering is not available.
rod worth data.
Tech Data Book entered.
TASK ELEMENT 4 STANDARD Grade Proc.
Step Record current cycle burnup.
Record current cycle burnup = 7000.
Comment:
CRITICAL STEP I
PALISADES NUCLEAR PLANT Page 4 of 15 AUGUST 2010
JPM SRO ADMIN l a TASK ELEMENT 5 STANDARD Proc.
Step Grade Record current power level.
Comment:
'100' entered.
s u TASK ELEMENT 6 STANDARD Grade Proc.
step r
Control rod worth inserted into core.
'0' and 'Gp 4 @ 131/132" entered.
I s u Comment:
STANDARD TASK ELEMENT 7 Proc.
Step Grade Record PCS Boron concentration.
'865' entered.
Comment:
TASK ELEMENT 8 STANDARD
- Proc, Step Grade Determine and record worth of control
,7.05 (7.04 to 7.06), entered I
I rods at current power level.
I I s u Comment:
EVALUATOR NOTE: This will need to be obtained by interpolation of the graph.
PALISADES NUCLEAR PLANT Page 5 of 15 AUGUST 201 0
'1.17 (1.16 to 1.18)'entered.
s u Determine and record max worth of stuck rod at current power.
Comment:
STANDARD TASK ELEMENT 10 Proc.
Step Grade 5.G Determine and record power defect for
.53 to.55), entered.
I 5-H I 100% power.
I Determine and record PCS boron 7000 MWD/MTU.
concentration at 100% at
'865 (860 to 870)' entered.
s u l s u l TASK ELEMENT 11 STANDARD Proc.
Step Grade TASK ELEMENT 12 Proc.
Step PALISADES NUCLEAR PLANT STANDARD Grade Page 6 of 15 5.'
AUGUST 2010 s u Determine and record power defect at current power level.
,-3
.51 to.55), entered.
JPM SRO ADMlN l a TASK ELEMENT 13 STANDARD Proc.
S W Grade 5.5 Determine and record required SDM.
2.0 already entered.
s u TASK ELEMENT 14 STANDARD Proc.
step Grade Enter worth of untrippable rod.
1.17 (1.16 to 1.18)entered.
6.K Comment:
1.82 (1.80 to 1.84) entered.
s u Calculate Net amount of shutdown margin.
TASK ELEMENT 15 STANDARD Proc.
Step Grade PALISADES NUCLEAR PLANT TASK ELEMENT 16 STANDARD Proc.
step Page 7 of 15 Grade AUGUST 201 0 6mM Determine excess shutdown margin with the inoperable rod.
0.65 (0.645 to 0.655) entered. Determines Step 7 substeps are N/A.
JPM SRO ADMIN l a TASK ELEMENT 17 STANDARD Prac.
Step Grade IF Shutdown margin is negative, THEN...
I 7.N-Q I TASK ELEMENT 18 STANDARD Proc.
Step I s u I Determines Step 7 substeps are N/A.
Grade Comment:
TASK ELEMENT 19 STANDARD Proc.
Step Grade l s u I Determine and record PPC PDlL for at,ol,,
oo to 105)B entered.
I 8.R I current power level.
I TASK ELEMENT 20 STANDARD Proc.
step I
I I
Comment:
Grade Determine and record control rod shutdown margin.
8.S position corresponding to excess Group 4 at 20 (18 to 22) entered.
s u Comment:
I s u I Group 4 at 101 (100 to 105) entered.
I Determine and record PDlL for inoperable control rod condition.
I 8.T I Comment:
PALISADES NUCLEAR PLANT Page 8 of 15 AUGUST 2010
JPM SRO ADMlN l a TASK ELEMENT 21 Roc.
Step STANDARD Grade TASK ELEMENT 22 Proc.
Step Sign and date Step 9.
Operator signs and dates.
s u Comment:
STANDARD Grade TASK ELEMENT 23 Prw.
Step STANDARD Grade PALISADES NUCLEAR PLANT NA Page 9 of 15 CRS notified.
s u Report results to Control Room Supervisor.
AUGUST 2010
NONE PALISADES NUCLEAR PLANT JPM SRO ADMIN l a SIMULATOR OPERATOR INSTRUCTIONS Page 10 of 15 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 untriopable (Untrippable or Dropped)
- 2.
WORTH OF UNTRIPPABLE OR DROPPED 1.17
%Ap 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)
B.
CURRENT REACTOR POWER LEVEL (Percent of Rated Power) 7000 100 C.
CONTROL ROD WORTH INSERTED INTO CORE 0
(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 11 of 15 M W d/MTU
%Ap 865 PPm AUGUST 2010
- 5.
- 6.
Proc No EM-04-08 Revision 30 Page 2 of 4 UNTRIPPABLE OR DROPPED CONTROL ROD SHUTDOWN M ARGl N CALCU LATl ON GENERAL DATA E.
F.
G.
H.
I.
J.
WORTH OF ALL CONTROL RODS AT A (TDB Fig 1.1)
MAXIMUM WORTH OF STUCK CONTROL ROD AT A (TDB Fig 1.I)
PCS BORON AT 100% POWER AT A (TDB Fig 6.1, Reactor Log)
POWER DEFECT AT 100% POWER (TDB Fig 3.2 and G) 7.05 1.17 865 1.53 POWER DEFECT AT POWER B I
.53 H x B - (1.53) x (100) 100 100 REQUIRED SHUTDOWN MARGIN (4 PCPs Operating)
CALCU LATl ON 2.0 K.
NET AMOUNT OF SHUTDOWN MARGIN
- I - J (E - C - F) 1.I 1.82
%Ap C(7.05) - (0) - 1.171 1.1
- (1.53) - (2.0) =
%Ap
%Ap PPm
%Ap
%Ap
%Ap PALISADES NUCLEAR PLANT Page 12 of 15 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 = (
) + (
)
=
- 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.
Q.
power reduction is required, THEN after power reduction re-perform Attachment 1 to verify Shutdown Margin requirements are satisfied.
PALISADES NUCLEAR PLANT Page 13 of 15 NIA
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 Inches S.
CONTROL ROD POSITION CORRESPONDING Group Inches TO EXCESS SHUTDOWN MARGIN IN M (TDB Fig 1.3 or 5.1 and M)
T.
PDlL FOR UNTRIPPABLE OR DROPPED CONTROL ROD CONDITION (R or S, whichever is farthest withdrawn)
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 Forward Completed Form to Re PALISADES NUCLEAR PLANT ctor Engin Group Inches 4
101 4
20 4
101 NIA (Operators Name)
I (Today)
Performed By Date I
Reviewed By Date ering Supervisor I
Reactor Engineering Supervisor Date Page 14 of 15 AUGUST 2010
JPM SRO ADMIN l a (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
IN ITlAL CONDITIONS:
0 Rod #6 is inoperable and fully withdrawn.
0 It is believed that the rod is untrippable.
Burnup is 7,000 MWD/MTU.
0 Rx power is 100%.
0 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.
PALISADES NUCLEAR PLANT Page 15 of 15 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 1 b JOB PERFORMANCE MEASURE DATA PAGE Task:
Perform Safety Injection Refueling Water Tank Operations Alternate Path: NIA Facility JPM #: PL-OPS-ENG-O19J K/A:
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-2AI Chemical and Volume Control System Technical Data Book, figure 8.2 Validation Time: 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 8 AUGUST 2010
JPM SRO ADMIN I b Tools/Equipment/Procedures Needed:
0 SOP-2A, "Chemical and Volume Control System" Calculator 0
Pencil and paper 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:
0 Safety Injection Refueling Water Storage Tank boron concentration = 2149ppm Safety Injection Refueling Water Storage Tank level = 96%
0 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 SIRWT boron concentration.
PALISADES NUCLEAR PLANT Page 3 of 8 AUGUST 2010
JPM SRO ADMIN l b EVALUATOR CUE: Provide candidate a working copy of SOP-2A Section 7.6.1 TASK ELEMENT 1 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 fiII and drain operations TASK ELEMENT 2 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).I. 18,646 Where:
SlRW Tank Volume = SlRW total gallons
% meter reading = LIA-0332A or LIA-0331.
STANDARD Operator reviews caution s u STANOARO Operator calculates the following:
Amount of volume to add = 3000 gallons (give in initial conditions)
PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010 s u
I Operator calculates the following:
I 7.6-1.a.2 Blend Ratio = gallons of PMW per 1 gallon of concentrated Boric Acid BAST ppm = 12,524 SIRWT ppm = 2149 (12,524/2149) - 1 = 4.83 (allow 4.80 -
s u 4.85)
Comment:
EVALUATOR NOTE: Allow 4.80 fo 4.86 TASK ELEMENT 4 Gallons of concentrated boric acid to add = Total Volume Makeup to SIRW/(Blend Ratio + 1)
Where:
Total Volume Makeup to SIRWT =
Desired SIRWT level in gallons minus current level in gallons Blend Ratio = gallons of PMW per 1 gallon of concentrated Boric Acid 7'6'1'a'3 STANDARD Grade Operator calculates the following:
3000/(4.83 + 1) = 514.6 gal of boric acid s u
~
Comment:
EVALUATOR NOTE: Allow 511.9 - 517.2 PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010
JPM SRO ADMIN 1 b TASK ELEMENT 5 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 EVALUATOR NOTE: Allow 2483 - 2488 I
STANDARD Operator calculates the following:
3000 - 514.6 = 2485.4 gal of PMW TASK ELEMENT 6 STANDARD Proc.
Step Operator informs Control Room Supervisor of the volume of boric acid and primary makeup water to add.
nla I
CRS informed of the following volumes:
Primary Makeup Water: 2485.4 gal Concentrated Boric Acid: 514.6 gal s u -
Comment:
EVALUATOR NOTE: Allow 2483 - 2488 gal for Primary Makeup Water and 511.9 -
517.2 gal for Boric Acid EVALUATOR CUE: Role play as CRS END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 201 0
JPM SRO ADMIN I b SIMULATOR OPERATOR INSTRUCTIONS 0
NONE PALISADES NUCLEAR PLANT Page 7 of 8 AUGUST 201 0
JPM SRO ADMIN I b (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
IN ITlAL CONDITIONS:
0 Safety Injection Refueling Water Storage Tank boron concentration = 2149ppm Safety Injection Refueling Water Storage Tank level = 96%
0 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 SIRWT boron concentration.
PALISADES NUCLEAR PLANT Page 8 of 8 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:
SRO ADMIN 2 TITLE:
APPROVE A HEAVY LOAD MOVEMENT CANDIDATE:
EXAM1 NER:
JPM SRO ADMIN 2 JOB PERFORMANCE MEASURE DATA PAGE Task:
Approve a heavy load movement Alternate Path: N/A Facility JPM #: PL-OPS-ADM-001 J WA: 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 3-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 ADMIN 2 Tools/Equipment/Procedures Needed:
FHS-M-23, Movement of Heavy Loads in The Spent Fuel Pool Area,, 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:
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-14B 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 EVALUATOR CUE Provide candidate the completed FHS-M-23, Aft. 7 Working Copy.
Is the load a heavy load (>I300 Ibs)?
Att. 6 Proc. Step TASK ELEMENT I STANDARD Grade I
I SRO determines:
YES, Object is a heavy load (MSB Shield Lid weighs 6457 Ibs from Att. 2) s u Comment:
EVALUATOR CUE: Provide candidate with a working copy of FHS-M-23.
Proc. Step TASK ELEMENT 2 STANDARD Grade I
NO -
of DFS components between cask wash-down pit and cask loading floor area, Att.3 Is the load movement within Load Path 3 Att. 6 only?
Heavy Load path #4 determined for movement s u 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.
Evaluator Note: Candidate determines FHS-M-23 Attachment 7 working copy Block 7 "HL Path(s) Authorized For Use" is wrong and changes to reflect Load Path 4 (may be done at anytime prior to end of JPM).
Proc. Step TASK ELEMENT 3 STANDARD Grade I
I s u Will loads be moved over Load Path I? -
NO Att. 6 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.
PALISADES NUCLEAR PLANT Page 4 of 16 AUGUST 201 0
JPM SRO ADMlN 2 Proc. W p proc. step TASK ELEMENT 4 STANDARD Grade TASK ELEMENT 5 STANDARD Grade I
Will loads be moved over Load Path 4 Aft. 6 (Main Fuel Pool)?
YES Att. 6 s u Has fuel decayed 2 30 days?
YES (given in the initial conditions) s u Comment:
Evaluator Note: Candidate determines FHS-M-23 Attachment 1 working copy Block 7 "HL Path(s) Authorized For Use" is wrong and changes to reflect Load Path 4 (may be done at anytime prior to end of JPM).
Proc. Step TASK ELEMENT 6 STANDARD Grade
\\
s u Comment:
I PALISADES NUCLEAR PLANT Page 5 of 16 AUGUST 2010
JPM SRO ADMlN 2 Att. 6 Proc. Step TASK ELEMENT 7 STANDARD Grade I
Has fuel decayed 2 90 days?
YES (given in the initial conditions) s u Both CRHVAC filtration operable (refer to TS 3.7.10 if one train inoperable)
Att. 6 Both CRHVAC filtration trains verified operable S U 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.
Att. 6 Proc. Step TASK ELEMEPIT 8 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 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.
PrOC. step TASK ELEMENT 9 STANDARD Grade I
r Comment:
Rtoc. step TASK ELEMENT 10 STANDARD Grade I
I PALISADES NUCLEAR PLANT Page 6 of 16 AUGUST 2010
JPM SRO ADMIN 2 Att. 6 Proc. step TASK ELEMENT I 1 STANDARD Grade I
Will loads be moved over Load Path 3? -
NO s u Will loads be moved over Load Path 2?
I Att. 6 I Will non-heavy loads be moved under this Att. 6 procedure?
I I s u NO (given in initial conditions)
Comment:
Evaluator Note: Candidate determines FHS-M-23 Attachment 7 working copy Block 7 "HL Path(s) Authorized For Use" is wrong and changes to reflect Load Path 4 (may be done at anytime prior to end of JPM).
Proc. Step Proc. Step TASK ELEMENT 12 STANDARD Orade I
TASK ELEMENT 14 STANDARD Grade I
Proc. Step TASK ELEMENT 13 STANDARD Grade I
s u l s u l Will load be moved in an alternate path?
NO (Path 4 is the only path for this evolution)
I-I Att. 6 I Comment:
PALISADES NUCLEAR PLANT Page 7 of 16 AUGUST 2010
'.'.la Proc. Step TASK ELEMENT 15
. STANDARD Grade 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 I
I Comment:
TASK ELEMENT 16 I On-Shift, Duty SRO &aJ:
ENSURE plant systems and conditions are met.
5.1.I b
Comment:
STANDARD Grade SRO verifies plant systems and conditions are met (has effectively completed this step by ensuring Att. 6 complete) s u Proc. Step TASK ELEMENT 17 STANDARD Grade I
I I On-Shift, Duty SRO shall:
I SRO enters on FHS-M-23, Att. 1 :
I Complete Attachment 1 to document permission to commence heavy load movement for approved Load Paths during specified time period.
5'1'1c Signs, Dates and Times, in box (8)
Todav/l930 for Start in box (9) s u Todav/2300 OR 0700 tomorrow/ Sinned for Stop in box(9)
Comment:
Evaluator Note: Candidate determines FHS-M-23 Attachment 1 working copy Block 7 "HL Path(s) Authorized For Use" is wrong and changes to reflect Load Path 4 (may be done at anytime prior to end of JPM).
Evaluator Note: one-week duration limit found in Section 3.1.3d PALISADES NUCLEAR PLANT Page 8 of 16 AUGUST 2010
JPM SRO ADMlN 2 Roc. Step TASK ELEMENT 18 STANDARD 5'1'1md PALISADES NUCLEAR PLANT On-Shift, Duty SRO DOCUMENT authorization of heavy loads movements in the Operations log.
s u SRO makes END OF TASK Page 9 of 16 AUGUST 2010
JPM SRO ADMIN 2 SIMULATOR OPERATOR INSTRUCTIONS 0
NIA PALISADES NUCLEAR PLANT Page 10 of 16 AUGUST 2010
JPM SRO ADMIN 2 (I) Date: TODAY (4) Procedure used in conjunction w/FHS-M-23: NONE (2) Work Order No:
5199999 (3) Authorization Period:
(5) Special precautions to be taken:
Measure airder temperature for sinale failure Dower lift x Shift Daily Week (6) General Description of HL(s) Allowed (Can attach schedule to satisfv) 1 (7) HL Path@)
To Be Moved Authorized For Use MSB Shieldincl Lid I
4 (8) Approved By: On-Shift, Duty SRO (Name / Date / Time)
I IJ Operator/ TODAY I NOW I
I (9) HL Duration Approved Start: (Date / Time) Stop: (Date / Time)
TODAY START:
Tomorrow) 0700)
/IO) CALIBRATED EQUIPMENT Ilf Rewired)
Equipment Description Range / Accuracy Serial Number Calibration Date Calibration Due Date
_ _ _ _ _ _ _ _ ~
_ _ _ _ _ _ _ ~
FLUKE Model660 I
0-200"FI &.02"F I
CMS234567 06/01/2010
-1 06/01/2011 (11) HL PIC (12) Crane (1 3) Crane Operator (14) Signal Person (15) On-Shift, Duty SRO Name / Date / Time Inspection Name / Date / Time Name / Date / Time Contacted -- Name (Print)
Complete (4)
(Print)
(Print)
(Print)
J JOHNSON/ TODAY/ NOW X
I I
I I
ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY PALISADES NUCLEAR PLANT Page 11 of 16 AUGUST 201 0
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.
- 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 plantlsystedcornponent 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).
i
- 11.
- 12.
- 13.
- 14.
- 15.
- 16.
- 17.
- 18.
- 19.
- 20.
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, & 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 equipmentlplant 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
Proc No FHS-M-23 Revision 29 Page 2 of 4 HEAVY LOAD DATA SHEET (4) Procedure used in conjunction wlFHS-M-23: NONE (6) General Description of HL(s) Allowed (Can attach schedule to satisfv)
To Be Moved l(l) Date: TODAY (5) Special precautions to be taken:
Measure airder temDerature for sinule failure Dower lift (7) HL Path@)
Authorized For SRO Use (8) Approved By: On-Shift, Duty (Name / Date / Time)
(9) HL Duration Approved Start: (Date / Time) Stop: (Date / Time)
(2) Work Order No: 5199999 MSB Shielding Lid (3) Authorization Period:
1 x Shift 0 Daily 0 Week
~
~
~
~~~
2
/
I START:
/
STOP:
/
FLUKE Model 8660 0-200°F/
f.02"F CMS234567 0610 1 /2010 06/01/2011
/IO) CALIBRATED EQUIPMENT (If Rewired)
(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 / Date / Time Name / Date / Time Contacted -- Name Complete (4)
(Print)
(Print)
(Print)
X
oioz isnmv I N W d tlV313flN S3aVSllVd
~
~
I I
I I
Proc No FHS-M-23 Revision 29 Page 4 of 4 HEAVY LOAD DATA SHEET (1 7) Alternate Load Path (if used),
Description:
(1 8) Approved By:
I Reactor Engineer Date Attachment (YES I NO)
I (1 9) Approved By:
I On-Shift, Duty SRO Date PALISADES NUCLEAR PLANT Page 15 of 16 AUGUST 201 0
JPM SRO ADMIN 2 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
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-14B 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 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 CAN D I DATE:
EXAM1 NER:
JPM SRO ADMIN 3 JOB PERFORMANCE MEASURE DATA PAGE Task:
Alternate Path:
N/A Facility JPM #:
NEW K/A:
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.OE+03 to Respond to Steam Generator Tube leakage in accordance with ONP-23.2 9.OE+03 cpm)
Preferred Evaluation Location: Simulator -X-In Plant Preferred Evaluation Method:
Perform X
Simulate
References:
Validation Time: -
20-minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
ONP-23.2, Steam Generator Tube Leak Examiner:
Date:
Signature PALISADES NUCLEAR PLANT
~
Page 2 of 7 AUGUST 2010
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.
INITIAL CONDITIONS:
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.
0 Current estimated primary to secondary leakage is 0.01 gpm and stable.
PCS Gas Total Isotope = 0.5 VCi/cc 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 3 of 7 AUGUST 2010
JPM SRO ADMIN 3 Proc.Step EVALUATOR CUE:Provide candidate a working copy of ONP-23.2.
TASK ELEMENT 3 STANDARD Grade I
Att 2 step 3.a 1-t:
TASK ELEMENT 1 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.
STANDARD Refer to ONP-23.2 Attachment 1 page 2 of 3.
s u -
Proc.Step TASK ELEMENT 2 STANDARD Grade 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 />.
Pg 2 Step 1 Comment:
I I Step pg2 2 Determines PCS Gas Total Isotope =
0.5 pCi/cc from initiating cue.
I OBTAIN PCS Gas Total Isotope from Chemistry using last known analysis.
l s u l Comment:
PALISADES NUCLEAR PLANT Page 4 of 7 AUGUST 2010
JPM SRO ADMIN 3 Proe.$tep TASK ELEMENT 4 STANDARD Grade pg 2 Step 3 Comment:
Determines 0.02 gpm (from Attachment 2 s u DETERMINE maximum Primary to Secondary Leakrate based on current Action Level.
Step 3a.)
Proc.Step TASK ELEMENT 5 STANDARD Grade I
Step 4 Comme CALCULATE uncorrected leakrate using the following equation:
Uncorrected Leakrate (pCi-gal/min-kg) =
Primary to Secondary Leakrate (gallmin) X PCS Gas Total Isotope (pCi/cc) X 1000 (cc/kd Calculates uncorrected leakrate using formula:
0.02 gpm X 0.5 pCi/cc X 1000 =
10.0 pCi-gal/min-kg s u -
TASK ELEMENT 6 Pgs 2&3 Step 5 I-Comment:
ESTIMATE RIA-0631 count rate using the Uncorrected Leakrate Graph on page 3.
STANDARD Determines 8.5E+03 cpm using pg 3 graph with 4 scfm 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.*
Pg 2.*
s u EVALUATOR NOTE: allow 8.OE+03 to 9.OE+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 5 of 7 AUGUST 2010
JPM SRO ADMIN 3 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 is an at-power IC.
PALISADES NUCLEAR PLANT Page 6 of 7 AUGUST 2010
JPM SRO ADMIN 3 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
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 7 of 7 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMlN 3 TITLE: DETERMINE INCREASED MONITORING ACTIONS PER ONP-23.2, STEAM GENERATOR TUBE LEAK PROCEDURE CANDl DATE:
EXAM I NER:
JPM SRO ADMIN 3 JOB PERFORMANCE MEASURE 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.OE+03 to 9.OE+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: -
20-minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature AUGUST 2010 PALISADES NUCLEAR PLANT Page 2 of 7
JPM SRO ADMlN 3 Tools/Equi pment/Proced u res 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.
INITIAL CONDITIONS:
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.
0 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 7 AUGUST 2010
EVALUATOR CUE:Provide candidate a working copy of ONP-23.2.
Proc.Step TASK ELEMENT 2 STANDARD TASK ELEMENT I Grade Att 2 step 3.a Pg 2 Step 1 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.
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 />.
Comment:
Proc.Step TASK ELEMENT 3 STANDARD I
STANDARD Grade Refer to ONP-23.2 Attachment 1 page 2 of 3.
pg step 2 s u OBTAIN PCS Gas Total Isotope from Chemistry using last known analysis.
Comment:
I Comment:
PALISADES NUCLEAR PLANT JPM SRO ADMIN 3 s u Determines PCS Gas Total Isotope =
0.5 yCi/cc from initiating cue.
Page 4 of 7 AUGUST 2010
STANDARD Proc.Step TASK ELEMENT 4 Grade pg 2 step 3 I
STANDARD Grade Proc.Step TASK ELEMENT 5 s u Determines 0.02 gpm (from Attachment 2 Step 3a.)
DETERMINE maximum Primary to Secondary Leakrate based on current Action Level.
pg 2 Step 4 CALCULATE uncorrected leakrate using the following equation:
Uncorrected Leakrate (pCi-gal/min-kg) =
Primary to Secondary Leakrate (gal/min) X PCS Gas Total Isotope (pCi/cc) X 1000 (cc/kg)
Comment:
Calculates uncorrected leakrate using formula:
0.02 gpm X 0.5 pCi/cc X 1000 =
10.0 pCi-gal/min-kg s u -
Pgs 2&3 Step 5 TASK ELEMENT 6 ESTIMATE RIA-0631 count rate using the Uncorrected Leakrate Graph on page 3.
STANDARD
. Determines 8.5E+03 cpm using pg 3 graph with 4 scfm Off Gas flowrate line and 2.OE+00 Uncorrected Leak Rate line.
SIGNS Completed By on Attachment 1 Pg 2.*
Informs CRS of results and that Reviewed By signature is still required.*
s u Comment:
EVALUATOR NOTE: allow 8.OE+03 to 9.0+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 5 of 7 AUGUST 2010
JPM SRO ADMIN 3 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 is an at-power IC.
PALISADES NUCLEAR PLANT Page 6 of 7 AUGUST 2010
JPM SRO ADMIN 3 (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 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 7 of 7 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:
EXAM1 NER:
JPM SRO ADMIN 3 JOB PERFORMANCE MEASURE DATA PAGE Task:
Respond to Steam Generator Tube leakage in accordance with ONP-23.2 Alternate Path:
NEW KIA:
2.3.11 Importance:
RO:3.8 SRO:
4.3 K/A Statement: Ability to control radiation releases.
Task Standard: Determines RIA-0631 count rate of 8.5E+03 cpm (allow 8.OE+03 to 9.OE+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: -
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 7 AUGUST 2010
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.
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 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 7 AUGUST 2010
JPM SRO ADMlN 3 Att step 3.a EVALUATOR CUE:Provide candidate a working copy of ONP-23.2.
ESTIMATE the count rate indication on RIA-0631, Condenser Off Gas Monitor, secondary leakrate. Refer to Attachment 1, "Estimation of Primary to Secondary Leakrate."
which would result in a 0'02 gpm primary to Refer to ONP-23.2 Attachment 1 page 2 of 3.
Proc.Step TASK ELEMENT 1 STANDARD Grade I
Proc.Step TASK ELEMENT 2 STANDARD Grade s u Pg 2 Step 1 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 />.
pg Step 2 I
Proc,Step TASK ELEMENT 3 STANDARD 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.
Comment:
PALISADES NUCLEAR PLANT Page 4 of 7 AUGUST 2010
JPM SRO ADMIN 3 ProcSteR TASK ELEMENT 4 STANDARD Grade I
s u pg 2 Determines 0.02 gpm (from Attachment 2 Step 3a.)
DETERMINE maximum Primary to Secondary Leakrate based on current Step 3 Action Level.
Comment:
pg 2 Step 4 TASK ELEMENT 5 CALCULATE uncorrected leakrate using the following equation:
Uncorrected Leakrate (VCi-gal/min-kg) =
Primary to Secondary Leakrate (gal/min) X PCS Gas Total Isotope (VCikc) X 1000 (cc/kg)
Comment:
STANDARD Calculates uncorrected leakrate using formula:
0.02 gpm X 0.5 VCi/cc X 1000 =
10.0 VCi-gal/min-kg s u TASK ELEMENT 6 ESTIMATE RIA-0631 count rate using the Uncorrected Leakrate Graph on page 3.
Pgs 2&3 Step 5 Comment:
EVALUATOR NOTE: allow 8.0+03 to 9.0+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.
art of the critical step STANDARD Determines 8.5E+03 cpm using pg 3 graph with 4 scfm Off Gas flowrate line and 2.OE+00 Uncorrected Leak Rate line.
SIGNS Completed By on Attachment 1 Pg 2.*
Informs CRS of results and that Reviewed By signature is still required.*
s u END OF TASK PALISADES NUCLEAR PLANT Page 5 of 7 AUGUST 2010
JPM SRO ADMIN 3 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 is an at-power IC.
PALISADES NUCLEAR PLANT Page 6 of 7 AUGUST 2010
JPM SRO ADMIN 3 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
IN IT1 AL CONDITIONS:
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 7 of 7 AUGUST 2010
TITLE:
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 4 CLASSIFY EVENT AND DETERMINE PAR CAN D I DATE:
EXAM I NER:
JPM SRO ADMIN 4 JOB PERFORMANCE MEASURE DATA PAGE Task:
Classify an Event and Determine PARS - Protective Action Recommendations Alternate Path:
NEW WA:
2.4.41, 2.4.44 Importance:
RO:4.1, 4.0 SRO: 4.1,4.4 WA Statement: (2.4.41) Knowtedge of the emergency action level threshholds and classifications.
(2.4.44) Knowledge of emergency plan protective action recommend at ions.
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: Any 2-Preferred Evaluation Method:
Perform X
Simulate
References:
El-I I Emergency Classifications and Actions El-3, Communications and Notifications El-6.13, Protective Action Recommendations for Offsite Populations Validation Time: -
20-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 2010
JPM SRO ADMlN 4 Tools/Equ ipmenVProcedu res Needed:
El-I, Emergency Classifications and Actions, Attachment 1 E I -3, Co m mu n i ca t io n s and Not if i ca t io n s El-6.1 3, 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.
SIRWT level is 92% and lowering slowly.
A release IS occurring through a stuck open code safety valve on the A Steam Genera tor.
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 Proc.Step TASK ELEMENT 1 STANDARD I
EVALUATOR: Candidate may use placard of site emergency plan classifications or use paper copy from 1-1, attachment I.
Grade El-1 Att 1 Refers to lower right-hand corner of El-I,
(PCS > 200 degrees F)".
s u Refers to "Fission Product Barriers" section,
Conditions (lower right-hand corner)
Comment:
Proc.Step TASK ELEMENT 3 STANDARD I
TASK ELEMENT 2 Grade Determines status of fission product barriers.
STANDARD Refers to Table F1 Determines a POTENTIAL LOSS of Fuel Cladding (based on RVLMS < 614 ft 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).
El-I Declares Emergency Classification.
I Att 1 1 Declares a GENERAL EMERGENCY per FG1 based on status of fission product barriers (loss of TWO and potential loss of THIRD).
s u I Comment:
I CRITtCAI; @T'EP-- muat b pMormed wM%a 15 minutes of start of JPM.
I PALISADES NUCLEAR PLANT Page 4 of 10 AUGUST 201 0
JPM SRO ADMIN 4 Proc.Step TASK ELEMENT 4 STANDARD Grade I
Obtains El-I, Attachment 2 and fills out.
s u El-1 Prepares Emergency Actions/Notifications
~ t t 2 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.
Proc.Step TASK ELEMENT 5 STANDARD Grade s u EI-3 Att 1 Obtains EI-3, Attachment 1 and fills out per attached KEY.
Prepares Event Notification Form.
~~~
~~~
Comment:
EVALUATOR CUE: 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 CUE: If JPM is not conducted in the Simulator, hand them a blank Event Notification form to fill out (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.
Proc.Step TASK ELEMENT 6 STANDARD Grade 1-6.1 3 Att 1 Determines Protective Action Recommendations (PARS).
Obtains EI-6.13 and corresponding and determines:
Evacuate Areas 1 and 3 (minimum GE recommendation on bottom of Pg 1 of )
s u Comment:
EVALUATOR NOTE: Provide candidate with a working copy of El-6.13.
PALISADES NUCLEAR PLANT Page 5 of 10 AUGUST 2010
JPM SRO ADMlN 4 E'-1 ProcStep TASK ELEMENT 7 STANDARD Grade 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.
Et-3 Att 1 Comment:
EVALUATOR NOTE: If candidate attempts to pertbrm this step, provide them with a working copy of 1-11, attachment 2.
Palisades Event Notification Form completely filled per attached KEY AND form is approved (Candidate initials, date, and time entered at bottom of form)
- Completes filling out Palisades Event Notification Form.
Prgc.SCp TASK ELEMENT 8 STANDARD Grade I
I I CRITICAL STEP - must be performed wlthfn 13 minutes of deQlaration of General Qnergency.
END OF TASK PALISADES NUCLEAR PLANT Page 6 of 10 AUGUST 201 0
ANSWER KEY JPM SRO ADMIN 4 Proc No El-3 Revision 29 Page 1 of 1 PALISADES EVENT NOTIFICATION FORM 0 ActualEvent Drill Plant Contact Information Nuclear Power Plant:
Plant Communicator:
Time of Communication: V.B.
S.O.M.
NRC Plant Message Number Calling From:
0 Control Room 0 TSC OEOF 0 Other Call Back Telephone Number:
Current Classification 0
Unusual Event 0 Alert Site Area Emergency General Emergency 0 Termination Time: Within 15 minutes from start of JPM This Classification was declared as of:
Date: Today Reason for Classification 0
Abnormal Rad Levels / Radiological Effluent 0 Hazards and Other Conditions Affecting 0 System Malfunctions Cold Shutdown / Refueling System Malfunction 0
Independent Spent Fuel Storage Fission Product Barrier Degradation Plant Safety Installation Events IC Number: FGl Radiological Release in Progress Due to Event IXI Yes 0
No Protective Action Recommendations 0
None Evacuation of Areas(s):
1 2
3 4
5 In-Place ShelterofArea(s) 0 1 0 2
3 c]
4 5
PAR based on:
[7 Dose Calculation (Palisades Event Technical Data Sheet required)
Plant Status 0 Security Event Other Meteorological Data Wind Direction (degrees): From 305 To 125 Wind Speed (MPH): 1 Stability Class: G Precipitation: 0 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, have a release in progress.
\\
candidate IS in the simulator while doing this JPM, THEN ensure the IC does NOT ENSURE ALL DATA IS CLEARED FROM EP NOTIFICATION COMPUTER ON BACK-BAR OF CRS ISLAND PRIOR TO NEXT USE OF THIS JPM.
PALISADES NUCLEAR PLANT 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)
- 2.
WD, Wind Direction = 305 O from (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 ADMIN 4 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
e e
e e
e e
e e
e e
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.
SIRWT 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 10 of 10 AUGUST 2010