Text

Initial Exam 2011-302 Final Administrative JPMs
	ML113390452
Person / Time
Site:	Oconee
Issue date:	12/01/2011
From:	; NRC/RGN-II
To:	;
References
	Download: ML113390452 (87)
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REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-1 31 (RO Only)

Admin-131 fs Page 1 of 10 CANDIDATE EXAMINER

Admin-131 fs Page 2 of 10 REQNll V

V INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Perform Manual RCS Leakage Calculation Alternate Path:

No Facility JPM #:

CRO-43 KIA Rating(s):

System: Gen K/A:

2.1.7 Rating

4.4/4.7 Task Standard:

RCS Leakage is correctly calculated per of attached key.

Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator In-Plant Classroom X

Perform X

Simulate

References:

PT/O/A/0600/00i A, Loss Of Computer, rev 30 PT/i /A/600/1 0, Reactor Coolant Leakage, rev 91 Validation Time: 18 minutes Time Critical: NO Candidate:

Time Start:

NAME Time Finish:

Performance Rating:

SAT UNSAT Performance Time Examiner:

I NAME SIGNATURE DATE COMMENTS

NONE SIMULATOR OPERATOR INSTRUCTIONS Admin-131 fs Page 3 of 10

Admin-131 fs Page 4 of 10 ToolslEguipment/Procedures Needed PTI1IAI600/10 Enclosure 13.3 READ TO OPERATOR DIRECTION TO TRAINEE 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 Oconee Unit I computer repairs are expected to be extended through turnover for hardware replacement. The Loss of Computer procedure PTIO/AJO600IOO1A, Loss of Computer, is in progress, however an RCS Leakage Calculation has not been performed during this shift.

INITIATING CUES The Control Room SRO directs you to perform a manual RCS leakage calculation per PT/I A/600/10 (Reactor Coolant Leakage), Enclosure 13.3 (Manual RCS Leakage Calculation Data Sheet) using the data collected below.

Manual RCS Leakage Data Parameter Initial Final Time 0015 0115 Pzrlevel 219.0 inches 219.5 inches Tave Indication 579.1°F 579.0°F Quench Tank Level 86.5 inches 86.5 inches LDST Level 76.7 inches 74.0 inches Power Range NI 100.0%

100.1%

RCSNRPressure 2150 psig 2150 psig Group 7 Control Rod Position 92.7%

92.7%

START TIME:

STEP 1:

Step2.1 Record Initial Data in Table #1 Admin-131 fs Page 5 of 10 Value Initial Data Minus Final Data Equals Change PZR Level 219.0 inches RCSTemp 579.1°F

=

QT Level 86.5 inches

=

LDST Level 76.7 inches

=

RxPower 1000%

=

RCS Press 2150 psig

=

CRPos 92.7%

=

STANDARD:

Student enters initial set of data into Table #1 of Enclosure 13.3 (Manual Leakage Calculation Data Sheet) from the initiating cue.

COMMENTS STEP 2:

Step 2.2 Record time Initial Data recorded:

STANDARD:

Student enters 0015 (from initiating cue)

Sat COMMENTS Unsat Sat Unsat

STEP 3:

Step 2.3 After 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , record Final Data in Table #1.

Admin-131 fs Page 6 of 10 Value Initial Data Minus Final Data Equal Change PZRLeveI 219.Oinches 219.5inches

=

RCS Temp 579.1°F 579.0°F

=

QT Level 86.5 inches 86.5 inches

=

LDST Level 76.7 inches 74.0 inches

=

RxPower 100.0%

100.1%

RCS Press 2150 psig 2150 psig CR Pos 92.7%

92.7%

STANDARD:

Student enters final set of data into Table #1 of Enclosure 13.3 (Manual Leakage Calculation Data Sheet) (from initiating cue)

COMMENTS STEP 4:

Step 2.4 Record time Final Data recorded:

STANDARD:

Student enters 0115 Sat COMMENTS Unsat STEP 5:

Step 2.5 CRITICAL STEP Record time elapsed time:

minutes STANDARD:

Student enters 60 minutes Sat COMMENTS Unsat Sat Unsat

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Admin-131 fs Page 8 of 10 STEP :10 Step 2.10 CRITICAL STEP Convert LDST Level Change to gallons STANDARD:

+2.7 inches X 30.956 gallons I inch = +83.5812 gallons

(+83.5 to +83.6)

Sat COMMENTS Unsat STEP :11 Step 2.11 CRITICAL STEP Calculate Total Volume Change STANDARD:

-16.994 gallons + 0 gallons + 83.5812 gallons = 66.5872 gallons

( -16.95 to -17.24)

(+83.5 to +83.6)

(66.26 to 66.65)

Sat COMMENTS Unsat STEP :12 Step 2.12 CRITICAL STEP Calculate RCS Unidentified Leakage Rate STANDARD:

66.5872 gallons /60 minutes = 1.109 gpm (66.26 to 66.65)

(1.104 to 1.11)

Sat COMMENTS Unsat END TASK STOP TIME:

Admin-131 fs Page 9 of 10 CRITICAL STEP EXPLANATIONS:

STEP #

Explanation 5

Necessary data calculation to properly determine manual RCS leakage rate.

6 Necessary data calculation to properly determine manual RCS leakage rate.

7 Necessary data calculation to properly determine manual RCS leakage rate.

8 Necessary data calculation to properly determine manual RCS leakage rate.

9 Necessary data calculation to properly determine manual RCS leakage rate.

10 Necessary data calculation to properly determine manual RCS leakage rate.

11 Necessary data calculation to properly determine manual RCS leakage rate.

12 Necessary data calculation to properly determine manual RCS leakage rate.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Oconee Unit 1 computer repairs are expected to be extended through turnover for hardware replacement. The Loss of Computer procedure PT/O/AJO600IOOIA, Loss of Computer, is in progress, however an RCS Leakage Calculation has not been performed during this shift.

INITIATING CUES The Control Room SRO directs you to perform a manual RCS leakage per PT/I A/600/1O (Reactor Coolant Leakage), Enclosure 13.3 (Manual RCS Leakage Calculation Data Sheet) using the data collected below.

Manual RCS Leakage Data Parameter Initial Final Time 0015 0115 Pzrlevel 219.0 inches 219.5 inches Tave Indication 579.1°F 579.0°F Quench Tank Level 86.5 inches 86.5 inches LDST Level 76.7 inches 74.0 inches PowerRangeNl 100.0%

100.1%

RCSNRPressure 2150 psig 2150 psig Group 7 Control Rod Position 92.7%

92.7%

ADM1n 3.3 Manual RCS Leakage Calculation Data Sheet PT/1/A/0600/0 10 Page 1 of2 2.

Procedure NOTE:

If Tav is on-scale, use Tave. If Tave is off-scale, use T 0

Id.

If RCS NR Pressure is on-scale, use NR Pressure. If RCS NR Pressure is off-scale, use RCS WR Pressure.

2.1 kecord initial Data in Table #1.

/ 2.2 Record time Initial Data recorded:

..2.3 After 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , record Final Data in Table #1.

v 2.

4 Record time Final Data recorded: / /5_

i.. 2.5 Record elapsed time:

6° minutes NOTE:

Change = Initial - Final Negative sign (-) should be included with values as appropriate.

Calculate and record Change values in Table # 1.

Table # 1

\\,

1.

Initial Conditions N one 3.3 PT/1/A/0600/O1O Manual RCS Leakage Calculation Data Sheet Page 2 of 2 NOTE:

Conversion Factor (6.831 inches/°F) must be positive (+) value. {7 2.7 Calculate Corrected Pzr Level Change:

c inches (6.831 inches/°F x OF)

LI3_

inches (I) PZR Level Change Level Change due to Temp. (2)

Corrected PZR Level Change 2.8 Convert Corrected Pzr Level Change to gallons:

inches x14.364 gallons/inch

=

Corrected PZR Level Change Conversioli corrected to 68°F PZR Volume Change V

2.9 Convert QT Level Change to gallons: {4}

x 34.94 gallons / inch =

0 gallons (3) QT Level Change Conversion corrected to 68°F QT Volu,ne Change 2.1O Convert LDST Level Change to gallons:

inches x30.956 gallons/inch =

S9/.

gallons (4) LDST Level Change Conversion corrected to 68°F LDST Volume Change V 2.11 Calculate Total Volume Change:

Lj gallons +

gallons + ?3. S\\ )

gallons =

gallons PZR Volume Change QT Volume Change LDST Volume Change Total Change 2.12 Calculate RCS Unidentified Leakage Rate:

t?)-...

gallons÷ Minutes =

________gpm Total Change (5) Duration RCS Leakage Rate 3.3 PT/1/A10600/OlO Manual RCS Leakage Calculation Data Sheet Page 1 of 2 1.

Initial Conditions None 2.

Procednre NOTE:

If Tave is on-scale, use Tave. If Tave is off-scale, use T 0

Id.

If RCS NR Pressure is on-scale, use NR Pressure. If RCS NR Pressure is off-scale, use RCS WR Pressure.

2.1 Record Initial Data iiiTable #1.

2.2 Record time Initial Data recorded:

2.3 After 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , record Final Data in Table #1.

2.4 Record time Final Data recorded:

2.5 Record elapsed time:

minutes NOTE:

Change = Initial

- Final Negative sign (-) should be included with values as appropriate.

2.6 Calculate and record Change values in Table # I.

Table # 1 Value initial Data Minus Final Data Equals Change Pzr Level inches inches

=

inches (1)

RCS Temp.

°F

=

°F (2)

(Tave_or_T 0

1d)

QT Level inches inches

=

inches (3)

LDST Level inches inches

=

inches (4)

RxPower

=

RCS Pressure (NR or WR) psig psig

=

psig Control Rod Position p

PT/1/A10600/0 10 Page 2 of 2 3.3 Manual RCS Leakage Calculation Data Sheet Conversion Factor (6.831 inchcs/°F) must be positive (+) value. {7}

Calculate Corrected Pzr Level Change:

inches (6.831 inches/°F x OF)

=

inches (1) PZR Level Change Level Change due to Temp. (2)

Corrected PZR Level Change 2.8 Convert Corrected Pzr Level Change to gallons:

inches x 14.364 gallons /inch

=

gallons Corrected PZR Level Change Conversion corrected to 68°F PZR Volume Change 2.9 Convert QT Level Change to gallons: {4}

inches x 34.94 gallons / inch =

gallons (3) QT Level Change Conversion corrected to 68°F QT Volume Change 2.10 Convert LDST Level Change to gallons:

inches x 30.956 gallons/inch =

gallons Conversion corrected to 68°F LDST Volume Change (4) LDST Level Change 2.11 Calculate Total Volume Change:

gallons +

PZR Volume Change QT Volume Change 2.12 Calculate RCS Unidentified Leakage Rat&:

gallons ÷ Minutes =

Total Change (5) Duration

[NOTE:

2.7 gallons =

gallons LDST Volume Change Total Change

________gpm RCS Leakage Rate

REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-1 17 RO ONLY Admin-1 17 fs Page 1 of 12 CANDIDATE EXAMINER

Admin-117 fs Page 2 of 12 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Perform a power Imbalance verification and incore detector operability.

Alternate Path:

NO Facility JPM #:

Admin-1 17 K/A Rating(s):

System:

G K/A:

2.1.25 Rating:

3.9/4.2 Task Standard:

Candidate determines that Axial Power Imbalance is within the limits of the COLR and the minimum Incore Detectors are NOT operable.

Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator In-Plant Classroom X

Perform X

Simulate

References:

PTI1IA/06001001 (Periodic Instrument Surveillance) procedure and Enclosures 13.1 OP/1/AJ11O5/014 (Control Room Instrumentation Operation and Information)

PT/0/AJ1 103/019 (Backup Incore Detector System)

Core Operating Limits Report Validation Time: 35 mm.

Time Critical: NO Candidate:

Time Start:

NAME Time Finish:

Performance Rating:

SAT UNSAT Performance Time:

Examiner:

/

NAME SIGNATURE DATE COMMENTS

None SIMULATOR OPERATOR INSTRUCTIONS:

Admin-1 17 fs Page 3 of 12

Admin-117 fs Page 4 of 12 ToolsIEg u ipmentlProcedu res Needed:

PTIIIAIO600IOOI, Periodic Instrument Surveillance Procedure and Enclosure 13.1 OP/i /A/1105/014, Control Room Instrumentation Operation and Information PT/0/AJi 103/019 (Backup Incore Detectors)

Core Operating Limits Report READ TO OPERATOR DIRECTIONS TO STUDENT:

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:

1.

Unit I had a transient from 100% power 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago

2. The current time is 0800.

3. The Reactor Calculation package is NOT running.

4.

All other equipment is operable

5. PT/i/A/0600/00i, Periodic Instrument Surveillance, Enclosures 13.1 has been completed up to page 7, Axial Power Imbalance Operating Limits.

INITIATING CUE:

The SRO directs you to:

I. Verify Axial Power Imbalance is within operational alarm limits in the COLR in accordance with OP/i /A/i105/014 (Control Room Instrumentation Operation And Information)

2. Verify the minimum backup incore detector points are operable per PT/0/Ai103/019 (Backup Incore Detector System) and determine any required actions.

Adm in-i 17 fs Page 5 of 12 START TIME:

STEP 1:

PTIIIAJO600IOO1, SR 3.2.2.1 Axial Power Imbalance Operating Limit:

IF > 40% RTP, verify Power imbalance within operational alarm limits in COLR.

SAT IF Reactor Calculations package is NOT running on computer, refer to OP/I /A/1105/014 (Control Room Instrumentation Operation And Information).

UNSAT STANDARD:

Determine reactor power is greater than 40%.

Determine Reactor Calculation package is NOT running per Initial Conditions and refer to OP/i /A/1105/014 (Control Room Instrumentation Operation And Information).

PT/i /A/0600/001 Enclosure 13.1 Page 7 of 27 COMMENTS:

STEP 2:

OP/i/Ni 105/014 End 4.13 Step 3.2 3.2 Reactor Power Axial Imbalance and Quadrant Power Tilt:

SAT 3.2.3 Order of preference of measurement systems to determine axial imbalance and quadrant power tilt is as follows:

UNSAT A. Incore Detectors (Computer Reactor Calculation Package).

B. Outcore Detectors (Power Range Outcore Detectors).

C. Backup Incore Detectors. Refer to PT/0/Ni 103/019 (Backup Incore Detector System).

STANDARD:

Candidate reviews step and continues to Step 3.2.4 COMMENTS:

Admin-1 17 fs Page 6 of 12 STEP 3:

Step 3.2.4 IF at least one power range outcore detector is NOT operable in each quadrant (N 1-5 thru N 1-8), outcore detectors shall NOT be used to SAT measure axial imbalance or quadrant power tilt STANDARD:

Determine NI-S thru Nl-8 are operable and can be used to measure axial imbalance.

UNSAT COMMENTS:

STEP 4:

Step 3.2.5 IF Outcore Detectors (Power Range Outcore Detectors) are needed for tilt calculations, contact Rx Engineering group to perform SAT PTIOIAI1 103/018 (Excore Tilt Calculations).

STANDARD:

Determine this step does not apply because they are NOT determining a tilt calculation at this time.

UNSAT COMMENTS:

STEP 5:

Step 3.2.6 CRITICAL STEP IF Outcore Detectors (Power Range Outcore Detectors) are needed for imbalance calculations, refer to the following alternate method for determining (%) Reactor Power Axial Imbalance:

SAT Nl5* + Nl6* + Nl7* + NI8* = % Imbalance (Avg.)

4

Use Imbalance CR gauges reading for each NI.

UNSAT STANDARD:

Using the attached NI graphic determine that % Imbalance (Avg.) is 17.3.

Refer to the Unit 1 COLR and determine that this is within the limit for current plant conditions.

COMMENTS:

Adm in-i 17 fs Page 7 of 12 STEP 6:

Step 3.2.7 IF Reactor Calculations package is NOT running, verify minimum incore detector operability requirements are met. Refer to PT/0/AI1 103/019 SAT (Backup Incore Detector System).

STANDARD:

Determine Reactor Calculations package is NOT running, verify minimum incore detector operability requirements are met. Refer to UNSAT PT/0/A/1 103/019 (Backup lncore Detector System).

COMMENTS:

STEP 7:

Perform PT/0/A/1 103/019 (Backup lncore Detector System).

CRITICAL STEP Step 12.1 (Verification of Minimum Incore Detector Operability)

SAT Step 12.1.1 On Enclosure 13.1, Required Backup Recorder Points for Calculating Axial Power Imbalance AND 13.2, Required Backup Recorder Points for UNSAT Calculating Quadrant Power Tilt, place an X next to the backup recorder points which are inoperable as indicated by off-scale readings OR notes attached to the recorders.

Step 12.1.2 Verify that all three required points on at least three detector strings are operable per instructions on Enclosure 13.1, Required Backup Recorder Points for Calculating Axial Power Imbalance. (Acceptance Criteria 11.1.1)

Step 12.1.3 Verify that all four required points on at least four sets (two sets in each axial core half) are operable per instructions on Enclosure 13.2, Required Backup Recorder Points for Calculating Quadrant Power Tilt.

(Acceptance Criteria 11.1.2)

STANDARD:

Perform Enclosure 13.1 and determine that there are not sufficient recorder points for calculating Axial Imbalance. (Acceptance Criteria 11.1.1 is NOT met)

Perform Enclosure 13.2 and determine that there are not sufficient recorder points for calculating Quadrant Power Tilt. (Acceptance Criteria 11.1.2 is NOT met)

COMMENTS:

Admin-1 17 fs Page 8 of 12 STEP 8 Step 12.1.4 CRITICAL STEP IF either step 12.1.2 OR 12.1.3 CANNOT be satisfied; A. Notify the Unit Supervisor.

SAT B. Take actions described in 6.2.

Step 6.2 IF the incore system is NOT available on the unit computer AND the backup UNSAT recorder points are NOT operable per this procedure, then the reactor power shall be reduced below 80% of the power allowable for the existing reactor coolant pump combination within eight hours unless:

6.2.1 The incore system is restored on the unit computer.

OR 6.2.2 The backup recorder points are restored to meet the minimum requirements for operability. (ref. SLC 16.7.8)

STANDARD:

Notify the Unit Supervisor Recommend reducing reactor power to below 80% power within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR 1.

restoring operability to lncores system (OAC)

OR 2.

the backup recorder points are restored to meet the minimum requirements for operability COMMENTS:

END TASK TIME STOP:

Admin-1 17 fs Page 9 of 12 CRITICAL STEP EXPLANATIONS:

STEP #

Explanation 5

Required to determine imbalance is within the COLR limit.

7 Candidate determines that there are not sufficient incore detectors per End. 13.1 and 13.2.

8 Candidate determines the requirement to reduce power to < 80% within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

BACKUP INCORE CHART A POINT #

Location 1

132.7 G09-L2 2

QQS G09-L4 3

138.0 G09-L6 4

143.1 E09-L2 5

133.3 E09-L4 6

QQS E09-L6 7

128.8 G05-L2 8

154.1 G05-L6 9

133.8 M07-L2 10

QQS M07-L6 11 133.8 K11-L2 12 145.6 K11-L6 13 142.5 F13-L2 14 144.4 D05-L2 15 133.8 F13-L4 16

QQS C06-L2 17

QQS C06-L6 18 144.5 F13-L6 19

QQS 010-L6 20

QQS L03-L6 21

QQS L03-L2 22

QQS D05-L6 23

QQS O10-L2 24 122.9 D05-L4

Work Request written BACKUP INCORE CHART B POINT #

Location 1

QQS E-07-L6 2

142.5 G11-L6 3

128.8 M09-L6 4

132.7 K05-L6 5

133.3 K05-L4 6

QQS L06-L2 7

QQS L06-L4 8

QQS L06-L6 9

QQS M09-L2 10 154.1 K05-L2 11 138.0 G11-L2 12

QQS E07-L2 13 133.8 C1O-L2 14 145.6 C10-L6 15

QQS F03-L2 16 122.9 F03-L6 17

QQS N04-L2 18 144.4 N04-L4 19

QQS N04-L6 20 145.0 006-L2 21 136.1 006-L4 22 133.8 006-L6 23

QQS L13-L2 24 133.8 L13-L6 Note: Listed points with values are in calibration.

POWER RANGE NIS 99.9 1OD.)

A A

A 125

+60 125

+60 125 +60 100 +40 100 +40 100 +40 80

+20 80

+20 60 0

60 0

40

-20 40

-20 20

-40 20

-40 0

-60 0

-60 V

V V

-17.5

-1712

-17.2

%IMB

%IMB N15

%FP N16

%FP N17

%FP N18

%FP A

125

+60 100 +40 80

+20 60 0

40

-20 20

-40 0

-60 V

-17.3

%IMB

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1.

Unit I had a transient from 100% power 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago

2. The current time is 0800.

3. The Reactor Calculation package is NOT running.

4.

All other equipment is operable 5.

PTIIIAIO600IOOI, Periodic Instrument Surveillance, Enclosures 13.1 has been completed up to page 7, Axial Power Imbalance Operating Limits.

INITIATING CUE:

The SRO directs you to:

1. Verify Axial Power Imbalance is within operational alarm limits in the COLR in accordance with OP/I 1A111051014 (Control Room Instrumentation Operation And Information)

2. Verify the minimum backup incore detector points are operable per PTIOIA/11031019 (Backup Incore Detector System) and determine any required actions.

REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-237 (Both)

Admin-237 fs Page 1 of 9 CANDIDATE EXAMINER

Admin-237 fs Page2of9 REGION1I INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Perform SG Downcomer Temperature Surveillance Alternate Path:

No Facility JPM #:

Admin-207 K/A Rating(s):

System:

Gen K/A:

2.2.12 Rating:

3.7/4.1 Task Standard:

Perform SG Downcomer Temperature Surveillance by procedure for the 1A (ONLY) SG and determine that the surveillance requirement is NOT met.

Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator In-Plant Classroom X

Perform X

Simulate

References:

OP/1/A/1105/014 End 4.1 (Mode 1&2), rev 024 OP/i/Ni 105/014 End. 4.19 (Channel Check Of OTSG Downcomer Temperatures), rev 024 Validation Time: 18 minutes Time Critical: NO Candidate:

Time Start:

NAME Time Finish:

Performance Rating:

SAT UNSAT Performance Time:

Examiner:

NAME SIGNATURE DATE COMMENTS

NONE SIMULATOR OPERATOR INSTRUCTIONS Admin-237 fs Page 3 of 9

Admin-237 fs Page4of9 ToolslEci uiprnent!Procedures Needed:

OPIIIAI11O5/014 (Control Room Instrumentation Operation And Information)

OAC Screen capture image for SG Downcomer temperatures and Outlet Pressures READ TO OPERATOR DIRECTION TO TRAINEE:

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:

Reactor power = 100%

OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Enclosure 4.1 (Mode I & 2) in progress.

INITIATING CUES:

CR SRO directs you to perform OP/11A111051014 (Control Room Instrumentation Operation And Information) Enclosure 4.1 (Mode 1 & 2) on page 4 component check for the 1A SG Downcomer Temperature.

Admin-237 fs Page5ofg STARETTtME STEP 1:

SLC 16.7.5 CRITICAL STEP Verify All SG Downcomer Temperature computer points agree within 3°F of each other.

SAT IF All SG Downcomer Temperatures DO NOT agree within 3°F of each other, then perform Enclosure Channel Check Of OTSG Downcomer Temperatures.

UNSAT 01 E2008 534.4°F 01 E2009 529.3°F 01E2012 535.7°F 01E2013 532.8°F STANDARD:

Determine that the above OAC points do NOT agree within 3°F of each other, and perform Enclosure 4.19 Channel Check of OTSG Downcomer Temperatures.

COMMENTS:

STEP 2:

Step 3.1 (Enclosure 4.19)

Determine saturation temperature for 1A OTSG based on power level and IA OTSG outlet pressure as follows:

SAT Step 3.1.1 Determine 1A OTSG outlet pressure using any one of the following computer points:

UNSAT 01 E2281 885.0 psig 01 E2283 884.9 psig 01E2031 885.1 psig 01 E2032 885.0 psig STANDARD:

Using the OAC determine that 1A OTSG pressure is between 884.9 and 885.1 psig.

COMMENTS:

Admin-237 fs Page6of9 STEP 3:

Step 3.1.2 CRITICAL STEP Using table in Section 4, determine the 1A OTSG saturation temperature based on power level and 1A OTSG Outlet Pressure obtained in step 3.1.1.

SAT IA OTSG saturation temperature UNSAT STANDARD:

Determine that IA OTSG saturation temperature is 534.45°F (534.4°F to 534.5 °F) by using the table in section 4.

COMMENTS:

STEP 4:

Step 3.1.3 CRITICAL STEP Compare 01 E2008 SG Lower Downcomer Temperature Loop A to the 1A OTSG saturation temperature determined in step 3.1.2:

SAT Step 3.1.4 IF 01 E2008 SG Lower Downcomer Temperature Loop A is NOT within

+/- 4.9 °F of the IA OTSG saturation temperature, then enter Condition A UNSAT of SLC 16.7.5 for OTSG overfill protection system inoperable.

STANDARD:

Determine that 01 E2008 SG Lower Downcomer Temperature Loop A is within +/- 4.9 °F of the 1A OTSG saturation temperature and N/A this step.

COMMENTS:

Admin-237 fs Page7of9 STEP 5:

Step 3.1.5 CRITICAL STEP Compare O2OO G Lower Downcomer remperature Loop Ato the 1A OTSG saturation temperature determined in step 3.1.2:

SAT Step 3.1.6 IF 01 E2009 SG Lower Downcomer Temperature Loop A is NOT within LJNSAT

+/- 4.9 °F of the 1 A OTSG saturation temperature, then enter Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable.

STANDARD:

Determine that 01 E2009 SG Lower Downcomer Temperature Loop A is NOT within +/- 4.9 °F of the 1A OTSG saturation temperature, and enter Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable.

Cue: SRO is notified to enter SLC 16.7.5 Condition A and another operator will complete this procedure, the JPM is complete.

COMMENTS:

END TASK STOP TIME:

Admin-237 Page8ofg CRITICAL STEP EXPLANATIONS:

STEP #

Explanation 1

Step is required to complete the surveillance.

3 Step is required to complete the surveillance.

4 Step is required to complete the surveillance.

5 Step is required to determine that entry into SLC 16.7.5 is required.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)-

INITIAL CONDITIONS:

Reactor power = 100%

OPIIIAI11O5/014 (Control Room Instrumentation Operation And Information) Enclosure 4.1 (Mode 1 & 2) in progress.

INITIATING CUES:

CR SRO directs you to perform OP/I/Ni 105/014 (Control Room Instrumentation Operation And Information) Enclosure 4.1 (Mode I & 2) on page 4 component check for the IA SG Downcomer Temperature.

REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-330 (Both)

Admin-330 fs Page 1 of 12 CANDIDATE EXAMINER

Admin-330 fs Page 2 of 12 RGIOttJI INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Calculate the Maximum Permissible Stay Time Alternate Path:

N/A Facility JPM #:

CRO-302 K/A Rating(s):

System:

Gen K/A:

2.3.4 Rating

3.2/3.7 Task Standard:

Calculate the Maximum Permissible Stay Time Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator In-Plant Classroom X

Perform X

Simulate

References:

NSD-507, Radiation Protection, rev 014 Validation Time: 10 mm.

Time Critical: NO Candidate:

Time Start:

NAME Time Finish:

Performance Rating:

SAT UNSAT Performance Time Examiner:

/

NAME SIGNATURE DATE COMM ENTS

NONE SIMULATOR OPERATOR INSTRUCTIONS Admin-330 fs Page 3 of 12

Admin-330 fs Page 4 of 12 Tools/EguipmentlProcedures Needed Color copies of the following:

Room 254 (3B SFP Filter) Plan View RWP#116 READ TO OPERATOR DIRECTIONS TO STUDENT 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 3B SEP Filter is required to be isolated for filter replacement.

All work will be performed in the vicinity of the 3B SEP filter.

NECs current dose for the year is 1500 mr INITIATING CUE Refer to RWP #116 and the plan view for Unit 3 SEP Demineralizer and Filters Room and determine how long the NEC can stay in the room performing this isolation before he must exit due to a dose alarm or exceeding his yearly administrative limit Assume no dose received in transient to and from the task.

Admin-330 fs Page 5 of 12 START TIME:

Note: Candidate may perform these steps in a different order however the calculated stay time should be correct.

STEP 1:

From the Plan View of room 254 (Unit 3 Demineralizer and Filter)

CRITICAL STEP determine dose rate in the vicinity of the 3B SEP filter.

SAT STANDARD:

Plan View is referenced and the general area dose rate is determined to be 250 mr/hr at the 3B SEP Filter.

UNSAT COMMENTS:

STEP 2:

Determine from RWP the dose alarm setpoint.

CRITICAL STEP SAT STANDARD:

RWP #116, Task 2 (High Radiation Area Entry) Dose alarm set at l5Omr COMMENTS:

UNSAT STEP 3:

Calculate maximum stay time the NEC has to complete the isolation CRITICAL STEP before he must exit due to a dose alarm and exceeding the 2000 mr yearly administrative limit.

SAT STANDARD:

Stay time is calculated to be:

Available Dose 150 mrem

= 0.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (36 mm) (Dose alarm)

UNSAT Dose Rate 250 mrem/hr Available Dose

=

500 mrem

= 2.0 hours0 days 0 hours 0 weeks 0 months (120 mm) (Admin limit)

Dose Rate 250 mrem/hr 36 minutes would be the maximum stay time.

COMMENTS:

END OF TASK TIME STOP:

Admin-330 fs Page 6 of 12 CRITICAL STEP EXPLANATIONS STEP #

Explanation 1

The plan view must be referenced to determine the dose rate in the room.

2 Required to calculate how much dose the NEO has available before a dose alarm is received.

3 Required to calculate stay time.

CANDIDATE CUE SHEET

- (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS 3B SEP Eilter is required to be isolated for filter replacement.

All work will be performed in the vicinity of the 3B SEP filter.

NECs current dose for the year is 1500 mr INITIATING CUE Refer to RWP #116 and the plan view for Unit 3 SEP Demineralizer and Eilters Room and determine how long the NEC can stay in the room performing this isolation before he must exit due to a dose alarm or exceeding his yearly administrative limit Assume no dose received in transient to and from the task.

m254 UniL3 SEP Derninetaflzer and FUars jsurvey # M-02155519[ Dat&Tirne TODAY 0630 983

+320 650 Unless otherwise noted, dose rates in mremlhr.

1) 52K DPM/100 cm2 13/v 2) 162K DPM/100 cm2 13/v 3) 22K DPM/100 cm2 13/y 4) 78K DPM/100 cm2 13/y 10 1

250 0

25 0

0 Comments:

Summary of Highest Readings Smears Air Samples & Wipes Symbol Legend (for example only)

Type: Job Cove RWP: 116 1 50

-Cont Read HS-50 Hot Spot

-30 cm Read RX Power=1 00°!

20

-Gen Area RCA Posting Smear 15 Air Sample Wipe

1) ODAC Surveyor: W Winters:

I Approved by: N. Wilson, Today

TRAINING Oconee Nuclear Station TRAINING US ONLY RditiOh Work Prmit uSE ONIX Entry For Routine Plant And Systems Operation (Operations)

RWP #116 Rev: 0 Task#1 Entry For Routine Plant And Systems Operation (Operations)

ED Alarm Set Points:

Dose Alarm: 10 Dose Rate Alarm: 50 Stay Time Alarm: 50:00 RWP Requirements Dress Category/Work Description

Dress Category A Work in a non-contaminated area

Dress Category B Work in a non-contaminated area with contaminated material where there is NO potential for contact with contaminated material other than by hand and durability of surgical gloves is sufficient (e.g., taking smears, etc.).

Dress Category C Work in a non-contaminated area with contaminated material where there is NO potential for contact with contaminated material other than by hand AND durability of surgical gloves is NOT sufficient.

Dress Category D Work of short duration, in open area(s) with NO obstructions that could contribute to contamination of unprotected skin or clothing

Dress Category E Work where: (1) Complete protection of skin and clothing is NOT required; (2) Durability of surgical gloves requires consideration; (3) Radioactive material is handled and/or transported AND the potential for loose surface contamination exist.

Dress Category F Work in a contaminated area where complete protection of skin and clothing is NOT necessary.

Dress Category G Work in a dry contaminated area.

Dress Category H Work in a contaminated area.

Dress Category N Performing work in contaminated wet conditions.

Modesty garments, top & bottom, are required under protective clothing where personal outer clothing is not worn Contamination Control

Wipe down AND bag all tools and equipment prior to removal from a contaminated area as directed by RP

Utilize facial protection (e.g. face shield, hood sock, power visor) as directed by RP

Install catch containments OR drain rigs to prevent spills if draining components If installing a drain rig, use hose clamps or similar device to secure hose OR tubing connections If installing a drain rig, secure hose OR tubing to floor drain

Wear disposable (plastic) booties inside of orex booties for work in wet conditions

Change outer rubber gloves often when handling highly contaminated material as directed by RP

Use surgical gloves in lieu of rubber gloves for the manipulation of small or specialty items as directed by RP

RPJobCverage

Start of Job, Intermittent or No Coverage In Radiation Areas or Less

RP Coverage Required To Transport Material> 100 Mrem/Hr Contact On Material Dosimetry Requirements

Monitor ED periodically while inside the RCA/RCZ (once or twice per hour in low dose rate areas). Monitor more frequently in higher dose rate areas, for example every 10 to 15 minutes.

If dress requirements prevent the monitoring of ED, and RP is not remotely monitoring (via teledose &

communications), place ED external to the outmost layer of protective clothing for monitoring RP Hold Points

RP survey required prior to handling debris or foreign material

Notify RP prior to reaching OR entry into the overhead (8 feet and above)

Accumulated dose higher than expected Stop Work Criteria

Dose Alarm

Unexpected dose rate alarm

Airborne conditions higher than expected

Actual dose rates are higher than the expected levels written on this RWP task

Actual contamination levels are higher than the expected levels written on this RWP task

Unexpected wet conditions

If monitoring of the ED indicates that the dose alarm set point will be exceeded prior to completing the job, leave the area and contact RP. Do not wait to receive an alarm before exiting the area

Failure of OR sweat soaked protective clothing Expected Radiological Conditions General area dose rates: 0.1 mrem/hr - 100 mrem/hr High contact dose rates: 0.1 mrem/hr - 3000 mrem/hr Contamination levels: <1000 dpm/lOOcm2 - 100,000 dpm/lOOcm2 (Beta/Gamma)

Contamination levels: 0 dpm/lOOcm2 - 300 dpm/lOOcm2 (Alpha)

Additional Instructions Utilize Mirrors and / or Remote Surveillance Equipment to Eliminate Room Entry When Feasible.

TRAINING Oconee Nuclear Station TRAINING USE OF4L(

Radiation Work Périnit tJS ONLY Entry For Routine Plant And Systems Operation (Operations)

RWP #116 Rev: 00 Task#2 Isolate and drain the 3B SFP Filter (Operations)

ED Alarm Set Points:

Dose Alarm: 150 Dose Rate Alarm: 500 Stay Time Alarm: 45:00 High Radiation Area Entry RWP Requirements Dress Category/Work Description

Dress Category A Work in a non-contaminated area

Dress Category B Work in a non-contaminated area with contaminated material where there is NO potential for contact with contaminated material other than by hand and durability of surgical gloves is sufficient (e.g., taking smears, etc.).

Dress Category C Work in a non-contaminated area with contaminated material where there is NO potential for contact with contaminated material other than by hand AND durability of surgical gloves is NOT sufficient.

Dress Category D Work of short duration, in open area(s) with NO obstructions that could contribute to contamination of unprotected skin or clothing

Dress Category E Work where: (1) Complete protection of skin and clothing is NOT required; (2) Durability of surgical gloves requires consideration; (3) Radioactive material is handled and/or transported AND the potential for loose surface contamination exist.

Dress Category F Work in a contaminated area where complete protection of skin and clothing is NOT necessary.

Dress Category G Work in a dry contaminated area.

Dress Category H Work in a contaminated area.

Dress Category I Hands on work with higher contaminated material or beta dose concerns to hands only.

Dress Category N Performing work in contaminated wet conditions.

Modesty garments, top & bottom, are required under protective clothing where personal outer clothing is not worn Contamination Control

Wipe down AND bag all tools and equipment prior to removal from a contaminated area as directed by RP

Utilize facial protection (e.g. face shield, hood sock, power visor) as directed by RP

Install catch containments OR drain rigs to prevent spills if draining components If installing a drain rig, use hose clamps or similar device to secure hose OR tubing connections If installing a drain rig, secure hose OR tubing to floor drain

Wear disposable (plastic) booties inside of orex booties for work in wet conditions

Change outer rubber gloves often when handling highly contaminated material as directed by RP

Use surgical gloves in lieu of rubber gloves for the manipulation of small or specialty items as directed by RP

RP Job Coverage

Start of Job, Intermittent or No Coverage for work in High Radiation Areas or less

Timekeeping/dose controller required for workers exposed to an actual dose rate >1500 mrem/hr OR dose will exceed 500 mrem for an individual entry

Pre-job briefing required Dosimetry Requirements

An Auxiliary ED alarm is required in areas where general area dose rates are> 100 mrem/hr if any of the following conditions exist:

1. High noise level in the work area.

2. Use of head phones

3. Hearing impairment

4. Any other condition that would impair hearing an ED alarm

Monitor ED periodically while inside the RCA/RCZ (once or twice per hour in low dose rate areas). Monitor more frequently in higher dose rate areas, for example every 10 to 15 minutes.

If dress requirements prevent the monitoring of ED, and RP is not remotely monitoring (via teledose &

communications), place ED external to the outmost layer of protective clothing for monitoring Respiratory Protection If weighted DAC-Hours are expected to result in greater than or equal to 4 DAC-Hours per person, perform a TEDE/ALARA evaluation

Full Face Particulate (Additional Hood Required) IF warranted by TEDE ALARA Evaluation OR directed by RP RP Hold Points

RP survey required prior to handling valve/pump parts or internals

RP survey required prior to handling debris or foreign material

Notify RP prior to reaching OR entry into the overhead (8 feet and above)

Accumulated dose higher than expected

Notify RP Prior to Start of Work

RP briefing required prior to entering High Radiation Areas Stop Work Criteria

Dose Alarm

Unexpected dose rate alarm

Actual dose rates are higher than the expected levels written on this RWP task

Actual contamination levels are higher than the expected levels written on this RWP task

Unexpected wet conditions

Work scope changes If monitoring of the ED indicates that the dose alarm set point will be exceeded prior to completing the job, leave the area and contact RP. Do not wait to receive an alarm before exiting the area

Failure of OR sweat soaked protective clothing Expected Radiological Conditions General area dose rates: 100 mrem/hr - 700 mrem/hr High contact dose rates: 0.1 mrem/hr - 3000 mrem/hr Contamination levels: <1000 dpm/lOOcm2

- 100,000 dpm/lOOcm2 (Beta/Gamma)

Contamination levels: 0 dpm/lOOcm2 -300 dpm/lOOcm2 (Alpha)

Additional Instructions Position body as far away from high dose sources as practical

REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-I 30 (SRO Only)

Admin-130 fs Page 1 of 11 CANDIDATE EXAMINER

Admin-130 fs Page 2 of 11 REGLONII

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Perform Manual RCS Leakage Calculation and TS Determination Alternate Path:

No Facility JPM #:

CRO-43 K/A Rating(s):

System:

Gen K/A:

2.1.7 Rating

4.4/4.7 Task Standard:

RCS Leakage is correctly calculated per of attached key.

TS 3.4.13 Condition A entered.

Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator In-Plant Classroom X

Perform X

Simulate

References:

PT/O/A/0600/OOIA, Loss Of Computer, rev 30 PTI1/A10600/10, Reactor Coolant Leakage, rev 91 TS 3.4.13 RCS Operational LEAKAGE Validation Time: 18 minutes Time Critical: NO Candidate:

Time Start:

NAME Time Finish:

Performance Rating:

SAT UNSAT Performance Time Examiner:

NAME SIGNATURE DATE COMM ENTS

NONE SIMULATOR OPERATOR INSTRUCTIONS Admin-130 fs Page 3 of 11

Admin-l3Ofs Page4ofll ToolslEguipmentlProcedures Needed:

PT/l/A1600110 Enclosure 13.3 Technical Specifications READ TO OPERATOR DIRECTION TO TRAINEE 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 Oconee Unit I computer repairs are expected to be extended through turnover for hardware replacement. The Loss of Computer procedure PTIOIA/0600/OO1A, Loss of Computer, is in progress; however an RCS Leakage Calculation has not been performed during this shift.

INITIATING CUES The OSM directs you to perform a manual RCS leakage calculation per PT/I A/600/10 (Reactor Coolant Leakage), Enclosure 13.3 (Manual RCS Leakage Calculation Data Sheet) using the data collected below.

Evaluate leakage and determine if any TS LCOs are not met.

Assume all leakage is unidentified Manual RCS Leakage Data Parameter Initial Final Time 0015 0115 Pzrlevel 219.0 inches 219.5 inches Tave Indication 579.1°F 579.0°F Quench Tank Level 86.5 inches 86.5 inches LDST Level 76.7 inches 74.0 inches PowerRangeNl 100.0%

100.1%

RCS NR Pressure 2150 psig 2150 psig Group 7 Control Rod Position 92.7%

92.7%

START TIME:

STEP 1:

Step2.1 Record Initial Data in Table #1.

Admin-130 ft Page5ofll Value Initial Data Minus Final Data Equals Change PZR Level 219.0 inches RCS Temp 579.1°F

=

QT Level 86.5 inches

=

LDST Level 76.7 inches

=

RxPower 100.0%

=

RCS Press 2150 psig

=

CR Pos 92.7%

=

STANDARD:

Candidate enters initial set of data into Table #1 of Enclosure 13.3 (Manual Leakage Calculation Data Sheet) from the initiating cue.

COMMENTS STEP 2:

Step 2.2 Record time Initial Data recorded:

STANDARD:

Candidate enters 0015 (from initiating cue)

Sat COMMENTS Unsat Sat Unsat

STEP 3:

Step 2.3 After 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , record Final Data in Table #1.

Admin-130 fs Page6ofll Value Initial Data Minus Final Data Equal Change PZR Level 219.0 inches 219.5 inches

=

RCS Temp 579.1°F 579.0°F

=

QT Level 86.5 inches 86.5 inches

=

LDST Level 76.7 inches 74.0 inches

=

RxPower 100.0%

100.1%

=

RCS Press 2150 psig 2150 psig

=

CR Pos 92.7%

92.7%

=

STANDARD:

Candidate enters final set of data into Table #1 of Enclosure 13.3 (Manual Leakage Calculation Data Sheet) (from initiating cue)

COMMENTS STEP 4:

Step 2.4 Record time Final Data recorded:

STANDARD:

Candidate enters 01 15 Sat COMMENTS Unsat STEP 5:

Step 2.5 CRITICAL STEP Record time elapsed time:

minutes STANDARD:

Candidate enters 60 minutes Sat COMMENTS Unsat Sat Unsat

Admin-130 fs Page7ofll STEP 6:

Step 2.6 Calculate and record Change values in Table # 1..

Value Initial Data Minus Final Data Equal Change PZR Level 219.0 inches 219.5 inches

=

-.5 inches RCS Temp 579.1°F 579.0°F

=

+.1°F QT Level 86.5 inches 86.5 inches

=

0 inches LDST Level 76.7 inches 74.0 inches

=

+2.7 inches RxPower 100.0%

100.1%

=

-.1%

RCS Press 2150 psig 2150 psig 0 psig CR Pos 92.7%

92.7%

=

0 %

STANDARD:

COMMENTS STEP :7 STANDARD:

Candidate calculates the change in data and fills in Table 1 change column.

Step 2.7 Calculate Corrected Pzr Level Change:

-0.5 inches (6.831 inches/°F X +1°F) = -1.1831 inches CRITICAL STEP Sat Unsat CRITICAL STEP Sat

(-1.18 to -1.2)

Unsat COMMENTS STEP :8 Step 2.8 CRITICAL STEP Convert Corrected Pzr Level Change to gallons STANDARD:

-1.1831 inches X 14.364 gallons! inch = -1 6.994 gallons

(-1.18 to -1.2)

( -16.95 to -17.24)

Sat COMMENTS Unsat

Admin-130 fs Page8of 11 STEP :9 Step 2.9 CRITICAL STEP Convert QT Level Change to gallons:

STANDARD:

No change Sat COMMENTS Unsat STEP :10 Step 2.10 CRITICAL STEP Convert LDST Level Change to gallons STANDARD:

+2.7 inches X 30.956 gallons I inch = +83.5812 gallons

(+83.5 to +83.6)

Sat COMMENTS Unsat STEP :11 Step 2.11 CRITICAL STEP Calculate Total Volume Change STANDARD:

-16.994 gallons + 0 gallons + 83.5812 gallons = 66.5872 gallons

( -16.95 to -17.24)

(+83.5 to +83.6)

(66.26 to 66.65)

Sat COMMENTS Unsat STEP :12 Step 2.12 CRITICAL STEP Calculate RCS Unidentified Leakage Rate STANDARD:

66.5872 gallons /60 minutes = 1.109 gpm (66.26 to 66.65)

(1.104 to 1.11)

Sat COMMENTS Unsat

Admin-130 fs Page 9 of 11 STEP :13 Refer to TS 3.4.13 RCS Operational LEAKAGE CRITICAL STEP STANDARD:

Determine leakage exceeds 1 gpm unidentified and TS 3.4.13 Condition A applies. Reduce LEAKAGE to within limits with a completion Sat time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

COMMENTS Unsat END TASK STOP TIME:

Admin-130 fs Page 10 of 11 CRITICAL STEP EXPLANATIONS STEP #