Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML102670524
Person / Time
Site:	Calvert Cliffs
Issue date:	07/13/2010
From:	Mark Draxton; Constellation Energy Nuclear Group
To:	Peter Presby; Operations Branch I
	Hansell S
Shared Package
ML100560028	List: IR 05000317/2010301; ML102070208; ML102670378; ML102670380; ML102670391; ML102670392; ML102670396; ML102670401; ML102670495; ML102670496; ML102670508; ML102670524; ML111670753;
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2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: RO-ADMIN-1

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-ADMIN-l Task

Title:

Respond to a complete loss of SDC (Estimate Time to Boiling & Core Uncovery)

Task Number: 202.023 KIA

Reference:

2.1.20 (4.6, 4.6)

Method of testing:

Simulated Performance: D Actual Performance: C8J Classroom: ~ Simulator: D Plant: D READ TO THE APPLICANT:

Initial Conditions:

1. Unit-2 RCS is drained to 39 feet.

2. Nozzle Dams are not installed

3. RCS temperature is 120 OF.

4. The reactor was shut down 20 days ago after an extended period of full power operation.

S. Refueling operations were completed 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ago. 91 fresh fuel assemblies were loaded in the core.

6. A loss of shutdown cooling has occurred.

7. You are performing the duties of an extra CROw Initiating Cue:

The Shift Manager directs you to estimate the time to boiling AND core uncovery per AOP-3B, Step IV.B.S.

Task Standard:

Determine Time to Boil and Time to Core Uncovery.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant

2. A copy of AOP-3B, ABNORMAL SHUTDOWN COOLING CONDITIONS, ATTACHMENT (11), to fill out in completing this JPM.

General

References:

AOP-3B, ABNORMAL SHUTDOWN COOLING CONDITIONS, ATTACHMENTS 8 thru 13 Time critical task:

No Validation Time:

20 minutes Simulator Setup:

1. None required

ELEMENT STANDARD

(* = CRITICAL STEP)

I Time Start:

i 0 Locates AOP-3B, Step IV.B.5 Same as element

1. Calculate Time To Boil.

a. Determine the Time To Boil at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after I shutdown from the appropriate figure, based on RCS level and RCS temperature:

Note to evaluator:

Completion of this JPM requires interpreting graphs that have the potential to induce minor variations in calculated results.

Determines TTB @ 24 hrs is approximately 11.3 minutes (11 to 11.5 minutes) o Attachment (9), Time to Start Boiling After LOSDC 24 Hours After Shutdown SG U Determines this step is NIA Tubes Full

- mpltipHer,fromAttachmellt(lO),

n<Frme to$tartBoilingOrOQre US~gATTACHME~

determines multiplier of 3.08

.ery, based OIltime afteN;huidown.

c. Multiply the Time To Boil at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after shutdown by the multiplier:

r--.,.-----..---..------------~-t---~- . .- - - - - - - - - - t Using ATTACHMENT (10), page 1, determines the Post Refueling multiplier is applicable with a value of 1.4 Performs calculation 11.3 X 3.08 X 1.4 48.7 mins o d. Independently verify the calculation. Requests independent verification

2. Calculate Time To Core Uncovery:

a. Determine the Time To Core Uncovery at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after shutdown from the appropriate figure, based on RCS level and RCS temperature:

Note to evaluator:

Completion of this JPM requires interpreting graphs that have the potential minor variations in calculated results.

Determines Time to Core Uncovery

@ 24 hrs is approximately 128 minutes (126 - 130 mins) o Attachment(13), Time to Core Uncovery After LOSDC 24 Hours After Shutdown With Determines this step is NIA Nozzle Dams, No Injection, No Cold Leg Hole o b. Obtain the multiplier from Attachment(l 0),

Using ATTACHMENT (10),

Multiplier on Time to Start Boiling Or Core determines multiplier of 3.08 Uncovery, based on time after shutdown.

c. Multiply the Time To Core Uncovery at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after shutdown by the multiplier.

Using ATTACHMENT (10), page 1, I

determines the Post RI~fueling

o Obtain value for Post Refueling Multiplier multiplier is applicable with a value of 1.4 1'iri1e:t().~rt¥"i:.rp.covery@.24 hrsX multiplier Performs calculation

- Xppst1refqe1irl:g multiplier:;: Time to Cbre 128 X 3.08 X 1.4 = 552 mins or 9.2 un'6bve~ .~.. . hrs o d. Independently verify the calculation. Requests independent vl~rification I Terminating Cue: This JPM is complete when the AOP-3B, ATTACHMENT (11),

CALCULATION OF TIME TO BOIL OR CORE UNCOVERY, worksheet has been i completed. No further actions are required.

~

Verification of Completion Job Performance Measure Number: RO-ADMIN-l Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _~. _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _~ _ _ __ UNSAT _ _ _ _ _ _ __

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

AOP-3B Rev 23/U nit 2 ATfACHMENT(11)

Page 1 of1 CALCULATION OF TIME TO BOIL OR CORE UNCOVERY NOTE Perform the applicable Step 1 or 2.

1. Calculate Time To Boil:

a. Determine the Time To Boil at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after shutdown from the appropriate figure, based on RCS level and RCS temperature:

ATTACHMENT (8), TIME TO START BOILING AFTER LOSDC 24 HOURS AFTER SHUTDOWN

ATTACHMENT (9), TIME TO START BOILING AFTER LOSDC 24 HOURS AFTER SHUTDOWN SG U-TUBES FULL

b. Obtain the multiplier from ATTACHMENT(10). MULTIPLIER ON TIME TO START BOILING OR CORE UNCOVERY. based on time after shutdown.

c. Multiply the Time To Boil at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after shutdown by the multiplier.

t\,3 nuns.

TTB at 24 hrs X 3.08 multilier

'.4 X ---,.:..-.-::--

post refueling 4&,1 m\r, Time To Boil 02300 multiplier (IF applicable)

d. Independently verify the calculation.

2. Calculate Time To Core Uncovery:

a. Determine the Time To Core Uncovery at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after shutdown from the appropriate figure, based on RCS level and RCS temperature:

ATTACHMENT(12), TIME TO CORE UNCOVERY AFTER LOSDC 24 HOURS AFTER SHUTDOWN NO NOZZLE DAMS, NO INJECTION, NO COLD LEG HOLE

ATTACHMENT(13). TIME TO CORE UNCOVERY AFTER LOSDC 24 HOURS AFTER SHUTDOWN WITH NOZZLE DAMS. NO IN,IECTION. NO COLD LEG HOLE b, Obtain the multiplier from AITACHMENT(10), MULTIPLIER ON TIME TO START BOILING OR CORE UNCOVERY. based on time after shutdown,

c. Multiply the Time To Boil at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after shutdown by the multiplier.

/' SS'Z. W",",S,

,'Z8 VV\ H\S

X 3. 0 e, X _ _\_,--':4:----::-_ q I ~ hrs 02300 Time to Core Uncovery multiplier post refueling Time To Core at 24 hrs multiplier Uncovery (IF applicable) d, Independently verify the calculation.

APPLICANT'S CUE SHEET Initial Conditions:

1. Unit-2 RCS is drained to 39 feet.

2. Nozzle Dams are not installed

3. RCS temperature is 120 °P.

4. The reactor was shut down 20 days ago after an extended period of full power operation.

5. Refueling operations were completed 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ago. 91 fresh fuel assemblies were loaded in the core.

6. A loss of shutdown cooling has occurred.

7. You are performing the duties of an extra CRO.

Initiating Cue:

The Shift Manager directs you to estimate the time to boiling AND core uncovery per AOP-3B, Step IV.B.S.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: RO-ADMIN-2

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-ADMIN-2 Task

Title:

Monitor Azimuthal Power Tilt (Tq) using Excore Nuclear Instrumentation Task Number: 204.129 KJ A

Reference:

2.1.25 (3.9, 4.2)

Method of testing:

Simulated Performance: D AcruaIPerrormance:i:8J Classroom: i:8J Simulator: D Plant: D READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Unit-1 power was recently reduced to 70% power to facilitate repairs to 11 SGFP.

2. CEAs are currently inserted to lOS inches on Group 5.

3. Channel "D" LRNI is out of service for maintenance. T.S. LCOs 3.3.1.A and 3.3.1.D have been entered.

4. The plant computer has "crashed" and is inoperable.

5. OPS CALC is not available.

6. You are performing the duties of the CRO.

7. NI Readings are as follows:

Channel Upper Lower A 70.9 69.9 I B 6S.3 67.2 C 69.7 6S.7 D 0 0 Initiating Cue:

AOP-7H, Loss of Plant Computer, has been implemented and the CRS directs you to determine the Azimuthal Power Tilt (Tq) using the excore Nls per Section IV.E alnd determine if any limits are being exceeded.

Task Standard:

Calculate and determine whether or not Tq is in spec.

.-----'-------~------------------------~ .... -----,

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant

2. AOP-7H, Loss of Plant Computer in Mode One or Two, ATTACHMENT (2)

3. AOP-7H, Loss of Plant Computer in Mode One or Two, ATTACHMENT (5)

General

References:

1. AOP-7H, Loss of Plant Computer in Mode One or Two.

2. AOP-7H, Loss of Plant Computer in Mode One or Two, ATTACHMENT (2)

3. T.S. 3.2.4 Azimuthal Power Tilt - Tq Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

1. None

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start:

CUE: The CRS directs you to determine the Azimuthal Power Tilt (Tq) using the excore NIs per AOP-7H,Section IV.E.

o Locates AOP-7H,Section IV.E. - IF Greater than Same as element.

50% Rated Thermal Power, Monitor Tq.

0 1. Calculate upper AND lower Tq using ANY of the following:

0 IF ALL four Linear Power Channels are operable, Determines Step is NtA THEN perform EITHER of the following:

OR NOTE A total of 3 upp.er and 3 lower Linear detectors are required to be operable. The failed I detectors can be on dIfferent channels.

o IF only 3 Linear Power Channels are operable AND Reactor Power is less than 75%,THEN Determines Step is applicable perform EITHER of the following:

o b. Calculate Tq using the method in ATTACHMENT 5), Tq CALCULATION USING EXCORE DETECTORS Records Readings on Attachment 5 o Recordthereadin~s on ATrA H MENT and performs calculations per formula on Attachment 5 (5J~ Tq CAL U LATION USING EXORij'.DETECTORS Calculates Upper Tq .02970 Calculates Lower Tq .03152 o Notify the Reactor Engineering Work Group Determines Step is NtA to provide an alternate method to monitor Tq.

o 2. Once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , recalculate the Azimuthal Determines step is NtA at this time OR Power Tilt using the Excore Detectors PER Step Adds note to Shift Turnover E.l, Page 11. Information Sheet

ELEMENT STANDARD

(* == CRITICAL STEP) o 3. IF Tq is greater than 0.03, THEN perform the Determines Tq is greater than 0.03 following actions: and escalates issue to CRS I Terminating Cue: This JPM is complete when calculated azimuthal power tilt (Tq) is determined I to be outside acceptable limits. No further actions are required.

Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: RO-ADMIN-2 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ _ __

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:

1) Unit-l power was recently reduced to 70% power to facilitate repairs to 11 SGFP.

2) CEAs are currently inserted to 108 inches on Group 5.

3) Channel "D" LRNI is out of service for maintenance. T.S. LCOs 3.3.l.A and 3.3.1.D have been entered.

4) The plant computer has "crashed" and is inoperable.

5) OPS CALC is not available.

6) You are perfonning the duties of the CRO.

7) NI Readings are as follows:

Channel Upper Lower A 70.9 69.9 B 68.3 67.2 C 69.7 68.7 D 0 0 Initiating Cue:

AOP-7H, Loss of Plant Computer, has been implemented and the CRS directs you to detennine the Azimuthal Power Tilt (Tq) using the ex core NIs per Section IV.E and determine if any limits are being exceeded.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: RO-ADMIN-3

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-ADMIN-3 Task

Title:

Verify CC system valve operability Task Number: 015.004 KJA

Reference:

2.2.21 (2.9,4.1)

Method of testing:

Simulated Performance: 0 Actual Performance: L8J Classroom: L8J Simulator: 0 Plant: 0 READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1) Unit-l is at 100% power

2) Maintenance has just been completed with repacking 11 SDC HX CC DISCH valve 1 CC-3828-CV. The appropriate TS LCOs are in effect.

3) The valve has been stroked and the limit switches adjusted for PMT with all local observations by the Mechanics and 1M satisfactory.

4) The CV has been turned over to Operations for PMOT.

5) You are performing the duties of the CRO.

Initiating Cue:

The CRS has directed you to complete PMOT testing requirements for l-CC-3828-CV under Work Order C90811426. The CRS has also provided EN-4-108 Attachment (7) and STP-O-65G-l, Component Cooling Valve Quarterly Operability Test.

Task Standard:

This JPM is complete when the CRO has determined that the stroke times for l-CC-3828 CV are outside of the allowable PMOT deviation, are repeatable, and must be evaluated by the 1ST Engineer prior to declaring the CV operable. No further actions are required.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant

2. EN-4-108, ASME In-service Testing of Power Operated Valves and Manual Valves, Attachment (7), EvaluationlDocumentation of Stroke-Time Test Results During PMOT.

General

References:

I. STP-O-65G-l, Component Cooling Valve Quarterly Operability Test

2. EN-4-108, ASME In-service Testing of Power Operated Valves and Manual Valves Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

a. None

ELEMENT STANDARD

(* = CRITICAL STEP)

. Time Start: - - -

CUE: Provide the candidate EN-4-108 Attachment (7) and STP-O-65G-l

. 0 Locates EN-4-1 08 Attachment (7) I S a m e as element.

Determines that maintenance performed could affect the stroke time and that Section 1 and Section 2 o Reviews PMOT Test Requirements must be completed and Section 3 may need to be completed based on PMOT stroke results.

i CUE: Local observations were completed during PMT by both the Mechanics and IM, with satisfactory results.

This section may not be referenced if i 0 Reviews LocallRemote Observations to Assess Valve candidate determines observations Performance/Condition During Stroke-Time Baseline were performed by Mechanical and Tests 1M during PMT. If section is referenced, same as element.

Section 1.0 Determine Allowable PMOT Deviation Uses STP 0-650-1 Section 6.3 to determine RV OPEN=23.8 secs, and calculates:

PMOT Deviation OPEN= +/-2.3 secs OR +/-2.4 secs (depending on ~ow value was truncated) i Uses STP 0-650-1 to determine RV CLOSED=N/A and calculates: .

PMOT Deviation CLOSED=N/A Uses STP 0-650-1 Section 6.3 to determine LVFST OPEN==35.7 secs and completes OPEN Acceptance Criteria table using a combination of STP 0-650-1 values and calculations to determine:

LVFSTmax = 35.7

PMOTmax = 26.1 OR 26.2 secs

ELEMENT STANDARD

(* = CRITICAL STEP)

Uses STP 0-65G-l Section 6.3 to detennine RV LVFST CLOSED=N/A, and calculates completes CLOSED Acceptance Criteria table using a combination of STP 0-65G-I values and calculations to detennine:

o CLOSED Stroke PMOT Deviation Table

LVFSTmax = N/A

PMOTmax = N/A

RV =N/A

PMOTmin=N/A

LVFSTmin=N/A CUE: When candidate requests I-CC-3828-CV stroke times or is referring to STP 0-65G-I to perform the valve strokes, either hand candidate a copy of Attachment (I) OR provide the following information: Valve opened in 26.4 secs, closed in 26.3 secs, and all local observations and indications were satisfactory.

Section 2.0 Validate Existing Reference Value

~---------------------------------.----~------------------------~

o Record PMOT Stroke Time (both directions

Records OPEN stroke as 26.4 sees required) and CLOSED stroke as 26.3 secs d';cf;>idC~a~h *. PM()T PMOTdeviattori?

tjilie fall withinthe ~lowable Ale.!.

(;t.<. TI (.

~~~~~~--~----~--~~~~~~~=-~~,

0 If the PMOT stroke times(s) fall within the PMOT Detennines stroke time did not fall within the PMOT deviation.

'I Deviation, then: . Detennines step is NIA and that

. I Section 3.0 must now be perfonned

~--------------------------------------

Section 3.0 Baseline Stroke-Time Tests o Perfonn at least three baseline stroke tests in each direction (in addition to the PMOT strokes),

regardless of the valves safety function(s) ....

Determines that at least 3 =-l strokes in each direction are required i JPM continued on next page

ELEMENT STANDARD

(* = CRITICAL STEP)

CUE: When candidate requests l-CC-3828-CV stroke times or is referring to STP 0-65G-l to perform the additional valve strokes, either hand candidate a copy of Attachment (2) OR provide the following information:

First Baseline Stroke-Valve opened in 26.5 secs, and valve closed in 26.2 secs, All local observations and indications were satisfactory.

Second Baseline Stroke-Valve opened in 26.3 sees, and valve closed in 26.3: sees. All local observations and indications were satisfactory,

Third Baseline Stroke-Valve opened in 26.3 sees, and valve closed in 26.3 sees. All local observations and indications were satisfactory.

I Records:

o Baseline Stroke # 1 Open = 26.5, Closed = 26.2 I

Records:

o Baseline Stroke #2 Open 26.3, Closed = 26..3 I Records:

o Baseline Stroke #3 Open = 26.3, Closed 263 CUE: Only if an additional stroke was performed, when candidate requests l-CC-3828-CV stroke times or is referring to STP 0-65G-l to perform the additional valve strokes,

. provide the following information: Additional Baseline Stroke-Valve opened in 26.4 secs, I and valve closed in 26.3 sees. All local observations and indications were satisCactory.

If perfonned, records:

o Additional Strokes

. Open 26.4, Closed = 26.2 Regardless of number of strokes, o Baseline Stroke Time Average records:

Open 26.4, Closed 26.3 Detennines that both OPEN and

CLOSED strokes are repe:atable and

circles Y for both OPEN ~md CLOSED References Section 2.0 or STP 0 65G-l Section 6.3 and detennines the litnits~tabIished)llYc that only the LVFST in the OPEN direction applies and that the valve No <<

strokes were within the LVFL"'--________~ cril1' v u s. ircles Y for OPEN ~

~~~~~~~~____~________~~fu~rC~L~O~S~E~D~~~~~==~Sp~~o I 0 ObservationslAssessment (include any new

May note that conditions Condition Reports) : were sat

ELEMENT STANDARD

(* = CRITICAL STEP)

CUE: If candidate does not indicate that valve is still inoperable, ask "Can l-CC-3828-CV i now be declared operable?"

JSfu,~~g4feermust review Same as element 7)l'esultSbi?foredeciaring CVoper,aple.

Tenninating Cue: This JPM is complete when it is detennined that the 1ST Engineer must evaluate the PMOT results in order to declare l-CC-3828-CV operable. No further actions are required. The evaluator is expected to end the JPM.

Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: RO-ADMIN-3 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _~_ _ _ _ __

Time to Complete:

Follow up Question: _________________________

Applicant Response: _ _ _ _ _ _ _ _ _ _.. . . _______________

Result: SAT ____________ UNSAT ______________

Examiner's Signature and Date: _______________________

Appendix C Job Performance Measure Form ES-C-l ATTACHMENT 1 PMOT Stroke Times for 11 SDC HX CC DISCH valve l-CC-3828-CV PMOT Stroke Time All local observations and indications were satisfactory

Appendix C Job Performance Measure Form ES-C-I n T.

1.*1.

VV UIA;:)}I\;\;

ATTACHMENT 2 Baseline Stroke Times for 11 SDC HX CC DISCH valve, l-CC-3828-CV Open = 26.5 seconds Baseline Stroke Time #1 Closed = 26.2 seconds Open 26.3 seconds Baseline Stroke Time #2 Closed 26.3 seconds

---J Open 26.3 seconds Baseline Stroke Time#3 Closed = 26.3 seconds Local observations and indications were satisfactory for all 3 Baseline Stroke tests

Appendix C Job Performance Measure Form ES-C-l ATTACHMENT 3 Additional Stroke Times for 11 SDC HX CC DISCH valve l-CC-3828-CV (if performed)

Open 26.4 seconds Additional Stroke Time Closed = 26.2 seconds !

All local observations and indications were satisfactory I

EN-4-10B ASME Inservice Testing of Power-Operated Valves & Manual Valves Revision 00300 Page 83 of 86 Attachment 7, Evaluation/Documentation of Stroke-Time Test Results During PMOT (Page 1 of 4)

PMOT Test Requirements When maintenance is performed on power-operated valves that could affect the stroke-time, must be completed as follows:

Complete Section 1, Determine Allowable PrvoT Deviation.

Complete Section 2, Validate Existing Reference Value.

o If the stroke-time is within the deviation determined in Section 1, no abnormal valve operation was observed, and the maintenance was NOT intended to change the valve stroke time (e.g, replacing solenoid val..e with one having a different venting capacity),

no further testing or evaluation is required and the valve may be declared operable.

NOTE Performance of Section 3 requires that the 1ST Engineer evaluate the stroke time tests declaring the valve operable.

Complete Section 3, Baseline Stroke-Time Tests for the following conditions:

o Section 2 stroke time was outside of the allowable dENiation determined in Section 1.

o The maintenance was intended to change the valve stroke time (Le. modification)

Local/Remote Observations to Assess Valve Performance/Condition During Stroke-Time Baseline Tests Observe the performance/condition of the valve, actuator, and associated subcomponents/support systems locally (if accessible) and remotely during at least one of the PMT/Baseline strokes. Look for typical symptoms of improper operation or degradation. If none are noted, the possibility that the maintenance may have created any new issues, or that there was any previously unidentified degradation, is reduced. Ensure components that were disturbed by the maintenance are specifically assessed, but do not focus exclusively on only those components:

a. Verify the valve strokes smoothly with no binding or scoring on stem. Document any flow noises heard.

b. Verify the actuator operates smoothly with no air leaks or binding.

c. Verify limit switches function properly and appear to be properly set and secure.

d. Verify the air system solenoid val-.e, the pressure regulator, and other subcomponents appear to operate properly with no air leaks. Verify the air pressure regulator appears to be set and operating properly.

e. Verify the control system appears to be set up and working properly.

f. Verify the stroke times collected are repeatable, random (i.e. not all rapidly increasing or decreasing), and appear to be representative of valve performance.

EN-4-108 ASME lnservice Testing of Power-Operated Valves & Manual Valves Revision 00300 Page 84 of 86 Attachment 7, Evaluation/Documentation of Stroke-Time Test Results During PMOT (Page 2 of 4)

Valve: \~tt.. 38?8-C" STP: 0 - (c,S~ - , Maintenance Order(s): c.qoe,\ \42" 1.0 Determine Allowable PMOT Deviation Enter Reference Value(s) from associated STP for valve being tested in spaces below.

Calculate PMOT Deviation as follows:

For Reference Values (RV) ~ 10 seconds: PMOT Deviation = 1 second For Reference Values (RV) > 10 seconds: PMOT Deviation =0.1 X RV = second PMOT Deviation OPEN = 0.1 X 23~ = +/- 2.3 seconds (N/A if no OPEN Reference Value) RV PMOT Deviation CLOSED = 0.1 X ~/A = +/- jllA seconds (N/A if no CLOSED Reference Value) RV Enter PMOT Max and PMOT Min Deviations in spaces below.

Enter LVFST(s) from associated STP for valve being tested in spaces below.

OPEN Stroke (seconds)

(N/A if OPEN Reference Value not assi ned

=l .

CLOSED Stroke (seconds)~

(N/A if CLOSED Reference Value not I assig_nedt LVFST = >35.1 LVFST = _~lA PMOT Max = RV + PMOT Dev. 2(" \ PMOT = RV + PMOT Dev. >>IA RV = '23.8 RV = t4IA PMOT Min = RV - PMOT Dev. -..!\, 5 PMOT Min = RV - PMOT Dev. N/A LVFST Min = ~'A LVFST = NfA.

(N/A if not assigned) (N/A if not assigned) 2.0 Validate Existing Reference Value Record PMOT Stroke Time (both directions required)

OPEN stroke CLOSED stroke Did each PMOT stroke time fall within the allowable PrvDT deviation?

OPEN stroke: Y N/A (Circle one)

CLOSED stroke: Y N @ (Circle one)

If the PMOT stroke time(s) fall within the PMOT Deviation, then

The Reference Value has been reconfirmed.

If no other immediate operabilly concerns were identified, then the PMOT is satisfactory and the valve may be returned to an Operable status.

Performed By: ~ Date: ~

Approved By: _..--!.._ _ _ _ _ __ Date: _ _ _ __

EN-4-108 AS ME Inservice Testing of Power-Operated Valves & Manual Valves Revision 00300 Page 85 of 86 Attachment 7, Evaluation/Documentation of Stroke-Time Test Results During PMOT (Page 3 of 4) 3.0 Baseline Stroke-Time Tests I NOTE

Performance of this Section requires that the 1ST Engineer evaluate the stroke time tests PRIOR to

declaring the valve operable. .._ _ _ _ _ _ _ _ _ _ __

PERFORM at least three baseline stroke tests in each direction (in addition to the PMOT strokes), regardless of the valve's safety function(s). Allow the valve/actuator to reach equilibrium conditions between each stroke/direction and RECORD the times below.

Open Strokes (sec) Closed Strokes (sec)

Baseline Stroke #1 (required) 2<",5 2.~. 2 Baseline Stroke #2 (required) 2lD.3 21,. ;

Baseline Stroke #3 (required) 2G, c 3 2(,

3 Additional Strokes (optional)

Baseline Stroke Time Average (sec)

Repeatability A minimum of three stroke times in both directions is required. The stroke times should be reasonably repeatable and deviations should appear to be random. If they do not, then additional stroke-time data should be collected and documented. A good rule of thumb to assess stroke time repeatability for most valves is that each stroke time should be within approximately :t10% or :t 1 second, whichever is greater, of the average of the stroke times.

Are the stroke times in each direction adequately repeatable?

OPEN stroke: & N (Circle one)

CLOSED stroke: (1) N (Circle one)

Are all stroke times within the limits established by the LVFST value(s)?

OPEN stroke: <2:> N N/A (Circle one)

CLOSED stroke: Y N @ (Circle one)

Observations/Assessment (include any new Condlion Reports):

VALVfE S1l?OKED SMo01Hl'i. AlL lOCAL o@fSW"",otJS Slrr Performed By: ____ ~ _ _ _ __ Date: ~

Approved By: _ _ _ _ _ _ _ __ Date: _ _ _ __

Notification and Disposition

Notify the 1ST Program implementer/Designee that a Post-Performance Evaluation is required prior to restoring the valve to service.

Attach the completed form to the STP used for PMOT.

Performed By: _ _ _ _ _ _ _ __ Date: _ _ _ __

Reviewed By (CRS): Date: _ _ _ __

EN-4-108 ASME Inservice Testing of Power-Operated Valves & Manual Valves Revision 00300 Page 86 of 86 Attachment 7, EvaluationlDocumentation of Stroke-Time Test Results During PMOT (Page 4 of 4) 4.0 1ST Program Requirements:

The 1ST Program Implementer/Designee is required to perform a Post-Performance Evaluation of this attachment. The evaluation will bedone either in support of an impending reference value re-baseline prior to declaring the power-operated valve operable oras a subsequent task following reconfirmation of an eXisting reference value.

5.0 Post-Performance Evaluation:

Date:

1ST Engineer

Appendix C Job Performance Measure Form ES-C-l APPLICANT'S CUE SHEET Initial Conditions:

1) Unit-l is at 1000/0 power

2) Maintenance has just been completed with repacking 11 SDC HX CC DISCH valve l-CC-3828-CV. The appropriate TS LCOs are in effect.

3) The valve has been stroked and the limit switches adjusted for PMT with all local observations by the Mechanics and 1M satisfactory.

4) The CV has been turned over to Operations for PMOT.

5) You are performing the duties of the CRO.

Initiating Cue:

The CRS has directed you to complete PMOT testing requirements for l-CC-*3828 CV under Work Order C90811426. The CRS has also provided EN-4-108 Attachment (7) and STP-O-65G-l, Component Cooling Valve Quarterly Operability Test.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: RO-ADMIN-4

Facility: Calvert Cliffs 1 & 2 Job Perfonnance Measure No.: RO-ADMIN-4 Task

Title:

Recall Emergency Response Organization Task Number: 204.138 KJ A

Reference:

2.4.39 (3.9, 3.8)

Method of testing:

Simulated Perfonnance: D Actual Perfonnance: [gj Classroom: [gj Simulator: [gj Plant: D READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Unit-2 tripped from 100% power

2. EOP-S, Loss of Coolant Accident, has been implemented

3. The SM has declared an Alert Condition on Unit 2.

4. You are performing the duties of an extra licensed operator.

S. This JPM is time critical Initiating Cue:

You are directed to recall the Emergency Response Organization and notify offsite agencies according to ERPIP 3.0, Attachment 11, Steps B.l and c.l.

Task Standard:

Recall of the Emergency Response Organization & notification of off-site agencies.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant

2. Completed ERPIP 3.0 Attachment 3

3. ERPIP 3.0, Attachment 11.

General

References:

1. ERPIP 3.0, Immediate Actions

2. ERPIP 105, Control Room Communicator, Attachment 1 Time critical task:

No Validation Time:

15 minutes Simulator Setup:

1. Simulator not required, however, access to a PC is required

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start: - - -

ACTIVATE the Emergency Response Organization Notification System (ERONS)

CUE: Provide Candidate with completed ATTACHMENT 3, Initial Notification Form and copy of ATTACHMENT 11, Step B.t.

elemen~

o Locates ERPIP 3.0 Attachment 11, Alert Actions, Step B.t OR Same as Locates ERPIP 105 Attachment 1, Personnel Notification, Step 1 o a. HAVE the Initial Notification Form immediately available for reference.

Same as element o 1. IF at any time the Internet cannot be accessed, THEN IMMEDIATELY GO TO step B.2 of this Determines step is NIA attachment.

Same as element CAUTION Username, CCNPP Trainer, and password, Train6 A now, MUST be entered as specified.

Failure to do so may result in activation of the Emergency Response Organization NOTE The user name and password are case sensitive Same as element etoNotiFbld" screen~\THEN Same as element ation?~. ... .

~

Same as element Notification/Select Notification SELECT "ERO Notification Same as element CK oil "Next".

ELEMENT STANDARD

(* = CRITICAL STEP)

h. ON the Create NotificationINotification Details screen, THEN:

.CTtil~ 'fEvent"-miiicated on the Initial Determines Drill is correct event nf~(~ectiql1B) .

o 2. SELECT the "Unit" indicated on the Initial Determines Calvert Cliffs is Notification Form (Section B) applicable Unit Q *3. SELEer"Retison forNotification~ indicated Determines Alert is applicable on.tP-eh1itifiL~No.dfication Form (Sectiqll13) . Reason for Notification Determines Staff Normal

[J *4. SELEC'FERPpersonnel "Action" indiqated Emergency Facilities for

-oll,i~e hrltialNotification Form.{Secfion B) Emergency is correct Action o 5. VERIFY that the message in the "Message Same as element Text" box is correct.

o 6. UTILIZE the "Back" button as required to correct errors NOTE The selection under "Polling Options" and "Security Options" are pre-populated and should not be altered .

. Name:

i -L:-:','

leave*bla11k:

'::C", t"/ -, '7, Same as element

\(;allerID: 41 O~495-4444 Eft?ail:~~CNPP_EP@constellation.com

(;li~k onthe"~'Next" button

~AUTION Failure to select "Simulator Test" may result in activation of the Emergency Response Organization CJ )~~;~.O~-;dl~. otfticationINotifi;~ationListS"

'Lsatee~~~. . .....L.Jhe box next to the>

.*~~'S1mU1atoltesf' ~DtLICK on the '4Nexe'~'

..* ttofi~.; .. . .

Same as eleme~

'QNthe "~r~ateNotificatioo!Notifiqfltion Verify

)~Se~a"Bareen,i!flJENVERIFY information is . Same as element aceurateAND CLICK on the "SEND" button.

j . '

ELEMENT STANDARD

(* = CRITICAL STEP) o 1. RECORD the time sent from the Track Delivery Same as element Summary page: (Time) o 1. CHECK Status is "Delivery in Progress" from Same as element the Track Delivery Summary page.

o m. IF the Status is not "Delivery in Progress",

THEN GO TO Step B.2.

o n. INFORM Security (4695) that ERONS has been Same as element activated.

NOTIFY Offsite Agency (Within 15 minutes) o Locates ERPIP 3.0 Attachment 11, Alert Actions, Step C.l OR Same as element Locates ERPIP 105 Attachment 2, Offsite Agency Notifications Same as element. Mark time when

~iVSIN~~the deq!cated phone, DEPQSS the first agency is contacted (must be

'.- . 'CON:pBRENCB" button to' within 15 minutes of when applicant usly catIilie 5 Agencies. was handed Attachment (3) and Attachment (II) o AS each agency answers, THEN SAY "This is Calvert Cliffs. Standby for an emergency Same as element message. Please report your agency and your name."

o RECORD time, name, and method of contact in Same as element Contact Table below.

Terminating Cue: This JPM is complete when the Candidate has informed Security that ERONS has been activated to recall the Emergency Response Organization and has established contact with the first offsite agency.

Verification of Completion Job Performance Measure Number: RO-ADMIN-4 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _~. . ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __

Examiner's Signature and Date: ______________________

IMMEDIATE ACTIONS ERPIP*3.0 Revision 04600 Page 15 of 143 Page 1 of 2 ATIACHMENT 3, INITIAL NOTIFICATION FORM USE THIS FORM FOR INITIAL NOTIFICATION AND EMERGENCY CLASS UPGRADING AND DOWNGRADING ONLY

~~~~~~~~~~~~

1. This rgJ is a drill 0 is an actual event.

2. Facility: Calvert Cliffs Nuclear Power Plant Unit 0 1 f8J 2 0 Common/Both/ISFSI

3. Emergency Class 0 Unusual Event g] Alert 0 Site Area Emergency 0 General Emergency o None (downgraded)

4. EAL Number: ~ ~ ~ or 0 None (downgraded)

5. Radioactivity is/was released to the environment due to the event KI Yes 0 No

a. Radioactivity released is/was monitored: 0 N/A KI Yes 0 No

b. Type of Release: 0 N/A XI Airborne 0 Liquid

6. Protective Action Recommendation (Must choose one from b through f for General Emergency)

I----L---.--c----------------------------------------------- - - - - - - - -

a. ~ None (for downgrade, unusual event, alert or site area emergency only)

b. 0 Shelter entire 10 mile EPZ

c. 0 Evacuate PAZ 1 unless conditions make evacuation dangerous, notify the public in PAZ 1 to take KI, shelter remainder of the 10 mile EPZ.

d. 0 Evacuate PAZ 1 & 2 unless conditions make evacuation dangerous, notify the public in PAZ 1 & 2 to take KI, shelter remainder of the 10 mile EPZ.

e. 0 Evacuate PAZ 1 & 3 unless conditions make evacuation dangerous, notify the public in PAZ 1 & 3 to take KI, shelter remainder of the 10 mile EPZ.

f. 0 Evacuate PAZ 1, 2 & 3 unless conditions make evacuation dangerous, notify the public in PAZ 1, 2 & 3 to take KI, shelter remainder of the 10 mile EPZ.

Date: lb~'('S. l)A,E.

ACTION mDrill 0 Unusual Event o Actual Event ~ Alert 18l Staff Normal Emergency Response Facilities UNIT 0 Site Area Emergency o Staff Alternate Emergency Facilities 181 Calvert Cliffs 0 General Emergency o Staff Normal Emergency Facilities as a PrE~caution o Event Termination o Staff EOF and JIC Only o Staff TSC and OSC Only ED Name (print) ~ \ 't),fZEC,.,oR. Signature.----!I....-L....J~~~~L----_,---

IMMEDIATE ACTIONS ERPIP-3.0 Revision 04600 Page 37 of ll43 ATTACHMENT 11, ALERT ACTIONS (CONTINUED)

B.l. ACTIVATE the Emergency Response Organization Notification System (ERONS).

a. HAVE the Initial Notification Form immediately available for reference.

b. ACCESS a computer with Internet capability.

1. IF at any time the Internet cannot be accessed, THEN IMMEDIATELY GO TO step B.2 of this attachment.

c. CLICK the Internet Explorer icon AND TYPE the following into the address bar: http://www.envoyprofiles.com/ce/.

NOTE The user name and password are case sensitive.

d. WHEN the NotiFind log in page appears, THEN ENTER:

=

Username: CCNPP Trainer Password: Train6"now Hit "Login"

e. ON the "Welcome to NotiFind" screen, THEN CLICK on "Activation".

f. ON the "NotiFind Main Menu" screen, THEN CLICK on "Activate System".

g. ON the "Create Notification/Select Notification Type" screen, THEN SELECT "ERO Notification System" AND CLICK on "Next".

h. ON the Create NotificationINotification Details screen, THEN:

1. SELECT the "Event" indicated on the Initial Notification Form (Section B)

2. SELECT the "Unit" indicated on the Initial Notification Form (Section B)

3. SELECT "Reason for Notification" indicated on the Initial Notification Form (Section B)

4. SELECT ERO personnel "Action" indicated on the Initial Notification Form (Section B)

5. VERIFY that the message in the "Message Text" box is correct.

J

6. UTILIZE the "Back" button as required to correct errors NOTE The selection under "Polling Options" and "Security Options" are pre-populate:d and should not be altered.

IMMEDIATE ACTIONS ERPIP-3.0 Revision 04600 Page 38 of 143 Page 3 of5 AITACHMENT 11, ALERT ACTIONS (CONTINUED)

i. UNDER "Sender Information", THEN ENTER the following:

Name: leave blank Caller ID: 410-495-4444 Email: CCNPP_EP@constellation.com Click on the "Next" button

j. ON the "Create NotificationINotification Lists" screen, THEN CHECK the box next to the "Simulator Test" AND CLICK on the "Next" button.

k. ON the "Create Notification/Notification Verify and Send" Screen, THEN VERIFY information is accurate AND CLICK on the "SEND" button.

1. RECORD the time sent from the Track Delivery Summary page::

_ _ _ _ _ _ _ CTime)

1. CHECK Status is "Delivery in Progress" from the Track Delivery Summary page.

m. IF the Status is not "Delivery in Progress", THEN GO TO Step B.2.

n. INFORM Security (4695) that ERONS has been activated.

NOTE The following actions are steps which activate ERONS if the Internet is non-functional.

This method does NOT have all the selection features as the Internet-based ERONS.

B.2. IF the internet is non-functional, THEN ACTIVATE the Backup Process for ERONS:

a. USING the initial notification form, THEN NOTIFY the ERO AND DETERMINE which of the following actions should be performed:

1. NOTIFY the ERO of an emergency and direct them to staff the normal emergency facilities.

2. NOTIFY the ERO of an emergency and direct them to staff the alternate emergency facilities.

b. DIAL the following number on ANY working telephone: 8-1-800-735-0318

1. WHEN prompted, THEN PRESS "2" for Scenario Activation Line.

2. WHEN prompted, THEN ENTER the Account Number for Calvert- 4955201#.

3. WHEN prompted, THEN ENTER the PIN number as follows:

00000#.

IMMEDIATE ACTIONS ERPIP-3.0 Revision 04600 Page 39 of 143 Page 4 of5 ATTACHMENT 11, ALERT ACTIONS (COl'ITINUED)

4. WHEN prompted, THEN ENTER the access code as follows:

(a) To direct the ERO to staff normal emergency facilities, enter access code: 5555#

(b) To direct the ERO to staff alternate emergency facilities, enter access code: 6666#

(c) To notify ERO of an emergency, but no response is required, enter access code: 7777#

c. WHEN ERONS reads the "Subject" line of the message, THEN PRESS "I" to accept the message.

d. WHEN prompted, THEN PRESS"1" to send the message

e. RECORD the time that you completed step B.2.d. above _ _ _ _ (TIME).

f. INFORM Security (4695) that ERONS has been activated.

C.l. NOTIFY Offsite Agency (Within 15 minutes).

a. USING the dedicated phone, DEPRESS the "OFFSITE CONFERENCE" button to simultaneously call the 5 Agencies.

1. IF not working, THEN USE Btu OFFSITE CONFERENCE button.

(REFER to ERPIP 105 if further issues occur with agency contact.)

r-------

NOTE:

During off hours MDE is not staffed. No answer from them is satisfactory.

b. AS each agency answers, THEN SAY "This is Calvert Cliffs. Standby for an emergency message. Please report your agency and your name."

c. RECORD time, name, and method of contact in Contact Table below.

d. AFTER all agencies are on line, THEN SAY "Please get an Initial Notification Form."

e. WHEN all agencies have the form OR 1 minute has elapsed, THEN SAY "I will give out the information on the form completely once". Page 4 of 5

f. GIVE OUT the form information.

g. ASK each agency if the full message was received. (REFER to ERPIP 105 if problems occur transmitting the form information.)

C.2. VERIFY the Control Room pager activation via ERONS. IF the pager in the Control Room does not receive the intended ERO notification within 5 minutes ofthe message being sent then repeat steps B.l or B.2 as appropriate

IMMEDIATE ACTIONS ERPIP-3.0 Revision 04600 Page 40 of 143 Page 5 of5 ATTACHMENT 11, ALERT ACTIONS (CONTINUED)

C.3 NOTIFY NRC (Within 1 Hour).

a. USING the NRC Emergency Notification System (ENS) phone, DIAL the phone number listed on the label attached to the phone.

(1) IF there are any issues using the NRC Emergency Notification System (ENS) phone, THEN USE another phone.

b. IDENTIFY yourself AND ASK for the name of who you are talking with.

c. RECORD time, name and method of contact in Contact Table below.

d. PROVIDE all form information AND VERIFY they received it.

e. STAY on line with the NRC until released AND to respond to any inquiries.

CA. TRANSMIT completed Attachment 3, Initial Notification Form.

a. SIGN Table below.

b. FAX Attachment 3 form to the Plant Parameters Communicators for the TSC.

c. FAX Attachment 3 form to EOF and lIC when manned.

d. KEEP completed forms with communication records.

Contact Table Location *Time Received by: Method of Contact i

! Calvert DP Rad OL StMary's DP Rad OL Dorchester DP Rad OL MEMA DP Rad OL MDE DP Rad OL NRC DP OL DP dedicated phone Rad = Radio OL = outside line

Record Time that all calls to the above agencies were completed.

Printed Name and Signature: _ _ _ __

APPLICANT'S CUE SHEET Initial Conditions:

1. Unit -2 tripped from 100% power

2. EOP-5, Loss of Coolant Accident, has been implemented

3. The SM has declared an Alert Condition on Unit 2.

4. You are performing the duties of an extra licensed operator.

5. This JPM is time critical Initiating Cue:

You are directed to recall the Emergency Response Organization and notify offsite agencies according to ERPIP 3.0, Attachment 11, Steps B.1 and C.l.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-1

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-l Task

Title:

Ability to implement plant procedures for a Condenser Tube Leak Task Number: 202.008 KJA

Reference:

2.1.34 (2.7, 3.5)

Method of testing:

Simulated Performance: D Actual Performance: cgj Classroom: cgj Simulator: D , Plant: D READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

I) Unit-l is at 88% reactor power.

2) At 0015, 12A Waterbox was secured lAW AOP-IO, Abnormal Secondary Chemistry Conditions, due to a condenser tube leak.

a. Condensate Demineralizers are in service with full flow

b. Condenser High Level Dump is manually isolated

c. S/G Blowdown flow has been maximized

3) At 0045, exceeded Action Level 2 values for sodium in the Steam Generators, 52 ppb in 11 S/G & 55 ppb in 12 S/G.

4) At 1800, Chemistry notifies the Control Room we are still exceeding Action Level 2 values that sodium levels are lowering slowly. Chemistry anticipates exiting Action Level 2 at 0330

5) You are performing the duties of an extra SRO.

Initiating Cue:

The Shift Manager directs you to perform AOP-I0,Section VI. (Please verbalize progress thru the AOP with the evaluator.)

Task Standard:

This JPM is complete when it is determined a reactor trip is required. No further actions are required. The evaluator is expected to end the JPM.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

1. AOP-IO, Abnormal Secondary Chemistry Conditions.

2. CP-217, Specifications and Surveillance - Secondary Chemistry Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

a. None

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start:

CUE: The Shift Manager directs you to evaluate continued operation per AOP-IO,Section VI 0 Locates AOP-I 0,Section VI Same as element.

Reviews step and determines step is 0 A. Determine if a reactor trip is required. NIA at this tim;!

CUE: The CRS is directing the Crew in the performance of AOP-IO,Section VI.B Determines required actions are in 0 B. Determine required plant conditions. progress NOTE:

If SG chemistry levels are reduced below the Action Level 3 value, before or during the power reduction, power level is still required to be reduced below 5%.

C. Actions with power greater than or equal to 30%

o 1. IF Plant Chemistry determines SG Chemistry is in Action Level 3, as a result of a Condenser tube leak, Determines step is N/A at this time THEN commence an orderly plant shutdown to be less than 5% power as quickly as safe operation permits PER OP-3 and OP-4.

2. IF Plant Chemistry determines that SG Chemistry is in Action Level 2, as a result of a Condenser tube leak, THEN perform the following actions:

h':O a.Withitl 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initiating ActionrLevel Determines power must be reduced 2, reduce, power to less than30%PER rOP:;'3, to less than 30% by 0045 NORM'ALPOWEROPERATION.

0 b. WHEN the following conditions exist:

The source of the impurity ingress is controlled Determines step is NIA at this time

SG Chemistry is less than the value for Action Level 2 THEN the power reduction may be terminated and power stabilized.

ELEMENT STANDARD

(* = CRITICAL STEP) o c. IF the SO chemistry level has NOT been reduced to less than Action Level 1 within 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months of entering Action Level 2 THEN consider the SO Chemistry level to be in Determines step is NIA at this time Action Level 3, AND commence an orderly plant shutdown to be less than 5% power as quickly as safe operation permits PER OP-3 and OP-4.

CUE: 12A Waterbox is secured for leak location/repair Determines actions already in o 3. Attempt to locate and repair the tube leak. progress CUE: Chemistry reports SG sodium has exceeded Action Level 3 values Note to evaluator: Candidate will have to refer back to Step VI.C.l o ....1 qnemistry deterinifies$9Cpemistry

-" !~

1 , ~A as

'(wel~~, a result ~fa:Con~enser tube l e a k , . . . . . . . . . . . . . " .. Determines a plant shutdown to <5%

7 THEN commence an orderly planfshufdownto:be power is required.

less than; ...' :power0f1S quickly as safe operation~"Y permits .... . Or(3 and 0P-4. '. ,

CUE: Chemistry reports Condensate and Feedwater Sodium levels are 210 ppb and rising rapidly. The source appears to be 13B Waterbox.

o VLA. Determine if a reactor trip is required .

. IFFeed$~ter $odiumi§ greater1llan. 200ppb Condens.ateSodium is greaterj;han 2QO pPh,

.*~.JL.I..£/i~*" perfoni}the following: Determines reactor trip is required Terminating Cue: This lPM is complete when it is determined a reactor trip is required~

further actions are required. The evaluator is expected to end the lPM. _

Appendix C Job Performance Measure Form ES-C-I Worksheet Verification of Completion Job Performance Measure Number: SRO-ADMIN-l Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Appendix C Job Perfonnance Measure Fonn ES-C-I Worksheet APPLICANT'S CUE SHEET Initial Conditions:

1) Unit-l is at 88% reactor power.

2) At 0015, 12A Waterbox was secured lAW AOP-I0, Abnormal Secondary Chemistry Conditions, due to a condenser tube leak.

a. Condensate Demineralizers are in service with full flow

b. Condenser High Level Dump is manually isolated

c. S/G Blowdown flow has been maximized

3) At 0045, exceeded Action Level 2 values for sodium in the Steam Generators, 52 ppb in 11 S/G and 55 ppb in 12 S/G.

4) At 1800, Chemistry notifies the Control Room we are still exceeding Action Level 2 values and sodium levels are lowering slowly. Chemistry anticipates exiting Action Level 2 at 0330

5) You are performing the duties of an extra SRO.

Initiating Cue:

The Shift Manager directs you to perform AOP-I0,Section VI. (Please verbalize progress thru the AOP with the evaluator.)

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-2

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-2 Task

Title:

Verify an Estimated Critical Condition Calculation Task Number: 202.247 KIA

Reference:

2.1.25 (3.9, 4.2)

Method of testing:

Simulated Performance: D Actual Performance: lSI Classroom: lSI Simulator: D Plant: D READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Unit-2 is in MODE 3 at normal operating temperature and pressure. Current time is 0800.

2. The reactor tripped while performing RPS testing 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months ago. Preparations are underway for a quick trip recovery startup to begin within the next 30 minutes with criticality anticipated in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at lOam.

3. The following conditions exist:

a. Unit-2 tripped from 100% power 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months ago.

b. Power history: Prior to the trip, Unit-2 operated at 100% for the previous 68 days.

c. Burnup from the plant computer point "CEBURNUP" is 14,400 MWDIMTU.

d. Nuclear Fuels has provided a Xenon Worth Calculation and a B-I0 Correction factor of 0.971.

4. An ECC has been prepared by an extra licensed operator.

Initiating Cue:

The Shift Manager has directed you to Verify the Estimated Critical Concentration calculation per NEOP-302, Estimated Critical Condition, Step 6.1.23. Identify and correct any errors. Do not verify the +/-lhr or the +/-2hr values. Do not verify the ECC tolerance band values.

Task Standard:

Verify an Estimated Critical Condition Calculation.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

NEOP302, Estimated Critical Condition NEOP-23, Technical Data Book (Unit-2)

Time critical task:

No Validation Time:

20 minutes Simulator Setup:

_ _ 1. None required

ELEMENT STANDARD

(* = CRITICAL STEP)

I Time Start:

.0 Locates NEOP-302, Step 6.1.23 Same as element 10 6.1.23. The Shift SRO shall perform the following:

0 6.1.23.1. Verify the previous critical condition is I

correct Same as element I

Cl 6.1.23.2. Verify that criticality is expected within the +/-2 hour window bounded by the time points- Same as element 2hand+/-2h.

I 0 6.1.23.3 Independently verify the ECC is calculated correctly Note to Evaluator: Candidate will complete independent verification of the calculation using NEOP-302, Section 6.1

! Cl 6.1.1 Complete the previous critical conditions section of Attachment 2, Four Hour Window With Same Boron:

Cl 6.1.1. Verify correct Unit and cycle numbers Same as element 0 6.1.2. Verify correct date and time the unit shut Same as element down CUE: Burnup from the plant computer point "CEBURNUP" is 14,400 MWDIMTU Determines correct Burnup is 14,400 Cl 6.1.3. Verify correct burnup, for the cycle, has MWDIMTU. Verifies correctly been recorded entered on Attachment 2 Cl 6.1.2 Complete the "Current Conditions" section of Attachment 2:

CUE: Candidate will reference Cl 6.1.2.1. Verify correct value for Excess Determines correct value for Excess Reactivity has been determined and entered on Reactivity is 9.9375 %Ap. Verifies Attachment 2. correctly entered on Attachment 2.

Cl 6.1.2.2. Verify correct HZP Inverse Boron Worth Determines correct value for HZP (lBW) has been determined and entered on IBW is 116.2 ppml%Ap. Verifies Attachment 2. correctly entered on Attachment 2.

Cl 6.1.2.3. Verify correct B-1O Correction Factor Verifies B-I0 Correction Factor has has been determined and entered on Attachment been entered as .971 on Att 2 2.

0 6.1.3 Verify correct estimated date and time of Verifies correct estimated date and reactor criticality entered on Attachment 2 for the time of reactor criticality entered on time point "Oh" Attachment 2 for the time point "Oh"

ELEMENT STANDARD

(* = CRITICAL STEP)

Verifies correct elapsed time from o 6.1.4 Verify correct elapsed time from reactor reactor shutdown to the estimated shutdown to the estimated time of criticality, as "Hours After Shutdown", is entered on Attachment 2 time of criticality, as "Hours After Shutdown", is entered on Attachment for time point "Oh".

2 for time point "Oh".

o 6.1.5 Verify correct shutdown xenon worth, at the Determines correct xenon worth is estimated time of criticality, is entered on 1.120 %~p. Verifies com~ctly Attachment 2. entered on Attachment 2 Note to Evaluator: Steps 6.1.6 and 6.1.7 are not performed during verification Determines correct CEA heights are:

Group 3 @ 135 inches o 6.1.8 Verify correct CEA position for criticality is .* Group 4 @ 90" determined and entered on Attachment 2.

Group 5 @ 0" Verifies correctly entered on Attachment 2 Determines correct CEA worth is o 6.1.9 Verify correct CEA reactivity worth has been .6808 %~p. Verifies corrc~ctly determined and entered on Attachment 2.

entered on Attachment 2 Determines a math error exists in the calculation (HZP IBW multiplied by B-lO Correction Factor. HZP IBW should be divided by the B-I0 Correction Factor). Determines Correct value for Corrected HZP IBW 119.67 ppmJ%~p r-------~--------------------------------~--

Determine Boron Worth value of D 6.1.11 Verify correct Boron Worth has been 8.1367 %~p. Verifies correctly determined and entered on Attachment 2 entered on Attachment 2 o .Q,1,J2 '\l~Iy correctE~timated Critical Boron Determine Estimated Critical Boron Co . fionhas b'eerr.determinet:f11nd entered on LL""" ......Ucnt 1; . ' " ...... Concentration value of 974 ppm.

',~ -, , .' ~\

D 6.1.23. (continued) The Shift SRO shall perform the following:

CUE: Verification of the ECC Upper and Lower bounds are beyond the scope of this JPM D 6.1.23.4. Verify the ECC Upper and Lower bounds are calculated correctly and the established bounds are between 135 inches No actions are required withdrawn on Reg Group 5 and the Zero Power PDIL

ELEMENT STANDARD

(* = CRITICAL STEP) o 6.1.23.5. If an error is found, Then instruct the Returns ECC Calculation worksheet preparer to make the necessary corrections and repeat the review to the preparer for correction Terminating Cue: This JPM is complete when errors in the Estimated Critical Boron ::J Concentration calculation have been identified & corrected and the Estimated Critical Boron Concentration has been correctly determined. No further actions are required.

I Time Stop: _ __

Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SRO-ADMIN-2 Applicant:

NRC Examiner: -- -------------

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _~_ _ _ _ _ _ _ _~_ _ _ _ _ _ _ _ _ _._ _

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

XENON WORTH CALCULATOR Revision 3 Change 0 Unit 2 Cycle 18 Burnup = 14,400 MWD/MTU Trip from Equilibrium at 99.5% Power At 07/09/201000:00 Calculation performed 05/1312010 15:52 Hours After Trip (DatelTime) Xenon Worth o (07/09/201000:00) ----------- 2.531 %.1p 1 (07/09/201001:00) --*------ 2.904 %.1p 2 (07/09/201002:00) ----------- 3.172 %.1p 3 (07/09/201003:00) ------------ 3.372 %Ap 4 (07/09/201004:00) --------- 3.513 %6p 5 (07/09/201005:00) ----------- 3.604 %.1p 6 (07/09/2010 06:00) ----------- 3.654 %.1p 7 (07/09/201007:00) ------- 3.668 %.1p 8 (07/09/201008:00) ------ 3.652 %ap 9 (07/09/201009:00) ----------- 3.612 %ap 10 (07/09/201010:00) ----------- 3.552 %6p 11 (07/09/2010 11 :00) ------------ 3.476 %6p 12 (07/09/201012:00) ---------- 3.386 %Ap 13 (07/09/2010 13:00) --------- 3.286 %Ap 14 (07/09/2010 14:00) ------------ 3.179 %.6p 15 (07/09/2010 15:00) --------- 3.065 %Ap 16 (07/09/201016:00) ----------- 2.948 %.6p 17 (07/09/201017:00) ----------- 2.829 %Ap 18 (07/09/201018:00) ----------- 2.708 %Ap 19 (07/09/201019:00) ------------ 2.588 %Ap 20 (07/091201020:00) ---------- 2.468 %Ap

XENON WORTH CALCULATOR Revision 3 Change 0 Hours After Trip (DatelTime) Xenon Worth 21 (07/091201021:00) -------- 2.350 %Llp 22 (07/091201022:00) ------- 2.235 %Llp 23 (07/09/201023:00) -------- 2.122 %Llp 24 (07/10/201000:00) ------- 2.012 %Llp 25 (07/10/201001:00) -------- 1.905 %Llp 26 (07/10/2010 02:00) ---------- 1 .802 %l1p 27 (07/10/201003:00) ---------- 1.703 %l1p 28 (07/10/201004:00) ------- 1.608 %l1p 29 (07/10/201005:00) --------- 1.517 %l1p 30 (07/10/201006:00) ---------- 1.430 %Ap 31 (07/10/201007:00) ------- 1.346 %l1p 32 (07/10/201008:00) -------- 1.267 %Ap 33 (07/10/201009:00) --------- 1.192 %l1p 34 (07/10/2010 10:00) ---------- 1.120 %Ap 35 (07/10/201011 :00) ------------ 1.052 %Ap 36 (07/10/201012:00) ----------- 0.987 %Ap 37 (07/10/201013:00) ---------- 0.926 %Ap 38 (07/10/2010 14:00) ------------ 0.868 %Ap 39 {07/10/2010 15:00) ---------- 0.814 %l1p 40 (07/10/2010 16:00) ------------ 0.762 %Ap 41 (07/10/2010 17:00) ---------- 0.714 %Ap 42 (07/10/2010 18:00) --------- 0.668 %l1p 43 (07/10/2010 19:00) -------- 0.625 %l1p 44 (07/10/201020:00) ---------- 0.584 %6p 05/1312010 15:52 Page 2 of4

XENON WORTH CALCULATOR Revision 3 Change 0 Hours After Trip (DatefTime) Xenon Worth 45 (07/10/2010 21 :00) ---------- 0.546 %.1p 46 (07/10/201022:00) ---------- 0.510 %~p 47 (07/10/201023:00) --------- 0.477 %~p 48 (07/11/201000:00) ---------- 0.445 %~p 49 (07/111201001 :00) ----------- 0.416 %~p 50 (07/111201002:00) ----------- 0.388 %.1p 51 (07/11/201003:00) ---------- 0.362 %.1p 52 (07111/201004:00) ----------- 0.338 %.1p 53 (071111201005:00) ----------- 0.315 %.1p 54 (07/1112010 06:00) -------- 0.294 %Ap 55 (07/111201007:00) ---------- 0.274 %~p 56 (07/11/201008:00) --------- 0.255 %Ap 57 (07/1112010 09:00) -------- 0.238 %Ap 58 (07/11/201010:00) ---------- 0.221 %~p 59 (07/11/2010 11 :00) ---------- 0.206 %L\p 60 (07/11/2010 12:00) --------- 0.192 %Llp 61 (07/11/201013:00) -------- 0.179 %.6p 62 (07/11/201014:00) ------------ 0.166 %.6p 63 (07/11/201015:00) ------------ 0.155 %.6p 64 (07/11/201016:00) ----------- 0.144 %hp 65 (07/111201017:00) ------------ 0.134 %hp 66 (07/111201018:00) ---------- 0.125 %hp 67 {07/11/2010 19:00) ----------- 0.116 %hp 68 (07/11/2010 20:00) ----------- 0.108 %.1p 05/13/2010 15:52 Page 30f4

(", '

XENON WORTH CALCULATOR Revis ion 3 Change 0 Hours After Trip (DatefTime) Xenon Worth 69 (07/11/201021:00) ------- 0.100 %6p 70 (07/11/201022:00) ------- 0.093 %6p 71 (07/11/201023:00) ------- 0.087 %6p 72 (07/12/201000:00) --------- 0.081 %Llp 73 (07/12/201001:00) --------- 0.075 %Llp 74 (07/12/201002:00) ------------ 0.070 %Llp 75 (07/12/201003:00) ----------- 0.065 %Llp 76 (07/12/201004:00) ------------ 0.060 Llp 77 (07/12/201005:00) ----------- 0.056 %Llp 78 (07/1212010 06:00) ------.----- 0.052 %Llp 79 (07/12/201007:00) ----------- 0.048 %tlp 80 (07/121201008:00) ---------- 0.045 %Llp 81 (07/12/201009:00) ---------- 0.042 %tlp 82 (07/12/2010 10:00) --------- 0.039 %tlp 83 (07/12/2010 11 :00) ----------- 0.036 %Ap 84 (07/12/2010 12:00) ----------- 0.033 %tlp

~/~~----

Prepared by Date

~~--~~------~/~------

Reviewed by Date

Units 1 & 2 "

I Estimated Critical Condition NEOP-302 Revision 0700 Page 27 of 33 Attachment 2, ECC - Four Hour Window With Same Boron #_--

Iunit~

Previous Critical Conditions 2

Cycl.

18 nat.

812/10 1- T;m' 0000 Burnup, MWDIMTU 14,400 L~~

Current Conditions Excess Reactivity, %)A fA]

9.9375 HZP mw, (ppm/%)&

_ [B]

116.2 B-1 o Correction 0.971 Estimated Critical Conditions

,:~-~

Hour~~~non

--~ ~-~

Group I Grou; Group CEA Worth, Corrected Boron Critical Boron Time After ~

Worth, 3, 4, 5, HZpmW, Worth, Date Time Shutdown ' 0/0).1\ %).1\ Cone., ppm Point inches inches inches ppm/%)A %)&

[E] (for Oh) or [H] = F*G

[0] [F] = B/C [G] A-(O+E)

[E] = A-(O+G)

'--------~ r----- ~-

-2h 8/3/10 0800 32 1.267 135 104.25 14.25 .5410 112.83 8.1367 918

-lh 8/3/10 0900 33 1.192 135 97.5 7.5 .6160 112.83 8.1367 918

,-----~

Oh 8/3/10 1000 34 1.120 135 90 0 --~

.6808 112.83 8.1367 918

+lh 8/3/10 1100 35 1.052 135 78.75 0 .7560 112.83 --~

8.1367 918

~-~

+2h 8/3/10 1200 36 0.987 135 67.5 0 .8210 112.83 8.1367 ~---~

918 ECC Tolerance Band Lower CEA B~und (ECC Wort~ + 0.5 %).1\) Upper CE~Bound ECC Worth - 0.5 %)&)

Time Date Time Bounding Group 3, Group 4, Group 5, Bounding Group 3, Group 4, Group 5, Point Worth inches inches inches ----~

Worth inches inches inches

-2h rs/4/10

--~ --~

0800 1.0410 --~

30 120 0 .0410 135 135 117.75

-lh 8/4/10 0900 1.1160 24.75 114.75 0 .1160 135 135 104.25 Oh 8/4/10 1000 1.1808 19.5 109.5 0 .1808 135 135 91.5

+lh 8/4/10 1100 1.2560 15 105 0 .2560 135 135 68.25

+2h 8/4/10

~-~

1200 1.3210 99.75 9.75 0 .3210 135 126 -

36 Excess Reactivity Source: NEOP-23, Figure 2-II.A.7 IBW Source: NEOP-23, Figure 2-II.A.2 B-10 Source: Isotopic sample analysis CEA Worth Source: NEOP-23, Figure 2-II.B.l Prepared by: SRO Verification by: _ _ _ _ _ _ _--.: _ _ __

Signature Date Signature Date

Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:

1. Unit-2 is in MODE 3 at normal operating temperature and pressure. Current time is 0800.

2. The reactor tripped while performing RPS testing 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months ago.

Preparations are underway for a quick trip recovery startup to begin within the next 30 minutes with criticality anticipated in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at lOam.

3. The following conditions exist:

a. Unit-2 tripped from 100% power 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months ago.

b. Power history: Prior to the trip, Unit-2 operated at 100% for the previous 68 days.

c. Burnup from the plant computer point "CEBURNUP" is 14,400 MWDIMTU.

d. Nuclear Fuels has provided a Xenon Worth Calculation and a B-10 Correction factor of 0.971.

4. An ECC has been prepared by an extra licensed operator.

Initiating Cue:

The Shift Manager has directed you to Verify the Estimated Critical Concentration calculation per NEOP-302, Estimated Critical Condition, Step 6.1.23. Identify and correct any errors. Do not verify the + 1hr or the +2hr values. Do not verify the ECC tolerance band values.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-3

Facility: Calvert CUffs 1 & 2 Job Perfonnance Measure No.: SRO-ADMIN-3 Task

Title:

Monitor Azimuthal Power Tilt (Tq) using Excore Nuclear Instrumentation Task Number: 204.129 KIA

Reference:

2.2.42 (3.9, 4.6)

Method of testing:

Simulated Perfonnance: D Actual Perfonnance: C8J Classroom: C8J Simulator: D Plant: D READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job perfonnance measure will be satisfied.

Initial Conditions:

1. Unit-l power was recently reduced to 70% power to facilitate repairs to 11 SGFP.

2. CEAs are currently inserted to 108 inches on Group 5.

3. Channel "D" LRNI is out of service for maintenance. T.S. LCOs 3.3.I.A and 3.3.1.D have been entered.

4. The plant computer has "crashed lt and is inoperable.

5. Last "good" values for FxyT and FrTwere:

a. FxyT 1.81

b. FrT 1.64

6. OPS CALC is not available.

7. You are perfonning the duties of an extra SRO.

8. NI Readings are as follows:

Channel pper Lower 69.9

.3 67.2 69.7 68.7 D o o Initiating Cue:

AOP-7H, Loss of Plant Computer, has been implemented and the Shift Manager has directed you to perfonn Section IV.E, to monitor Tq. Detennine if any limits are being exceeded and any actions that may be required.

Task Standard:

Calculate and detennine whether or not Tq is in spec. Evaluates administrative requirements to detennine if any additional action is necessary.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant

2. AOP-7H, Loss of Plant Computer in Mode One or Two, ATTACHMENT (2)

3. AOP-7H, Loss of Plant Computer in Mode One or Two, ATTACHMENT (5)

General

References:

1. AOP-7H, Loss of Plant Computer in Mode One or Two.

2. T.S. 3.2.4 Azimuthal Power Tilt - Tq

3. Unit-I, Cycle 19, Core Operating Limits Report Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

1. None

I' ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start:

CUE: The Shift Manager directs you to determine the Azimuthal Power Tilt (Tq) using the excore NIs per Section IV.E.

o Locates AOP-7H,Section IV.E. - IF Greater than Same as element.

50% Rated Thermal Power, Monitor Tq.

0 1. Calculate upper AND lower Tq using ANY of the following:

0 IF ALL four Linear Power Channels are operable, Determines Step is NIA THEN perform EITHER of the following:

OR NOTE A total of 3 upper and 3 lower Linear detectors are required to be operable. The failed detectors can be on different channels.

0 IF only 3 Linear Power Channels are operable AND Reactor Power is less than 75%,THEN Determines Step is applicable perform EITHER of the following:

0 b. Calculate Tq using the method in ATTACHMENT 5), Tq CALCULATION USING EXCORE DETECTORS Records Readings on Attachment 5 CJ Rec()rd the readings on ATTACHMENT and performs calculations per formula on Attachment 5 (5),tq CALCULATION USING EXCbRE DETECTORS Calculates Upper Tq .02970

, ' " I : ; ,:",:,

Calculates Lower Tq .03152 OR 0 Notify the Reactor Engineering Work Group Determines Step is NIA to provide an alternate method to monitor Tq.

0 2. Once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , recalculate the Azimuthal Determines step is NIA at this time OR Power Tilt using the Excore Detectors PER Step Informs CRO to add notle to Shift E.l, Page 11. Turnover Information Sheet

ELEMENT STANDARD

(* = CRITICAL STEP) o 3. IF Tq is greater than 0.03, THEN perform the Determines Tq is greater than 0.03 following actions:

NOTE The Reactor Engineering Work Group will determine what actions are necessary to correct .

Tq.

a.;fbolOti'NiJitbeR.:ea~or Engineering WorkGroup Same as element

"" :Q;Qf.actu,hl Tqi NOTE IfTq is greater than 0.10, a two hour action applies.

Determines Tq is less than .10 o b. Enter the following Technical Specifications as applicable:

Determines T.S. 3.2.2 limits have been exceeded per COLR Figure 3.2.2 and that FxyT must be restored to within limits with a completion time of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Verifies CEAs withdrawn to or above the Long Term Steady State Insertion Limits .of Figure 3.1.6 (Not critical)

Determines T.S. 3.2.3 limits have not been exceeded per COLR Figure 3.2.3.

Determines T.S. LCO 3.2.4.A is applicable with a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months completion time I Terminating Cue: This JPM is complete when calculated azimuthal power tilt (Tq) is determined to be outside acceptable limits with T.S. components appropriately addressed. No further actions Stop: _ __

Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SRO-Admin-3 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _________________

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT ____~___.____

Examiner's Signature and Date:

Appendix C Job Perfonnance Measure Fonn ES-C-I Worksheet APPLICANT'S CUE SHEET Initial Conditions:

1. Unit-l power was recently reduced to 70% power to facilitate repairs to 11 SGFP.

2. CEAs are currently inserted to 108 inches on Group 5.

3. Channel "D" LRNI is out of service for maintenance. T.S. LCOs 3.3.l.A and 3.3.1.D have been entered.

4. The plant computer has "crashed" and is inoperable.

5. Last good values for F xyT and F rT :

a. FxyT = 1.81

b. FrT= 1.64

6. OPS CALC is not available

7. You are perfonning the duties of an extra SRO.

8. NI Readings are as follows:

Channel Upper Lower A 70.9 69.9 B 68.3 67.2 C 69.7 68.7 D 0 0 Initiating Cue:

AOP-7H, Loss of Plant Computer, has been implemented and the Shift Manager has directed you to perfonn Section IV.E, to monitor Tq. Detennine if any limits are being exceeded and any actions that may be required.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-4

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-4 Task

Title:

Approve a Liquid Waste Discharge Permit Task Number: 064.040 KIA

Reference:

2.3.6 (2.0, 3.8)

Method of testing:

Simulated Performance: Actual Performance: ~

Classroom: ~ Simulator: 0 Plant: 0 READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1) Unit-l is in Mode 3 with llA and 13B Waterboxes removed from service for cleaning

2) Unit-2 is at 88% power with 21A Waterbox removed from service for cleaning

3) 12 RCWMT discharge has been risk assessed and is on the schedule for today.

4) You are performing the duties of the CRS.

Initiating Cue:

The Shift Chemistry Technician has delivered a permit for the discharge of 12 RCWMT for your review and approval. If necessary, identify any issues associated with the planned discharge.

Task Standard:

This JPM is complete when the candidate rejects the permit because the required numbers of Circulating Water Pumps are not operating and RMS values are inconsistent. No further actions are required.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

1. CP-601, Liquid Radioactive Waste Release Permit Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

1. None

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start:

CUE: Provide the candidate the prepared copy of CP-601, Attachment 2 (12 RCWMT Discharge Permit) 0 Release Criteria is understood: Same as element.

0 Discharge Point Determines Unit 1 is checked.

0 Min # Circ Water Pumps Required Determines 5 CW Pps an~ required Determines 1,000,000 GPM is 0 Dilution Flow Rate Pre-Release: consistent with 5 CW Pps running 0 Maximum Release Flow Rate: 120 GPM I

i 0 RMS Number: 0-RE-2201 CUE: If checked, RMS reads as stated on permit.

Checks RMS reading for agreement 0 RMS

Background:

with permit value Notes value is above RMS 0 Expected RMS Reading: background Notes that Adjustable Setpoint is 0 'Adjustable Sctpoint: lower then Expected Reading Note to Evaluator: Candidate may determine permit criteria not met when reviewing Min

of eirc Water Pumps required.

Determines Unit 1 has only 4 CW eqwrM plant coitfiguration for cond:UGt~ngre~ease Pps running and does not meet asJ5~en'establisbed ' "

-" "-~ "

.:;-:"t~

\';' :.~ "

permit conditions

<:; ,.,."',,c,", 'f .

Informs Chemistry Tech of mistakes 0 C1:lemistryTech discus§ed permit with SR{)J~~ found on permit and does not

-/J-Sl; approve permit.

Terminating Cue: This JPM is complete when the candidate rejects the permit because the required numbers of Circulating Water Pumps are not operating and RMS values are inconsistent. No further actions are required. The evaluator is expected to end the JPM.

Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SRO-ADMIN-4 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ __

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _._ _

LIQUID RADIOACTIVE CP 601 WASTE RELEASE PERMIT Rev. 01403 Page 126 of 136 CHEMISTRY ATTACHMENT 2 12 RCWMT LIQUID RADIOACTIVE WASTE BATCH RELEASE PERMIT PERMIT #: 'lOIIO Recirc Start Date!Time: Pre-Release Gamma Sean#:

f>/41?c\D O\'l1 ~/{)I{)()

Release Source Level:

21.1 feet Release Volume: '2,3{"zeS liters RELEASE CRITERIA Discharge Poin!: Unit 1 X Unit 2 0 I Min # Circ Water Pumps Required: r:,

Dilution Flow Rate Pre-Release: 1i:.C. gpm i Maximum Release Flow Rate: 120 gpm RMS Number: O*RE*2201 RMS

Background:

cpm 28,000 Expected RMS Reading: cpm

'2:27,055 Adjustable Selpoln!: cpm Z25.lDlcf>

APPROVAL (Release Criteria Is within ODCM ReQuirements)

Independent Verification for Calculations: ~L'~t Prepared By: ~~6 V"" U

~"Setup Iliw".......y- , DatelTime 814/2010 tq~

sitor Setup Peer Ctfeck By: "'iZt=ltl dAh DatelTime 8141ZOtO \q4<>

SCO Approval:

WY~I DatelTime

~14 '~Ofb 1..000 Release Criteria Is understood, PUmt Sy stems are In 0 p eratlon, Req ulred p lant confi g uratlon for conductlng release has been established. Chemistry Tech discussed permit with SRO/SM.

SM/CRS: DatelTime i If discharging RCWMT, tank has been flushed thru 0*RI*2201. and response reported to Chemistry. RMS Pre-Op checks have been I completed and release criteria reviewed.

! Correct Setpolnts entered In computer and Peer Checked.

CRO: DatelTime Independent Verification of Alarm Setpolnts CRO: DalelTime RELEASE DATA Release Start DatelTime: Chemistry Informed Initial Level: feet Release End Date!Time: Chemistry Informed Final Level: feet RMS Reading Near Start of Discharge cpm Time:

RMS Reading at Midpoint of Discharge cpm Time:

RMS Reading Near End of Discharge cpm Time:

Background Count Rate O-RE-2201 During 01 Flush cpm

Clrc Waler Pps Operating During Release: I # Saltwater Pps Operating During Release:

POST RELEASE DATA AND REVIEW PERMIT COMPLETE. Release Criteria and Discharge Procedure Requirements Satisfied.

I CRO:

I Post Release Gamma Scan #: Post Release Volume: liters I Post Release Dilution Flow Rate: gpm Sample Composited (init/date):

Independent Verification for Calculations:

Permit Closed Out (Sign/date): SCO Approval/Date:

.----.~----------------------------------------------------------------------------.

Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:

1) Unit-l is in Mode 3 with llA and 13B Waterboxes removed from service for cleaning

2) Unit-2 is at 88% power with 21A Waterbox removed from service for cleaning

3) You are performing the duties of the CRS.

Initiating Cue:

The Shift Chemistry Technician has delivered a permit for the discharge of 1:2 RCWMT for your review and approval. If necessary, identify any issues associated with the planned discharge.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-5

Facility: Calvert Cliffs 1 & 2 Job Perfonnance Measure No.: SRO-ADMIN-5 Task

Title:

Emergency Response Plan Implementation Procedures for a General Emergency (Time Critical)

Task Number: 204.101,204.032 KIA

Reference:

2.4.41 (2.9,4.6)

Method of testing:

Simulated Perfonnance: D Actual Perfonnance: [gI Classroom: [gI Simulator: D Plant: D READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Unit-1 was at 100% power when the letdown line radiation monitor alarmed.

2. RCS sample analysis indicated RCS activity of 650 p,ci/cc Dose Equivalent Iodine l3l.

3. A plant shutdown, to comply with Technical Specification requirements, was begun.

4. At 97% power, 11 SG was diagnosed with a SG tube leak. Pressurizer level was rapidly lowering. A manual trip was initiated due to Pressurizer level <101" and continuing to lower.

5. On the trip, a S/G safety lifted and has not yet reset. During EOP-O, the leaking safety was identified as being on 11 S/G.

6. SG BD RMS showed rising trends prior to blowdown being isolated. The Main Steam Effluent Radiation Monitor for 11 S/G continues to increase and currently reads 3.2E-4 mrlhr. Blowdown was going overboard prior to the event.

7. The meteorological data screen (DRDT) indicates 90° for DIRIO and 80° for DIR60.

8. You are performing the duties of the Shift Manager and have not yet referenced the ERPIP.

9. This JPM is Time Critical.

Initiating Cue:

Per EOP-8, you are to determine the appropriate emergency response actions per the ERPIP.

Task Standard:

EAL classification is determined based on given plant conditions, initial notification form completed, and Protection Action Recommendation is completed.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

1. ERPIP 3.0, Immediate Actions Time critical task:

Yes Validation Time:

10 minutes Simulator Setup:

Not required

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start: _ __

o Locate ERPIP 3.0 Same as element o Refers to Immediate Actions, identifies the category Determines ATTACHMENT 2 is from the listing and goes to the appropriate applicable Attachment.

ATTACHMENT 2, EMERGENCY CLASSIFICATION

. 0 A. CLASSIFY the Event

1. WHEN an event is in progress potentially requiring emergency response, THEN CONDUCT the following actions in parallel:

~~----

o a. DETERMINE if existing conditions warrant implementation of one of emergency response attachments:

Personnel Emergency, Att 15

Fire, Att 16,17,18

Radiological Event, Att 19

Severe Weather, Att 20,21

Hazardous Material Release, Att 22 May determine a Radiological Event

Containment Evacuation, Att 23 exists

Security, Att 24

Large Area Loss, Att 25

Large Steam Leak, Att 26

Extensive Damage Mitigation Guidelines, Att27

SIG Level Monitoring During Extensive Damage Mitigation, Att 28 l NOTE to Evaluator: 15 minute clock starts AFTER applicant reads APPLICANT CUE SHEET.

TIME: _ __

ELEMENT STANDARD

(* = CRITICAL STEP)

Determines a GENERAL

. EMERGENCY classification is warranted under FISSION PRODUCT BARRIER DEGRADA TION, based on a loss of all 3 barriers-H.G.5.IA Fuel Clad Barrier- Coolant activity is> 600 Ilci/cc DEQ 1-131 RCS Barrier- SGTR>available charging pump capacity.

Containment Barrier- Ruptured SG is also faulted outside of containment CUE: U-2 CRS will handle Attachment 19 for a Radiological Event o B. IMPLEMENT Emergency Response Actions o 1. IF existing conditions warrant implementation Determines that U-2 CRS will handle i of an emergency response attachment, in parallel, the Radiological Event attachment.

THEN GO TO that attachment AND begin response actions.

o 2. IF an EAL condition is met, THEN OBTAIN an Attachment 3, Initial Notification Form, AND GO TO the appropriate EAL Declaration Determines from previous evaluation attachment: that an EAL is satisfied and obtains an Initial Notification form.

General Emergency Actions, Att 4 Identifies General Emergency Actions as the appropriate

Site Area Emergency Actions, Att 9 declaration attachment and goes to Attachment 4.

Alert Actions, Att 11

Unusual Event Actions, Att 13 CUE: Candidate commences actions per Attachment 4, General Emergency o A.I COMPLETE Attachment 3, Initial Refers to Attachment 3, Initial Notification Form. Notification Form.

NOTE TO EVALUATOR:

Page 2 of ATTACHMENT 3 contains instructions for completing the form and mayor may not be referred to as the applicant completes page 1.

CUE: Candidate completes Attachment 3 Initial Notification Form, following instructions provided on the back of the form

ELEMENT STANDARD

(* = CRITICAL STEP) , Initial Notification Form; Page-l Section -A 0 Complete Item AI. Checks "is" a drill O,;,~iCQ~plete Ite111\t\2;'

f,{I", ;"';91',<1;:'

Checks "Unit 1"

,<' 'v,? ,. 'v' o *Complete Item A3. Checks "General Emergency" tl *CQniplete Item,A4. ,

Enters "H.G.5.lA"

,q:.~~9ropleteItem AS. Checks "Yes" O)"Complete Item A5a Checks "Yes" o 'Compieteltem ASb Checks "Airborne" Note to Evaluator:

Applicant should proceed to Attachment (5) to determine Protective Action Recommendations and complete Item 6 on Attachment (3).

ATTACHMENT 5 GENERAL EMERGENCY PROTECTIVE ACTION RECOMMENDATIONS A. SELECT A PROTECTIVE ACTION RECOMMENDATION 0 A.l.0 - IF a controlled release of radioactive material from containment is to be commenced in less than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND there is assurance that the Determines step is NIA.

release will be a short term puff release lasting no more than 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

NOTE: If using the meteorological data screen (DRDT), then the DIR "60" indication is to be used for a release from the main vent. The "DIR 10" indication will be used for any other release. If using a backup meteorological data source, then the direction the wind is "from" is to be used.

A.l.l - IF the criteria of A.l.0 are not met, THEN SELECT one the following Protective Action Recommendations:

0 If "From" wind direction is between 168.75- Determines recommendation is NIA 303.75, then: due to DIRI0.

0 If "From" wind direction is between 303.75- Determines recommendation is NIA 33.75, then: due to DIRt O.

ELEMENT STANDARD

(* = CRITICAL STEP)

CJ If "From" wind direction is between 33.75-56.25, Detennines recommendation is NIA then: due to DIRIO.

~{'

Detennines recommendation is applicable using DIRIO. Selects hetvV'een 56.2S-1(iS~7S.

"Evacuate PAZ I & 2 unless

...... ~.....l"',"" conditionSIm ' conditions make evacuation the pubUQin P~ dangerous, notify the public in PAZ ofthe'HXmile EPZ:' 1 & 2 to take KI, shelter n::mainder of the 10 mile EPZ."

Note to Evaluator:

Applicant returns to ATTACHMENT 3, Page 1, Section A Checks box for "A.6.d" Completes A.7 only after items 1 through 6 are completed, and within 15 minutes of detennining an EAL is met.

ATTACHMENT 3, Page 1, Section B Selects blocks for:

Drill (not a critical task)

General Emergency StaffNonnal Emergency Response Facilities.

Prints name and signs (only after Section A is completed)

Terminating Cue: This JPM is complete when an EAL classification is detennined based on given plant conditions, the Initial Notification Fonn is completed, and a Protective Action Recommendation is completed. No further actions are required.

Appendix C Job Performance Measure Form ES-C-I Worksheet Verification of Completion Job Performance Measure Number: SRO-ADMIN-5 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

IMMEDIATE ACTIONS ERPIP*3.0 Revision 04600 Page 16 of 143 Page 1 of2 ATTACHMENT 3,INITIAL NOTIFICATION FORM USE THIS FORM FOR INITIAL NOTIFICATION AND EMERGENCY CLASS

'P.!'I~rr.:I:":I":!~':I"'r.P.!W~~P!'I'Irr.U~P.,Gr-RADING AND DOWNGRADING ON L Y Radioactivity is/was released to the environment due to the event: g) Yes 0 No

a. Radioactivity released islwas monitored: 0 N/A ~ Yes No

b. Type of Release: 0 N/A ~ Airborne 0 Liquid Protective Action Recommendation (Must choose one from b through f for

~.~-----------~ ....--------~~~ ....... ------------~.-----------,

o None (for downgrade, unusual event, alert or site area emergency only)

b. 0 Shelter entire 10 mile EPZ

c. 0 Evacuate PAZ 1 unless conditions make evacuation dangerous, remainder ofthe 10 mile EPZ.

d. t)l Evacuate PAZ 1 & 2 unless conditions make evacuation dangerous, notify the public in PAZ 1 & 2 to take KI, shelter remainder of the 10 mile EPZ.

e. 0 Evacuate PAZ 1 & 3 unless conditions make evacuation dangerous, notify the public in PAZ 1 & 3 to take KI, shelter remainder of the 10 mile EPZ.

Evacuate PAZ 1, 2 & 3 unless conditions make evacuation dangerous, notify the public in PAZ 1, 2 & 3 to take KI, shelter remainder of the 10 mile EPZ.

ACTION

~Drill o Unusual Event D Actual Event o Alert Staff Normal Emergency Response Facilities UNIT D Site Area Emergency o Staff Alternate Emergency Facilities

[8:1 Calvert Cliffs MGeneral Emergency D Staff Normal Emergency Facilities as a Precaution D Event Termination D Staff EOF and JIC Only

-;t" WI'" \N 'IS t.-\ttJUTES AC:1E.J {leAl>ltJC, CuE. S"'EeT

--.----------------------------------------------------------------------------~

Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:

1. Unit-1 was at 100% power when the letdown line radiation monitor alarmed.

2. RCS sample analysis indicated RCS activity of 650 JLci/cc Dose Equivalent Iodinel3l *

3. A plant shutdown, to comply with Technical Specification requirement, w:as begun.

4. At 97% power, 11 SG was diagnosed with a SG tube leak. Pressurizer level was rapidly lowering. A manual trip was initiated due to Pressurizer level <101" and continuing to lower.

5. On the trip, a S/G safety lifted and has not yet reset. During EOP-O, the leaking safety was identified as being on 11 S/G.

6. SG BD RMS showed rising trends prior to blowdown being isolated. The Main Steam Effluent Radiation Monitor for 11 S/G continues to increase and currently reads 3.2E-4 mr/hr. Blowdown was going overboard prior to the event.

7. The meteorological data screen (DRDT) indicates 90° for "DIRIO" and 80° for "DIR60".

8. You are performing the duties of the Shift Manager and have not yet referenced theERPIP.

9. This JPM is Time Critical.

Initiating Cue:

Per EOP-8, you are to determine the appropriate emergency response actions per the ERPIP. This JPM is Time Critical.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-1

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-l (Alt Path)

Task

Title:

Respond to CEA(s) Misaligned by 15" or more Task Number: 202.008 KIA

Reference:

001 A2.11 (4.4,4.7)

Method of testing:

Simulated Performance: D Actual Performance: C8J Classroom: D Simulator: C8J Plant: D READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Unit 1 is in Mode 1 at 100% power.

2. STP 0-29-1, MONTHLY CEA PARTIAL MOVEMENT TEST, was in progress.

When CEA 01 was being exercised, it became misaligned from its group.

3. AOP-IB has been implemented and all stabilizing actions have been performed.

4. You are performing the duties of the Unit 1 RO.

5. You have been assigned the trip criteria of 'If Any CEAs continue to move without operator action, then trip the Reactor."

6. Electrical Maintenance discovered and replaced a faulty power supply during troubleshooting.

7. CEA alignment time expires in 45 minutes.

Initiating Cue:

The CRS directs you to realign CEA 01 per AOP-IB step VI.B.

Task Standard:

Manually realigns CEA-Ol and trips reactor due to 2 dropped CEAs.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

1. AOP-IB, CEA Malfunction Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

1. Reset to IC-24 (both units at 100%)

2. Enter malfunctions:

a. Dropped CEA #01; ceds012_1 on Fl

b. Dropped CEA #64; ceds012_64 on F2

3. Place CEA #01 in desired condition:

_ _ a. Manually insert CEA #01 to 110" withdrawn.

_ _ b. Place CEDS control panel in OFF

c. Place the Group 5 inhibit Bypass to OFF

_ _ d. Select Group 4 and the individual CEA button for CEA #35

e. Allow plant to stabilize.

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start:

CUE: The CRS directs you to realign CEA 01 per AOP-IB step VI.B.

0 Locates AOP-IB,Section VI.B Same as element.

0 1. IF at any time the CEA is realigned, THEN perform the subsequent actions in Section Determines step is currently NIA IV., PRELIMINARY, Step B, Page 16.

0 2. IF the CEA alignment time has expired, Determines step is N/A THEN PROCEED to Step B.4, Page 24.

CAUTION: CEA movement should be minimized until the cause of the misalignment has been determined.

CUE: The CRS has directed the CRO to maintain power level no higher than the present level via boration.

o 3. Attempt to realign the affected CEA(s): Same as element 0 a. Maintain Reactor Power as required by:

Boration PER 01-2B, CVCS BORATION, Determines CRO will maintain DILUTION AND MAKEUP OPERATIONS. power with no action necessary on OR his part

Adjust Regulating CEAs .

0 b, Select1he desired group. "

Selects Group 5 tJ c~Selecfthe desired CEA.

Selects CEA 01 0 d. Select Manual Individual Mode. Same as element Q e. IF CMI is in effect, THEN override CM! as

.i* Determines CMI is in effect

....."*follows

NOTE: CMI will be bypassed to the affected group and applied to all other groups, and CMI bypass annunciation will alarm.

r"~ (1) Depress the Group Inhlbit,Bypass Same as element

,';pushbutton. -'"'" -

d (2) Depress and hold the Motion1nhibit Bypass pushbutton for at least 5 seconds before Same as element AND 5 seconds after CEA motton.

ELEMENT STANDARD

(* = CRITICAL STEP)

CAUTION: Do NOT allow Reactor Power to rise above the power the unit was stabilized at in Section IV. PRELIMINARY, Step A.2, while the CEA is being realigned. Turbine load shall NOT be raised until the CEA is within its alignment requirements.

f. Realign the CEA.

Detennines SID CEA rates are N/A.

Detennines Regulating CEA rates are appropriate. Commences For shutdown CEA's, pull 3.75inchesa:ng .'. recovery of CEA using the shim stick wait l Q s e c o n d s " ; on IC05. (Pull no more than 6.75" on CEA #0 I each time CEA is ForregulatingCEAs, pull 525 inches and withdrawn).

wait 15' seconds

2. IF the CEA must be inserted, THEN insert Detennines step is NIA the CEA.

NOTE TO EVALUATOR: The intent of the JPM going forward is for the student to recognize that a Rx trip is required when two CEAs become misaligned by > IS" per Step V.A.I.

CUE: Cue the Booth Operator to initiate Fl and F2, simultaneously, to drop CEAs 01 and 64 into the core when either CEA 01 is within 7.S inches of its respective group OR when cued by the Evaluator.

Candidate secures attempts to

lCOS alarms DROPPED CEA PI, PRIMARY PPDIL, withdraw CEA. Observes. alarms .

PRIMARY PDIL, SECONDARY PPDIL, Reviews the 1COS indications and SECONDARY PDIL, and the CEA deviation alarms detennines that two CEAs have annunciate fallen into the core, using CEAPDS and the CEA mimic display.

0 Locates AOP-l B,Section V Same as element i

0 1. IF two or more CEAs are misaligned from the other CEAs in their respective group by greater than Detennines 2 CEAs havl;! dropped.

15 inches, THEN perfonn the following actions:

i CUE: If the candidate recommends tripping the reactor to the CRS, Acknowledge and Direct the RO to trip the reactor and implement EOP-O

Depresses the two manual reactor 3~c1'id ~a, Trip $e Reactor trip buttons on 1C05.

0 b. Implement EOP-O, Post Trip Immediate No action required Actions

~.--- ,--------------~------------------------------------------------------------.

Terminating Cue: This JPM is complete when the manual reactor trip PB's are depressed. No further actions are required. The evaluator is expected to end the JPM.

I I

Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SIM-l Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _,

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

~r'-------------------------------------------------------------------------~

Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:

1. Unit 1 is in Mode 1 at 100% power.

2. STP 0-29-1, MONTHLY CEA PARTIAL MOVEMENT TEST, was in progress.

When CEA 01 was being exercised, it became misaligned from its group.

3. AOP-IB has been implemented and all stabilizing actions have been performed.

4. You are performing the duties of the Unit 1 RO.

5 . You have been assigned the trip criteria of' If Any CEAs continue to move without operator action, then trip the Reactor."

6. Electrical Maintenance discovered and replaced a faulty power supply during troubleshooting.

7. CEA alignment time expires in 45 minutes.

Initiating Cue:

The CRS directs you to realign CEA 01 per AOP-IB step VI.B.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-2

~-----------------------------------------------------------------------------~

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-2 Task

Title:

Restart RCPs Task Number: 201.028 KIA

Reference:

002 A2.03 (4.1, 4.3)

Method of testing:

Simulated Performance: D Actual Performance: cgJ Classroom: Simulator: cgJ Plant: D READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Unit-l is shut down for a short maintenance outage.

2. The Unit is expected to be maintained in Mode 3 per OP-4.

3. A short time ago RCP Feeder Breaker, 252-1201, tripped.

4. AOP-3E has been implemented.

5. The cause of the breaker trip was determined to be personnel error. There is no common mode failure. RCP Feeder Breaker, 252-1201, has been reclosed.

6. It has been determined that no RCP CBO temperatures exceeded 250 of.

7. You are performing the duties of the Unit 1 RO.

Initiating Cue:

The CRS has directed you to start Reactor Coolant Pumps per AOP-3E Step IV.I.5.

Task Standard:

This JPM is complete when a RCP has been started. No further actions are necessary.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

1. AOP-3E- LOSS OF ALL RCP FLOW, MODES 3,4, OR 5 Time Critical Task:

No Validation Time:

15 minutes Simulator Setup:

1. Reset to IC-ll

_ _ 2. Cool down to approximately 520 OF Tc.

3. Place TBV controller in Auto with a setpoint of 810#

4. Freeze simulator.

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start:

0 Locate AOP-3E, Step IV.I.5 Same as element.

0 5. Reduce TCOLDto less than 525 of using Checks loop TCOLD indications (IC06) and/or the ADV s or TBV s average TCOLD (1 COS).

D 6. Raise PZR level to between 155 and 170 Checks in-service PZR level control channel inches. (IC06)

D 7. IF TCOLD is less than 369 of, Checks loop TCOLD indications (IC06) and/or THEN perform the following: average TCOLD (lC05). Determines step is NIA

CUE: RCP restart criteria are met

8. Verify that ALL of the following RCP restart criteria are met:

D Verify electrical power is available to Checks 12 SERV BUS VOLTS ~13.8KV the RCPs Checks lights for l2AIB RCP Oil Lift Pps on D RCP BUS or contacts ABO to verify D MCC-115 (ALL RCPs) Checks lights for 11AlB RCP Oil Lift Pps on 0 MCC-105 (11A111B RCP) or contacts ABO to verify 0 12/22 SERV BUS VOLTS is less than Checks 12 SERV BUS VOLTS (IC20) 14.8 KV 0 4KV bus voltage is greater than 4100 Checks 11,12,13,14,15/16 4KV bus volts volts (IC17,18,19) 0 RCP CSO temperatures are less than Checks CBO temps on the plant computer 200'F D RCS subcooling is greater than 30 of Checks CET SCM indicators (ICOS) based on CET temperatures D At least ONE S/G available for heat removal Checks SIG levels (1 C03) 0 S/G level greater than (-)170 inches Checks Main or Aux Feedwater in operation and feeding SIG (lC03I1C04) 0 capable of being supplied with feedwater Checks ADVs or TBVs in operation (lC03) and controlling RCS temp (1 C06)

D capable of being steamed

ELEMENT STANDARD

(* = CRITICAL STEP) o PZR level is greater than 155 inches Checks PZR level on in-service level control and NOT lowering channel or PZR level recorder (1 C06).

~~------------------------------~----------

o TcoLD is less than 525 of Checks 100.p Tc indications (IC06) and or I average T COLD (1 COS)

+-----

ORCS temperature and pressure are greater than the minimum operating limits PER Attachment (1), RCP Refers to EOP Attachment (1)

PRESSURE/TEMPERATURE LIMITS of the EOP ATTACHMENTS.

CUE: If applicant requests guidance on which RCP to start first examiner should ask for applicant's recommendation.

NOTE If 11 RCS loop is available, then a RCP in that RCS loop should be started to restore Main Spray capability_

NOTE Determines IlA & B RCPs will be started first. (JPM is written anticipating IIA RCP The second RCP in the same loop should be will be started. It would also be acceptable to started within S minutes of starting the first start any of the remaining RCPs)

RCP. This should be done due to the NPSH requirements for two RCPs in the same loop being less restrictive than NPSH requirements for single RCP operation.

9. WHEN RCP restart is desired, AND RCP restart criteria are met, THEN start one RCP in a loop with a SG available for heat removal as follows:

o a. On IC07, verify that the RCP BLEED-OFF ISOL valves are open:

Same as element o l-CVC-505-CV o l-CVC-S06-CV o b. Verify that the "CCW FLOW LO" Checks alarm on IIA RCP alaIm panel alarm is clear. (IC07)

Places HS for IIA RCP to Start Imd checks Oil Lift Pp running

ELEMENT STANDARD

(* CRITICAL STEP)

I !

0 d. Verify that the "OIL LIFT PP PRESS Checks RCP alarm on IIA RCP alarm panel LO" alarm is cleared. (IC07) 0 e. Operate the Oil Lift Pump for at least Same as element 60 seconds before starting the RCP.

0 f. Insert the RCP sync stick. Inserts Sync Stick in HS for 252-11P02 0 g. On panel 1C 19, verify that the Same as element synchroscope is NOT rotating.

I I

CAUTION Starting an RCP may cause a Pressurizer level transient. The potential for a pressure transient exists if an RCP is started in a loop in which no S/G is available for heat removal.

Places HS for IIA RCP to start and check Oh. Start the RCP.

lights and motor amps 0 i. Verify that the RCP is NOT cavitating by observing that running current is Checks motor amps at RCP HS steady.

0 10. Operate Charging and Letdown to Checks in-service PZR level control channel, restore and maintain PZR level between 101 on 1C06. Checks LID flow and Chg Pps are and 180 inches. consistent restoration of PZR level.

I 0 11. Monitor RCP seal parameters following Checks IIA RCP Middle and Upper seal pump restart. pressure indicators on 1C06 0 12. Allow backflow to equalize Checks loop temperature indicators on 1C06 1

temperatures in the opposite loop.

13. Start a second RCP in the same loop by performing the following actions:

Terminating Cue: This JPM is complete when a RCP has been started. No further actions are required. The evaluator is expected to end the JPM

Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SIM-2 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _______________________

Time to Complete:

Follow up Question: _____________________________________________

Applicant Response: __________________________________

Result: SAT _ _ _ _ __ UNSAT __________

Examiner's Signature and Date: ____________________________________

Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:

1) Unit-l is shut down for a short maintenance outage.

2) The Unit is expected to be maintained in Mode 3 per OP-4.

3) A short time ago RCP Feeder Breaker, 252-1201, tripped.

4) AOP-3E has been implemented.

5) The cause of the breaker trip was determined to be personnel error. There is no common mode failure. RCP Feeder Breaker, 252-1201, has been reclosed.

6) It has been determined that no RCP CBO temperatures exceeded 250 OF.

7) You are performing the duties of the Unit 1 RO.

Initiating Cue:

The CRS has directed you to start Reactor Coolant Pumps per AOP-3E Step IV.LS.

,--'--.,-~--------------,

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-3

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-3 (AU Path)

Task

Title:

Respond to RCS leakage exceeding one Charging Pump, Modes 1 and 2 Task Number: 202.015 KIA

Reference:

004 A4.08 (3.8, 3.4)

Method of testing:

Simulated Performance: 0 Actual Performance: I:8J Classroom: 0 Simulator: I:8J Plant: D READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Unit 1 is at 100% power and operating with steady state conditions.

2. Pressurizer level begins to steadily lower and the backup charging pumps automatically start.

3. Pressurizer level is still slowly lowering.

4. You are performing the duties of the Unit 1 CRO.

Initiating Cue:

The CRS directs you to perform Block Steps VI.B thru VI.E of AOP-2A.

Task Standard:

This JPM is complete when AOP-2A Block Steps VI.B thru VI.E are completed. No further actions are required.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

1. AOP-2A, Excessive Reactor Coolant Leakage Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

_ _ 1. IC-24, 100%.

_ _ 2. Insert malfunction CVCS 020 (Charging header break inside Containment) with a value of 22.5%.

3. Run simulator until the second backup charging pump starts. Lower leak size to

~5% so that PZR level is still lowering, but charging header pressure is > RCS pressure. Ensure both Pressurizer Level channels indicate greater than a 15 inch deviation from program level.

4. Makeup to VCT to ensure level is high in the band when the simulator is taken out of freeze.

5. Shut l-CVC-183 when requested.

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start:

CJ Locate AOP-2A,Section VI. Same as element B. Verify the event is not challenging RPS CUE: The RO will be responsible for monitoring for trip criteria.

CJ B.l IF, at ANY time, PZR pressure reaches the TMiLP pretrip setpoint, Determines RO will be assigned to THEN, with the permission of the SM/CRS, monitor trip criteria perform the following actions:

C. Control Pressurizer Level Monitors Pressurizer level (LI-llOX-l and LI-llOY-l andlor Cl C.l Verify that Charging Pumps are maintaining LR-llO, on lC06). Notes that PZR level within 15 inches of programmed level. Pressurizer level is slowly lowering with all backup ~harging pumps runllIng.

o C.I.l IF PZR level is NOT being maintained by ALL available Charging Pumps, THEN shut the LID CNTMT ISOL valves:

Same as element Cl l-CVC-515-CV Cl l-CVC-516-CV CUE: RO will initiate makeup to VCT if (as) required. (Cue Booth Operator to initiate makeup to VCT if necessary).

o C.l.2 Makeup to the VCT to maintain level Determines no action required at this as necessary. time.

rn.a 1 i" n ~/G Tube Leak

ELEMENT STANDARD

(* = CRITICAL STEP)

(J D.1 Determine if a SG Tube Leak exists by observing a rise in ANY of the following:

(J SG sample activities (J Condenser Off~Gas radiation levels at 1~RI~

1752 Monitors RI-1752, RI~40l4 andlor (J SG Blowdown radiation levels at I~RI-4095 or RI-4095 on lC22, and RIC-5421 and 5422, on 2C24B.

1~RI~40l4 Monitors LIA-ll 05 and (J MAIN STEAM EFFL RAD MONITOR LIA-l106 andlor LR-l111 and LR radiation levels at 1-RIC-5421 or l-RIC-5422 1121, on 1C03. Chemistry

! acknowledges samples requested.

(J MAIN STM N-16 RAD MONITOR levels at l-RIC-5421A or l-RIC-5422A (J SG water level (Unexplained)

(J Feed flow mismatch (J D.2 IF a SG Tube Leak is indicated, THEN Determines step is NIA perform the following actions:

E. Attempt to Isolate the Leak (J E.l Verify that the LID CNTMT ISOL valves are shut:

(J Same as element l-CVC-515-CV (J l-CVC-516-CV (J E.2 Check there is NO PORV leakage by the following indications: Monitors Quench Tank parameters (LIA-116, PA-116 and PA-116A and (J Quench Tank Parameters TIA-116, on 1C06). Monitors (J PORV discharge piping temperatures, computer point Tl 07 and TI0S.

Monitors acoustic monitor computer points T107 and TlOS indication.

(J Acoustic Monitor indication (J E.3 Verify that RCS SAMPLE ISOL valve, Same as element 1-PS-5464-CV, is shut.

ELEMENT STANDARD

(* = CRITICAL STEP) o E.4 Verify that the Reactor Vessel Vent valves are shut:

Same as element 0 l-RC-103-SV 0 l-RC-I04-SV o E.S Verify that the Reactor Vessel Vent valves are shut:

Same as element 0 l-RC-IOS-SV 0 I-RC-I06-SV NOTE:

A leak on the Charging header which exceeds the capacity of the charging pumps can be identified by Charging header pressure indicating less than RCS pressure. Identification of the leak may be missed if more than one charging pump is running.

0 E.6 Determine if the leak is on the Charging header by performing the following actions:

0 a. Stop .

all but .ONE CHG PP. Same as element 0 b. IF Charging header pressure is less than RCS Pressure, Determines charging header pressure is less than RCS pressure, verifies THEN assume the leak is on the Charging leak is on the charging header.

header.

0 c. IF the leak is NOT on the Charging header, THEN start any CHG PPs that were Determines step is N/A stopped.

0 E.7 IF the leak is on the Charging header, Determines step is applicable THEN perform the following actions:

0 a. Place all Chg Pps in Pull To Lock. Same as element 0 b. Dispatch an operator to determine the Dispatches an operator to determine location of the leak. the location of the leak.

NOTE: CHG PP HDR XCONN, l-CVC-182, is located near 12 Charging Pump.

ELEMENT STANDARD

(* = CRITICAL STEP)

CUE: ABO reports no leakage in CHG PP Room. RadCon reports video surveillance indicates no abnormal leakage anywhere in the Aux Building.

[J c. IF the leak is upstream of CHG PP HDR XCONN, I~CVC-182, THEN shut l-CVC- Determines leak is downstream of I 182, AND start 12 or 13 CRG PP as l-CVC-182 and this step is NIA.

required.

[J d. IF the leak is downstream of I l-CVC-182, Detennines step is applicable THEN align Charging to the Auxiliary HPSI Header:

o (1) Verify that the following valves are shut:

0 AUX SPRAY valve, l-CVC-S17-CV Same as element 0 l-CVC-518-CV Same as element

[J l-CVC-SI9-CV NOTE: The Auxiliary HPSI Header is out of service and T.S. 3.5.2 applies when 1-S1-656-MOV is shut.

CUE: The CRS will handle all TS entries.

o (2) Shut the HPSI AUX HDR ISOL Same as element valve, 1-SI-656-MOV:

[J (3) Open ONE of the followingAUX HPSI HDR valves:

0 1-SI-617-MOV Same as element 0 I-S1-627 -MOV 0 1-S1-637-MOV 0 I-S1-647-MOV I 0(4) Open the SI TO CHG HDR valve, 1- Obtains key from locker & opens 1- !

CVC-269-MOV. CVC-269-MOV I

NOTE:

REGEN HX CHG INLET, l-CVC-183, is located in the 27 foot West Penetration Room.

ELEMENT STANDARD

(*

= CRITICAL STEP)

CAUTION:

=:l When a Charging Pump is started, Reactor power will lower due to the concentration of

Boric Acid in the Auxiliary HPSI header being 2300 PPM or greater.

CUE: ABO reports no leakage in either the 5' or 27' West Penetration rooms, concurring with RadCons earlier report. Containment parameters clearly indicate the leak is inside containment. When dispatched, ABO reports l-CVC-183 is shut. (Cue booth operator to shut l-CVC-183)

Ok~JIJftheleak isdownstreaIl1 ofthe

., ~(JEN~:HXCHG INL1~'irval",e. Determines leak is downstream of 183, THEN shut l-CVC':'183. CVC-I83. Dispatches ABO to shut CVC-I83.

AND start any available CHGPP.

o (6) IF the leak is upstream of I-CVC-I83, Determines step is NIA CUE: CRS will review LCO actions o (7) Declare the Auxiliary HPSI Header Informs CRS of need to refer to T.S out of service and refer to T.S. 3.5.2 ECCS-Operating . 3.5.2

NOTE: If charging via the Auxiliary HPSI header, the Reactor power reduction will result

, in an initial PZR level reduction.- - - - - - -

NOTE TO EVALUATOR: Cue the booth operator to lower turbine load and restore T COLD to program as necessary. Once turbine load is being reduced, PZR level starts to rise.

Determines that PZR level is o e. Verify charging flow by observing a rise

lowering due to boron addition from i SI line. When turbine load is being in PZR level. reduced, determines PZR level is increasing.

Monitors TI-5309 and 5311, on o E.8 IF the leak is determined to be occurring

IClO. Monitors PI-5308, on IClO.

inside Containment by checking the following

Monitor MI-53lO and 5312, on indications: IClO. Monitors sump level alarm I frequency. ~

o Rise in Containment temperature, pressure,

! Detennines leak is in co~

humidity or sump level alarm frequency o Rise in Containment gaseous or particulate Monitors RI-5281 and 5280, on activity IC22.

ELEMENT STANDARD

(* = CRITICAL STEP)

"U-l WR NOBLE GAS RAD MON" and Monitors window 18, on 1C 10 and "UNIT 1 MAIN VENT GASEOUS" alanns RI-5415, on lC22.

clear 0 THEN perform the following actions:

o a. Start ALL available CNTMT AIR Starts all available Containment air CLRs in HIGH. coolers in high.

o b. Open the CNTMT CLR EMER OUT valves for the operating CNTMT AIR Same as element CLRs.

0 E.9 IF the leak is NOT occurring inside of Determines step is N/A Containment, 0 E.lO Determine that NO leakage into the Component Cooling System is indicated by:

0 NO rising trends on Component Cooling Radiation Monitor, Monitors RI-3819, on lC22.

l-RI-3819.

Determines there is no leak into the 0 ncc HEAD TK LVEL" high alarm clear CC system.

Terminating Cue: This JPM is complete when AOP-2A Block Steps VI.B thru VLE are completed. No further actions are required.

Verification of Completion Job Performance Measure Number: SIM-3 (Alt Path)

Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _~.~ ________~ ________

Applicant Response: _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

~-------------------------------------------------------------------------------~

APPLICANT'S CUE SHEET Initial Conditions:

1. Unit 1 is at 1000/0 power and operating with steady state conditions.

2. Pressurizer level begins to steadily lower and the backup charging pumps automatically start.

3. Pressurizer level is still slowly lowering.

4. You are performing the duties ofthe Unit-l CRO.

Initiating Cue:

The eRS directs you to perform Block Steps VI.B thru VI.E of AOP-2A

.' --~------ -----,

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-4

Facility: Calvert Cliffs 1 & 2 Job Perfonnance Measure No.: SIM-4 (AU Path)

Task

Title:

Verify RAS Task Number: 201.063 KIA

Reference:

006 A3.08 (4.2, 4.3)

Method of testing:

Simulated Perfonnance: D Actual Perfonnance: IZI Classroom: D Simulator: IZI Plant: D READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Unit 1 Tripped from 100% power due to a LOCA.

2. RWT Level - 1.0 feet and decreasing.

3. You are performing the duties of the Unit-l CRO.

Initiating Cue:

The CRS directs you to verify RAS Actuation per EOP-5, Step IV.S.

Task Standard:

This JPM is complete when the operator stops 12 LPSI Pump and aligns ECCS for RAS operation.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

1. EOP-S

2. EOP Attachment (10)

Time critical task:

No Validation Time:

20 minutes Simulator Setup:

_ _ 1. IC-13, VI, 100% power

_ _ 2. Set controller for I-SW-S208 to 0% output

_ _ 3. Insert Malfunction RCS002 at 2000 gpm.

- - a. Run simulator until RAS actuates

b. Reduce leak rate to restore Pressurizer level to 120"

- - c. Freeze simulator

ELEMENT STANDARD

(* = CRITICAL STEP)

CUE: Have simulator driver place simulator in "run".

Time Start: - - -

o Identifies and locates EOP-5, Block Step "IV.S" Same as element S.l - WHEN RWT level drops to 0.75 feet OR the "ACTUATION SYS RAS TRIP" alarm is received, THEN perform the following actions:

NOTE TO EVALUATOR Applicant must perform critical task of securing 12 LPSI Pump due to its failure to stop automatically upon receipt of RAS. If applicant does not secure 12 LPSI during RAS verification in step 1.a, then it must be secured during verification of RAS lineup per Attachment (6) in step S.l.e.l ALTERNATE ACTION Verifies RAS actuation, by "ACTUATION SYS RAS TRIP" alarm actuated, LPSI pumps stopped and containment sump valves opening. Secures 12 LPSI Pump due to receipt of RAS END OF ALTERNATE ACTION o S.l.b. - Check a minimum containment sump level Monitors containment sump level on of at least 28 inches is indicated on the CNTMT l-LI-4146 or l-LI-4147, on lC08 WR WATER LVL indication, I-LI-4146 or l-LI and IC09.

4147.

o S.l.c. - Verify the CNTMT SUMNP DISCH valves open:

Same as element o I-SI-4144-MOV o I-SI-4145-MOV o S.l.d. - Shut the RWT OUT valves:

o I-S1-4142-MOV Same as element o I-S1-4143-MOV S.l.e. - Verify RAS lineup PER ATTACHMENT (6), RAS VERIFICATION CHECKLIST.

ELEMENT STANDARD

(* = CRITICAL STEP)

Secures 12 LPSI Pump due to receipt ofRAS (if not secured in step l.a see previous note to evaluator)

END OF ALTERNATE ACTION ATTACHMENT (6), RAS VERIFICATION CHECKLIST IC08, lC09, lCIO o a. - 11 and 12 LPSI PPs - Off Same as element o b. - MIN FLOW RETURN TO RWT ISOL MOVs:

01-SI~659-MOV ~ Open Same as element Ol-SI-660-MOV - Open o c. - CNTMT SUMNP DISCH valves:

Ol~SI-4144-MOV ~ Open Same as element 01-S1-4145~MOV ~ Open o a. - CAC SRW INL valves Ol-SRW-1581-CV - Open Ol-SRW-1584-CV Open Same as element Ol-SRW-1589-CV - Open Ol-SRW-1592-CV - Open S.l.f. - Verify Component Cooling in service as follows:

o S.l.f.! - Throttle open BOTH CCHX SALTWATER OUT valves:

Same as element o I-HIC-5206 o I-HIC-5208

ELEMENT STANDARD

(* = CRlTICAL STEP) o S.I.f.2 - Verify BOTH CCHX OUT valves are open:

Same as element o l-CC-3824-CV o 1- CC-3826-CV o S.1.f.3 - Verify TWO CC PPs in operation. Same as element NOTE TO EVALUATOR The applicant must end up with HPSI Pump flow split such that minimum flow requirements of 90 GPM per PP are met for running HPSI Pumps.

Applicant throttles HPSI flow to 250 GPM per header ensuring operating HPSI PP mini flow requirements are met o S.l.h - IF one HPSI PPs is running, THEN throttle HPSI flow to achieve 150 GPM through each of Determines this step is NIA the four headers.

Determines HPSI header flow is o S.l.i - Check HPSI MOVs with flow are at least being maintained at the required 30% open. value Terminating Cue: This JPM is complete when the operator has secured 12 LPSI Pump, verified the post-RAS alignment and, throttled the Main and AUX HPSI Loop flows to approximately 250 GPM per loop. No further actions are required.

Verification of Completion Job Performance Measure Number: SIM-4 (Alt Path)

Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __

Examiner's Signature and Date:

Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:

1. Unit 1 Tripped from 100% power due to a LOCA.

2. RWT Level,..., 1.0 feet and decreasing.

3. You are performing the duties ofthe Unit-l CRO.

Initiating Cue:

The CRS directs you to verify RAS Actuation per EOP-5, Step IV.S.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-5

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-5 (Alt Path)

Task

Title:

Verify the Containment Environment Safety Function is satisfied Task Number: 201.016 KIA

Reference:

022 A3.01 (4.1,4.3)

Method of testing:

Simulated Performance: D Actual Performance: ~

Classroom: Simulator: ~ Plant: D READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. A transient, resulting in a Reactor trip, has occurred on Unit-I.

2. EOP-O, Post Trip Immediate Actions, has been implemented.

3. You are performing the duties of the CRO.

Initiating Cue:

The CRS directs you to verify the Containment Environment Safety Function.

Task Standard:

Applicant determines Safety Function is not met and performs Containment Environment required actions.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

ReQuired Materials:

1. Procedures and manuals normally available in the plant General

References:

1. EOP-O, Post Trip Immediate Actions Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

1. IC-24, Unit 1, 100% power

_ _ 2. Insert the following Malfunctions:

_ _ a. ESFAOOI 01

b. ESFAOO 1 02

c. SIAS auto failure

_ _ d. RCSOOl cold leg rupture

3. Run simulator for 2 minutes then freeze.

_ _ 4. Override Containment Narrow Range pressure on 1CIO, 1-PI-5308, to 0#.

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start: - - -

F. VERIFY THE CONTAINMENT ENVIRONMENT SAFETY FUNCTION IS SATISFIED.

Checks containment pressure indication on I C09 and determines that containment pressure is greater than 0.7 PSIG based on WR indication. Though not critical, o 1. Check containment pressure is less than 0.7 PSIG.

identifies that NR pressure indicator is suspect and makes report to CRS that Alternate Actions are being taken for Containment Environment due to high pressure.

NOTE TO EVALUATOR:

The report of "Taking Alternate Actions" can be made at the direction of the candidate but should be reported as soon as practical.

The candidate may manually initiate SIAS early if it is recognized SIAS has not automatically actuated. Equipment may already be in its desired condition when Containment Environment is checked.

1.1 IF containment pressure exceeds 0.7 PSIG, THEN perform the following:

Checks all four containment air coolers on I C09/1 0 to determine if D;;~a.Verify:.ALL available CNTMT AIR CLRs are all available coolers are operating,

~!~~rating: . starts any not running, or may recognize that SIAS failed to initiate and may manually initiate SIAS.

Checks valve indication on IClO and

b. OpelttfieCNTMT CLR EMEROl.IT valves places the valves in open or may operating CNl'MT AIR CLRsF recognize that SIAS failed to initiate and may manually initiate SIAS 1.2 IF containment pressure exceeds 2.8 PSIG, THEN verify ESFAS actuation of the following

NOTE: SIAS has NOT actuated. SIAS alarm not actuated, 11 & 13 HPSI pumps are not operating and HPSI header MOVs are shut.

Determines that SIAS has failed to o SIAS actuate.

ELEMENT STANDARD

(* = CRITICAL STEP)

Channel A & B SIAS manual actuation pushbuttons are depressed on I C09/1 O. Checks SIAS alarm

'M@:~llyjnitiates SIAS "ACTUATION SYS SIAS TRIPPED" has actuated, 11 & 13 HPSI pumps are operating and HPSI header valves are open.

Checks CIS alarm "ACTUATION SYS CIS TRIPPED II has actuated 1:1 CIS and Containment CCW isolation valves are shut.

'0 .1.31F CIS has actuated, THEN trip ALL RCPs. Trips all RCPs at 1C06.

Verifies CSAS has actuated by CSAS alarm "ACTUATION SYS 1:1 1.4 IF containment pressure exceeds 4.25 PSIG, CSAS TRIPPED" has actuated, Containment Spray pumps are THEN verify CSAS actuation. operating and spray discharge valves are open. Verifies CS flow and that the CBP's are not running.

Checks containment temperature 1:1 2. Check containment temperature is less than 120 indication on 1C09 and determines OF. that temperature is greater than 120 OF.

NOTE TO EVALUATOR: Actions in step F.2.1 may not be performed because these actions were taken earlier in the JPM.

2.1 IF containment temperature exceeds 120 of, THEN perform the following:

Checks all four Containment Air 1:1 a. Verify ALL available CNTMT AIR CLRs Coolers on 1C09ll 0 to determine are operating. that all available coolers are operating.

1:1 b. Open the CNTMT CLR EMER OUT valves Checks valve indication I C 10 to for the operating CNTMT AIR CLRs. ensure they are open

ELEMENT STANDARD

(* = CRITICAL STEP)

Verifies alarms clear on 1C 10 and I uses indications at 1C22 to identify that the containment RMS have a o 3. Check containment radiation monitor alarms are rising trend. Starts IRUs ifnot already running. May take actions clear with NO unexplained rise. based on temperature affects to the Cntmt High Range Monitors depending on interpretation of Containment RMS Reports to the CRS that the Containment Environment Safety o Report status of the Containment Environment Function CANNOT BE MET due to Safety Function to the CRS. high containment pressure and temperature, and rising Containment RMS indications.

I TERMINATING CUE: The JPM is complete when the CRS is informed of the status of the Containment Environment Safety Function. No further actions are required.

I Time Stop: _ __

Appendix C Job Performance Measure Form ES-C-I Worksheet Verification of Completion Job Performance Measure Number: SIM-5 (Alt Path)

Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ lWSAT ____________

Examiner's Signature and Date:

Appendix C Job Performance Measure Form ES-C-I Worksheet APPLICANT'S CUE SHEET Initial Conditions:

I. A transient, resulting in a Reactor trip, has occurred on Unit-I.

2. EOP-O, Post Trip Immediate Actions, has been implemented.

3. You are performing the duties of the CRO.

Initiating Cue:

The CRS directs you to verify the Containment Environment Safety Function.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-6

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-6 Task

Title:

Respond to a Fuel Handling incident in the Containment Task Number: 202.051 KIA

Reference:

034 A2.0l (3.6, 4.4)

Method of testing:

Simulated Performance: D Actual Performance: ~

Classroom: D Simulator: ~ Plant: 0 READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Unit-l is in Mode-6 with refueling operations in progress.

2. The FHS has informed the Control Room, via the RCRO, that a fuel assembly has been dropped in the reactor vessel. The FHS reports there is obvious damage to the fuel assembly.

3. You are performing the duties of an extra licensed operator.

Initiating Cue:

AOP-6D, FUEL HANDLING INCIDENT has been implemented. The CRS directs you to perform AOP-6D, Step V.A.

Task Standard:

This JPM is complete when the available Penetration Room Exhaust Filter trains have been placed in service. No further actions are required.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

1. AOP-6D, FUEL HANDLING INCIDENT Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

1. Reset simulator to IC-5

_ _ 2. Place a second SRW Pump in service.

_ _ 3. Place Containment Purge in operation.

_ _ a. Open Purge Supply & Exhaust Valves

_ _ b. Start Purge Exhaust Fan

_ _ c. Secure 3 Cntmt Clrs, place the fourth in "SLOW"

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start:

CI Locate AOP-6D,Section V, Step A. Same as element A. Control the Potential for a Radiological Release:

1. Isolate Containment Purge:

.'. Q,a.iS~op II CNTMT PURGE SUPPLYand

. ;:BXHFANS .

Places I-HS-5289 & 5290 in STOP Q 1:'HS-5290 and verifies green lights illuminate

>~+'J:r7:~i

.t::l 1..HS-5289 i\~ !\~o. Close 11 CNTMT PUROE SU~mand EXH valves:; ',. . Places I-HS-141O & 1412 in CLOSE and verifies red lights extinguish and CI I-HS-1410 green lights illuminate OJ I-HS-1412 CUE: No Containment Closure Deviations exist.

2. Restore any Containment Closure Deviations per NO-l 14, CONTAINMENT CLOSURE.

CAUTION: Mini-flow requirements for the SRW Pumps is 1700 GPM. Ensure operating SRW Pump differential pressure remains less than 87 PSID CI 3. IF the SRW system is aligned for reduced load Determines step is NIA.

operation, THEN start a second SRW Pump 4i)~~1lt1l~CA~~G~NCYOUT valveson. ".

AtJIJiavailableCon'tainfuent Ait Coolers:

Q*ltCAC 1'-HS-1582

\~" ~ ... Places I-HS-1582, 1585, 1590 and 1593 in OPEN and verifies open CI'12>CAC i'-HS-1585 .'. indications.

OJ 13 CAC 1..HS-1590 r O;*t4iCAC I-HS-1593 ii:

Verifies SRW flow increases to all CI 5. Verify SRW flow through all available CACs CACs

ELEMENT STANDARD

(* = CRITICAL STEP) tJ6. start ALL available CAC(s) in ruGH speed:

O. 11 CAC 1~HSw5299 Places I-HS-5299, 5300, 5301 and

..* 5302, not running in FAST speed, to

'tJ 12 CAC 1'-HS-5300 FAST and verifies all are running in

.. \to

~ ~, ,;/

13 CAG I-HS-5301 fast.

. "." .*'0 14CAC l wHSw5302 o 7. Start ALL available IODINE FILT FANS:.

0 11 FAN I-HS-5293 Places I-HS-5293, 5295 and 5297 in START and verifies running

0 12 FAN 1wHS-5295 indications.

0 IlFAN I-HSw5297 D 8. Log the start time of the Iodine Filter Fans Logs start time for each fan

9. Start the available Penetration Room Exhaust Filter trains:

D a. Verify open 11 and 12 Penetration Room FILT ISOL DMPRS Verifies the Unit-l Dampers are D 11 Damper 1-HS-5285 open D 12 Damper I-HS-5287 0 h. Start 11 and 12 PENET RM EXH FANS Places I-HS-5283 and 5284 in D 11 Fan I-HS-5283 START and verifies running

'0 12 Fan I-HS-5284 indications.

D c. Log the start time of the Penetration Room Logs start time for each fan Exhaust Fans.

Terminating Cue: This JPM is complete when the available Penetration Room Exhaust Filter trains have been placed in service. No further actions are required.

~eStop: _ __

Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SIM-6 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:

1. Unit-l is in Mode-6 with refueling operations in progress.

2. The FHS has informed the Control Room, via the RCRO, that a fuel assembly has been dropped in the reactor vessel. The FHS reports there is obvious damage to the fuel assembly.

3. You are performing the duties of an extra licensed operator.

Initiating Cue:

AOP-6D, FUEL HANDLING INCIDENT has been implemented. The CRS directs you to perform AOP-6D, Step V.A.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-7

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-7 (Alt Path)

Task

Title:

Recovery from Automatic Feedwater Isolation Task Number: 201.033 KIA

Reference:

059 A4.11 (3.1,3.3)

Method of testing:

Simulated Performance: D Actual Performance: IZI Classroom: D Simulator: IZI Plant: D READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. A total loss of all feedwater has occurred on Unit 1.

2. The reactor is tripped and EOP-O is complete.

3. The CRS directed the RCPs be secured and a cooldown started prior to the EOP-3 brief.

4. You are performing the duties of the Unit 1 eRO.

Initiating Cue:

The CRS directs you to establish natural circulation and cooldown the RCS per EOP-3, Step IV.G.

Task Standard:

SGIS is reset and a Condensate Booster Pump is started.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

1. EOP-3, Loss of All Feedwater.

Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

_ _ 1. Reset simulator to IC-24, 100% power

._ _ 2. Insert Malfunctions AFW005, AFWOOl_Ol, AFWOOl_02 for the trip of 13, 11 and 12 AFW Pps

___ 3. Trip the Reactor, the Main Feed Pumps and the RCPs, cooldown using the TBVs until just before SOlS actuates. Leave ADV controller output at ~ 100%. SGIS should actuate shortly after the candidate "assumes" the watch providing them with feedback indicating alternate actions are required.

_ _ 4. Panel Override 11 S/G SGIS Block and Reset HIS in the "Reset" position.

Remove override once SGIS actuates.

ELEMENT STANDARD

(* = CRITICAL STEP)

I Time Start:

I 0 Locate EOP-3, Step IV.G Same as element IV.G. Commence Natural Circulation RCS Cooldown To TCOLD Less Than 465 0 IV.G.t - IF, at ANY time, BOTH S/G levels are less Verifies S/G levels on t C03 or than (-)350 inches OR TCOLD rises uncontrollably SPDS. Verifies TCOLD is not rising 5° F or greater, THEN initiate Once-Through uncontrollably.

Cooling concurrently PER step J.

G.2 - Block SGIS as follows:

o WHEN the "SGIS A BLOCK PERMITTED" alarm is received THEN block SGIS A. Unsuccessfully attempts to block o WHEN the "SGIS B BLOCK PERMITTED" SGIS. Initiates Alternate Actions.

alarm is received THEN block SGIS B.

CUE: Inform applicant the RO will monitor for and Block SIAS. Cue Simulator Driver to perform this function if necessary.

IV.G.3 - Block SIAS as follows:

o WHEN the "PZR PRESS BLOCK A PERMITTED" alarm is received, THEN block The RO will monitor for and Block SIAS A.

SIAS 0 WHEN the "PZR PRESS BLOCK B PERMITTED" alarm is received, THEN block SIAS B.

IV.GA - IF 500KV offsite power has been lost, THEN protect the condenser from overpressure. Determines step is NIA o IV.GA.a - Shut BOTH MSIVs.

CONTINUES ON NEXT PAGE

ELEMENT STANDARD

(* = CRITICAL STEP)

NOTE:

Applicant will be unable to block SGIS actuation due to a faulty 11 S/G SGIS and Block Reset Handswitch CUE: Cue Booth operator to remove the panel override for 11 S/G Block and Reset HIS when SGIS actuates.

CUE:

D If SRO applicant requests or recommends stopping or slowing down the cooldown when SGIS Block fails, ask them what they would do. Then direct them to proceed with the cooldown.

D If RO applicant requests or recommends stopping or slowing down the cooldown when SGIS Block fails, then direct them to proceed with the cooldown.

D It is expected the applicant will continue the cooldown on the ADVs, while pursuing Alternate Path actions, when SGIS cannot be blocked.

D If the applicant takes no action to shift the cooldown to the ADVs, then request, as the CRS, the current cooldown rate. If there is no cooldown rate ask the applicant for his recommendation and acknowledge.

D If the applicant proceeds with cooldown using the ADVs and is not performing the Alternate Action to block and reset SGIS, Then ask the status of Block Step G.

IV.G.5 - Conduct a rapid RCS cooldown to TCOLD less than 465 OF using the TURB BYP valves OR ADV s, while maintaining the following:

Initiates plant cooldown using the D Cooldown less than 100 OF in anyone hour TBVs with a setting of D Subcooling between 30 and 140 OF based on CET approximately 17%

temperatures D Pressurizer level between 50 and 180 inches.

IV.G.6 - Verify adequate RCS heat removal via steam generators:

Monitors S/G parameters and TCOLD D At least ONE S/G has wide range level greater during conduct of cooldown than (-)350 inches D TCOLD is stable or lowering FAILURE OF SGIS TO BLOCK, IN STEP IV.G.2, INITIATES ALTERNATE PATH D IV.G.2.1 - IF SGIS actuates as a result ofthe Verifies loss of power has not cooldown AND the Non-Vital 4KV buses are occurred.

energized, THEN reset the SGIS as follows:

D IV.G.2.1.a. - Place the COND BSTR PPs in Places Condensate booster pump PULL TO LOCK. control switches in PTL.

ELEMENT STANDARD

(* = CRITICAL STEP) 0 IV.G.2.1.h. - Match handswitchpositiQn~ Places MSIV handswitches in PER AITACHMENT (7), SGrS .. SHUT. Places Feedwater isolation VERIFICATION CHECKLIST. ;

valve handswitches in SHUT.

CUE: Cue Booth operator to initiate SGIS Block"A" if applicant requests PWS be sent to initiate SGIS Block locally at the ESFAS cabinet Places 11 and 12 S/G SGIS keyswitches in BLOCK. MAY request PWS block SGIS "A" o IV.G.2.1.c. - Block SGIS. locally at the ESFAS cabinet.

Checks that Annunciators C59 and C60 (SGIS A (B) BLOCKED) actuate.

Places 11 and 12 S/G SOlS keyswitches in RESET. Checks that o IV.G.2.l.d. - Reset the SOlS signal. Annunciators G09 and 010 (ACTUATION SYS SGIS A (B)

TRIPPED) are clear.

CUE: Once MSIV handswitches are placed in the open position cue the applicant to proceed with the next step (don't wait for full open indication on the MSIVs) o IV.G.2.1.e. - Open the MSIV(s). Same as element o IV.G.2.1.f. - Open the SG FWISOL xi1l,,~(~):

," 'v/\/

I-FW-4516-MOV Same as element

I-FW-4517-MOV 0 IV.G.2.Lg. - Start a COND BSTR PP. Same as element END ALTERNATE PATH

[ Terminating Cue: This JPM is complete when SGIS is reset and a Condensate Booster Pump is started. No further actions are required.

Appendix C Job Perfonnance Measure Fonn ES-C-l Verification of Completion Job Perfonnance Measure Number: 81M-7 Applicant:

NRC Examiner:

Date Perfonned:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Jnitial Conditions:

1. A total loss of all feedwater has occurred on Unit 1.

2. The reactor is tripped and EOP-O is complete.

3. The eRS directed the Reps be secured and a cooldown started prior to the EOP-3 brief.

4. You are performing the duties of the Unit 1 eRO.

Initiating Cue:

The eRS directs you to establish natural circulation and cool down the ReS per EOP-3, Step IV.G.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-8

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-8 Task

Title:

Transfer 11117 4KV Bus Loads from lA DG to Offsite Power Source Task Number: 024.007 KIA

Reference:

064 A2.09 (3.1,3.3)

Method of testing:

Simulated Performance: 0 Actual Performance: I:8J Classroom: 0 Simulator: I:8J Plant: 0 READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. 4KV Bus 11 was on its alternate feed, for maintenance on the normal feeder breaker, when the alternate feeder breaker tripped. The lA DG started, loaded on and is supplying 4KV Bus 11.

2. Maintenance has been completed on the normal feeder breaker.

3. You are performing the duties of the Unit 1 CRO.

Initiating Cue:

The CRS directs you to Transfer 11117 4KV Bus Loads from lA DG to Offsite Power Source in preparation to shut down the lA Diesel Generator.

Task Standard:

This JPM is complete when offsite power is paralleled with the lA DG at approximately 2 MW and 4.0 KV. No further actions are required.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

1. OI-21A, lA Diesel Generator Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

1. Reset simulator to IC-24, 100% power

2. Open the 11 4KV Bus normal feeder breaker causing the lA to start and load on the Bus

_ _ 3. Reset the UV Sensor alarm using ESF AS Remote Function

4. Stabilize plant and clear associated alarms

_ _ 5. Place Alternate feeder breaker in PTL and place a "pinkie" on it to denote off normal position.

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start: - - -

CUE: General Precautions and Initial Conditions are met.

o Identify and locate OI-21A, Step 6.4.B.1. Same as element CUE: 11 4KV Bus normal feeder 152-1115 is expected to remain available.

o 1. CHECK the selected 11117 4KV Bus offsite power source IS. expected to remam. aVaI'1able:

114KVBUSALTFDR,152-1101 Same as element OR

11 4KV BUS NORMAL FDR, 152-1115 0 2. VERIFY DC control power is available by observing the 11117 4KV Bus Normal OR Alternate Same as element Feeder breaker position light being illuminated at the control switch.

3. PLACE lA DO in the TRANSFER MODE by performing the following:

o a.DEPRESS lA DO EMEROENC¥;

Same as element START, I-HS-1707, pushbutton. I;;

~

c:l ~~INSERT the Sync Stick for lA DO OUT Inserts Sync Stick for BKR, l-CS-152-1703. l-CS-152-1703 at lC18A.

"a c. DE;;l)RESS lA DO SLOW START,J-HS-Same as element

~!)l; 1708, pushbutton. .." .....

0 d. MOMENTARILY PLACE lADO SPEED CONTR, l-CS-1705, to RAISE OR Same as element LOWER.

0 e. MAINTAIN lA DO at approximately 60 Hz.using lA DO SPEED CONTR, Same as element 1-'CS-1705.

0 f. REMOVE the Sync Stick from lA DO Same as element OUT BKR, l-CS-152-1703.

I

ELEMENT STANDARD

(* = CRITICAL STEP)

CUE: CRS directs to close normal feeder.

[J g. INSERT the Sync Stick for the 11117 4KV Bus Normal OR Alternate Feeder breaker handswitch:

114KV BUS ALT FDR, l-CS-152- Places sync stick in sync jack next to control switch for 152-1115.

1101 OR

114KV BUS NORMAL FDR, I,:,CS 152-1115 D h. CHECK the associated Synchroscope Checks 1C 19 synchroscope.

AND Sync Lights are operating.

NOTE:

Offsite power voltage indication will be on the INCOMING voltmeter.

D i. ADJUST RUNNING VOLTS equal to Raises or lowers running volts to INCOMING VOLTS using 1A DG AUTO match incoming volts using 1-CS VOLT CONTR, 1-CS-1704. 1704.

NOTE:

The Synchroscope works in the opposite direction from normal when lA DG is the RUNNING power source.

D j. ADJUST 1A DG frequency so the synchroscope pointer is rotating slowly in the Adjusts synchroscope to slowly in FAST direction using 1A DG SPEED fast direction.

CONTR,1-CS-1705.

JPM continued on next page

ELEMENT STANDARD

(* = CRITICAL STEP)

CAUTION: To avoid improper paralleling, do NOT start OR stop any large loads on the 11/17 4KV Bus.

R.WHENfu~Synchroscope poiuter'1~

ately. 5'd~grees prior tqfue Ir,.

. position, THEN CLOSEt1i~JJ/1.7 Bus Normal OR Alternate Feeder breaker:

Closes l-CS-152-1115 at +/- 5° of the

114KV BUS ALT FDR, I-GS':15~- 12 o'clock position.

1101

11 4KV BUS NORMAL. FDR, l-CS 152-1115.

L CHECK lA DO load is approximately 2.0 Sarne as eIement MW.

D m. REMOVE the Sync Stick AND Same as element RETURN to Home Base.

ro- 4. Monitor 11117 4KV Bu-s voltage between 3.75 KV and 4.35 KV. Verifies voltage in spec.

CUE: Another operator will complete lA DG Shutdown D 5. IF continued parallel operation of lA DO for cleanout is desired, THEN GO TO Section 6.5.1, lA DO NORMAL SHUTDOWN FROM CONTROL No action required ROOM, Step B.I, to unload lA DO and restore non

'i~l trips.

CUE: Another operator will complete lA DG Shutdown D 6. IF IA DO will be stopped, THEN GO TO I

Section 6.5.1, lA DO NORMAL SHUTDOWN No action required FROM CONTROL ROOM. i Terminating Cue: This JPM is complete when offsite power is paralleled with the lA DO, on 11 4KV Bus, at approximately 2 MW and 4.0 KV. No further actions are required.

Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SIM-8 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: ________________________________

Time to Complete:

Follow up Question: _______________________________________________

Applicant Response: _______________________________________________

Result: SAT _ _ _ _ __ UNSAT ____________

Examiner's Signature and Date:

Appendix C Job Perfonnance Measure Fonn ES-C-I Worksheet APPLICANT'S CUE SHEET Initial Conditions:

I. 4KV Bus II was on its alternate feed, for maintenance on the nonnal feeder breaker, when the alternate feeder breaker tripped. The lA DG started, loaded on and is supplying 4KV Bus II.

2. Maintenance has been completed on the nonnal feeder breaker.

3. You are perfonning the duties of the Unit 1 CRO.

Initiating Cue:

The CRS directs you to Transfer 11117 4KV Bus Loads from IA DG to Offsite Power Source in preparation to shut down the IA Diesel Generator.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PLANT-1

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: PLANT-1 Task

Title:

Start 11 & 12 Containment Air Coolers Task Number: 032.049 KIA

Reference:

022 A4.01 (3.6, 3.6)

Method of testing:

Simulated Performance: [g] Actual Performance: D Classroom: D Simulator: D Plant: [g]

READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. A severe fire has resulted in Control Room evacuation. AOP-9A has been implemented.

2. You are performing the duties of the Unit-1 ABO.

Initiating Cue:

You have just completed Step BK, RESTORE SWITCHGEAR ROOM VENTILATION which directs you to "Go to the 45' West Penetration Room to perform Step BL".

Task Standard:

This JPM is complete when 1C43 has been notified that 11 and 12 Containment Air Coolers are in high speed.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

1. AOP-9A, CONTROL ROOM EVACUATION AND SAFE SHUTDOWN DUE TO A SEVERE CONTROL ROOM FIRE.

Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

1. None

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start:

CUE: You have just completed Step BK, RESTORE SWITCHGEAR ROOM VENTILATION which directs you to "Go to the 45' West Penetration Room to perform Step BL".

0 Locate AOP-9A, Step BL. Same as element.

0 Candidate proceeds to the Unit-l 45' West Same as element Penetration Room CUE: Have applicant describe how required keys are obtained. ANSWER: Keys and equipment are obtained at the Safe Shutdown Locker (per AOP-9A, Step IV.Y.I for the ABO). Keys required to operate the LocallRemote switches are found on this key ring.

CUE: When the LocallRemote Key is inserted and rotated each switch is in the LOCAL position.

1. Start 12 Containment Air Cooler in HIGH speed:

0 >1<. Place a LocallRemote Key into. 12

, Containment Air Cooler Load Contactor Panel Same as element handswitch, I-HS-5300Al, and unlock the handswitch.

0 h. Rotate the handswitch to LOCAL. Same as element CUE: When the Local Control handswitch is positioned 12 CAC is running in HIGH (green light for "OFF" is off, Red light for "HIGH" is on).

0 c. Blac~;'l2 Contain1l1enlAir Cooler Local Same as element HandsW;:tch,i-HS,;5300A, to HIGH. .

I,'

0 d. GO TO the 45' East Electrical Penetration Same as element Room.

CUE: When the LocallRemote Key is inserted and rotated each switch is in the LOCAL position.

2. Start 11 Containment Air Cooler in HIGH speed:

O';'a. Place.a LocallRemote Key into 11

'*"**ConiainmentAir.. Cooler,Eoad Contactor**Panel Same as element I,*' .,:i:11andswitch, I-HS-S299AI,and unlock the.

iharidsWitch.

,4:<\/" " :"'0. :

C'f Cf"::b. Rbkte the handswitch to LOCAL Same as element

ELEMENT STANDARD

(* = CRITICAL STEP)

CUE: When the Local Control handswitch is positioned 11 CAC is running in HIGH (green light for "OFF" is off, Red light for "HIGH" is on).

~.Place 11 Co > * *... '.

Air'Co61erLocal Same as element

'lJandsWitch, l1is"S299A, t(> HIGH.

CUE: Acknowledge communication that 11 and 12 Containment Air Coolers are in high speed using proper communication techniques.

3. Notify lC43 that 11 and 12 Containment Air Coolers Same as element are in high speed.

Tenninating Cue: This JPM is complete when 11 and 12 Containment Air Coolers are in LOCAL and operating in high speed. per AOP-9A, Section BL

Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: PLANT-l Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:

1) A severe fire has resulted in Control Room evacuation. AOP-9A has been implemented.

2) You are performing the duties of the Unit-l ABO.

Initiating Cue:

You have just completed Step BK, RESTORE SWITCHGEAR ROOM VENTILATION which directs you to "Go to the 45' West Penetration Room to perform Step BL".

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PLANT-2

Facility: Calvert Cliffs 1&2 Job Performance Measure No.: PLANT-2 Task

Title:

Respond to a FRV or FRV Controller Malfunction Task Number: 202.040 KIA

Reference:

059 A2.12 (3.1, 3.4)

Method of testing:

Simulated Performance: C8J Actual Performance: D Classroom: D Simulator: D Plant: C8J READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1) Unit-2 is at 100% power.

2) 21 SG FRV has an oscillation of about 5% output both in auto and manual.

AOP-3G has been implemented.

3) 21 SG FRV must be pinned to support Pri-l maintenance on the positioner.

4) You are performing the duties of an extra CRO.

Initiating Cue:

The CRS directs you to take local control of#21 SG FRV per AOP-3G, Step VII.D.7.d.

The Safer Brief has been completed and the 800 Mhz radios will be used for communication.

Task Standard:

This JPM is complete when 21 SG FRV is in Local Manual Control per AOP-3G VII.D.7.d and has been adjusted to the desired position.

Evaluation Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

1. AOP-3G, MALFUNCTION OF MAIN FEEDWATER SYSTEM Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

1. None

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start: --

CUE: The CRS directs you to take local control of #21 FRV per AOP-3G, Step VII.D.7.d.

D Locate AOP-3G, Step VII.D.7.d. Same as element.

D Candidate proceeds to the 27' Elevation of the Same as element Unit-2 Turbine Building CUE: Communications have been established with the Control Room.

D 1. Candidate establishes communication with the Same as element Unit-2 Control Room CUE: The holes in the valve bushing and stem are aligned.

D 2; Turn the handwheel until the holes in the Same as element valve bushing and stem are aligned.

WARNING The FRV pin may be hot due to heat conducted through the valve body. Gloves should be worn when handling the FRV pin.

CUE: The pin has been inserted.

D 3. Insert the FRV alignment pin. Same as element CUE: 2-IA-519 is shut.

D 4. Shut the Instrument Air isolation for the affected FRV:

Shuts 2-IA-S19

21 SO FRV 2-IA-SI9

22 SO FRV 2-IA-S23 CUE: 2-IA-1116 is open.

D S. Open the equalizing valve for the affected FRV:

Opens 2-IA-IIOO

21 SO FRV 2-IA-1l16

22 SG FRV 2-IA-1l18

ELEMENT STANDARD

(* = CRITICAL STEP)

e. IF in BYPASS OVERRIDE, THEN locally adjust the FRV to obtain a SG FW REG CONTROL BYPASS output of approximately 70% while maintaining SO level at approximately zero inches.

CUE: Provide direction to candidate to open 21 SIG FRV 1 turn (while the CR adjusts SG FW REG Control BYPASS output to approximately 70 % ).

Cl Control Room requests 21 S/G FRV be opened 1 tuin Candidate opens 21 FRV 1 tum while attempting to tldjust SG FW REG Control using manual hand wheel I; BYPASS output to approximately 70%

Terminating Cue: This JPM is complete when 21 SO FRV is in local manual control and has been adjusted to the desired setting per AOP-30,Section VII.D.7.d

~ --------------------------------------------

Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: PLANT-2 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _____________

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Appendix C Job Performance Measure Form ES-C-I Worksheet APPLICANT'S CUE SHEET Initial Conditions:

5) Unit 2 is at 100% power.

6) 21 SG FRV has an oscillation of about 5% output both in auto and manual.

AOP-3G has been implemented.

7) 21 SG FRV must be pinned to support Pri-l maintenance on the positioners.

8) You are performing the duties of an extra CRO.

Initiating Cue:

The CRS directs you to take local control of #21 SG FRV per AOP-3G, Step VII.D.7.d.

The Safer Brief has been completed and the 800 Mhz radios will be used for communication.

2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PLANT-3

Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: PLANT-3 Task

Title:

Deenergize/Energize a 4KV Bus Task Number: 004.001 KIA

Reference:

062 A4.04 (2.6, 2.7)

Method of testing:

Simulated Performance: [g] Actual Performance: D Classroom: D Simulator: D Plant: [g]

READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. A severe fire has resulted in a control room evacuation and AOP-9A implementation.

2. You are performing the duties of the Unit 1 RO.

3. Step "AT" (OPEN THE FEEDER BREAKERS FOR 4KV BUS 11) is complete.

Initiating Cue:

You have been instructed to align the OC DG to 11 4 Kv bus per AOP-9A Step AU.

Task Standard:

This JPM is complete when the OC DG is aligned to the 11 4Kv bus per AOP-9A Step IV.AU.

Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps (denoted by an asterisk) completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Required Materials:

1. Procedures and manuals normally available in the plant General

References:

1. AOP-9A, CONTROL ROOM EVACUATION AND SAFE SHUTDOWN DUE TO A SEVERE CONTROL ROOM FIRE.

Time Critical Task:

No Validation Time:

10 minutes Simulator Setup:

1. None

ELEMENT STANDARD

(* = CRITICAL STEP)

Time Start:

CUE: Give the operator a copy of appropriate section of AOP-9A.

o Locate AOP-9A, Step AD. Same as element.

o Candidate proceeds to the Unit-l 27' Switchgear Same as element Room CUE: ATTACHMENTS for determination of proper Electrical Safety PPE, along with PPE, are located at the Switchgear Room Tool Cabinets in both the 27' and 45' Switchgear Rooms Candidate determines required PPE for:

o Candidate determines PPE required to complete

Operation of a 4KV circuit breaker with enclosure doors assigned tasks closed

Operation of 4KV disconnects NOTE TO EVALUATOR Proper PPE for this task is: 100% Cotton Long Sleeve Shirt and Pants OR 100% Cotton short sleeve shirt and pants under FR Lab Coat and Safety Glasses. PPE matrix does not require gloves. Discussion indicating candidate correctly determines PPE requirements is acceptable in lieu of donning the PPE for a simulation.

CUE: Have applicant describe how required keys are obtained. ANSWER: Keys and equipment are obtained at the Safe Shutdown Locker (per AOP-9A, Step IV.P.I for the RO). Keys required to operate the LocallRemote switches are found on this key ring.

CUE: When the LocallRemote Key is inserted and rotated the switch is in the LOCAL position.

1. T4ke 10calGOntrol.of QC DO Output Breaker to 1,1 4kV Qus. 152,,1 106 by performing the following:

od$'R~inote key into OC DO Output Same as element dSwidih, Same as element

ELEMENT STANDARD

(* = CRITICAL STEP)

When taken to TRIP, 1-HS-1106B indicates trip.

Same as element CUE: When checked 152-1106 indicates open (green light is illuminated) o d. Verify OC DG Output Breaker, 152-1106 is Checks Bkr indicating lights open.

NOTE TO EVALUATOR Proper PPE clothing for this task is: FR Long Sleeve Shirt and FR Pants OR FR Coveralls (minimum 4 cal) over 100% cotton short sleeve shirt and pants OR FR Lab Coat (minimum 4 cal) over 100% cotton shirt and pants. Additional PPE required: Hardhat, Safety Glasses, Arc-Flash face shield, hearing protection and leather gloves. Discussion indicating candidate correctly determines PPE requirements is acceptable in lieu of donning the PPE for a simulation.

WARNING Improper operation of disconnects can result in serious injury. Keep body and head clear of the operating arc of the disconnect handle. Do NOT release handle prior to full travel.

When the disconnect is opened, a very loud bang will be heard, and a switch position flag indication will be visible indicating disconnect position" (Applicant should position their body such that they are to the side of and facing away from the disconnect cubicle when the disconnect lever is operated.)

CUE: Keys and equipment are obtained at the Safe Shutdown Locker (per AOP-9A, Step IV.P.1 for the RO). Keys required to operate the disconnect are found on this key ring.

CUE: The keys are inserted into Disconnect 189-1106 and the disconnect is unlocked.

~~!C;19S~iPCDO to 4KV Bus 11 Disconnect 189-11 06 by peffon@igthe!fdllowing;

,,/>;10(,'" ' "'A'~' "e<, , '

Same as element a~.i:insertupper keys AND unlock OC DG to 4KV Bus.ll Disconnect, 189-1106 CUE: When operated, the disconnect indicates closed.

it:l h. Close disconnect 189-1106. Same as element CUE: When the key is inserted and rotated, disconnect 189-1106 locks closed.

cr~~c *. InseIt lower key AND lock disconnect *189~

.~~:.J 106, 'in the closed position. Same as element

ELEMENT STANDARD

(* = CRITICAL STEP)

CUE: Acknowledge communication that OC DG Output Bkr is in local and open and disconnect 189-1106 is closed, using proper communication techniques.

CI 3. Notify lC43 that OC Diesel Generator Output Breaker to 11 4KV Bus, 152-1106 is in local and Same as element tripped and the OC DG Disconnect to 4KV bus 11, 189-1106 is closed.

Terminating Cue: This JPM is complete when OC DG Output Bkr is in local and open and disconnect 189-1106 is closed per AOP-9A, Section AU.

Appendix C Job Performance Measure Form ES-C-I Worksheet Verification of Completion Job Performance Measure Number: PLANT -3 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _._ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __

Examiner's Signature and Date:

Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:

1. A severe fire has resulted in a control room evacuation and AOP-9A implementation.

2. Step "AT" (OPEN THE FEEDER BREAKERS FOR 4KV BUS 11) is complete.

3. You are performing the duties of the Unit 1 RO.

Initiating Cue:

You have been instructed to align the OC DG to 11 4 Kv bus per AOP-9A Step AU.

Appendix D Scenario Outline Form ES-D-1 Facility: CCNPP Scenario No.: 1 Op-Test No.: 2010 Examiners: Operators:

Initial Conditions:

U-1 is at 100% l20wer MOC 10,885 MWD/MTU with long term stead~ state l20wer histoty. U-2 at 100% l20wer BOC.

Turnover:

1A DIG removed from service and tagged out for scheduled maintenance (return in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ), with OC DIG aligned to 11 4kv bus (disconnect 189-1106 shut). 13 CBP is in PTL and is considered emergenc~ use onl~ due to high vibrations. Instructions for the shift are to maintain l20wer @ 100%.

Event Event Malf. No. Event Type*

No. Description RCS023 02 PZR Press Xmtr 100Y fails low RCS024 03 I (ATC) PZR Press Xmtr 102C fails low 1

RCS025 02 TS (SRO) PZR Press Xmtr 103-1 fails low RCS026 02 PZR level XMTR 110Y fails high C (ALL) 2 RCS003 20 gpm RCS leak TS (SRO)

R(ATC/SRO) 3 Expeditious Downpower N (BOP) 4 HDV005 02 C (BOP/SRO) 12 Condensate Booster Pump Failure w/o auto start of standby 5 SWYD002 M (ALL) Loss of offsite Qower 6 CEDSOIO C (ATC) 2 Stuck CEA's 7 DG002 02 C (BOP) 1B DIG Auto Start Failure C (BOP/SRO) 8 4KVOOI 02 11 4kv bus electrical fault TS (SRO)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks: (bold)

Commence boration due to 2 stuck CEA's prior to losing 11 4KV bus on fault

Restore 4kv vital bus power with OC DIG to 14 4KV bus (after Station Blackout)

Op-Test No.: 2010 Scenario No.: _1_

SCENARIO OVERVIEW RCS LEAK WITH STATION BLACKOUT Initial Conditions: U-l is at 100% power MOC 10,885 MWD/MTU with long term steady state power history. U-2 at 100% power BOC. lA DIG removed from service and tagged out for scheduled maintenance, with OC DIG aligned to 11 4kv bus (disconnect 189-1106 shut). 13 CBP is in PTL due to high vibes when running, it is considered emergency use only. Instructions for the shift are to maintain power @ 100%.

An instrument failure occurs on PZR reference leg which affects multiple pressure and level instruments. The crew will need to shift Pressure control from 100Y to 100X or manually control PZR heaters. After a short delay the instrument line leak increases to 20 gpm leak which will prompt entry into AOP-2A, the leak is small enough to exercise AOP-2A completely (Section VI, leak> 1 Chg pump and Section V, leak < 1 chg pump after letdown isolated) and eventually lead to controlled SID.

During the down power a trip of 12 Condensate Booster Pump occurs without an auto start of standby CBP, the crew should implement AOP-3G Section V. The crew should start 13 CBP. After trip criteria is given out the CRS should direct bypassing Precoats and Demineralizers to maximize SGFP suction pressure. If the crew delays in starting 13 CBP the 11 CBP may trip on overcurrent (>380 amps for> 20 sec). If the crew loses CBP's then a reactor trip will be ordered. If the crew completes this malfunction without a trip the 13 CBP will trip a reactor trip should be ordered.

When crew directs tripping the reactor, a loss of offsite power will occur. Concurrent with the trip a failure of IB DIG occurs which leaves U-l without either vital4kv bus. When the CRO performs Vital Auxiliaries safety function he will align the OC DIG to 11 4kv bus but an electrical fault will occur after aligned for 5 minutes. There will be a problem closing disconnect 189-1406 which will prevent aligning the OC DIG to14 4kv bus. Two stuck CEA's will not be able to be identified (due to electrical malfunctions) so boration by ATC in EOP-O is required. All safety functions will not be met due to loss of power effects. Numerous alternate actions will be required in EOP-O (eg. Isolate MSR's or MSN's, PO operation of ADV's, align AFW Pumps, etc). The SRO should transition to EOP-8 due to RCS leakage and station blackout.

EOP-8 entry with Safety Function Assessment IA W Resource Assessment Table, with the following results RC-l Met, VA-2 Not Met, PIC-3 Met (PIC-4 Not Met ifSIAS actuates), HR-l Met (HR-2 Not Met if SIAS actuates), CE-l Met, RLEC-l Met.

The BOP should commence VA-2 immediately. Step B.2 will have him align OC to 14 bus (Electricians will have solved disconnect 189-1406 problem allowing alignment) or transition to VA 3 for SMECO. The ATC should commence RC-I.

When the crew has restored power to 14 4kv bus the scenario will end.

INSTRUCTOR SCENARIO INFORMATION

l. Reset to IC-24

2. Perfonn switch check.

3. Place simulator in RUN, advance charts and clear alarm display.

4. Place simulator in FREEZE.

5. Enter Malfunctions/ Triggers

a. CW002 01 at 0% as T-I on FI

b. PZR Press Xmtr IOOY fails low on T-I RCS023 02

c. PZR Press Xmtr 102C fails low on T-I RCS024 03

d. PZR Press Xmtr 103-1 fails low on T-I RCS025 02

e. PZR Level Xmtr 11 OY fails high on T-l RCS026_02

f. RCS Leakage 20 gpm after 5 min delay on T*l RCS003

--g. Loss of 12 Condensate Booster Pump CD005 02 on F2

h. Loss of 13 Condensate Booster Pump CD005 03 on F3

i. CEA-OI on bottom as T-2 Loss of Offsite Power SWYD002 on T-2

k. 2 Stuck CEA's CEDSOIO at Time Zero (4-3 & 4-5)

l. IB DG Auto-start Failure DGOO 1 02 at Time Zero

m. 11 4 KV bus electrical fault 4KVOOl 01 on F4

6 Enter Panel Overides

a. Shut disconnect 189-1106

b. Place 13 CBP in PTL c Hang tags on 1A DG

d. Place pink abnormal tags:

152-1406 in PTL

152-2106 in PTL

152-2406 in PTL

13 CBP in PTL

7. Set simulator time to real time, then place simulator in RUN.

8. Give crew briefing.

a. Present plant conditions: 100% load at MOC 10.885 MWD/MTU

b. Power history: Long term steady state for past 39 days

c. Equipment out of service:

lA DG removed from service for scheduled maintenance.

OC DG aligned to 11 4 KV Bus

13 CBP is emergency use only due to high vibes

d. Abnormal conditions: None

e. Surveillances due: STP 0-90-1 in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months

f. Instructions for shift: Maintain power

g. EOOS Risk: Low CDFl.43 LERF 1.47

h. Blowdown: Overboard at 100 gpm

9. Allow crew 3-5 minutes to acclimate themselves with their positions.

10. Instructions for the Booth Operator.

a. Once the crew accepts the watch use Fl to initiate PZR Instrument Failures

b. Once down power has begun for shutdown ofU-l use F2 to initiate failure of 12 Condensate Booster Pump.

c. approximately 4 minutes after 13 CBP is started, trip 13 CBP using F3

d. Approximately 5 minutes after crew aligns OC DG to 11 4KV bus use F4 to initiate electrical fault on 11 4KV Bus.

RESPONSES TO CREW REQUEST If a request and response is not listed, delay response until reviewed with the examiner. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.

REQUEST RESPONSE

1. OWC contact 1M shop, Rad Con, Matrix Acknowledge request notification.

2. PWS or PPO check ESF AS panel. After 3 minutes, report SIAS Pressurizer Pressure Channel ZF is reading low and tripped.

3. PWS bypass ZD SIAS PP. After 5 minutes, give ESFAS door alarm, then bypass SIAS ZD, then clear door alarm.

4. TBOIEM Shop check 12 CBP & Breaker After 3 min report pump is stopped but nothing else looks abnormal. After 5 min report breaker is tripped with dropped flags.

5. ESO how long until offsite power restored No idea at this time but will call when we find out

6. TBO shut MSR isolation valves and panel Acknowledge request loaders to zero

7. ABO open ADV's locally After 2 minutes adjust ADV's to requested position

8. TBO open 189-1106 and shut 189-1406 After 2 minutes open 189-1106, after another 3 minutes report problems with shutting 189-1406.

9. OWC have EM shop check 189-1406 After 10-15 min, shut 189-1406 and report

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 1 Page -L of J.Q Event

Description:

Instrument line failure causes multir;?le PZR level and r;?ressure instrument failures.

I {ATe) TS (SRO)

Time Position Applicant's Actions or Behavior RO Annonnr.f' mnltinl., alarms SRO Direct BOP to check ifRPS calling for a trip and ATC to monitor primary n

BOP RPS indications and determine RPS is not calling for a trip Monitors primary and recognizes PZR pressure is rising with no change in PZR ATC level or RCS temperature.

Reviews Alarm Response Manual (ARM) and recommends shifting PZR Pressure ATC Control to 100X and PZR heater low level cutout to X.

ATC Secures PZR BIU heaters using individual handswitches or shifts PZR Pressure Direct shifting PZR pressure control to 11 OX and PZR heater low level cutout to SRO channel X BOP/SRO Review CNG OP-I.O I-I 000 and/or system print to verify common tap analysis.

Review CNG OP-l.OI-IOOO and/or Tech Specs for proper actions to comply with Tech specs.

SRO

3.3.l.A

3.3.4.A

3.3.4.C

3.3.10.A Announce Containment Sump alarm and review ARM. Drain containment sump BOP lAW 01-17.

ATC Recognize RCS leakage due to lowering PZR level with minimum letdown.

SRO Implement AOP-2A Event conclusion is entry into AOP-2A

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 2 Page ..£.of J.Q Event

Description:

Instrument line leak increases to 20 g(2m ReS leak C (All} TS (SRO}

Time Position Applicant's Actions or Behavior Implement AOP-2A, make plant page announcement and announces trip criteria SRO and assigns to ATC.

Reports RCS leakage greater than capacity of one charging pump based on ATC lowering PZR level with LID at minimum.

BOP Drains containment sump and marks time to aid leak rate estimation BOP Ensures 2 nd charging pump auto starts or starts it manually SRO Confirms leak location & instruments affected using NO-1-200 or prints Direct ATC to control PZR level lAW block step VLC SRO Direct BOP to check for S/G tube leakage lAW VI.D Determines PZR level is being maintained within 15 inches of program. (No LID ATC isolation yet) and makes up to VCT as necessary BOP Determines no S/G tube leakae:e SRO Directs BOP to attempt to isolate leak lAW block step VI.E ATC Isolate LID by shuttine: CVC-5IS & 516 ATC Checks charging header for leakage (must go to single chg pp operation)

Determines leakage is inside containment and starts alI CAC's in fast speed with BOP emergency outlet valves open.

Determines a trip is not necessary due to leakage less than capacity of 1 charging SRO pump now that LID is isolated.

Proceeds to Section V "RCS Leakage within capacity of 1 charging pump" Determines leakage greater than allowed by TS 3.4.13 and commences shutdown SRO ofU-1.

SRO May direct restoration of letdown per Alternate Action VI.F.I ATC Mav restore letdown lAW 0l-2A Event conclusion is commencement of down power

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 3 Page~ of J.Q Event

Description:

Commence I2lant shutdown lAW OP-3.

R (ATC/SRO) N (BOP)

Time Position Applicant's Actions or Behavior Directs down power LAW OP-3. If SRO is concerned that leakage may increase then a rapid power reduction lAW Appendix B is appropriate. If a rapid power SRO reduction is not done then OP-3 section 6.4 should be used. (Steps shown below are for rapid downpower)

Borate RCS:

Open Boric Acid Direct Makeup valve CVC-514-MOV

Verify 2 charging pumps operating

Start Boric Acid pump for 30 seconds and shuts CVC-514-MOV.

Open RWT outlet to charging pump suction CVC-504-MOV

Shut VCT outlet valve CVC-501-MOV ATC Insert CEA's

Selects Manual Sequential Control

Insert Group 5 CEA's as necessary to support desired power reduction rate Initiate Boron Equalization

Energize all PZR Backup heaters

Adjust PZR Pressure controller I OOX to "" 2200 psia BOP Open Hi Level dump valves for 11 & 12 LPFW Heaters BOP Adjust turbine load to maintain Tcold within 5°F of program Tcold I '"'. _. -, n is trio of 12 CBP

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 4 Page...4.. of JQ Event

Description:

Loss of 12 Condensate Booster Pum!;! without Auto Start of standb~ CBP.

C (BOP/SRO)

Time Position Applicant's Actions or Behavior BOP Announce alarm and reference ARM SRO Implement AOP-3G determines proper section isSection V SRO Announces trip criteria (S/G level approaching -40) and assigns to ATC SRO Direct BOP to maximize SGFP suction pressure Maximize SGFP suction pressure

Place hotwell controller in manual at 50%

BOP

Open Condensate Precoat Sys bypass valve l-CD-5818-CV

Open Condensate Demin Sys bypass valve l-CD-4439-MOV SRO Direct start of 13 CBP BOP Starts 13 CBP SRO Notifies Chemistry that Condensate Precoats & Demins were bypassed.

SRO After 13 CBP trios, orders reactor trio Event conclusion is reactor trio Note: IF only 1 CBP is running it will trip on over current after 20 Seconds

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 5 Page ..Q.. of J..Q Event

Description:

Reactor Trig with loss of Offsite Power with failure of 1B DG M (All}

~

.... Applicant's Actions or Behavior ATC A Reactor is trinoed a Announces Reactor Trip and directs implementation ofEOP-O TC Perform Reactivity control safety Function (See Event 6 for actions)

Ensure Turbine trip:

Check Reactor tripped

Depress both turbine trip push buttons

Check Main Turbine Stop valves shut BOP 0 Shut MSIV's due to inability to determine stop valve position

Check turbine speed drops

Verify Turbine generator output breakers open

Send TBO to ensure MS-4017 & 4018 MOV's shut BOP Verify Vital Auxiliaries (See Event 7 for actions)

ATC Verify Pressure and Inventory Safety Function BOP Verify Core & RCS Heat Removal Safetv Function BOP Coordinate with ABO (via radio) control of ADV's for temperature control Note: 11 4KV bus will be lost 5 minutes after OC DG connected to 11 4KV bus SRO When 11 4KV bus is lost direct ATC & BOP to reverify Safety Functions

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 6 Page~ of J.Q Event

Description:

Two stuck CEA's on reactor tril2 C (ATC)

-, Position Applicant's Actions or Behavior ATe: nenre~~ ~et ofM::tmml Re::tctor Trin Pwmhllt on" ATC Check Reactor tripped by observing power & SUR ATC Announce U-I Reactor is tripped ATC Check CEA's fullv inserted Recognize 2 stuck CEA's (or inability to determine CEA position) and borates til 2300 ppm:

Ensure VCT MIU valve CVC-512 shut

Open BA Direct MIU valve CVC-SI4 ATC

Opens BAST Gravity Feeds CVC-50S & 509 MOV's (Critical)

Verify Makeup Modes Selector HS-210 in manual

Start a Boric Acid Pump

Shut VeT Outlet valve CVC-501-MOV

Start a~l available charging pumps Verify DI water MIU secured:

11 & 12 RCMU PP's secured ATC

VCT Makeup valve CVC-S12-CV is shut

Recognize not in direct lineup and leaves RWT charging pump suction CVC-504 open.

ATC Reports Reactivity Control complete.

Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 7 PageLof J.Q Event

Description:

1 S DG Auto Start failure C (SOP) e Position Applicant's Actions or Behavior Checks 11 or 14 4KV bus is energized:

Emergency start OC DG

Attempts to start IB DG (pushes emergency start button)

BOP

Verifies OC DG operating

Verify shut OC DG disconnect to 11 4 K V Bus 189-1106 shut

Verify OC DG output breaker 152-0703 is shut

Close 07 4 KV bus tie breaker 152-0701

Insert sync stick and close OC DG to 11 4 KV Bus 152-1106 BOP Check all 125 VDC buses> I OS VDC BOP Check at least 3 120 VAC buses ener!!ized BOP Check either 1Y09 or 1YlO energized Verify CC flow to the RCP's BOP

Starts 11 CC pp due to not getting start signal on shutdown sequencer BOP Dispatch ABO to verify switchgear room ventilation in service IA W 0I-22H BOP Reports Vital Auxiliaries complete Event conclusion is loss of 11 4KV bus (Station Balckout)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: _8_ Page JL of .1Q Event

Description:

Loss of 11 4KV bus {Station Blackout)

M {All) TS (SRO) e Position Applicant's Actions or Behavior SR() Direct ATC & BOP to re-verify Safety Functions ATC Reports Reactivity Control "Not Met" due to unable to borate due to loss of power BOP Reports Turbine trip complete Verify Pressure and Inventory Control

Check PZR press between 1850-2300 psia, trending to 2250 psia ATC

Check PZR level stabilizes between 80-180 inches trending to 160 inches

Ensure RCS subcooling >30°F Reports Pressure & Inventory as not met due to lowering PZR pressure and level Verify Vital Auxiliaries Safety Function

Recognize II 4KV bus faulted and reports to SRO BOP

Attempts to re-align OC DG to 144 KV bus (OSO reports 189-1406 disconnect problem)

Reports Vital auxiliaries cannot be met due to no 4 KV bus & 1Y09 & 10 not energized Verify Core & RCS Heat Removal Safety Function

Directs ABO to open ADV's manually (0:::.40%) and reports position to SRO BOP

Start 11 AFW pump due to loss of main feed water

Trip SGFP and shut S/G Feed Isolations Reports Core & RCS Heat Removal as not met due to no operating RCP's Verify Containment Environment Safety Function

Check pressure < 0.7 psig BOP/ATC

Check temperature < 120°F

Check radiation monitor alarms clear with no unexplained rise Reports Containment Environment as not met due to inability to assess due to power loss Verify Rad Level External to Containment Safety Function

Check RMS alarms clear with no unexplained rise BOP/ATC

Secures S/G Blowdown due to inability to assess Reports Rad Levels External to Containment as not met due to inability to assess SRO Brief crew on status of all Safety Functions & Actuations References Diagnostic Flowchart and Implements EOP-8 due to RCS leak with SRO Station Blackout

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 8 (cont) Page Jl of J.Q Event

Description:

EOP-8 Entrv due to to ReS leakage with station Blackout Time Position Applicant's Actions or Behavior

~RO Direct A Tr to r~

Rrp trin ;;tllte!>v SRO Contact Chemistry to monitor S/G activity and Containment Hydrogen Levels SRO Direct ATC & BOP to identify success paths per Resource Assessment Table Recommends RC-l Met due to no 4KV buses with WRNI <)0-4 and negative ATC SUR Recommends VA-3 Not Me due to no DG available and no 4KV buses (May BOP recommend V A-2 Not Met due to OC DG available but not able to be loaded on a bus currentlv with no 4 KV buses)t BOP Commences working on VA-3 (or VA-2) immediately Recommends PIC-3 Met due to no 4KV buses, No SIAS, subcooled margin>

ATC 25°F and RVLMS indicates core is covered. (IfSIAS has actuates then PICA Not Met and starts working immediately)

RecommendsHR-l Met due to No SIAS and AFW operating to keep subcooled ATC margin> 25°F and R VLMS indicates core is covered (If SIAS actuates then SRO must evaluate and determine HR-2 Not Met since ATC would be working PICA)

Recommends CE-l Met due to containment pressure < 2.8 psig and no ATC unexplained radiation alarms in containment with temperature <220°F Recommends RLEC-J Met due to normal rad levels and no alarms with ATC unexplained rise Performs VA-3 Appendix:

Align Electrical System for power restoration (This step is similar in both VA-2 & VA-3) 0 Ensure normal & alternate feeds open to 14 4KV bus 0 Verify 14 4KV bus vital load breakers open

12 LPS! pump BOP

12 & 13 SW pumps

12 CS pump

12 & 13 HPSI pumps

13 SRWpump 0 Place 14 4KV bus LOCI/SD Sequencer key switch is on

When report comes in that E&C has repaired disconnect 189-1406, recommend to SRO to switch to VA-2

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: _1!...-_ Event No.: 8 (cont) Page .1Q. of JQ Event

Description:

EOP-8 Entry due to to ReS leakage with station Blackout

.~==~~*~*~==~==============JA~~P~PII~iC~a~n!t'~SJA~c~t~io~n~s~o~r~B~e~ha!v~i~o~r==============~1 Perfonns PIC-l Appendix ATC

Verify a charging path is available, so when power is restored then charging flow can be restored When report comes in that E&C has repaired disconnect 189-1406, direct BOP to SRO switch to VA-2 and align OC DG to 144 KV bus Perfqrms YA-2 Appendix:

Align electrical syste~s for power restoration o Ensure nonnal& alternate feeds open to 14 4KV bus o Verify 14 4KV bus vital load breakers open

12 LPSlpump

12 & 13 SW pumps

12CS pump BOP

12 & 13 HPSI pumps (Critical)

13 SRWpump o Place 144KV bus LPPlISD Sequencer key switch is on

Verifies 07 4KV Bus. 152-0704 breaker is open

Vet;~fy OC DO outputbreaker 152-0703 is shut

Verifies OC DO disconnect to 14 4 KV bus is 189-1406 is shut

Close 0.7 4 KV Bus Tie breaker 152-0701

Insert synestick and close OC DG. to 14 4KV bus breaker152-1406 Note: Ask as scenario follow up Tech Spec LCO in effect with LOOP, 11 4KV bus faulted & 14 4KV bus energized from OC DG:

3.8.l.A, B, D, G, H, I, K SRO

3.0.3

3.8.9.A ERPIP call H.S.2.1.3 Station Blackout> 15 minutes

Appendix 0 Scenario Outline Form ES-D-l Facility: CCNPP Scenario No.: _2_ Op-Test No.: 2010 Examiners: Operators:

Initial Conditions:

U-1 is at 100% ~ower EOC, 15,500 MWO/MTU with long term stead~ state ~ower histor~. U-2 at 100% ~ower MOC Turnover:

11 HPSI Pum~ is removed from service for scheduled maintenance (return in 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months s}. 13 CCW ~um~

ra is OOS for work on 3 ~um~ disconnect. 13 CBP is for emergenc~ use onl~ due to high vibrations.

Instructions for the shift is to remain at 100% ~ower.

Event Event Malf. No. Event Type*

No. Description 1 CNTMOOI 04 TS (SRO) 14 Containment Air Cooler failure C (BOP/SRO) 2 TG017 Turbine vibration on bearing 4 R(ATC)

C (ATC) l-CVC-SI4-MOV breaker failure & l-CVC-S08-MOV, l-CVC 3 Various TS (SRO) S09-MOV fail to open.

4 TGOOI C(ALLJ Turbine trip RPSOOS, S RPS006 & C (ATC) RPS & Manual Trip Pushbutton failure DSS failure 6 CCW002 01 C (BOP) 11 Component Cooling Pump failure 7 RCS022 M (ALL) Pressurizer Safety Valve fails to reseat (leak on top ofPZR) 8 ESFAOOI 02 I (BOP) SIAS B failure

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks (bold):

Trip Reactor from electrical panels due to ATWS

Trip all Rep's due to no cooling prior to exceeding temperature limits

Manually actuate SIAS B prior to superheat

Op-Test No.: 2010 Scenario No.:

SCENARIO OVERVIEW ATWS WITH PZR SAFETY VALVE LEAKAGE Initial Conditions: U-l is at 100% power EOC 15,500 MWD/MTU with long term steady state power history. U-2 at 100% power MOC. 11 HPSI pump is removed from service for scheduled maintenance and will be returned in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . 13 CCW pump is OOS for work on480V disconnect. Instructions for the shift are to maintain power @ 100%.

Scenario starts with a trip of 14 Containment Air Cooler which requires entry in TS 3.6.6.C.

Also consideration should be made to start 13 CAC to maintain containment cooling.

Turbine bearing #4 a vibration problem develops, causing entry into AOP-7E. Crew must keep track oftime when vibration exceeds 10 mils (due to 15 minute limit for trip criteria). Vibration stabilizes at approximately 11 mils which will require a rapid downpower to attempt to lower vibration prior to exceeding 10 mils for 15 minutes.

When lining up for rapid downpower l-CVC-514-MOV will fail due to breaker trip, and Gravity Feed MOV's fail to open (due to over tight packing) requiring the crew to use a non-preferred method ofboration. Reducing power will have some affect on turbine vibration but not enough to avoid a trip. When crew is within 2 minutes of trip criteria the turbine will trip on its own due to vibration related problems.

When the turbine trips, RPS will be calling for the reactor to trip but due to a failure, both auto trip (including DSS) and manual pushbuttons fail. EOP-O ATWS actions (opening breakers at 1C18 & 1CI9) will trip the reactor.

Once the reactor is tripped a PZR safety valve will start to leak due to overpressure and 11 Component Cooling Pump will fail. The BOP attempts to start 12 CCW pump to provide cooling to RCP's, when it fails he must secure all RCP's. The ATC will shut PORV block valves due to flow readings for both PORV's & Safety Valves. When RCS pressure lowers to SIAS setpoint the A TC should verify SIAS and at that time manually initiate SIAS B and secure 2 RCP's. Pressure and Inventory will be reported as Not Met due to low PZR pressure and high PZR level. The CRO should recognize trends on containment pressure and temperature and take alternate action to increase cooling and eventually call Containment Environment as Not Met.

CRS will follow EOP-O flow chart and transition to EOP-5.

In EOP-5, the ATC will shut letdown isolation valves and verify PORV block valves shut in step IV.F Leak Isolation. The crew will also commence a cooldown using S/G's and also depressurize in an attempt to lower the leak rate. The scenario will end when cooldown is commenced.

INSTRUCTOR SCENARIO INFORMATION

1. Reset to IC-24

2. Perform switch check.

3. Place simulator in RUN, advance charts and clear alarm display.

4. Place simulator in FREEZE.

5. Enter Malfunctions/ Triggers

a. 14 Containment Air Cooler Failure CNTMOOI 04 on Fl

b. Main Turbine Bearing 4 high vibrations TGOl7 (7-11.5) over 5 min on F2

c. CVC-514-MOV HIS to Open as T-l

d. CVC-514-MOV HIS to close on T-l

e. CVC-514-MOV HIS lights to out on T-l

f. Main Turbine trip TGOl7 onF3

--g. RPS Failure to trip Reactor RPS005 & RPS006 at Time Zero

h. DSS failure to trip Reactor

i. CEA 01 on bottom as T-2

--j. 11 component cooling pump failure CCW002 01 on T-2

k. Pressurizer safety valve fails to reseat RCS022 (0-25) over 5 min on T-2 I. SIAS B failure ESFAOO 1 02 at Time Zero

6 Enter Panel Overides

a. Place 11 HPSI Pump in PTL with yellow tag

b. Override alarm H -17 "11 HPSI PP SIAS Block Auto Start" and place red dot on window

c. Place 13 CCW pump in PTL with yellow tag

d. Override 12CCW pump in PTL, with green off light lit.

e. CVC-508-MOV HIS to close at Time Zero

f. CVC-509-MOV HIS to close at Time Zero

7. Set simulator time to real time, then place simulator in RUN.

8. Give crew briefing.

a. Present plant conditions: 100% load at EOC 14.885 MWD/MTU

b. Power history: Long term steady state for past 16 days

c. Equipment out of service:

11 HPSI removed from service for scheduled maintenance.

13 CCW Pump OOS for work on 480V disconnect

d. Abnormal conditions: None

e. Surveillances due: None

f. Instructions for shift: Maintain power

g. EOOS Risk: Low CDF 1.76 LERF 1.79

h. Blowdown: Overboard at 100 gpm

9. Allow crew 3-5 minutes to acclimate themselves with their positions.

10. Instructions for the Booth Operator.

a. Once the crew accepts the watch use Fl to initiate trip of 14 CAC.

b. Once Tech specs reference and brief is complete then use F2 to initiate high vibrations on Main turbine bearing #4.

c. After crew lowers Reactor power <90% use F3 to trip Main Turbine.

RESPONSES TO CREW REQUEST If a request and response is not listed, delay response until reviewed with the examiner. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.

REQUEST RESPONSE

1. OWC contact EM shop, Matrix notification. Acknowledge request

2. TBO check 14 CAC breaker. After 3 minutes, report breaker is tripped but otherwise looks normal.

3. TBO man panel unloaders for down power. Acknowledge request.

4. ABO check eVC-514-MOV valve & breaker After 3 min report breaker appears tripped, after another 3 minutes report valve looks shut.

5. owe notify EM shop about eVC-514-MOV Acknowledge request breaker trip

6. ABO check 11 CC pump After 3 minutes report pump is not running but otherwise appears normal

7. OWC contact EM shop about 11 CC pump Acknowledge request trip

Appendix 0 ReQuired Operator Actions Form ES-p-2 Op-Test No.: 2010 Scenario No.: _ 2_ Event No.: _1_ Page -.1.. of .1Q Event

Description:

14 Containment Air Cooler (CAC) fails TS (SRO)

Time Position Applicant's Actions or Behavior BOP Announce alarm R-4 "U-I 480V ESF UN Trip" ATC Announce plant computer alarm for 14 CAC tripped SRO Reference Tech Specs and determine not meeting LCO 3.6.6.C BOP Align Service Water to 13 CAC lAW 0I-5A using I-HS-1591 BOP Start 13 CAC lAW 0I-5A using I-HS-5301 BOP Secure Service Water to 14 CAC using 0I-5A using I-HS-1594 SRO Contact work control for EM support and matrix notification Event conclusion is hi2h vibration bearin2 4 Main Turbine

Appendix 0 Required Operator Actions Form ES-P-2 Op-Test No.: 2010 Scenario No.: _2_ Event No.: Page.£ of 10 Event

Description:

High vibration on bearing #4 of Main Turbine C (BOP/SRO) R (ATC)

Time Position Applicant's Actions or Behavior BOP Announce alarm B-3 "Turbine Vibration" VerifY alarm valid by observing both X & Y probes reading high, and adjacent BOP bearing also elevated Implement AOP-7E "Main Turbine Malfunctions" and make plant page SRO announcement Announce trip criteria "12 mils or 10 mils for> 15 minutes", and assign trip SRO criteria to the BOP SRO Assign block step V.A to BOP Coordinate with the TBO to get Condenser Vacuum Breaker breaker 52-11618 BOP shut. (BOP holds HS for l-CAR-6717 in close while breaker is shut.

Coordinate with the Electrical System Operator to get reactive load reduced to BOP zero. When ESO gives permission then lowers Main Generator output voltage until V AR's read zero.

Direct ATC & BOP to perform rapid down power to reduce turbine loading to SRO reduce vibration Commences rapid down power procedure lAW OP-3 (See Event 3 for CVC-514 ATC failure actions)

Places all PZR heater handswitches to ON, lowers setpoint of on service PZR ATC Pressure Controller PIC-l OOX to 2200 psi a to equalize boron When RCS Tcold lowers to <537° F, lowers turbine load to maintain RCS Tcold within 5° F of program Tcold (5° is upper limit, should be maintained with 2° F):

BOP

Uses manual Turbine Load Set handswitch l-CS-80

Uses keyboard to set 3% minute ramp rate and puts turbine in auto After ensuring BOP is ready, insert CEA's as follows:

ATC

Selects Manual Sequential pushbutton at 1C05

Moves CEA Control Handswitch to lower position while observing multiple indications of Reactor Power.

Appendix 0 Required Operator Actions Form ES.p-2 Op-Test No.: 2010 Scenario No.: _2_ Event No.: Page ~ of 10 Event

Description:

Failure of CVC-514-MOV (Boric Acid Pump discharge to Charging Pump suction) and CVC-508 & 509 (BAST Gravity Feed MOV's) also fail C (ATC) TS (SRO)

POSition Applicant's Actions or Behavior ATC Takes Handswitch for CVC-514-MOV to open Recognizes indicating lights for CVC-514-MOV go out prior to open indication, ATC reports to SRO it appears MOV breaker has tripped.

Transitions to alternate method for borating to RCS:

Attempts to open II or 12 BAST Gravity Feed MOV's (fail to open due to over tight packing)

ATC

Starts a second Charging Pump (12 or 13)

Opens RWT outlet to Charging Pump Suction CVC-504-MOV and shuts VCT Outlet CVC-50 I.

ATC Rest of down power procedure actions are included with Event 2 SRO Enter TRM 15.1.2 Boration Flowpath Event conclusion is Main Turbine trip

Appendix D ReQuired Operator Actions Form ES-P-2 Op-Test No.: 2010 Scenario No.: _ 2_ Event No.: _4_ Page~ of 10 Event

Description:

Main turbine trip due to vibration induced event C (All)

Position Applicant's Actions or Behavior Recognize and announce "Main Turbine trip" BOP

BOP should verify vibration did not drastically rise >50mils SRO Order ATC to trip Reactor and implement EOP-O ATC Pushes Reactor trip pushbuttons on I C05 ATC Recognize ATWS and announce to SRO (ATWS actions listed in Event 5)

Ensure Turbine Trip:

Ensure Reactor tripped, then depress both Turbine Trip buttons

Check Main Turbine Stop Valves shut BOP

Check Turbine speed drops

Verify Turbine Generator breakers open

Ensure MSR 2nd stage MOV's shut Reports Turbine Trip is complete Verify Vital Auxiliaries:

Check 11 or 14 4KV Bus energized BOP

If either 11 or 14 4KV Bus de-energized then start OC DG

Check 125VDC & 120VAC buses energized

Check either 1Y09 or 1Y 10 energized

Verify Component Cooling flow to RCP's (See Event 6 for actions)

Event conclusion is EOP-O entry and recognition of ATWS

Appendix 0 Reguired Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: 2 Event No.: 5 Page..§.. of 10 Event

Description:

RPS, DSS, & Manual Pushbutton Reactor Trip Failure C (ATC) TS (SRO)

Position Applicant's Actions or Behavior ATC Depress ONE set of Manual REACTOR TRIP buttons.

Recognize Reactor NOT tripped:

Open 12A 480V BUS FDR

Open 12A-12B 480V BUS TIE

Open 13A 480V BUS FDR ATC

Open 13A-13B 480VBUS TIE Critical Task Checks Reactor tripped by observing power indications at ICtS Energizes 12A & 13A 480VBttses by shutting the two breakers that were originally shut:

12A 480V BUS FDR

13A 480V BUS FDR ATC ~hecks to ensure all CEA' s inserted Verifies no DI water aligned as makeup to the RCS:

ATC

11 and 12 RC MIU PPs are secured

VCT MIU valve, l-CVC-512-CV, is shut ATC Reports Reactivity control Complete Event conclusion is commencement of EOP-O Vital Auxilliaries

Appendix 0 Required Operator Actions Form ES-P-2 Op-Test No.: 2010 Scenario No.: _2_ Event No.: _6_ Page.§... of 10 Event

Description:

11 Component Cooling pump failure C (BOP)

Time Position Applicant's Actions or Behavior Verify Component Cooling flow to the RCP's:

BOP

Recognize 11 CCW pump not running

Attempts to start 11 and 12 CCW pump BQP Component Cooling now cannot be verified to RCP's:

Critical Task

Secures all RCP's using HIS's at lC06 Reports Vital Auxiliaries cannot be met due to no Component Cooling Water BOP supplied to RCP's

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: _2_ Event No.: _7_ Page of J.Q Event

Description:

Pressurizer Safety Valve fails to reseat (ReS leak on top of PZR)

M(AII)

, Time Position Applicant's Actions or Behavior Verity Pressure and Inventory Control:

Check pressure 1850-2300 psia trending to 2250 psia

Verifies all PZR heaters on and spray flow is secured (No RCP's)

IfPZR press <2300 psia and PORV cannot be verified closed (acoustic monitor indication) then:

o Shut PORV Block valve RC-403-MOV o Places PORV 402 Override in "Override to close"

IfPZR Press lowers <1725 psia, then verity SIAS (see event 8)

ATC

Verifies RCP's secured (BOP secured for no CCW pump)

Checks PZR level between 80 & 180 inches, trending to 160 inches o IfPZR level low and trending lower, then isolate letdown o IfPZR level high and trending higher then secure charging pumps one at a time (Discuss with SRO prior to securing fmal pump)

Ensurf: RCS subcooling >30 0 F

Reports RCS Pressure & Inventory not met due to low RCS pressure Verity Core & RCS Heat Removal safety Function

Verify TBV's or ADV's maintaining SIG press 850-920 psia and Tcold 525-535° F

Verity at least 1 S/G available for heat removal:

o SIG level (-)170 -(+)30 inches BOP o Main or Auxiliary Feed operating o Tcold >525° F

Check at least one RCP in loop with available SIG

If any RCP's operating ensure RCS 8.T <10 0 F

Reports Core & RCS Heat Removal cannot be met due to no operating RCP's.

Verity Containment Environment Safety Function:

Check containment pressure <0.7 psig:

o If>0.7 psig then verity all CAC's running with max SRW flow o If>2.8 psig then verity CIS & SIAS (not expected at this time)

Check containment temp < 120 0 F BOP/ATC o If>120° F then verity all CAe's running with max SRW flow

Check containment radiation alarms clear with no unexplained rise:

o If any alarms received then start all IRU's (not expected)

Reports Containment Environment Safety Function as Not Met due to containment pressure negative trend

Verify Radiation Levels External to Containment Safety Function; BOP/ATC

Check RMS alarms clear with no unexplained rise

Report Radiation Levels External to Containment is complete Hold crew briefing covering:

VA not met due to no operating CC pumps SRO

PIC not met due to low RCS press (maybe high PZR level)

HR not met due to no operating RCP's

CE not met due to containment pressure trends

SIAS actuation (SIAS B failure)

SRO Review Diagnostic flowchart and determines EOP-5 is correct path SRO Implements EOP-5, hold entry brief, assigns block steps to A TC & BOP Block step D "Monitor Depressurization" ATC

Uses Attachment 10 to verify HPSI flow is consistent with pump curve Block Step F "Attempt Leak Isolation";

Verifies LID isolation valves shut (CVC-515 & 516)

Checks for PORV leakage (leakage is present from RV) 0 Verifies PORV Block valve RC-403-MOV shut 0 Verifies PORV 402 Override handswitch in "Override to Close" BOP

Shut RCS Sample valve PS-5464-CV

Shut Reactor Vessel Vent valves RC-I03 & 104-SV's

Shut PZR vent valves RC-I05 & 106-SV's

Checks no leakage into CC system

Verifies leak is inside containment Block Step G "Maintain Containment Environment";

If containment pressure >2.8 psig then verify SIAS & CIS

If CIS actuated then ensure all RCP's secured BOP

Contact TBO to verify SRW pump room ventilation in service

If containment pressure >4.25 psig the verify CSAS (not expected)

Direct Chemistry to place Hydrogen Monitors in service

Verify all CAC's, at least one Cavity Cooling, at least one CEDM Cooler, and all PZR Vent fans are running

Block Step H "Commence Boration":

Verify SIAS actuated, then:

0 VCT Makeup CVC-SI2-CV shut 0 Boric Acid Direct Makeup CVC-514 open (breaker tripped earlier), directs ABO to manually open ATC 0 BAST Gravity Feed valves CVC-50S & S09-MOV's open, MOV's failed to open earlier, send ABO to manually open 0 All available Boric Acid pumps running 0 VCT Outlet valve CVC-50l-MOV is shut 0 All available Charging pumps operating Block step I "Commence Cooldown" BOP

Block SGIS when Block Permitted alarms are received

Commence cooldown to < 3000 Fusing TBV's (if available, may be lost due to SIAS causing vacuum to go away) or ADV's Event conclusion is SIAS actuation

Appendix P ReQuired Operator Actions Form ES-P-2 Op-Test No.: 2010 Scenario No.: _ 2_. Event No.: _8_ Page ~ of -.1Q Event

Description:

SIAS B failure (with 11 HPSI tagged out for maintenance)

I(ATC)

Time Position Applicant's Actions or Behavior SRO/BOPIATC Recognizes SIAS actuation and announces to the crew ATC SIAS actuated due to low RCS pressure therefore ATC should verify SIAS Verify SIAS:

Verify SIAS valid by checking RCS pressure

Verifies 11 & 13 BPSI pumps running 0 Recognizes 11 HPSI tagged out & 13 BPSI not running ATC 0 Reports failure ofSIAS B to SRO Crtical Task 0 Pushes SIAS B manual actuation pushbutton on 1C10 0' Verifies 13 BPSI pump running

Verifies all 8 HPSI header MOV's open

Reports SIAS verified to SRO After scenario ends ask SRO for ERPIP call. Alert H.A.5 .1.2 due to excessive SRO RCS leakage> capacity of charging pumps

Appendix 0 Scenario Outline Form ES-O-1 Facility: CCNPP Scenario No.: 4 Op-Test No.: 2010 Examiners: Operators:

Initial Conditions:

U-1 is at 100% power MOC 10,885 MWD/MTU long term steady state, U-2 is at 100% power EOC.

Turnover:

13 4kv bus aligned to alternate feed while normal feed breaker 152-1311 is OOS for scheduled maintenance.

Event Event Malf. No. Event Type*

No. Description C (SRO/BOP) 1 MS009 01 TBV 3940 fails open R(ATC) 2 480vOOI 04 C (SROIBOP) 12B 480V bus failure 3 CVCS003 01 C (ATe) 11 Charging Pump coupling failure I (BOP) 4 ESFA009 02 Spurious CIS B Actuation TS (SRO) 5 CVCS009 I (ATC) VCT level transmitter fails high 6 CCW003 C (All) Component Cooling leak in the containment M (All) 7 MS002 02 12 S/G tube rupture TS (SRO)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)aior Critical Tasks (bold):

Secure RCP's prior to exceeding temp limits.

Isolate S/G in EOP-6

Depressurize RCS to minimize leakage

Op-Test No.: 2010 Scenario No.: _4_

SCENARIO OVERVIEW CC LEAK & S/G TUBE RUPTURE Initial Conditions: U-l is at 100% power MOC 10,885 MWD/MTU long term steady state, U-2 is at 100% power EOC. 13 4kv bus aligned to alternate feed while normal feed breaker 152-1311 is OOS for scheduled maintenance.

The scenario starts with a failure ofTBV 3940 causing an overcooling event requiring entry into AOP-7K. Crew must control power <100% by unloading turbine and inserting CEA's, then isolate the affected TBV.

A loss of 12B 480V bus occurs next. The crew will implement AOP-7I, tying MCC-I06 to MCC 116 and verifying pumps and fans running.

When 11 charging pump coupling fails proper alarm response (F-46) should have ATC start 12 or 13 charging pump prior to losing letdown due to high temp. After another charging pump is started the crew should consult OI-2A for proper positioning of charging pump selector switch.

A spurious actuation of CIS B isolates component cooling to RCP's. When crew verifies containment pressure <2.8 psig they should reset CIS B lAW alarm manual using EOP Attachments.

When CIS is reset the crew should reinitiate cooling to RCP's by opening CC isolation valves. When component cooling is re-established to the containment a slow leak develops in the component cooling system.

VCT level transmitter failing high causes letdown to be diverted to waste processing, ATC will position Diversion valve from Auto to VCT which should align system back to normal.

When component cooling is re-established to the containment a leak develops in the component cooling system. AOP-7C should be implemented which leads to isolating the leak which will require tripping reactor and securing all RCP's after Reactivity Control is completed.

When the reactor trips EOP-O will be implemented and after reactivity control is complete the ATC will secure all RCP's. Trip transient will also cause a S/G tube rupture in 12 S/G which will force alternate actions for both Pressure and Inventory Control. At completion of EOP-O the SRO should select EOP-6 using EOP-O diagnostic flow chart.

When EOP-6 is entered the ATC should be assigned monitoring RCS Depressurization which will align Safety Injection in preparations for blocking SIAS. RCS boration will also be started and a rapid cooldown of the RCS to <515 Thot will be commenced. BOP should recognize that TBV 3940 is isolated so controller manual output signal must be 25% higher for same cooldown.

Once Thot <515, the BOP should slow the rate of cooldown and commence isolating 12 S/G lAW EOP-6. When 12 S/G is isolated the scenario will end.

INSTRUCTOR SCENARIO INFORMATION

1. Reset to IC-I7

2. Perform switch check.

3. Place simulator in RUN, advance charts and clear alarm display.

a. Ensure 12 CEDM Fan running

b. Ensure only 11 & 12 CAR's operating (secure 14 CAR)

c. Lower VCT level to approximately 95-97"

d. Align 13 4KV bus to alternate feed

4. Place simulator in FREEZE.

5. Enter Malfunctions! Triggers

a. TBV 3940 fails open MS009 on Fl

b. 12B 480V Bus failure 480vOO 1 040n F2

c. II Charging Pump coupling failure CVCS003 Oion F3

d. Spurious CIS B actuation ESF A009 02 on F4

e. VCT level transmitter fails high CVCS 009 high on F5

f. CCW leak in Containment CCW003 0-3% over 5 minutes on F6

g. CEAOI on bottom set as Tl

h. 12 S/G tube rupture MS002 _02 (1 tube) on Tl

6 Enter Panel Overides

a. 13 4KV Bus Normal Feeder breaker in PTL with yellow tag.

7. Set simulator time to real time, then place simulator in RUN.

8. Give crew briefing.

a. Present plant conditions: 100% load at MOC 10.885 MWD/MTU

b. Power history: Long term steady state for past 52 days

c. Equipment out of service:

13 4KV Bus normal feeder breaker OOS for scheduled maintenance.

d. Abnormal conditions: None

e. Surveillances due: None

f. Instructions for shift: Maintain power

g. EOOS Risk: Low CDF 1.16 LERF 1.19

h. Blowdown: Overboard at 100 gpm

9. Allow crew 3-5 minutes to acclimate themselves with their positions.

10. Instructions for the Booth Operator.

a. After crew assumes the watch use Fl to fail TBV -3940 open.

b. After TBV isolation is shut and crew has a brief use F2 to fail12B 480V Bus

c. After crew ties MCC-106 & 166 use F3 to fail 11 charging pump coupling.

d. Once CVCS returned to normal use F4 & F5 to give spurious CIS B actuation and the VCT transmitter failure.

e. Delete CIS malfunction immediately to allow reset

f. After the crew has reset CIS and initiated CCW flow to containment use F6 to initiate the CCW leak in the containment

RESPONSES TO CREW REQUEST If a request and response is not listed, delay response until reviewed with the examiner. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.

REQUEST RESPONSE

1. TBO check TBV 3940 After 3 minutes report valve is open, no apparent reason

2. Shut MS-120 to isolate TBV-3940. Shut MS-120 as requested

3. OWC direct EM to check 12B 480V Bus After 10 min report bus is grounded.

4. PPO/TBO tie MCC 106 & 116 After 5 min report ready to tie buses. Override SGFP A oil pump HIS's to off prior to tying bus using remote function.

5. ABO check II charging pump After 3 minutes report coupling failure

6. OWC direct 1M to evaluate CIS failure at Acknowledge request.

ESFAS

7. ABO check M/u to CCW Head Tank After 3 minutes report MIU valve open 8 TBO shift 12 ADV to IC43 with 0% output. After 3 minutes perform and inform Control Room

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: 3... Event No.: Page.L of 12 Event

Description:

TBV 3940 fails open C (SRO/BOP) R(ATC)

. Position Applicant's Actions or Behavior T. A l>. D.

!!!,to SRO BOP Recognize TBV-3940 failed open and reports to SRO SRO Implements AOP-7K due to overcooling event Assigns trip criteria to ATC:

SRO

Reactor trip imminent

Tcold <515 0 F Direct ATC to control Reactor Power < 100% by:

SRO

Insert CEA's as necessary to control power

Borate via fast boration to control power Control Reactor Power < 100% by:

ATC

Insert CEA's as necessary to control power

Borate via fast boration to control power SRO Direct BOP to lower turbine load to maintain Tcold on program Lowers turbine load using Load Set HIS l-CS-80, to raise Tcold back to program BOP without exceeding 5480 F BOP Direct TBO to investigate TBV-3940 and standby to isolate SRO When plant is stable direct BOP to work with TBO to get TBV isolated.

Direct shutting TBV isolation valve MS-120 while adjusting turbine load to BOP maintain temperature constant SRO Review Tech Specs for any reQuired entries

Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: ~ Event No.: _2_ Page .£of 11 Event

Description:

12B 480V bus failure C(SRO/BOP)

Time Position Applicant's Actions or Behavior ATC/BOP Recognize multiple alarms and report to SRO SRO Direct ATC to monitor the primary and BOP to check RPS for a trip BOP Checks RPS and reports "RPS not calling for a trip" BOP Checks electrical buses and reports loss of 12 B 480V bus Implements AOP-7I and directs BOP to perform Block step IV.A to verify failed SRO bus BOP Determines only 12B 480V Bus is lost and reports DeterminesSection XV appropriate for 12B 480V Bus and direct BOP to perform SRO stepXV.A BOP Directs TBOIPPO/OWC to tie MCC-I06 to MCC-116IAW AOP-7I XV.A.3 Performs remainder of Block step A:

Verify Emergency H2 Seal Oil Pump running BOP

Place 11 & 12 CAR's in PTL and starts 13 & 14 CAR's

Verifies 12 CEDM fan running

Verify 12 Gland Exhaust Blower in operatin SRO Directs OWC to have EM shop investigate loss of 12B 480V bus

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: ~ Event No.: _3_ Page .l.. of .16 Event

Description:

11 Charging Pump coupling failure C (ATC)

Time Position Applicant's Actions or Behavior ATC Recognize & report alarm F45 "CHG HDR FLOW LO, PRESS LO" ATC Recognize and report II Charging pump amps low and charging header low flow IA W Alarm Response Manual direct ATC to start 12 or 13 Charging pump and SRO place II Charging pump in PTL ATC Start 12 or 13 Charging Pump and secure 11 Charging pump Review 0I-2A for shifting charging pumps and place Backup Charging Pump ATC Selector Switch to "13 & 11" Eosition BOP Direct ABO to check 11 Charging pump locally SRO Direct OWC to contact Mechanical Maintenance to check 11 Charging pump

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: ~ Event No.: _4_ Page...4.. of 12 Event

Description:

Spurious CIS B Actuation I (BOP) TS (SRO) e Position Applicant's Actions or Behavior AT Recognize & Report CIS Actuation alarm SRO Direct A TC to monitor primary and BOP to investigate CIS alarm BOP Determine and report CIS actuation is invalid due to normal containment pressure BOP Review alarm manual and recommend resetting CIS SRO Direct resetting invalid CIS alarm using EOP Att. 4 Match "*,, handswitches :

CC-3832-CV & CC-3833-CV BOP

IA-2080-MOV Reset CIS by depressing CIS rest push buttons on 1C09 & 1C 10 After CIS is reset open valves shut during rest IA W ARM to restore CC & IA to the containment.

Direct ATC to monitor RCP temperatures and trip criteria lAW ARM for RCP SRO Aux Status Panel alarms due to no CC flow to RCP's ATC Monitor RCP temperatures on Plant Computer SRO TS call LCO 3.3.5.C for one logic channel OOS

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: ~ Event No.: _5_ Page ~of.1l Event

Description:

VCT level transmitter fails high I (ATe)

Time Position Applicant's Actions or Behavior ATC Recognize and report Low VCT level alarm F-ll Refer to ARM for alarm window F-II and recognize CVC-500 is diverting to ATC WPS and requests permission to place CVC-500 to VCT position SRO Direct A TC to place CVC-500 in VCT position ATC Places CVC-500 in VCT position and verifies valve changes position.

ATC Prepare to fill VCT lAW 0I-2B SRO Direct OWC to contact 1M shop to determine cause for CVC-500 failure to WPS

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: ~ Event No.: _6_ Page..§.. of 12 Event

Description:

Component Cooling leak in the containment C (All)

Time Position Applicant's Actions or Behavior BOP Recognize & report containment sump alarm BOP Monitor containment parameters and report no abnormalities.

BOP Reference ARM and drain containment sump lAW 01-17 BOP Recognize & report low Component Cooling Head Tank alarm SRO Implement AOP-7C Direct ATC to monitor for trip criteria:

RCP upper or lower thrust bearing temp> 195 0 F SRO

RCP upper or lower guide bearing temperature> 195 0 F

RCP controlled Bleed-Off flow temperature>200° F SRO Direct BOP to perform Block step C BOP Verify CC pump not cavitating BOP Bypass CVCS IX's using CVC-520-CV Determines leak location is in the containment and requests permission to isolate BOP CC to the containment SRO Direct BOP to shut Containment CC isolation valves Shut CC-3832 & 3833-CV's and verify leak is isolated by verifying CC Head BOP Tank level rise Direct A TC to trip the Reactor and when Reactivity Control Safety Function is SRO complete, then secure all RCP's Trip's Reactor & implements EOP-O:

Depress one set of Reactor trip pushbuttons ATC

Verifies prompt drop in Reactor Power and negative SUR

Verifies no more than 1 CEA fails to insert Critical Task

Verifies Dr water makeup to RCS is secured.

Reports Reactivity Control Safety Function is complete Trips all RCP's due to no CC flow

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: --..L Event No.: Page of-.1l Event

Description:

12 SIG tube rupture M (All) TS (SRO)

Time Position Applicant's Actions or Behavior Verify Turbine is tripped:

Check Reactor is tripped

Ensure Turbine is tripped o Depress both turbine trip push buttons BOP o Check Turbine Stop valves shut o Check turbine speed drops o Ensure TG breakers open

Ensure both 2nd stage MSR MOV's shut Report Turbine Trip complete to SRO Verify Vital Auxiliaries:

Check 11 or 14 4KV Bus energized

If either 11 or 14 4KV Bus de-energized then start OC DG

Check 125VDC & 120VAC buses energized BOP

Check either 1Y09 or 1YIO energized

Verify Component Cooling flow to RCP's

Directs ABO to verify Switchgear Room Ventilation operating Reports Vital Auxiliaries cannot be met due to Component Cooling flow to RCP's.

Verify Pressure and Inventory Control:

Check pressure 1850-2300 psia trending to 2250 psia o Opeates PZR heaters & spray to maintain o IfRCS Press <1725 psia verify SIAS ATC

Checks PZR level between 80 & 180 inches, trending to 160 inches o IfPZR level low and trending lower, then start all available charging pumps and isolate letdown

Ensure RCS subcooling >30 0 F Reports RCS Pressure & Inventory cannot be met due to low PZR level and negative trends on PZR level & pressure

Verify Core and RCS Heat Removal Safety Function

Verify TBV's or ADV's maintain S/G press 850-920 psia and Tcold 525 535 0 F

Verify at least one S/G available for controlled heat removal 0 S/G level (-) 170 - (+)30 inches BOP 0 Main or Aux Feedwater operating to maintain level 0 Tcold >525 0 F

Check at least one RCP in loop with S/G available

IfRCP's operating check ~T <100 F Report Core and RCS Heat Removal cannot be met due to no operating RCP's Verify Containment Environment Safety Function:

Check containment pressure <0.7 psig:

BOPIATC

Check containment temp < 1200 F

Check containment radiation alarms clear with no unexplained rise:

Reports Containment Environment Safety Function as complete Verify Radiation Levels External to Containment Safety Function:

Check RMS alarms clear with no unexplained rise BOP/ATC 0 Valid condenser off-gas & S/G blow down radiation alarms, verify S/G blow down isolated.

Report Radiation Levels External to Containment is complete Hold crew briefing covering:

Vital Auxiliaries not met due to no component cooling flow to RCP's SRO

PIC not met due to PZR level & pressure low and/or negative trends

Heat Removal not met due to no operating RCP's

RLEC not met due to valid off gas & blow down alarms

SIAS actuation (if actuated)

SRO Review Diagnostic flowchart and determines EOP-6 is correct path SRO Implements EOP-6, hold entry brief, assigns block steps to A TC & BOP

Block Step D Monitor RCS Depressurization:

If RCS pressure < 1725, psia verifY SIAS

If RCS pressure> 1725 psia, take actions top block SIAS:

0 Open Main & Aux HPSI header valves 0 Start 11 & 13 HPSI pumps 0 Start all available charging pumps 0 When PZR Press Block Permitted alarm is received, then Block ATC SIAS with key switches on 1C 10 0 When RCS pressure is below 1270 psia, then verifY HPSI flow lAW Att. 10

If SIAS has actuated:

0 VerifY 11 & 13 HPSI running 0 VerifY 11 & 12 LPSI running 0 Verify all available charging pumps operating 0 VerifY HPSI & LPSI flow per Att. 10 & 11 Block Step F Commence RCS Boration:

If SIAS has actuated then:

0 VerifY VCT MIU valve CVC-5I2-CV shut 0 BA Direct M/u valve CVC-514-MOV open 0 BAST Gravity Feed valves CVC-50g & 509*MOV's open 0 RWT CHG PP Suction valve CVC-504-MOV shut 0 All BA pumps running ATC 0 VCT outlet CVC-50I-MOV shut 0 All available charging pumps operating

IF SIAS has not actuated then:

0 Same actions as above with.

0 MIU Mode selector in Manual

Record time boration started and BAST levels I

Block Step G Commence RCS Cooldown:

IfSGIS not actuated then:

o Block SGIS A & B when SGIS Block Permitted alarms are received

If SGIS actuates with vacuum available: (not expected) o Place all CBP HIS's in PTL o Verify SGIS lAW Att. 7 o Block SGIS o Reset SGIS signals o Open both MSIV's

Cooldown RCS using TBV's o Ensure AOV's shut o Perform rapid cooldown to 515 0 F Thot, while maintaining <

100° F cooldown in anyone hour (TBV controller to approximately 17 + 25 42%)

If any of the following conditions exist:

BOP o SIAS actuated o TBV's not available o Main Feedwater not in operation then:

Establish AFW flow with 13 AFW pump

Open all Motor train block valves

Start 13 AFW pump

Restore unaffected S/G level (-)24 (+)30 inches using flow control valve

Secure Main Feedwater system:

If SIAS not actuated, TBV's available & Main Feedwater in operation:

o Establish shutdown feed lineup

One SGFP, One CBP, Two Condensate pumps, no HOP's

Ensure feed flow restoring S/G level (-)24 - (+)30 inches wlo exceeding 100° F in anyone hour

Dispatch TBO to standby in 45' SWGR room for shifting AOV control Ii

Block Step H Evaluate Need for HPSI Throttling:

If all following conditions met 0 At least 25 0 F subcooling based on CET's 0 PZR level> 10 linches ATC 0 One S/G available for heat removal, then

HPSI flow may be reduced by throttling or stopping HPSI pumps one at a time to maintain:

CET Subcooling 25 - 1400 F

PZR level 101-180 inches Block Step I Depressurize RCS to reduce subcooling and maintain PZR, level

If a bubble exist in PZR then maintain subcooling as low as possible but between 25 & 140

RCS Press < 900 psia

RCS PreSS approximately: equal to SIG pressure by ATC 0 Initiation of Aux. Spray Critlc.al Task

Record PZR water temp & Charging temp

.

Open ~ux. Spray valve CVC*517*CV

"

Shut Charging loop stops as necessary CVC-518 &

519-CV's

Sbift PZR Main spray controller HIC-110 to manual with 0% output

Maintain PZR CID rate < 2000 F per hour

Block Step J Identify,Isolate and Confirm affected S/G

Identify affec.ed S/G using:

0 S/G samples 0 Main Steam Rad Monitor trends 0 S/G level trends when not*feeding 0 Post trip S/G level trends

When Thot < 51.5~,.F then isolate most affected S/G 0 Shut 12A:J)V using hand transfer valve in 45' SWGR room 0 Shut 12 MSIV.

0 Verify 12 MSIV Bypass MS-4052-MOV shut BOP 0 Verify 12 S/G Feedwater Isolation valveFW-4517-MOV shut Critical Task 0 Shut 12 S/g AFW Steam Supply valves MS-4071 7 4071A CV's 0 Shu112 S/G AFW Block valves

l-AFW-4530-CV

l-AFW-4531-CV

l-AFW-4532-CV

l-AFW-4533-CV 0 Shut 12 S/G Blowdown valves BD-4012 & 4013-CV's 0 ShutMS Upstream drain Isolation valves with HS-662tin close 0 Direct ABO or OSO to verify no 12 S/G Safety valves leaking After the scenario ends ask SRO for ERPIP call. Alert H.A.5.1.2 for S/G tube SRO leakage > available charging pump capacity

v t e Letter Sequence Other
TAC:U01770, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML102670378, ML102670380, ML102670495, ML102670496, ML102670508, ML102670524, ML111670753
MONTHYEAR2010-07-13 [Table View]

ML102670524

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